# DOCKET NO: A-98-49, II-A4-62

DRAFT

WASTE CHARACTERIZATION INSPECTION REPORT

EPA BASELINE INSPECTI ON NO. EPA-SRS-10.05-8

OF THE CENTRAL CHARA CTERIZATION PROJECT

WASTE CHARACTERIZATION PROGRAM AT THE SAVANNAH RIVER SITE

October 31–November 3, 2005

U.S. Environmental Protection Agency

Office of Radiation and Indoor Air

Center of Federal Regulations

1200 Pennsylvania Avenue, NW

Washington, DC 20460

February 2006

# TABLE OF CONTENTS

Section Page

1.0 Executive S u mm ary

............................................................................................................ 1

2.0 Purpose of Inspections

........................................................................................................ 3

3.0 Purpose of This Report

....................................................................................................... 5

4.0 Scope of Inspection

............................................................................................................. 6

5.0 Inspection-Related Definitions

........................................................................................... 7

6.0 Personnel

............................................................................................................................. 7

6.1 EPA Inspection Team

............................................................................................. 7

6.2 Personnel C ontacted

................................................................................................ 8

7.0 Perform a nce of the Inspection

............................................................................................ 9

8.0 Technical Waste Characterization Areas

.......................................................................... 10

8.1 Acceptable Knowledge and Load Managem e nt

................................................... 10

8.2 Nondestructive Assay

........................................................................................... 23

8.3 Real-Tim e Radiograph y (RTR)

............................................................................ 41

8.4 Visual Exa m ination

............................................................................................... 45

8.4.1 Visual Exam ination Technique for Newly-generated W a ste

.................... 46

8.4.2 Visual Exam ination as a QC Check of RTR and VE in lieu of RTR

....... 48

8.5 W I PP W a st e Inform ation System

......................................................................... 53

9.0 Response to Comm ents

..................................................................................................... 56

10.0 Summ ary of Results

.......................................................................................................... 56

10.1 Findings

................................................................................................................. 56

10.2 Concerns

............................................................................................................... 57

10.3 Response to Inspection Issues

............................................................................... 58

10.4 Conclusions

........................................................................................................... 58

11.0 References

......................................................................................................................... 60

i

# ATT ACH MENTS

Attachm e nt A.1 Acceptable Knowledge (AK) Checklist

Attachm e nt A.2 Visual Exam ination (VE) Checklist

Attachm e nt A.3 Visual Exam ination Technique (VE T ) Checklist

Attachm e nt A.4 Real-Tim e Radiograph y (RTR) Checklist

Attachm e nt A.5 Nondestructiv e Assay (NDA) Chec klist—IPAN

Attachm e nt A.6 Nondestructiv e Assay (NDA) Chec klist—IQ3

Attachm e nt A.7 W I PP W a st e Inform ation System ( W W I S) Che c klist

Attachm e nt A.8 W I PP W a st e Inform ation System ( W W I S) Dat a Requirem e nts

Attachm e nt B.1 Replicate Testing IPAN Data for Container SR144771

Attachm e nt B.2 Replicate Testi ng IPAN Results for Container S R 144771

Attachm e nt B.3 Replicate Testing IPAN Data for Container FBL04011

Attachm e nt B.4 Replicate Testing IPAN Results for Container F B L04011

Attachm e nt B.5 Replicate Testing IPAN Data for Container SR138868

Attachm e nt B.6 Replicate Testi ng IPAN Results for Container S R 138868

Attachm e nt B.7 Replicate Testi ng IQ3 D a ta for Container MDL0506073

Attachm e nt B.8 Replicate Testing IQ3 Results for Container MDL0506073

Attachm e nt B.9 Replicate Testi ng IQ3 D a ta for Container MDL0506146

Attachm e nt B.10 Replicate Testing IQ3 Results for Container MDL0506146

Attachm e nt B.11 Replicate Testi ng IQ3 D a ta for Container SR123477

Attachm e nt B.12 Replicate Testi ng IQ3 Results for Container SR123477

Attachm e nt B.13 Replicate Testi ng IQ3 D a ta for Container SR546270

Attachm e nt B.14 Replicate Testi ng IQ3 Results for Container SR546270

Attachm e nt B.15 Replicate Testi ng IQ3 D a ta for Container SR611807

Attachm e nt B.16 Replicate Testi ng IQ3 Results for Container SR611807

Attachm e nt B.17 Replicate Testi ng IQ3 D a ta for Container MDL0506241

Attachm e nt B.18 Replicate Testing IQ3 Results for Container MDL0506241

Attachm e nt C.1 EPA I n spection Is sue Track in g Form

, EPA Issue No. SRS-CCP-AK-05-004

Attachm e nt C.2 EPA I n spection Is sue Track in g Form

, EPA Issue No. SRS-CCP-AK-05-005

Attachm e nt C.3 EPA I n spection Is sue Track in g Form

, EPA Issue No. SRS-CCP-NDA-05-006

Attachm e nt C.4 EPA I n spection Is sue Track in g Form

, EPA Issue No. SRS-CCP-RTR-05-

003CR

Attachm e nt C.5 EPA I n spection Is sue Track in g Form

, EPA Issue No. SRS-CCP-VE-05-001F

Attachm e nt C.6 EPA I n spection Is sue Track in g Form

, EP A Issue No. EPA SR S-C C P-VE-05-

002CR

Attachm e nt D Response to EPA Inspection Issues

ii

# 1.0 EXECUTI V E SUMM ARY

In acco rdan ce with 40 C F R 194.8(b), from October 31–Novem b er 3, 2005, the

U.S. Environm ental Protection Agency (EPA or the Agency) conducted Baseline Inspection

No. EPA-SRS-10.05-8 of the Central Characterizat ion Project’s (CCP) wa ste characterization

(WC) program at the U.S. Departm e nt of Ener gy’s (DOE) Savannah River Site (SRS) located in

Aiken, South Carolina. EPA conducted a base line inspection of the site’s program to

characterize wastes prop osed for dis posal in the Waste Isolation Pilot Plant (W IPP). As a result

of our baseline inspection, EPA is proposing to approve the S R S-CCP WC program based on a

dem onstration of the site’s capabil ities, with con d itions and lim ita tions discussed in this report,

in acco rdance with 40 CFR 194.8(b).

EPA m u st verify com p liance with 40 CFR 194.24 be fore waste m a y be disposed of at the W I PP,

as specif i ed in Condition 3 of the Agency’s c e rt if ication of th e W I PP’s compliance with disposa l

regula tions f o r tran suran i c (TRU) rad i oactive was t e (63 Federal Register (FR) 27354 and 27405,

May 18, 1998). EPA had previously evaluated and approved W C syste m s at SRS-CCP (EPA

Docket A-98-49, II-A4-29, II-A4-40 , II-A4-49, and II-A4-50 ). SRS-CCP was approv ed to

dispose of only debris waste (S5000) prior to th is baseline inspection. During this baseline

inspection E P A evaluated the SRS-CCP’s ability to characterize soils/gravel waste (S4000) for

the first tim e. EPA Baseline Inspection No. SR S- 10.05-8 was perform e d in accordance with the

provisions of 40 CFR 194.8(b), as issued in a July 16, 2004, FR notice (V ol. 69, No. 136, pages

42571–42583). The purpose of the SRS-CCP WC inspect ion was to evaluate the adequacy of

the site’s WC program s for two TRU waste categories, debris and soils/gravel , to be disposed of

at the W I PP. The scope of the EPA inspection did not include solid TRU waste (S3000). The

activ ities ex am ined during the insp e c tion includ ed the f o llo wing:

• Acceptable knowledge (AK) and load m a nagem e nt for contact-hand led (C H) retrievab l ystored and newly-generated TRU debris waste (S5000) and soils/gravel (S4000)

• Visual exam ination technique (VET) for CH newly-generated debris waste (S5000) and

soils/gravel (S4000)

• Visual exam ination (VE) as quality contro l (QC) check of real-tim e radiography (RTR)

for CH retrievably-stored TRU debris wa ste (S5000) and soil/gravel wastes (S4000)

• RTR for CH retrievab l y-stored TRU debris was t e (S5000) an d soil/g ravel waste (S40 00)

• Nondestructive assay (NDA) and the W I PP W a st e Inform ation System ( W W I S) for CH

retrievably-stored and newl y-generated TRU debris waste (S 5000) and soils/gravel

(S4000)

Two NDA system s (Im a g ing Passive-Active Ne utron/Gamm a Energy An alysis (IPAN/GEA)

system and MCS IQ3 gamma system) were eval uated for characterizing debris (S5000) and

soil/g ravel (S4000) wastes. 1 

# EPA’s inspection team identified one finding and five concerns.

The one finding and two of the concerns requir ed a response from DOE. All concerns and

findings are docum ented on EPA Inspection Issu e Tracking F o rm s (see Attachm e nts C.1 through

C.6). Personnel from the site, the C a rlsbad F i eld Office (CBFO), and the CCP provided

1 

# The NDA syste m s are not m a trix-s pecific i n the sam e m a nner as ot he r c h ar act eri zat i on t e c hni que s.

Sp ecifically, an y m a trix within th e syste m ’s calib ration p a ra m e ters can b e assayed

.

1

# inform ation regarding the finding and concerns to the EPA inspection te am prior to the

inspection closeout on site and also subsequent to the insp ection (see Attachm e nt D). The

inform ation provided by CBFO addre ssed the finding and two concerns that required a response,

as well as one concern that did not require a resp onse. The EPA inspection team m e mbers

evaluated all responses f o r com p leteness and adequacy, and concluded th at each h a d been

resolved satisfactorily. EPA cons iders all concerns and the f i nding to b e resolved, an d there are

no open issues resulting fr om this inspection.

EPA’s inspe c tion team determ ined th at SRS-CCP’s W C program activities were techn i cally

adequate. E P A is proposing to approve the SRS-CCP WC program in the configuration

observed during this inspection and describ e d in this r e por t a nd in the ch ecklists in

Attachm e nt A. This appr oval includes the following:

(1) The AK and load m a nagem e nt process fo r CH retrievably-stored TRU debris and

soil/g rave l

(2) The IPAN and IQ3 NDA system s for assay i ng soil/g rave l a nd debris wa ste

(3) VE as a QC check of the RTR process f o r retr ieva bly-sto r ed s o il/g rave l an d debris was t e

(4) The VET process f o r ne wly-gener a ted debris an d soil/g rave l wastes

(5) The nondestructive exam ination process of RTR for retriev a bly-s t ored soil/g ravel and

debris wastes

(6) The W W IS process f o r tracking of waste con t ents of debris a nd soil/g rav e l wastes

Any changes to the W C activ ities f r o m the date o f the baseline inspection must be reported to

and, if applicable, app r o v ed by EPA, accord ing to the following table.

Proposed Tiering of TRU WC Pr ocesses Implemented by SRS-CCP

(Based on October 31–Novemb er 3, 2005, Baseline Inspection)

WC Proces s

Elements SRS-CCP W C Pr ocess

Specific T1 Changes S R S- CC P WC P r o c e s s

Specific T2 Changes * SRS

- CCP Ge neral T 2

Ch an ges*

AK in clud ing

Loa d M a na ge m e nt Any ne w wast e category

Ch ang e s to WW IS

algorithm s specific to loa d

m a nagem e nt WSP F s, i n cl u d i ng u pdat e s

or

ad di t i ons t o wast e

stream (s) withi n a n

approve d wast e category

(see Sect i o n 8. 1)

Ch ang e s i n lo ad

m a nagem e nt st at us of

approve d wast e stream (s) C h an ges t o si t e p r oce d ures

requ iring CBFO ap pro v a ls

and ot her cha n ges as

di scuss e d i n Se ct i on 8. 1 of

th is rep o rt

NDA New equipm ent or physical

m odi fi cat i ons t o a p p r ove d

equi pm ent **

C h an ges t o a p pr o v ed

calibration ra n g e fo r

app r ove d e q ui pm ent (see

Sect i on 8. 2 ) Chan ges t o s o f t ware fo r

app r ove d e q ui pm ent (see

Sect i on 8. 2 )

Changes t o operating

r a ng e(s) up on CBFO

app r oval C h an ges t o si t e p r oce d ures

requ iring CBFO ap pro v a ls

and ot her cha n ges as

di scuss e d i n Se ct i on 8. 2 of

th is rep o rt

2

# Proposed Tiering of TRU WC Pr ocesses Implemented by SRS-CCP

(Based on October 31–Novemb er 3, 2005, Baseline Inspection)

WC Proces s

Elements SRS-CCP W C Pr ocess

Specific T1 Changes S R S- CC P WC P r o c e s s

Specific T2 Changes * SRS

- CCP Ge neral T 2

Ch an ges*

R T R N / A New eq ui pm ent or cha n ges

to appr ov ed equ i p m en t C h an ges t o si t e p r oce d ures

requ iring CBFO ap pro v a ls

and ot her cha n ges as

di scuss e d i n Se ct i on 8. 3 of

th is rep o rt

VE a n d VET C h an ges i n ve nd o r

per f o r m i ng VE an d/ o r VE T N/ A C h an ges t o si t e p r oce d ures

requ iring CBFO ap pro v a ls

and ot her cha n ges as

di scuss e d i n Se ct i on 8. 4 of

th is rep o rt

WWI S N/A N/A Chan ges t o site p r oce d ures

requ iring CBFO ap pro v a ls

and ot her cha n ges as

di scuss e d i n Se ct i on 8. 5 of

th is rep o rt

* Up on receiv in g EPA approv al, SRS-CC P will repo rt al l T2 ch an g e s to EPA ev ery three m o n t h s

.

** M o d i ficatio n s to app r ov ed eq u i p m en t in clu d e all ch an ges with th e po ten tial to affect NDA d a ta relativ e to

wast e i s ol at i o n an d e x cl u d e m i no r c h an ges, s u ch as t h e a ddi t i on of safet y

- r e l a t e d eq ui pm ent

.



# EPA will notify the public of the re s u lts of its ev aluations of pr oposed Tier 1 (T1) an d Tier 2

(T2) changes through the EPA W e b site and by sending e-m a ils to the W I PPNEWS list (see

Section 2.0, below, for a brief discus s i on of tieri n g ). All T1 changes m u st be subm itted for

approval b e f o re the i r implem entatio n and will b e evalua ted by EPA. Upon approval, EPA will

post the results of the evalua tions through the EPA W e b site and the W I PPNEWS list, as

describ e d ab ove. EPA will pos t T2 c h anges appr oxim a tely every thr ee months begin n ing with

the date of EPA’s approval of the TRU WC program i m ple m e n ted at SRS-CCP. EPA expects

the first report of SRS-CCP’s T2 changes appr oxim ately three m onths from date of EPA’s

approval of the TRU WC program i m plem ented at SRS-CCP.

The scope of the proposed site baseline com p liance decision is based on EPA’s inspection

com p leted on Nove m b er 3, 2005. EPA will not a pprove any changes to the SRS-CCP program

until this p r o posed baseline approva l is f i nalized by EPA.

Based on prior approvals, SRS-CCP i s currently a pproved to dispose of debris waste (S5000) at

the W I PP. SRS-CCP is perm itted to continue W C and disposal of debris waste while EPA

evalua tes pu blic comm ent to this proposed approval and establishes a final approval.

2.0 PURPOSE OF INSPECTIONS

On May 18, 1998, EPA c e rtified that the W I PP will co m p ly with the radioactive was t e disposal

regulations at 40 CFR Part 191. In this certif ication, EPA also included C ondition No. 3, which

states that “the Secretary shall no t allow shipm e nt of any waste from ...any waste generator site

other than L ANL [ L os Alam os National Labora t o r y] f o r disposal a t the W I PP until th e Agency

has approved the processes for characterizing thos e waste stream s for shipm e nt using the process

3

# set forth in §194.8.” The approval proce ss described at 40 C F R 194.8 requires DOE to

(1) provide EPA with infor m ation on AK 2 

# for waste stream s proposed for disposal at the W I PP,

and (2) im plem ent a system of controls used to co nfirm that the total am ount of each waste

com ponent that will be emplaced in the W I PP will not exceed lim its id entified in the W I PP

Com p liance Certif ica tion Application (CCA).

Under the changes to 40 CFR 194.8 prom ulgate d in the July 16, 2004, FR notice, EP A m u st

perform a single baseline inspecti on of a TRU waste generator site’s W C program . The purpose

of

the baseline inspec tio n is to app r o v e the s ite ’s WC program based on the dem onstration that

the program’s com pone nts, with ap plicab le con d itions and lim itations, can adequately

characterize TRU wastes and com p ly with the re gulatory requirem ents imposed on TRU wastes

destined for disposal at the W I PP. An EPA in spection team conducts an onsite inspection to

verify that the site’s system of controls is techn i cally ad equate a nd properly im ple m ented.

Specifically, EPA’s inspection team verifies compliance with 40 CFR 194.24(c)(4), which states

the f o llowin g :

Any compliance application shall: . . . Pr ovide information which demonstrates

that a sys t e m of controls has been a nd will con t inue to be im plemented to confirm

that th e tota l amount of each waste component th at will b e emplaced in the

disposal s y stem will not exceed the u pper limitin g value or fa ll be low the lower

limiting value described in the introductory text of paragraph of this section. 3



# The system of controls sha ll include, but shall not be limited to: measurement;

sampling; chain of custody records; record keeping systems; waste loading

schemes used; and other documentation.

In other words, the purpose of the baseline in spection is to assess whether DOE sites that

characterize TRU waste prior to disp osal at th e W I PP are capable of characterizing and track i ng

the waste in such a m a nner tha t EPA is conf ident that the waste w ill no t ex ceed the app r oved

lim its. By proposing the approval of WC sy ste m s and processes at SRS-CCP, EPA ha s

evaluated th e capabilities of system s and pr ocess e s to ac complish two tas k s: (1) the

identification and m easurem ent of waste com ponent s (such as plutonium ) that m u st be tracked

2 

# As of the FR notice of J u ly 16

, 2004, EPA has re placed t h e term process k now l e dge with accept able

know l e dge

. Acceptable knowledge refe rs t o a n y inform ation a b out t h e proces s used to gene rate waste

, m a terial

in pu ts to th e p r o cess, and t h e t i m e p e riod d u rin g wh ich t h e wastes were g e n e rated

, as wel l as d a ta resu ltin g fro m th e

analysis of was t e conducted prio r to or sep a rate fro m th e waste cer t i f i cat i on pr ocess aut h ori z e d by an E P A

certificatio n d e cisio n t o sh ow co m p lian ce with C o nd itio n 3 o f th e certificatio n d ecision

. 3 

# The i n t r od uct o ry t e xt o f 40 C F R 1 9 4

. 2 4 ( c) st at es, “F or ea ch wast e c o m pone nt i d e n t i f i e d a n d assesse d pu rs uant

t o [ 4 0 C F R 1 9 4

. 2 4 ( b)]

, t h e D e part m e nt shal l speci fy t h e l i m i ti ng val u e (e xp resse d as an up pe r or l o we r l i m i t of

mass, volum e , curies, conce n t r ation, et c.), a n d the ass o ciated unce r tainty (i .e., m a rg in of erro r) for each limit in g

val u e, o f t

h e t o t a l i nvent ory o f s u ch wast e p r op ose d fo r di s pos al i n t h e di spos al sy st em .”

4

# for com p liance, 4 

# and (2) the confirm a tion th at th e waste in any given container has been properly

identified as belonging to the group of approved waste stream s.

Following E P A’s approval of W C pr ocesses ev aluated during the baseline inspection, EPA is

authorized to evaluate and appr ove, if necessary, changes to th e site’s approved WC program by

conducting additional inspections under the authority of 40 CFR 194.24(h). Under 40 CFR

194.24, EPA has the authority to conduct continued com p liance inspections to verify that the site

continues to use only the approved WC processe s to characterize the was t e and rem a ins in

com p liance with all the regulatory requirem e nts. Based on the adequacies of the W C processes

dem onstrated during th e baseline ins p ection, including all co nditions and lim itations, EPA will

specify which subsequent WC program changes or m odifications m u st undergo further EPA

inspection o r approval u nder 40 CFR 194.24. This will b e accom p lished by assignin g a tier lev e l

to each aspect of the characterization program

. Tier 1 activ ities have m o re stringent reporting

requirem e nts and require that DOE notify EPA, and that EP A provide approval prior to

im ple m entation. Tier 2 activities are repor ted to EPA by DOE based on the frequency

established in the inspection repor t. DOE m a y c hoose to operate at risk while EPA considers the

proposed T2 changes. If SRS CCP c ontem plates a change that is not iden tified in this report,

EPA recomm ends that the site in consultation w ith CBFO discuss the nature of the change with

EPA. This would m i nim i ze a possibility of EPA not approving the site-assigned tiers. The rule

under which this baseline inspection was conduc ted can be found in the F R (Vol. 69, No. 136,

pages 42571–42583, July 16, 2004).

3.0 PURPOSE OF THIS REPORT

This inspe c tion repor t pr esents the r e sults of EP A’s inspection of the W C program at SRS-CCP

and describes the conditions that EP A is proposing for approval. This report docum ents the basis

for EPA’s proposed approval decision and explai ns the results of Base line Inspection No. EPASRS-10.05-8 in term s of findings or concerns. S p ecifically, this report does the following:

• Describes the characterization system s proposed for approval

• Identifies all relevant system li m itations and or conditions

• Provides objective evidence of outstanding fi ndings or concerns in the form of

docum entation, as applicable

• Describes any tests or dem onstrations com p le ted during the course of the inspection and

their relevance to EPA’s proposed approval decision

4 

# The p o t e nt i a l cont e n t s of a w a st e st ream or gr o u p o f waste stream s determ ine whic h processes can adequately

characte r ize the waste. For e x am ple, if AK in fo rm atio n sug g e sts th at the waste form is h e terog e n e ou s, t h e site

shoul d select a n NDA tec hni que that suits s u ch waste i n o r d e r f o r a d eq uat e m easurem ent s t o be obt ai ned

. R a di o g ra phy a n d V E hel p b o t h t o co n f i r m and qua nt i f y was t e com pone nt s, suc h as cel l u l o si cs, r u

bbe rs, p l ast i c s, and

m e t a l s . Once t h e nat u re of t h e wast e has be en c o n f i r m e d, t h e assay t e c hni que s t h e n q u an t i f y sel ect ed ra di o nucl i d e s

in the waste. In s o m e cases, a TRU waste generat o r site m a y be a b l e t o c h aract eri z e a w i de ra n g e of he t e ro gene o u s

waste stream s o r on ly a few. A site ’s stated li mits o n t h e ap p licab ility o f p r op o s ed WC p r o cesses gov ern EPA’s

in sp ection scop e.

5

# The com p leted checklists attached to this report reference th e docum ents that the EPA inspection

team m e mbers reviewed in support of the technical determ ination. To see or obtain copies of

any item s identified in th e attached check lists, write to the following address:

Quality Ass u rance M a n a ger

USDOE/Carlsbad Field Office

P.O. Box 3090

Carlsbad, N M 88221

EPA’s final approval d e cision regarding the SR S-CCP WC program will be conveyed to DOE

separa tely b y letter f o llo wing the co nsidera tion of public co mments on this repo rt. EPA will als o

announce the decision on its W e b site at http://w ww.epa.gov/radiation/W I PP , in accordance with

40 CFR 194.8(b)(3).

4.0 SCOPE OF INSPECTI ON

The scope of Baseline Inspection No. EPA-SRS-1 0.05-8 included the techni cal adequacy of the

WC system s in use at SRS-CCP to characterize T R U wastes. These system s were evaluated with

respec t to th eir ab ility to perf orm the f o llowing:

• Identify and quantify the activities of the 10 W I PP-tracked radionuclides ( 24 1 

# Am

, 137 

# Cs,

238 

# Pu, 239 

# Pu, 240 

# Pu, 242 

# Pu, 90 

# Sr, 233 

# U, 234 

# U, and 238 

# U) using a combination of AK and NDA

system s

• Assign waste m a terial p a ram e ters (WMP s) correctly using RTR and VE for

CH retrievably-stored solid and debris wast e, and VET for newly- generated debris and

soil/g rave l wastes

• Perform effective was t e infor m ation (data) tran sfer using th e WW IS

Specifically, these system s consisted of the following com p onents:

• The AK and load m a nagem e nt processes that support retrievably-st ored S 4000 soils and

S5000 debris wastes

• Two NDA s y stem s (IPAN and IQ3 system s, as de scrib e d in this repo rt) f o r the an alys is

of CH retrievably-s t ored or newly-generated S4000 soil/g rav e l and S500 0 debris was t es

• VE as a QC check for RTR for retrievably- stored S5000 debris and S4000 soil and gravel

wastes

• VET for ne wly-generated S5000 debris and S40 00 soil/g rav e l wastes

• RTR for retrievably-stored S5000 debris and S4000 soil and gravel wastes

• The WW IS for the purpose of data transfer for waste containers of all w a ste m a trices

destin ed for W I PP em placem ent

During an inspection, EPA does not approve charact erization data; that function is the sole

responsibility of the site bei ng evaluated during the inspection, in this case SRS-CCP. EPA

evaluated the W C processes im plem ented by th e site to cha r a c ter i ze CH retrievably-stored debris

6

# and soils wastes, and newly-genera ted debris and soil. The eval uation consists of interviewing

personnel, observing equipm ent operations that co m port with the site pr ocedures, and inspecting

records related to each o f the W C pr ocesses with in the inspection’s scope. An i m portant aspect

of

this evalu a tion is the objectiv e ev idence that d o cum e nts effectiv enes s of the W C processe s.

Objectiv e ev idence typic a lly takes th e f o rm of ba tch data reports (BDRs); radioassay datasheets;

AK accuracy reports; V E , VET, and RTR tapes; and WW IS printou t s for specific TR U

containers. During this inspect ion, EPA selected sam p les of e ach of these item s , based on the

num b er and variety of item s each WC process p r o duced, consistent with standard aud i ting

techniques. For exam ple, the sam p le of NDA BD Rs that were evaluated to verify com p liance

was chosen such that it included a contributi on from both operating system s, represented all

pertinent waste m a trices, and spanned each system ’s operatin g range to th e exten t pos sible.

Based on the evaluation of the W C processes in conjunction w ith the s a mple of objective

evidence, E P A determ ined the technical adequ a cy of the W C processe s within the in s p ection ’ s

scope.

5.0 INSPECTI ON-RELATED DEFI NITIONS

During the course of an inspection, EPA inspectors m a y encounter item s or activities that require

further inquiry for their potential to adversely affect W C and/ or isolation within th e re pository.

The two m a in catego r ies relev a nt to W C inspections are id entified below:

Finding : A determ ination th at a s p ecific item or activity does not conform to

40 CFR 194.24(c)(4). A finding requ ires a response from CBFO.

Concern : A judgm e nt that a specific item or activity m a y or m a y not have a negative effect on

com p liance and, depending on the magnitude of the issue, m a y or m a y not require a

response.

Note: Concerns not requiring a response are no t required to be addressed prior to program

approval. H o wever, EPA recomm e nds that when DOE accepts the site’s response ad dressing the

issue raised in the EPA concern, EPA should be in for m ed concurrent with im ple m entation of the

correctiv e action in resp onse to th e c oncern sim i lar to a T2 is sue.

6.0 PERSONNEL

6.1 EPA Inspec tion Team

The m e mbers of the EPA W C inspection team are identified b e low.

EPA Inspection Team Members

Inspecti o n Te am Member Po siti o n A f f i l i a tion

Mr. E d Feltcorn Ins p ection Tea m Leader U.S. EPA ORIA

Ms. Raja ni J o glekar Ins p ector U.S. EPA ORIA

Ms. Connie Walker Ins p ector S. Cohe n & As sociates, Inc

. Ms. Do ro th y Gill In sp ector S. Coh e n & Asso ciates, In c.

Mr. Pat r ick Ke lly Ins p ector S. Cohe n & As sociates, Inc

.

7

# 6.2 Personnel Contacted

EPA and its support personnel c onducted interviews with SR S-CCP personnel in several

disciplines. The personnel cont acted repres ented only a sam p le of the CH TRU WC st aff, and

they ar e liste d in the table below, alo ng w ith the i r af f iliation a nd technical area.

Personnel Contacted During Inspection

Perso n nel Affilia tion Area of E x pertise

R obe rt T hom ason M C S C a nb er ra ND A, I Q 3

Bru ce Gillesp i e BII NDA, IQ3

Th om as Peterson BII ND A, IP A N

Alan Sim p son BII ND A, IP A N

Dave Haa r CCP AK , S P M

Jeff Ha rris on C C P A K

, A K E

Kevi n Pet e rs C C P A K

, A K E

Lee Sm ith CCP RTR, SME & Op erator

Su san Sm ith CCP RTR, SME & Op erator

J.R. Strob l e CCP WWI S

, W C O

Jam e s Mobley C C P V E / V E T

, VEE

Marcus Steade C C P V E / V E T

, VEE

Bu dd y Fu sel C C P V E / V E T

, VP M

M a uri ce “C hi p ” Hat c he r C C P V E / V E T

, O p e r a t o r

Steve Pi per C C P V E / V E T

, O p e r a t o r



# During the baseline inspection, SRS-CCP provide d a list of TRU WC personnel from which

EPA selected a few individuals to be inte rviewed

. The EPA inspectors reviewed the

qualif ica tion s and tra i nin g record s of these individuals to assess their W C capabilities. Based on

this evaluation, EPA determ ined that SRS-CCP WC personnel responsible for characterizing

TRU waste and certifyin g it as TRU waste were qua lified and had received adequate training to

perform their assigned function. EP A is not requ iring that S R S-CCP provide changes in the key

areas of expertise every three m onths, beginni ng with the date of EPA’s SRS-CCP pr ogram

approval, as a T2 change. EPA, however, can ask the site about cha nges in the W C personnel

anytim e after the site approval at its discretion. If the key WC personnel changes had occurred,

EPA m a y re quest qualification and training records of the new indi viduals identified as key WC

personnel. EPA will review thes e records and m a y interview the person nel to determ ine their

abilities to produce quality data. This personne l qualification evaluation and review of training

records is sim ilar to the evalua tion done by the E P A inspection team during each inspection.

8

# 7.0 PERFORM ANCE OF THE INSPECTION

Site Background and H i story

SRS is located in South Carolin a approxim a tely 25 m iles southeas t of Augusta, Georgia. It

encom p asses 310 square m iles and occupies portions of Aiken, Ba rnwell, and Allendale counties

on the western border of South Carolina. This site has played an integral role in supporting the

production and m a intenance of nuc lear m a terials for the nation ’s weapons program since its

inception in 1951. Its current m i ssion focuses mo re on waste stabilization and m a nagem e nt, and

a considerable part of that wast e is CH TRU materia l s th at a r e sl ated for disposal at W I PP. SRS

also m a nages significant am ounts of r a dioactive and chem ical wastes, and the site’s current

inventory of CH TRU waste in storage is approxim ately 2,900 cubic m e ters. SRS-CCP has been

characterizing TRU was t es for W I PP since the site’s in itial approval by EPA in 2001

.

Inspection Process Ov erview

EPA Inspection No. EPA-SRS-10.05-8 took place from October 31 to N ovem b er 3, 2005. The

inspection had the scope described in Section 4.0, above, for the purpose of determ ining the

site’s com p liance with 40 CFR 194.24. The in spection was conducted in the following steps:

(1) Preparing d r aft checklists specific to each technical area prio r to the inspection

(2) Reviewing the results of EPA’s and CBFO’ s previous inspections and audits of SRSCCP’s WC program , including findings/concer n s identified by EP A and/or CBFO and

correctiv e actions

(3) Obtaining and reviewing site procedures, re ports, and other technical inf o rm ation related

to W C activities at SRS- CCP in advance of the in spection

(4) Interacting with CBFO and SRS-CCP pe rsonnel to arrange inspection logistics

(5) Verifying onsite the technical adequacy or qualifications of WC personnel, procedures,

processes, and equipm e n t by m eans of inte rviews, observation, and dem o nstrations, and

record ing th e results on checklists

(6) Recording all concerns on EPA issue tracking form s, which were com p leted and

provided to CBFO and s ite pers onnel as they were generated

(7) Communicating all pertinent information with CBFO and SRS-CCP personnel on site, as

appropriate

(8) Pursuing re s o lution of all iden tif ied issu es prior to com p letion of the inspection by

discussions with CBFO and SRS-CCP personnel

(9) Conducting entrance, exit, and daily br iefings for CBFO and SRS-CCP managem e nt

personnel, as appropriate

9

# 8.0 TECHNICAL WASTE CHARACTERI Z A TION AREAS

8.1 Acceptable Know ledge and Load Management

EPA exa m ined the AK process and load m a nage m e nt and associated inf o rm ation to determ ine

whether SRS-CCP de monstrated complian ce with 40 CFR 194.8 requirem e nts for CH

retr ievab l y-s t ored so ils /g ravel a nd debris waste. See Item 4 be low f o r CCP’s asse rtion that a ll

SRS waste received for characterization by CCP would be considered retrievably

- sto r ed

regardless of when the waste was generated, becau se CCP is the characterization entity and did

not generate the waste. EPA’s evaluation of the CCP’s argum ent is also presented.

Waste Characteriz a tion Element Description

As part of the inspection, EP A reviewed the elem e n ts of the AK process listed below:

• Overall p r ocedural techn i cal sufficiency and scope and ability to follow the AK WC

process for containers an d waste stream s

• Waste-generating procedures, processes, and docum entation

• Characterization of required W M Ps a nd radionuclides

• AK infor m a tion assem b ly and com p i l ation

• AK confir mation and associat ed discrepancy resolution

• Sufficiency of AK characterization results

• Assem b ly of required inf o rm ation and use of supplem ental infor m ation

• AK summary preparatio n

• Reassignm ent of waste stream due to AK and discrepancy analysis

• AK accuracy

• Load m a nagem e nt

The checklis t included as Attachm e nt A.1 identifie s the ob jective evid ence reviewed b y the EPA

inspector. AK is used to provide infor m ation regarding sev e ral asp ects o fTRU wastes at SRSCCP, including but not lim ited to the following:

• Defense waste status

• Mat e ri al paramet e rs

• Waste stream

• Radionuclid e com position

• Waste m a trix codes (WMCs)

10

# Documents Review ed

During the inspection, EPA inspectors exam ined a variety of procedures and docum ents related

to AK, inclu d ing the following. Please note th at because CCP does not assign unique identifiers

to AK docum ents, the sam e reference num ber can a pply to different ref e re nces in different AK

summaries. To avoid confusion, the AK summary report applicable to the specific reference has

been added in parenthesis before the reference number, i.e., (AK8).

• CCP-QP-002, Revision 17, CCP Tra i ning and Q u alification Plan, June 6, 2005

• CCP TP-005, Revision 15, CCP Ac ceptable Knowledge Docum e ntation, March 31, 2005

• CCP-TP-066, Revision 3, Radi ography Screening Procedure for Prohibited Item s,

effective June 14, 2005

• Inter-Office Correspondence, from Irene Quintana to CCP Records Custodian, Savannah

River Site Summ ary Category Group S5000 Specific Miscertification Rate, May 19,

2005

• Burial Ground Record, Drum SR 98079 (debris), January 11, 1979

• TRU Waste Package Data), Drum 570782 (debris), 1990

• Radioactive Waste Burial Ground Reco rd), Drum 570782 (debris), July 1990

• Retrievable Alpha W a ste for Pad and Conc rete Category Drum 570782 (debris), July

1990

• Transuranic Waste Container Characteri zation Form , Drum 773A-02-0021 (debris),

Decem ber 9, 2003

• SW 15.3-SOP-CAND-01, Revision 15, Initial Screening of Candidate Drum s (u),

Decem ber 9, 2005

• Attachm e nt 12, Acceptable Knowledge Re-e valuation Checklist, SR SRS- W 027-FBPre86-C waste stream , October 24, 2002

• Program Tracking System (PTS)/Container Tr acking System (CTS) Data Searches fo r

Containers MDL050673, MDL0506241, 773A020021, SR570782, SR98079, printed

Nove m b er 2, 2005

• NCR-SRS 0561 from CTS Tracking System , Us e of IQ3, Oc tober 20, 2004

• NCR-SRS 0289 from CTS Tracking System

, No TRU Radionuclides Measured Above

MDA for Container SR606827, February 22, 2005

• Go- W est Database Query, Containers SR57082, MDL0506073, MDL0506241,

773A020021, SR98079, printed Novem b er 2, 2005

• CCP Acceptable Knowledge Confirmation Check list for SR-MD-SOIL, Oc tober 2005

• Inter-Office Correspondence, from C.M. Go m ez to S.B. Rose, Acceptable Knowledge

Accuracy R e port: Mound Site Transurani c W a ste Stored at Savannah River Site,

SR-MD-SOIL, Lot 1, October 18, 2005

• Waste Stream Profile Form ( W SPF) SR-SRS- W 0 27-773A-HET, March 10, 2005

11

# • (AK7) P010, Radioactive W a ste Dispos al-SRL (Procedure), DPSTOM-22-30, 1981

• (AK7) P006, Savannah River Technology Center Procedures Manual L1, Procedure 6.24,

SRS Revision 0-6, May 18, 1998 through August 8, 2002

• (AK7) P001, Savannah River Plant, Managem e nt of Solid Radioactive Waste/Radiation

and Contamination Control Including DPSCP 40 : Burial Container Lim its, SRS Special

Hazards Bulletin and DPSOP 40 History, 1970–1980s, undated

• (AK7) M028, Acceptable Knowledge Payload Managem e nt Calculations for CCP-SRS

AK Reports 1–7, Nove mber 15, 2004

• (AK7) M024, Radiological Evaluation for 773-A, Anne K Hallm an, April 12, 2004

• (AK7) M022, W 017-773A-HET, 773A-29-90 WMP calculations, David Becker, April 7,

2004

• (AK7) D152, TW BIR Update 2004 for Com p lian ce Recertificati on Application, 2004,

Bev Crawford and Sheila Lott, LANL, DOE/ W I PP 2004-3231, March 2004

• (AK7) D122, Citation Determ ination and Evaluation of W a ste Incidental to

Reprocessing, K.J. Collins, LL W

- SUP-99-0060, Revision 0, April 2000

• (AK7) D077, Savannah River Laboratory Tech nical Progress Report Converter Fuel

Cycle Technology, July–Septem b er 1978

• (AK7) D061, Production of the Transplutonium Elem ents at Savannah River, C.H. Ice,

DUPONT, DP-MS-66-69, October 10, 1966

• (AK7) D020, Savannah River Laboratory Qu arterly Report(s), W a ste Managem e nt

(1975), DPST-75-125-1, E. I. du Pont de Ne m ours & Com p any, January–Decem b er 1975

• (AK7) C003, SRS- W 027-773A-HET, DW PF Canist er Fill Level Detector Cf-252 Source

Replacem ent Radiation Dose Rates, M.O. W h itaker, ESH-HPT-900350, February 20,

1990

• (AK7) C019, Savannah River Laboratory Actini de Technology Division Process Incident

Report No. PI-ATD-83-1, J.H. Gray, DPST-83-907, October 13, 1983

• (AK7) C023, Californium -252 Wastes on TRU Pads—Reassignm ent to LLW and

Disposal, A Gibbs, SW D-SW E-99-00, October 18, 1999

• (AK7) C040, For 773A AL RE: Dried Sludge, M. Bulling t on, Septem ber 11, 2003

• (AK7) C068, High Level Caves Monthly Re port, Decem ber 21, 1967–January 20, 196 8

• (AK7) D001, W e stinghouse Savannah River Company, W S RC-TR-2002-00001-01

through 12, Monthly Technical Repor ts, January through Decem ber 2002

• (AK7) C074, Mem o randum to Steve Rose from J e ff Harrison, RE: Evaluation of

TW BIR Wa ste Stream s for Building 773-A, May 18, 2004

• (AK7) D037, Safety Analysis Savannah River Laboratory T e chnical Area, DUPONT

Savannah River Laboratory, DPSTSA-700-38, Septem ber 1, 1988

12

# • CCP-AK-SRS-7, Central Characterization Project Acceptable Knowledge Summ ary

Report for Savannah River Site Building 773-A, Transuranic Debris W a ste StreamSRSRS- W 027- 773A-HET, Revision 1, Decem ber 3, 2004

• (AK7) M025, Evaluation of the Radiological Characterizatio n of W a ste Stream SR- S RSW027-773A-HET, July 23, 2004

• (AK7) NDA-AK Me m o

, Evaluation of the Ra diological Character ization of W a ste

Stream SRS-W 027-773A-HET, August 31, 2004

• Manual No. 1S, SRS Waste A ccep tance Criteria Manual, Ap pendix A-23 , Revision 5,

Transuranic Waste Container Form (O SR 29-90) Instructions, April 30, 2005

• Savannah River National Laboratory, Tran suranic W a ste Procedure, Procedure 6.24,

Revision 11, August 10, 2005

• CCP-TP-005, Attachm e nt 1, AK Docum e nta tion Checklist for SRS- W 0 27-773A-HET,

October 22, 2004

• CCP-TP-005, Attachm e nt 4, Source Docum e ntation Reference List for S R S- W 027-

773A-HET, October 17, 2005

• CCP-TP-005, Attachm e nt 6, W a ste Form s, Wast e Material P a ram e ters, P r ohibited Item s

and Packaging for SRS- W027-773A-HET, October 19, 2004

• CCP-TP-005, Attachm e nt 8, W a ste Contai ners for SRS- W 0 27-773A-HET, October 14,

2004

• CCP-TP-005, Attachm e nt 1, AK Docum e nta tion Checklis t f o r SR-MD-SOIL, October

15, 2005

• CCP-TP-005, Attachm e nt 4, Source Docum e nt ation Referen ce List for S R -MD-SOIL,

October 5, 2005

• CCP-TP-005, Attachm e nt 6, W a ste Form s, Wast e Material P a ram e ters, P r ohibited Item s

and Packaging for SR-MD-SOIL, Septem ber 23, 2005

• CCP-TP-005, Attachm e nt 8, W a ste Contai ners for SR-MD-SOIL, September 23, 2005

• CCP-AK-SRS-8, Central Characterization Project Acceptable Knowledge Summ ary

Report for Mound Site Transuranic Waste Stor ed at Savannah River Site Waste Stream s

SR-MD-HE T, SR-MD-SOIL, SR- M D-HOM-A , SR-MD-HOM-B, Re vision 2, Septem ber

23, 2005

• Rockwell International, Letter from J.K. Paynter to B.C. Barrett, RE: Radionuclide

Inform ation Required for TRUPACT II Sh ipm e nts; WCP8-20, N/A, March 23, 1989

• (AK8) DR005, Discrepancy Resolution for all Waste Stream s in SRS-AK-8, J. Harrison,

August 17, 2005

• (AK8) DR006, Discrepancy Resolution for Soil with Sm aller Am ounts of Debris, J.

Harrison, N A , August 17, 2005

• (AK8) IO31, Plutonium Working Group Report on Environm ental, Safe ty and Health

Vulnerabilities Associated with the D e partm e nts Plutonium Storage, Volum e 2,

Appendix B, Part 7, Septem ber 1994

13

# • (AK8) IO82, Tables of TRU W a ste Packages, 1980s

• (AK8) P028, Mound Building 38 FSAR: Pu-239 Repackaging, Phase 1, Soil,

T. Khericha, et al., Lockheed Idaho T echnologies Com p lex, INEL-95/0519, Revision 3,

June 1996

• (AK8) P040, Executive Summ ary of TRU Wa ste at Mound, Revised Septem ber 15, 1993

• WSPF SR- M D-SOIL, October 18, 2005

• (AK8) CCP- T P-005, Attachm e nt 8, SR-MD-HE T, W a ste Containers, August 12, 2005

(includes explanation of m i side ntification of waste via RTR)

• (AK8) M064, Em ail Correspondence (and att ached RTR Data) from S. Rose to

J. Harrison, RE: SR-MD-SOIL, Oc tober 10, 2005

• MDL0506073, Transuranic W a ste Characteri zation Container Form OSR 29-90 and

Radioactive Waste Input Form , Drum SD006073, February 2005

• MDL0506241, Transuranic W a ste Characte rization Container Form OSR 29-90,

Radioactive Waste Input Form

, Drum SD006241, January/February 2005

• (AK8) P054, Mound Site Radionuclides by Location, Issue 1-3, MD 22153, Issue 1,

Revision 3, 95, 98, 2000

• (AK8) P056, Decontam ination and Decomm issioning Projects, Findings of No

Significant Impact for M ound, undated (possibly 1995)

• (AK8) P058, Mound Site W a ste Managem e nt Reports and S ite Plans, 1977–1980,

Mound/Monsanto, June 1, 1977

• (AK8) P064, Mound Site W a ste Managem e nt Reports and S ite Plans, 1981–1989,

Monsanto R e search Corporation, Novem b er 1, 1991

• (AK8) P086, Mound Laboratory Environm enta l PlutoniumStudy, D.R. Rogers, MLM2249, Monsanto Research Corporation, Septem ber 15, 1975

• (AK8) P120, Radioactive W a ste Procedur es—L oading/Sealing Transuranic W a ste

Destined for SRS in Drum s, R.S. Tuning, MD-10167, ECN No. 040131MD, Revision 2,

Nove m b er 8, 2004

• (AK8) U018, UGL Action Mem o [EE/CA] Re moval Action of Soil and Underground

Waste Trans f er Lines Leading to WD Building, CH2MHill, Septem ber 2003

• Rockwell International, Letter from J.K. Paynter to B.C. Barrett, RE: Radionuclide

Inform ation Required for TRUPACT II Sh ipm e nts; WCP8-20, N/A, March 23, 1989

• (AK8) SRS-8, (Soils Only) NDA-AK Mem o, Part of Attachment 7, Radiological

Characterization Form CCP-TP- 005, J. Harrison, Septem ber 6, 2005

• (AK7) CCP- T P-005, Attachm e nt 7, Radionuc lides for SRS-W027-773A-HET, May 18,

2004

14

# Waste Container and Batch Data Reports Review ed

BDRs for the following waste containers (55-gallon drum s) were exam ined:

Drum Nu mbe r VE BD R N o

. RTR B D R No

. ND A B D R N o

. Load Ma na ge d?

7 73A 020 021

- SRRTR1 316 SRN DA5 91 N o

SR5 7078 2

- SRRTR1 318 SRN DA5 73 N o

SR9 8079

- SRRTR1 316 SRN DA5 76 N o

MD L050 624 1 S R V E MS0 0 0 2

- SRN DA9 18 Y e s

MD L050 607 3 S R V E MS0 0 0 1

- SRN DA9 17 N o



# Technical Evaluation

The inspection team evaluated th e ad equacy of AK inf o rm ation specif ic to the CH TRU

retrievably-stored debris a nd soil waste, and m a de the following observations:

(1) Data documentation and transfer were evaluated.

EPA exa m ined how radiological, waste m a teri al param e ter (WMP) inform ation, prohibited

item s , and other data are assem b led and tran sferred through various databases at SRS.

Inform ation generated or assem b led by the SRS ge nerators is input by SRS into the T r ansuranic

Waste Characterization Database. T h is database is an assem b ly point for characterization data

(historic analytical data, AK in for m a tion, data from SRS waste an alysis activities, etc.) from

SRS generator sites, including data assem b led us ing various characteriza tion process controls

im ple m ented for the tim e periods prior to 1986, 1986–1998, and after 1998. Radiological and

WMP infor m ation is docum ented on OSR For m 29-90 for waste generated after 1998. From this

site-wide database, the Go- W est database is generated, which includes infor m ation about TRU

waste containers potentially elig ible for disposal at the W I PP. The Go- W est “screen ” allows th e

user to acces s radio l ogical, W M P, physical form

, and other relevant inform ation from the various

historic databases. Inform ation from the Go-W es t database is used to initially populate the CCP

project track ing system (PTS) database m a intain ed by CCP for each s ite, which is con tinually

updated as W I PP-required NDE and NDA are perform e d. Container status is tracked within this

system with respect to WIPP readines s, and the co ntainer tracking status (C TS) database is used

to track, among other things, noncompliance (nonconfor m a nce reports or NCRs) for e ach

container. T h is inform ation is ultim ately used to populate the WW IS. The process used by CCP

is consistent with that implem ented at other site s; the SRS site data ac quisition and input process

was not exam ined because it h a d been adequately dem onstrated by the sam e personnel at o t her

sites recently inspected and found to be adequate.

(2) Calculation of AK accuracy was assessed.

The AK accuracy calculations for th e soil was t es from Mound, Lot 1, waste streamSR-SDSOIL, were evaluated. The AK accuracy report wa s based o n five drum s and showed that no

changes to the waste m a nagem e nt codes (W MC) or radionuclide distribution were required, so

“accuracy” was 100%. The AK accuracy report provide d for review did not include analytical

data or other inform ation required to assess whet her the determ ination was valid. Further, the

report was apparently assem b led after the perform a nce of QuickScan, which showed 40 of the 53

15

# soil containers to have been m i sidentified, in th at the 40 containers should have been identified

as debris (see Item 8, below). W ithout the us e of QuickScan or other m e thods, the original AK

record in th is case was n o t accu rate, i.e., m i side ntifying 40 of the 53 contai ners corresponds to an

AK summary waste category group accuracy of 24%. EPA has allowed the use of QuickScan in

the past for the purpose of augm enting a poor AK record, and this app ears to be a prudent

m e thod for a ssessing waste content, particularly f o r the example cited above. This action should

be clearly recognized in the AK accu racy calculation, as it m e ans that the origin al AK was

lacking. See Item 8 below for additional d i scus sion of QuickScan results for soils. In addition,

the AK confirm a tion checklist for SRS- W 027-773A-HET wa s exam ined, which showed that

232 

# Th was apparently present in this lot, even though AK predicted it wo uld occur in only a few

contain e rs. The site staf f did not reevaluate the stream because they d i d n o t believe en ough of

the waste s t ream had been characterized to warr a n t this actio n. This im plies th at da ta are

available that show 232 

# Th to be present in m o re than the anticipated containers, which w a s

apparen tly n o t detected in the five co ntaine rs co mprising Lo t 1 described in the AK accuracy

report. Th e AK accuracy report is o f lim ited value, because it is no t sufficiently specific with

respec t to nu clide com p arisons

(3) AK-NDA c o mm unication was assessed.

AK-NDA c o mm unication is presented in the A K -NDA me mos for the Mound Soil and

Building 773 debris. The SRS- W 0 27-773A-HET wast e stream was generated in a f acility that

perform e d e xperim e ntal work. W h ile data show ed that 238 

# U and 239 

# Pu will be the pre d om inant

nuclide s by weight, any num b er of addition a l nu c lide s m a y be presen t on an indiv i dua l conta i ner

basis ( 252 

# Cf, 244 

# Cm , etc.). The m e mo stated that AK personnel will provide a disk to NDA

personnel containing container-specif i c AK ra diological inform ati on, and that the NDA

personnel w ill look at A K assay data for each dr u m , com p aring and using that inform a tion in

conjunction with their NDA results . The NDA mem o is generally su fficient, but should include

references for the 1, 1.4, and 1.57 90 

# Sr/ 137 

# Cs ratios used; further, the sp ec if ic calcula tion used to

determ ine 23 4 

# U should be provided or referenced, as should the scaling factors used for 242 

# Pu.

This stream is unique in that NDA personnel will review individual drum AK data as part of

their asses s m ent process.

In the case of SR-SD-S O IL, the NDA m e m o indicates that 238 

# Pu and 237 

# Np are th e m o st

prevalent nuclides by weight, while 238 

# Pu and 241 

# Am are the most prevalent nuclides by activity.

CCP expects this was t e stream to be com p rised alm o st exclusively of heat-source 238 

# Pu. Drum

specific radioassay data generate d by Mound are available on a pe r-container basis, but it does

not appear that NDA personnel will use these. The m e mo is generally adequate, although the

derivation or technical basis for the deri vation of the scaling factors used for 242 

# Pu and 234 

# U

should be justified through reference or addi tional text. Further, all assum p tions of

“conservatism ” must be explained.

(4) The CCP interpretation of newl y-generated waste was evaluated.

During the EPA inspection, SRS-CCP offered an interpretation of the definition of n e wlygenerated vs. retrievably-stored waste. CCP st ated that all w a ste it recei v es from SRS t o

characterize should be considered retrievably-stored waste, regardless of when the waste was

generated. CCP believes this is appropriate because the definiti on of newly-generated waste vs.

retrievably-stored waste hinge s on approval of the CCP program co m p liance with NQA-1. CCP

16

# asked that the definition of newly-generated be predicated upon approvals for the

characterization entity, n o ting th at in the cas e of SRS, CCP does not generate any waste, so all

waste received from SRS would be considered retr ievably-stored. At SRS, CCP de fines itself as

a characterization entity and not a generation program

. EPA agreed to as sess th is app r oach; the

results of this assessm ent follow.

The newly-generated/retrievably-stored distinctio n is a DOE construct. E P A’s rule does not

identify or define newly-generated and retr ievably-stored waste, and EPA’s Com p liance

Application Review Docum e nt (CARD) Nos. 22 and 24 m e nti on this term inology only in a

lim ited sense. However, DOE specifically defines ne wly-generated and retrie vably-stored waste.

Chapter 4 of the Com p liance Recertification Ap p lication (CRA) states the following:

Waste gen e r a ted after 19 70, but befo re implemen tation o f

[ a ] CBFO certified

waste quality assurance (QA) program is refe rred to as retrievably-stored waste.

Waste generated after a site’s implemen tation of [a ] CBFO certified QA program

is defined as newly-generated.

Based on this, there is a clear m echanism for distinguishing newly-gene rated and retrievablystored waste proposed by DOE that is related to waste generation and C B FO certification of the

site generating the waste. EPA requires that entiti es involved with activities that directly im pact

quality comply with the NQA requirem e nts, whic h is one reason why CC P m u st be approved.

However, it appears that the newl y-generated/retrievably-stored distinction is keyed to DOE’s

own approval of sites and is linked to waste ge neration, not characteriza tion. Theref ore, based

upon DOE’s own documentation and EPA’s understa nding that SRS stil l has an “approved QA

program ” related to waste genera tion activ ities, th e newly-generated distin ction cannot be linked

to characterization activitie s, as this contradicts D O E’s own requirem e nts.

This distinction m eans that waste stream SRS- W027-773A-HET has both a newly-generated and

retrievably-stored com ponent. EPA’s ev aluation of ongoing process controls and

characterization activities show s that approval of both the ne wly-generated and retrievablystored com ponents of this waste stream, and others sim ilar to it, is techni cally valid. T h erefore,

EPA proposes to expand the scope of this propo sed approval to include both newly-generated

and retrievably-stored debris a nd soil waste, noting the specific exclusions stated in T i ering

Elem ent 1, below.

(5) Physical waste descriptors were evaluated.

CCP assigned the S5400 WMC to debris waste originating from the SRS laboratories in

Building 773. S5400 is defined as follows:

Waste that is at least 50% by volum e debris materials that do not meet the criteria

for assignm ent as either Inorganic ( S5100) or Organic (S5300) debris. An

example is waste that is essentially en tirely debris, but is not dominant (i.e.,

estimated to be 80% by volume or more ) in either inorganic or organic debris

materials. Another example is waste t hat is at least 50% by volume debris

materials, w ith the balance being soil (S4000) or homogeneous solids (S3000’s)

.

17

# The AK summary states that wa ste stream SRS- W027-773A-HET is comprised of a variety of

debris m a terials, with no specific m a terial per centages provided. The content of waste generated

after 1998 is controlled by pr ocesses docum ented on the OSR Form 29-90, which requires

identification of W M Ps, radionuc lides, etc. The CCP AK expe rt (AKE) indicated that CCP

perform e d a n analysis of AK data obtained af ter 1998 to determ ine whether the S5400 waste

catego r y was accurate. This analy s is showed th e SRS- W 0 27-773A-HET waste stream to be

com p rised of 82% organics and 18% inorganics [(AK7) M022]. Further, CCP personnel also

assessed W M P AK data for waste generated fr om 1986–1990 and found this waste to contain

about 78% o r ganics. CC P rejected th e use of inform ation presented in M0 22 because it

represented a “sm a ll portion” of the 773 waste stream s (i.e., 89 drum s of 1500). It is unknown

how m a ny drum s were included in the 1986–1998 data analysis. W h en interviewed, CCP site

personnel rejected assig n ing a m o re accurate WMC of S5300 (greater th an 80% organics)

because CCP represen tatives felt that SRS pr ocess/adm i nistrative contro ls had a very low

reliability w ith respec t to accura tely docum enting W M P content.

Available data rev i ewed during th e in spection sho w ed that S5 300 would be a m o re accurate

WMP assignm e nt for SRS- W 027-773A-HET than S 5400. By assigning the waste to the m o re

general waste category, the waste is alm o st ensu red of showing 100% accur acy with respect to

“m atching” the ass i gned W M C. EPA recomm e nds that accurate W M P data be acquired,

particularly since with 100% VE and RTR perfor m e d on waste, this inf o r

m ation is availab l e.

Therefore, the m i sassignm e nt of WMC, while noted, does not jeopardize W M P identif ica tion a t

this tim e . However, should the requirem e nt to perform VE or RTR be reduced in the future, the

assignm ent and dete rm ination of W M P percenta ges based on the AK rec o rd will b e imperative,

and EPA would need to review for ap propriate nes s the m o re general ass i g n m e nt becau se it

would not result in an adequate AK determ ination of W M Ps. Further, this approach invalidates

all AK accuracy calculations performed base d on WMC agreem ent between AK and NDE.

(6) The inclusion of high-leve l waste in waste stream SR S- W027-773A-HET was assessed.

The AK summary and several supporting docum e nts (e.g., P001, P006, M024, D122, D077,

C068, C040, CCP-AK-SRS-7) were reviewed to evaluate whet her high-level wastes w e re

generated in Building 773, and whether any of these wastes would be included in S R S- W 027-

773A-HET. References exam ined acknowledge that high-level waste has been generated, but

CCP rem o ved any m e ntion of the waste from th e m o st recent rev i sion (Revision 1 ) of CCPAK-7 (it was m e ntioned in the previous version, Revision 0). High-level waste is prohibited

from disposal at the W I PP, so CCP must ensure that the AK record asso ciated with any waste

for m erly identified as being high-level but now c onsidered for inclusion in this or any other

W I PP-bound waste stream must be adequately jus tified and supported. To docum ent this as an

EPA issue, we provided the following AK concer n during the inspection, wh ich did not require a

response:

Several AK referen ces ( e .g., C040) indi cate that the Savanna h River Tech nology

Center generates Waste Stream SR-S RS-W027-773A-HET (de b ris) that may

contain materials iden tified as High Level Was t e (HLW )

. An earlier revis i on of

AK-7 (SR-SRS-W027-773A-HET) included the HLW component that has since

been removed in the latest revision o f

the AK su mmary. The AK record must

include why this in forma tion was re moved from AK-7. Also, in the future, CCP

must adequately document and justify th e inclusion of any waste in AK-7

18

# previous ly o r currently id entified as being high level . [See E P A Issue Tracking

Form No SRS-CCP-AK- 05-005]

(7) The definition of waste stream was evaluated.

SRS- W 027- 773A-HET was created through com b in ation of three prev iously identified

individual w a ste stream s, as presented in the 2002 Transurani c W a ste Baseline Inventory Report

(TW B IR). All thr ee of the par e nt stream s were described as com p rising debris created by “job

control” actions performed in Building 773, with the distincti ons m a de ba sed apparently upon

chem ical content of the waste. CCP reassesse d this subdivision and elected to com b ine the

stream s because two of the stream s actually co ntained the sam e che m icals, even though one

stream identified the ch em ical in a certain m a nner, while the other waste stream did not. The

third stream was added due to the potential pres en ce of a m e tal that woul d warrant inclusion in

the sam e chem ical groupings as the other streams.

The waste stream s are also described as containi ng very large m e tal item s (e.g. several feet in

length, width, and height). These m a terial s m a y originate from decontamination and

decomm issioning (D&D) activities that m a y not be considered norm a l “job control” waste,

noting that “job control” can incl ude size reduction of larger item s, such as gloveboxes or other

sim ilar wastes generated when processes are ch anged or when equipm ent is upgraded, m odified,

etc. EPA expects CCP to carefully exam ine the definition of waste stream SRS- W027-773AHET when i t considers including large objects in the future. Using EPA Issue Tracking Form

No. SRS-AK-05, EPA expressed th e following concern that did not require a response during the

inspec tion:

AK reference D152 indicates that w a st es in SR -SRS-W027-773A-HET include

large items such as boxed wastes. This waste stream is classified as job control

waste that typically exclude s large metal items like those found in SR-SRS-W027-

773A-HET. The AK Summary (AK-7) does not yet address the boxed waste

component and CCP is encouraged to asse ss whether the boxed waste belongs in

SR-SRS-W027-773A-HET based on the similari ty of processes, physical form and

material typ e . [See EPA Issue Tracking Form No SRS-CCP- AK-05-004]

(8) The inclusion of QuickScan and invalidat ed RTR inf o rm ation in the AK r ecord was

exam ined.

Mound originally identified 53 containers in waste stream SR-SD-SOIL. SRS-CCP c onducted

RTR on 10 of these containers, but it was disc overed that the person that conducted this

characterization activity was not tr a i ned with res p ect to soil m a tr ices, so RTR results could not

be used as R T R data. However, inform ation obtained indicated that the summ ary category group

within the drum s could have b een m i sidentified, so SRS-CCP a pparently perform e d QuickScan

on all 53 containers. As a resu lt, 40 of the 53 containers were found to technically contain

“debris ” ra ther than so il, noting th at this distin ction is based on the percentage of debris content

within the container, not a vast m i sidentification of m a terial cont ent in the waste. Neverthe less,

40 of the 53 containers w e re rem oved from the SR-SD-SOIL waste strea m as a result of this

action.

19

# (9) Training was exam ined.

Training records for the AKEs and site project m a nager (SPM) were exam ined. All had

com p leted the assigned reading, and m o st had take n additional external and internal classes

pertaining to RCRA and other t echnical areas. H o wever, none appeared to have received

training specific to 40 C F R 194.8 or 194.24 requirem e nts, which are both pe rtinent to EPA’s W C

and inspection processes. Traini ng in this area is recomm ended.

(10) Sa m p le AK summary report contents we re exam ined, including load m a nagem e nt.

CCP-AK-SRS-8 and CCP-AK-SRS-7 were exam ined. By a nd large, both docum ents were well

written, easy to follow, and com p lete. The AK s u mm ary for SR-SRS- W 027-773A-HET

included load m a nagem e nt, and sufficient info rmation was provided to substantiate this

inform ation (e.g., M024, M025). Comparison of sele ct references with in for m ation in each of

the docum ents showed that the supporting refere nces were adequately reflected in the body of

each AK summary. Analytical d a ta exam ined as pa rt of the traceab ility analysis sho w ed that one

Mound soil container, MDL0506241, exhibited an NDA measurem ent less than 100 nCi/g. It is

recomm ended that CCP-AK-SRS-8 be revised to a ddress load m a nagem e nt for this w a ste stream

and other Mound waste stream s, if applicable. F u rther, it is recomm ende d that CCP exam ine

NDA-AK mem o s for both SR-SD-SOIL and SR -SRS- W 027 -773A-HET to ensure that the

radio l ogical discuss i ons in each coin cide.

(11) Managem e nt of waste generation and wa ste contents by site process controls was

exam ined.

SRS-CCP included historic proce ss controls (e.g., (AK7) P006, (AK7 ) P001) in the AK record to

dem onstrate that SRS had procedurally controll ed waste conte n t to ex clude high-level wastes

from the SR-SRS- W 027-773A-HET waste stream. Furt her, SRS uses process controls to ensure

that was t e contents are appropria tely identified, the results of which are docum e nted on the OSR

Form 29-90 that are one input to the Transuranic Waste Character ization Database. Note that

current OSR Form 29-90 do not require identificat ion of prohibited item s as a lin e item , but the

body of Manual No. 1S, Appendix A-23, which in cludes waste container for m (OSR 29-90)

instructions, does require the individuals packagi ng the waste to ensure th at the p r ohib ited item s

are not included. The inclusion of relevant process controls in the AK record appears

appropriate, particularly when th ese controls show that process contro ls were histo r ically in

place to m a nage waste.

(12) Lim itations and exclusions in the AK record were assessed.

Data lim itations are presented on the CCP-T P-005, Attachm e nt 3, “Source Docum e nt

Summ ary,” and are a good way to ensure that AK da ta are used appropriately and in context.

Data lim itations identif i e d in the Atta chm e nt 3 samples exam ined were te c hnically app r opria te

and relevant.

20

# (13) Overall p r ocedural techn i cal sufficiency and scope and ability to follow the AK WC

process for containers and wa ste stream s were ev aluated.

CCP provided eight separate AK summaries (CCP-AK-SRS, No s.1–8), from which two waste

stream s were random ly selected for review . AK Summ ary CCP-AK-SR S-7 included AK data

for waste stream SRS- W027-773A-HET that consis ted of debris waste generated through “job

control” activities in laborato ry building 773. A final W S PF for this waste stream wa s also

provided, w h ich included a com p leted Characteri zation Inform ation Summ ary (CIS). A data

traceability analysis showed that the random ly selected containe rs exhibited radiological and

physical characteristics consistent with the de scriptions presented in the A K summ ary and

WSPF. CCP also provided AK Su mmary CCP-AK-SRS-8, which in cluded AK data for waste

stream SR-MD-SOIL, consisting of soil genera ted through rem e diation and D&D work at the

Mound facility. A WSPF for this waste stream wa s also provided, including a draft CIS. A data

traceability analysis showed that the random ly selected containe rs exhibited radiological and

physical characteristics consistent with the de scriptions present in the AK summ ary and W S PF,

although one drum had less than 100 nCi/g TRU alpha waste, so the stream would require load

m a nage m e nt if this container were to be shipped to the W I PP.

(14) Defense origin of waste was exam ined.

CCP-AK-SRS-7 and CCP-AK-SRS- 8 both include Section 4.2.1, which addresses defense

determ ination. Inform ation presented in this section and derived through interview of the AKEs

indicated that while nuclides in SR-MD-SOIL m a y have both defense and nondefense origin, the

nature of the waste (i.e., rem e dia tion waste) m a kes differentiation of nuclides by origin difficult.

EPA expects DOE to determ ine the defense waste st atus for all waste intende d for all disposal at

the W I PP. EPA’s role is to ver i f y th at the was t e identified as defe nse-related is properly

characterized and com p l i es with the re gulatory lim itations at 40 CFR 194.24.

(15) AK infor m a tion pertaining to radiologi cal characteris tics of waste was ex am ined.

Radiological inform ation presented in each AK summary pertinent to SR-MD-SOIL and

SRS- W 027- 773A-HET was exam ined for adequacy a nd supportability by references and through

interview. Waste stream SR-MD-SOIL is thought to com p rise prim arily heat source 238 

# Pu (and

related daug hter produ cts), although because the wast e orig in ated from a waste line leak, it cou l d

also con t ain 239 

# Pu and other nuclides. Note that AK suggests each drum from Mound underwent

NDA prior to shipm e nt, and this inform ation w ould have been entered into the Transuranic

Waste Characterization Database (w ith data apparently transferre d to OSR For m 29-90 as well).

The AK summary inclu d ed isotop ic distributions for heat-source, weapons-grade, and plutonium

neutron sources. A review of select references supports the prem ise that 238 

# Pu will m o st lik ely

be the pr edo m inant nuclide presen t in soil, but that other nuclides m a y be present (e.g.,

(AK8)DR005, (AK8)I082, (AK8)P028, (AK8)P040 and (AK8)P054). Note that the AK

summary states that AK did not show any drum s to be less than 100nCi/g TRU alpha, but one

container measured by S R S-CCP ha d a TRU alpha concentration of less than 100nCi/g.

Radiological data for SRS- W 027-773A-HET indicates that the waste m a y c ontain any num b er of

individu al radionuclides because the waste was g e nerated prim arily throu gh research and

developm ent. SRS-CCP expects 238 

# U and 238 

# Pu to be the m o st prevalent nuclides by m a ss, but

any num ber of individual nuclides ma y be present, including several that are not TRU. Table 5-2

21

# of CCP-AK- SRS-7 shows there coul d be any of 50 different radi onuclides present in quantities

varying fro m trace to almost 100% by weight (d ep ending up on the nuclide). Further, the tab l e’s

f ootnotes cite sever a l ca veats and ad dition a l con s idera tion s with respe c t to nuclide c ontent,

including consideration of daughter products, identification of thorium

- bearing containers, etc.

Review of select references pertinent to nuclide content in this waste stream shows that the

stream m a y indeed consist of several di fferent radionuclides (e.g., (AK7)D152, (AK7)M024,

(AK7)D122, (AK7)D061, (AK7)D020 and (AK7)C003) . As required in “Contact-Handled

Transuran i c Waste Acceptance Cr ite ria f o r th e W a ste Isolation Pilo t Pla n t (CH-W A C),”

Appendix E, each drum must contain m easurable TR U isotopes, so this waste strea m will require

particula r sc rutiny in the f u ture to en sure tha t ea c h contain e r com p lies with this requ ir em ent.

Inspection Issues

Findings

The EPA inspection team did not identify any findi ngs in the areas of AK or load managem e nt

during the inspection.

Concerns

The following two concerns were identifie d, neither of which require a response:

EPA Inspec tion Issue T r acking Form, Issue No . SRS-CCP- A K-05-004 C: AK reference

D152 indicates that wastes in SR-SRS- W 027- 773A-HET include large item s , such as boxed

wastes. This waste stream is class i fied as j ob co ntrol was t e that typ i cally excludes large m e tal

item s like those found in SR-SRS- W 027-773A-HET. The AK Summary (AK-7) does not yet

address the boxed waste com ponent and CCP is en couraged to assess whether the boxed waste

belongs in S R -SRS- W 027-773A-HET based on the si m ilarity of processes, physical form and

m a terial typ e

.

EPA Inspec tion Issue T r acking Form, Issue No . SRS-CCP- A K-05-005 C: Several AK

references (e.g., C040) indicate that the Sava nnah River Technology Center generates W a ste

Stream SR- S RS- W 027- 773A-HET (debris) that m a y contain m a terials identified as High-Level

Waste (HLW ). An earlier revision of AK-7 (SR-SRS- W 0 27 -773A-HET) included the HLW

com ponent that has since been rem oved in th e latest revision of the AK s u mm ary. The AK

record m u st include why this inform ation was removed from AK-7. Also, in the future, CCP

must adequately docum ent and justif y the inclusi on of any waste in AK-7 pr eviously or currently

identified as being high-level.

Resolution of AK Issues

Neither Issue No.SRS-CCP- AK-05-005 nor SRS-CCP-AK-05-004 required a written response

fro m C C P.

Proposed Baseline Approval

The AK and load m a nagem e nt system s evaluated during this baseline inspection are approved

for CH retrievably-stored and newly- generated debris and soil waste.

22

# Proposed AK Tiers

Based on the inspection and the results discu ssed above, EPA proposes to assign the following

tie rs:

Tier 1 AK changes that will r e quir e EPA review and approva l prio r to implem entatio n and

apply to any new waste category not evaluate d d u ring th e ba selin e inspe c tion includ e the

following:

• Categories of waste not approved und er this baseline (e.g., solids)

• Any waste identified outside of the wa ste profiles included in the 2002 T W BIR

• Newly-generated soil or debr is waste stream s created th rough rem e diation or D&D

activ ities

Tier 1 chang e s will b e re ported and d o cum e ntation will be su bm itted whe n SRS-CCP is ready

for EPA review. Upon initial review , EPA w ill infor m SRS-CCP and CBFO whethe r a site

inspection is necessary. EPA m a y re quest add itional information, choose to conduct a desktop

review, and/or confer with SRS-CCP AK personnel. Upon AK evaluation with or without site

inspection, EPA will iss u e a decisio n. Only upon receiving EPA written approval m a y SRS-CCP

dispose of the new waste at the W I PP.

Tier 2 AK changes that do not require EPA approval pr ior to im plem entation but requ ire

reporting an d subm itting docum entation discus sing changes by SRS-CCP include th e f o llowing:

• Changes m a de to AK procedure( s) that require CBFO appr oval

• WSPFs, including updates or additions to W S PFs for waste stream s within approved

waste categ o ries

• Changes in load m a nage m e nt st atus of approved waste stream s

• Revisions to AK-NDA Mem o s for Waste Stream s SR-S D- SOIL and W027-773A-HET

Every thr ee months f o llowing EPA approval, SRS-CCP will provide EP A with inf o rm ation

concern i ng T2 changes. EPA will evaluate thes e changes an d communicate with CB FO and

SRS-CCP as to whether the changes raise any co ncerns and require an SR S-CCP response, or

whether SRS-CCP can continue to implem e nt the changes.

8.2 Nondestructive Assay

EPA inspected two NDA system s to be used by SRS-CCP to characterize TRU wastes, the MCS

IQ3 gamma system and the BII IPAN/GEA system . Both system s had been evaluated and

approved by EPA for characterizi ng TRU wastes at SRS previousl y. As part of the inspection,

EPA reviewed the following elem ents of the NDA process:

• Capability of the m easurem ent hardware and software to perform the required analyses

f o r the rad i o nuclide s and wastes of in teres t

23

# • Technical adequacy of the NDA doc u m ents, procedures, and controls

• Knowledge and understanding of the pe rsonnel involved in the NDA prog ram

The checklis t s in Attach m e nts A.4 and A.5 identify the specific pieces of objective ev idence that

were exam ined and used to com p lete the technical assessm e n t for each of the two NDA system s

with the ins p ection ’ s sc ope.

Documents Review ed

The list of docum ents provided below, in conjun ction with those listed in the NDA checklists,

includes all docum ents related to NDA that were evaluated to support the assessm ent of the MCS

IQ3 at SRS-CCP. The docum e nts that pertain to both the IQ3 and IPAN/GEA NDA s y stem s in

general are provided following the IQ3 list.

MCS IQ3 System

• CPP-TP-047, CCP IQ3 Ga mm a Sca nner Operation, Revision 5

• CCP-TP-048, Mobile IQ3 System Data Revi ewing, Validating and Reporting Procedure,

Revision 7

• MCS-SRS-NDA-0504, Calibration and Verificati on Report for the Range Extension of

the MCS IQ3 at the Savannah River Site, Revision 0, June 11, 2004.

• MCS-SRS-NDA-0203, Calibration and Verifica tion Report for the MCS IQ3 at the

Savannah River Site, Revision 3, March 22, 2005

• MCS-SRS-NDA-0203, Calibration and Verifica tion Report for the MCS IQ3 at the

Savannah River Site, Revision 4, Septem ber 29, 2005

• MCS-SRS-NDA-TMU- 0203, Total Measurem ent Un certainty for the MCS IQ3 at the

Savannah River Site, Revision 1, June 10, 2004

• MCS-SRS-NDA-TMU- 2003, Total Measurem ent Un certainty for the MCS IQ3 at the

Savannah River Site, Revision 1, June 10, 2004

IPAN/GEA System

• CCP-TP-02 4, CCP Mob ile IPAN/GEA Operatin g and Data Generation Level Review,

Revision 20

• CCP-TP-02 5, CCP Mob ile IPAN/GEA Expert Analysis, Revision 10

• CCP-TP-026, CCP Mobile IPAN/ GEA Calibration, Revision 6

24

# • BII-5104-Q AO-001, BII Mobile Assay System Quality Assurance Objective (QAO)

Com p liance, Revision 7, January 2005

• BII-5104-T M U-001, Total Measurem ent Uncertain ty for the BNFL Instrum e nts Mobile

Assay System, Revision 1, August 2001

• BII-5104-C T R-001, Mobile Assay S y stem Calib ration Test Report for SRS Operations,

Revision 3, August 2001

Documents Related to the IQ3 and IPAN/GEA NDA Systems

• CCP-AK-SRS-7, Central Characterization Project Acceptable Knowledge Summ ary

Report for Savannah River Site Building 773-A, Transuranic Debris W a ste StreamSRSRS- W 027- 773A-HET, Revision 1, Decem ber 3, 2004

• CCP-AK-SRS-8, Central Characterization Project Acceptable Knowledge Summ ary

Report for Mound Site Transuranic Waste Stor ed at Savannah River Site Waste Stream s

SR-MD-HE T, SR-MD-SOIL, SR- M D-HOM-A , SR-MD-HOM-B, Re vision 2, Septem ber

23, 2005

• CCP-AK-SRS-6, Central Characterization Project Acceptable Knowledge Summ ary

Report for Savannah River Site Building 235- F Transuranic Debris W a ste StreamSRW027-235F-HET, Revision 2

Batch Data Reports and Waste Containers Review ed

During the course of this insp ection, NDA Batch Data Reports (B DRs) were evaluated for both

system s. The specific B D Rs that were evaluate d are listed below by th eir SRS-CCP identif ie r

followed by the system on which each was generated.

• SRNDA683 – IQ3

• SRNDA852 – IQ3

• SRNDA788 – IQ3

• SRNDA731 – IQ3

• SRNDA715 – IQ3

• SRS-NDA-050412 – IPAN/GEA

• SRS-NDA-050721 – IPAN/GEA

• SRS-NDA-050825 – IPAN/GEA

• SRS-NDA-050912 – IPAN/GEA

Radioassay Data Sheets for indivi dual waste containe rs (drum s ) from th e BDRs listed above

were chosen at random and evaluated in detail, as delineated in the check lists in Attachm e nts A4 and A-5. The num ber s of the containers evaluate d are listed below, preceded by the num b er of

the BDR from which they origin ated and the sys t em on which each was generated:

• SRNDA683 – IQ3: HBL 03103, SR513885, SR5608448, SR5608399 and SR5608415

25

# • SRS-NDA-050721 – IPAN/GEA: SR501764, SR518613, SR519719 and SR5101102

• SRS-NDA-050412 – IPAN/GEA: SR526637, SR173563, SR530020 and SR5546347

Waste Characteriz a tion Elem ent Description : MCS IQ3

The MCS IQ3 NDA system is housed in a trailer located at TRU Pad 4 of E-Area of the Solid

Waste Managem e nt Area of SRS. This system had been evaluated previously by EPA on several

occasions, most recen tly EPA Inspection No.CCP-SRS-09-04.24, EPA Docket A-98-49, II-A4-

50, and had been approved for W I PP assays prio r to this inspection. The IQ3 had not been

relocated since EPA certified it initially al though there had been som e system changes,

specif i ca lly rela tive to th e detec t ors ’ conf iguratio ns that EPA had evaluated and approved for use

in characterizing TRU wastes for W I PP.

The IQ3 is a m u lti-de tec t or gamm a detec tion sys t em consistin g of the f o llowing:

• Three (3 ) Segm ented Germ anium (SeGe) coaxial detectors fo r direct m easurem ent of

radionuclides

• Three (3) Low Energy Germ aniu m (LEGe) de tec t ors f o r iso t o p ic determ inations

• Separate electronics and software to support each set of gamma detectors

The system runs Canberra’s Gamm a W a ste Assay System (GWAS) software and is currently

configured to quantify 238 

# Pu, 239 

# Pu, 233 

# U, 235 

# U 5



# , 23 8 

# U, 241 

# Am and 137 

# Cs by direct m easurem ent as

well as other gamma e m i tting radionuclides cont ained in a variety of waste m a trices. The

rem a ining W I PP-tracked radionuclides 234 

# U, 240 

# Pu and 242 

# Pu are quantified us ing computational

techniques based on known or esta blished relationships with other m e asured quantities. Typical

SRS wastes are predom i n antly W eapons Grade Pl utonium (WG Pu) or Heat Source Plutonium

(HS Pu), i.e., 239 

# Pu or 238 

# Pu, respectively. In so m e cases waste drum s will con t ain a m i xture of

both. W h en the activity of 238 

# Pu dom inates, radionuclides including 238 

# Pu, 239 

# Pu, 241 

# Am

, 233 

# U,

235 

# U, 238 

# U, 137 

# Cs, and 237 

# Np are quan tified by direct m easurem ent. For waste con t ain e rs where

the ac tivity of 239 

# Pu dom inates, values for radionuclides such as 238 

# Pu, 24 0 

# Pu, and 242 

# Pu are

genera lly ob tained f r om m easured isotopic rati os that wer e b a sed on the Multi Group Analysis

(MGA) software using LeGe data

Technical Evaluation

(1) The design of the IQ3 was assessed.

The IQ3 system assays the gamm a-r a y em itting nuclide content of a 55-g a llon (208-liter) d r um

by using 3 three high purity germ anium (Ge) gamma -ray detectors arran g ed in a ve rtical line o r

“stack ” that effectively d e lineates three horizontal segm ents; the entire height of the drum is

viewed by the three detectors. Shielded 133 

# Ba transm ission sources ar e located 180o opposite the

SeGe detectors such th at gamma rays from each source pass through the d r um axis to its

corresponding SeGe detector. Th is allows the determ ination of ga mm a r a diation absorption by

the drum m a trix in the h o rizon t al p l a n e of the s ource. During the assay, the drum is rotated on a

turntable to provide an average of radial in-homogeneities.

5 235 

# U i s not o n e o f t h e 1 0 WI P P t r ac ked ra di o nucl i d e s but i s qua nt i f i e d beca use i t c ont ri b u t e s t o a

cont ai ne r’ s Fi s s i l e Gram Equi val e nt (F GE) a n d i t

i s use d i n con j unct i o n wi t h al 238 

# U i n t h e de ri vat i o n of 23 4 

# U.

26

# Two m easurem ent m e thodologies are em ployed in MCS IQ3 system ; segm ented analysis and

summed spectrum m u lticurve dens ity m ode analysis. The se gm ented ana l ysis app l ies a

transm ission source co rrection to account fo r gamma-ray attenuation in each segm ent, an

approach that applies to a wide variety of waste types at SRS. However for routine assays, a

transm ission-corrected system cannot com p ensa te for increasing m a trix densities beyond a

certain point. Therefore, in addition to th e transmission-correct ed com ponent of the

m easurem ent, the sys t em perf orm s analyses in the summed spectrum m u lticurve d e nsity m ode

for denser materials. This analysis mode appl ies to waste drum s with bulk densities up to a

m a xi m u m of 2.1g/cm 3 

# . The system had previously been approved to a m a xim u m waste density

of 1.7 g/cm 3 

# , which was changed to the current lim it in September 2005 based on the addition of

calibration data from a concrete m a trix drum with a density of 2 g/cm 3 

# to the m u lti-de nsity

calib ration f iles. The cu rrent configuration of th e IQ3 that in corporates these two op erational

modes is adequate to assay the wa ste mat r i c es obser v ed at SRS.

(2) System calibration of the IQ3 had been performed and confirm e d, and docum e nted, as

required.

Several types of calibration were perform e d on th e IQ3, all of which are described and detailed

in CCP-TP-046. These include calibrations for en ergy versus channel, efficiency, transm ission

and reference peak, all of which are discussed b e low. All calibra tion- rela ted ac tivities are

docum ented in Verification Report for the Calibration and MCS IQ3 at the Savannah River Site,

MCS-SRS-NDA-0203, Revisions 3 and 4. Only Revision 4 of this document was reviewed

specifically in conjunction with th is inspection, b ecause it reflected ch ang e s to th e IQ3 since the

last EPA inspection, specifically the following two m a jor changes:

• Extension of the m a ss calibration range for 238 

# Pu and 239 

# Pu on March 22, 2005

• Extension of the density calibration range for 238 

# Pu and 239 

# Pu in Summ ed Spectrum

Mode on Septem ber 27, 2005

As a result o f these chan ges, the docum ent was modified, most notably as follows: by adding

sections to p r esent n e w m easurem ent data to support the proposed changes; revising the

Calibration Qualification Summ ar y; and, m a king m i nor editoria l changes and corrections of

Tables, as appropriate. However, som e of the text in this report did not change between

revisions.

The calibration of the IQ3 in th e extended range mode using atte nuator caps is docum ented in

Calibration and Verification Report for the R ange Extension of th e MCS IQ3 at SRS , MCS-SRSNDA-0504, Revision 0. The extended range m o d e calibration was evaluated by EPA d u ring

EPA Inspection No. EPA-CCP-SRS-09.04-24 conduc ted in S e ptem ber 2004, and subsequently

approved. No changes relative to this operational m ode were disclosed by SRS-CCP and none

were noted by the EPA inspection team during this inspection.

Energy Calibration: Energy calibration for the S e Ge detectors was perform e d on February 17,

2003, using the 241 

# Am / 152 

# Eu gamm a m i xed ga mm a line sources described below. The gain and

offset for these detectors were set to nom i na lly 0.500 keV/Ch and 0.0 keV, respectively. The

efficiency calibration was perform e d at SRS in 2003 with a set of six (6) NIST-traceable

27

# 241 

# Am / 152 

# Eu gamma m i xed gamm a li ne sources from Nort h Am erican Scientific Inc. The sources

were placed in 55-gallon drum s that contained m a trix m a terials with densities ranging from

0.015 to 1.69 g/cm 3 

# . The certificates for these sources were exam ined during the inspection.

The energies of the 241 

# Am / 152 

# Eu m i xture are appropriate in th at they cover gamm a e missions

from 59.5 to 1408 keV, which brackets the range of ga mm a e n ergies of interest in SR S TRU

wastes.

Efficiency Calib ration: The efficiency calibratio n of record for this instrum e nt is based on the

data collected by SRS on January 22, 2003, and wa s approved for use and installed on the IQ3 on

January 23, 2003. The efficiency cal ibration technique is consistent with ASTM Standard Test

Method C1133, which form erly described a m a ss ve rsus count rate calibration only. Another

docum ent was needed to provide the com p lete technical basis for th e contention that the

efficiency calibration method is equivalent to the m a ss ve rsus count rate calibration 6 

# . However,

ASTM Standard Test Method C1133 was recen tly re v i sed an d now states explicitly th at the

efficiency calibration method is equivalent to a m a ss calibration. 7



# The efficiency calibration was conducte d with the six (6 ) NIST-traceable 241 

# Am / 152 

# Eu gamma

m i xed ga mm a line sources from North Am erican Scientif ic Inc. desc ribe d in this sec t ion

previously. The drum s were m easured and suffici ent counts were collected to perm it 1% to 2%

statistical precis i on for the m a jor 241 

# Am and 152 

# Eu peaks. Photon em issions at the following

energies were used: 59.5 keV, 121.8 keV, 244.7 keV, 344.3 keV, 411.1 keV, 444.0 keV, 778.9

keV, 867.3 keV, 964.1 keV, 1085.9 keV, 1112.1 keV and 1408.0 keV. MCS-SRS-NDA-0203

contain s plo t s of the efficiency calib ration for ea ch of the three segm ents, the Summ e d Spectrum

calibration in Appendix 5 and a full effici ency calibration report in Appendix 6.

Extension of the density range for the Summ ed Spectrum m o de that was perform e d in Septem ber

2005 used a set of six (6) NIST-traceable 241 

# Am / 152 

# Eu m i xed gamma line sources from North

Am erican Scientific Inc. sim ilar to those descri bed above. Different sources were used for this

activ ity be ca use the or iginal s ources had been m o ved to a diffe rent SRS area and were not

available. T h e certificates for these sources were exam ined as part of this inspection. These

sources con t ain 137 

# Cs in addition to 241 

# Am and 152 

# Eu that were present in the orig inal g a mma

sources, but the gamm a c ontribution f r om 137 

# Cs was not used in order to m a ke it com p a tible with

the 2003 calibration. An additional 55-gallon drum with concrete m a trix was added to the set of

four calibration drum s to provide a density range of 0.015 to 2.1 g/cm 3 

# . The data collected from

these assays were converted to calibration para meters by the GWAS soft ware and added to the

previous density parameters to yield a Summ ed Spectrum calibration that includes data from

foa m , softboard, hardboard, sand and concrete m a trices. This covers a range of m a trix densities

from 0.015 to 2.1 g/cm 3 

# . The parameters from the 2003 cal ibration are used for the Summ ed

Spectrum mode except f o r those that were determ ined using the concrete drum . The calibration

param e ters that were determ ined for the 2003 cali bration of the Segm ent e d Analysis mode were

not changed.

6 

# MCS Letter C O R-EXT-01 -00 1 7

, J. G. Fleissn e r to Bert Rollen

, Sub ject: Efficien cy versus Ma ss

C

a l i b rat i o n f o r

G a m m a -R ay Base d C o u n t i n g Met ho ds

, De ce m b er 5, 2001.

7 

# St a n d a r

d

Test Met ho d f o r N o nde st ruct i ve As say of Speci al N u cl ear Mat e r i al i n L o w de ns i t y Scra p a n d

Waste by Segmented Pas s ive Gamma-R a y Scanning

, C 11 3 3

- 0 3, a p pr ove d Jul y 10

, 20 0 3

.

28

# Ref e rence Peak Calib ration: The in itia l ref e re nce peak calibration was perform e d on J a nuary 9,

2003, using a pulser to provide dead tim e corrections for the SeGe detectors. The reference peak

calibration is perform e d without a w a ste drum a nd uses a nom i nal pulser setting of 100 c/s for

the segm ents and 300 c/s for the Summed spectrum

.

Transm ission Source Calibration: T h e 133 

# Ba transm ission sources located 180 degrees opposite

the SeGe detectors are u s ed to prov id e a correct io n f o r the waste m a trix d e nsity of the segm ent

directly in front of the detector. The tran sm ission calibration report shows the nuclide being

used, the transm ission peak energies used, peak area coun ts, uncertainties

, and half-life. The

initial transm ission calibration was perform e d on January 9, 2003.

Calibration Confir m a tion: The original ener gy calibration from 2003 wa s confirm e d by m a king

six (6) replicate m easurem ents for each of the three m a ss loadings of the com bustibles drum

. Based on the criteria in DOE/ W IPP- 02-3122, A ppendix A, a precision of 14% m u st be

dem onstrated; accu racy is reported as percen t rec overy (%R) and m u st be in the range of 70% to

130%. Perform a nce goals for precision and accur acy were m e t for loadings in all cases, as

docum ented in MCS-SRS-NDA-020 3, Revision 4.

The extension of the 239 

# Pu range upper lim it to 2.3 tim es the original lim it was applied to the

238 

# Pu range to provide a new upper lim it of 2.3 g 238 

# Pu. SRS- CCP personnel st ated that this was

acceptable b ecause GWAS uses the sam e analysis m e thod for all rad i onu clides and absolute

detector efficiency as a function of energy is used along with peak count rate, energy and

transition probability to quantify each isotope. E ssentially, this m eans that the IQ3 analysis

yields v a lid results when ever certain param e ters s u ch as dead tim e and transm ission are

acceptable. Since the cal ibration con f irm a tion of 239 

# Pu was acceptab l e, the range of 238 

# Pu range

was extended by the sam e factor to derive a new upper lim it of 2.3 g 238 

# Pu. This was not

confirm e d by m easurement becau se certified 238 

# Pu sources of sufficient strength were not

available.

Calibra tion Verif i cation s : The ca lib ration f o r IQ 3 had been verified several tim e s due to

perform a nce indicators, detector replacem ent, background failures and software upgrades.

Records that docum ented the execution of the ve rification and the m eeting of the perform a nce

goal required by DOE/ W I PP-02-3122, Appendix A we re exam ined for verifications that

occurred on the following dates: January 31, 2005; June 30, 2005, August 26, 2005 and October

18, 2005. All verifications were acceptable.

(3) The calibrated range and operational range of the IQ3 had been established and

docum ented.

In the case of the IQ3 the calibrated range and the operational range are synonym ous. The

instrum e nt’s range is expressed in MCS-SRS-NDA-0203, Revision 4 as 0 to 2.3 g 238 

# Pu

(administrative) and 0 to 35 g 239 

# Pu (administra t ive) although the IQ3 is not m a ss-calibrated in

the strict sense. Conceptually, the assay of any photon em ission within the bounds of the energy

and efficien cy calibratio ns (discu ssed below) th at is acceptab l e for the sy stem ’s perform a nce

param e ters, such as dead tim e, FWHM, etc., shou ld be valid, irrespectiv e of nuclear m a terial

m a ss. That the range is stated in terms of m a ss is more of a c onvention due in part to the fact

that there are other p e rtinent, m a ss-related lim its, e.g., adm i nistrative and accountab ility lim its,

as well as functional aspects, su ch as system dead tim e and pile up. The IQ3’s true operating

29

# range for quantitative operation is best expr essed in term s of t h e range of the energy and

efficiency calibrations, i.e., from 59 keV to 1408 ke V. The system ’s range was m odi fied several

tim es, and the EPA inspection team evaluated th e techn i cal b a sis for each m odificatio n and its

docum entation. Each range m odific a tion and its accom p anying docum entation were found to be

acceptable, and there were no issu es relative to th is. The rang e m odifications are sum m a rized

below.

In June 2004 the system’s opera tional range was extended to 7 g 238 

# Pu and 211 g 239 

# Pu by adding

a second calibration using atte nuator caps as docum ented in MCS-SRS-NDA-0504. During data

acquisition in support of the new calibration, it w a s observed that the ad ministrative range in

effect for the orig inal calibration cou l d also be extended. A calibration confirm a tion was

perform e d to provide a dem onstration of the te chnical basis for this range extension using a

com bustibles m a trix with 23.7 g 239 

# Pu.

In January 2005 the upper lim its of the system ’s calibration range was extended from 1 to 2.3 g

238 

# Pu and from 15 to 35 g 239 

# Pu, based on perform a nce testing and a calibration confirm a tion to

provide technical justification fo r the extension. No change was m a de to the system ’s original

calibration that had been perform e d in 2003. This range extension does not use attenuators and

does not affect the system ’s m i nim u m detectab le activ ity.

In Septem ber 2005, SCR-CCP personnel identifie d a need to assay drum s containing soil

contam inated with HS Pu, i.e., high 238 

# Pu fraction wastes. The system ’s original calibration

perform e d in January 2003 was valid to a m a xi mum density of 1.7 g/cm 3 

# which was less than the

2.1 g/cm 3 

# density exp ected f o r som e of the soil d r um s awaitin g assay. This range ex te nsion was

perform e d by incorporating new m e a s urem ent data from a concrete m a trix drum with a density

of 2 g/cm 3 

# to the m u lti- density calib ration f iles. Th is change did not af f ect the Segm ented

Analysis or the Summ ed Spectrum ca librations for densities below 1.7 g/cm 3 

# and the o r igin al

January 200 3 calib ration param e ters f o r the Segm ented Analysis the Su mmed Spectrum densitie s

were unchan g ed. The ne w calibr a tio n results f r o m the concr e te drum were added to the m u ltidensity calibration param e ter set and a calibra tion verif i ca tion of the Summ ed Spectru m

calibration was performed using softboard, sa nd, and concrete m a trices. A calibration

confirm a tion of both the Segm ented and th e Summ ed Spectru m calibratio n m odes was

perform e d using only 239 

# Pu standards at the low and hi gh ends of the calibration range.

(4) The tota l m e asurem ent uncertainty ( T MU) for assays perform e d on the IQ3 had been

determ ined and docum e n ted.

The TMU for the IQ3 system is docum ented in MCS-SRS-NDA-TMU-2003, Total Measurem ent

Uncertainty for the MCS IQ3 at the S a vanna h River Site, Revision 1, June 10, 2004. This

docum ent includes contributions from counti ng statistics, calibration, isotopic ratio

determ inatio n, m a trix in hom ogene ity, source self-absorption, sour ce distribution and the effects

of attenuato r caps. The recent ch ang e in the upp er lim it of the system ’s density range to

2.1 g/cm 3 

# was not a tech nical concern since this ch ange was based on previous work perform e d

by MCS that had assessed the effects on the system ’s TMU up to a m a ximum density of

2.5 g/cm 3 

# . The determ ination and docum e ntation of TMU for the IQ3 w e re acceptab l e.

Table 1 below shows an exam ple of t h e typica l T M U values f o r thre e was t e m a trices that

repres ent a range of densities that is acceptab l e for routine use w ith the IQ3. The value s used are

30

# based on the waste container having an HS Pu c ontent greater than approxim ately 0.05 gram of

238 

# Pu or a WG Pu content greater than approxim a tely1 gram of 239 

# Pu. The uncertainties are

propagated as the square root of the sum of the squares and all individual uncertainties are shown

as 1-sigm a values. The TMU in the bottom row of the table is expressed as a 1.96-sigm a li m it

and uncertainties are rep o rted as percentages of th e assay valu e.

Table 1. TMU Value s for a Range of Typical Waste Densities

Error Source Ma trix

Ma ss

Densit y Steel

( 100 kg )

(0 .4 8 g/ cc) Grap hite

(5 0 k g )

(0 .2 4 g/ cc) Com bus tibles

(2 5 k g )

(0.12 g/cc)

C o u n t i n g St at i s t i c s 1. 4% 1. 4% 1. 4%

M a t r i x I n hom ogenei t y 12 % 12 % 12 %

So urce Di st ri b u t i o n 24 % 16 % 11 %

Calib ratio n 4 % 4 % 4 %

TM U at 1. 96 si gm a 53 % 40 % 33 %



# (5) The Lower Lim it of Det ection (LLD) of the IQ3 had been determ ined and docum ented.

The LLD for each NDA system m u st be dete rm ined and docum ented. Additionally, N DA

system s perform i ng TRU/Non TRU waste discri m i nation m u st have an L L D of less than

100nCi/g and m u st include contributions of site-specific environm ental background and

contain e r-sp ecific in terferences, as ap plicab le. In this con t ext the LLD is d e f i ned as tha t leve l of

radioactivity, which, if present, yields a m easured value gr ea ter than the critica l lim it with 95%

probability, where the critical leve l is defined as that value which m easurem ents of bac kground

will exc eed with a 5% p r obability.

The LLD for the IQ3 system was de term ined by m a king 6 replicate assays of a com b ustibles

m a trix drum without added radioactivity, i.e., ra dioactive sources were not present in the drum

, for the purpose of determ ining the system ’s m i nim u m detectable ac tiv ity (MDA). These

activ ities we re used to ca lcula t e th e m i nim u m de tectable concentration (MDC) values based on

the nom inal weight of a com bustible drum , 54.4 kg. The LLD and MDC values are calculated

directly by the GW AS software using the Cu rrie for m ula as recomm ende d by the DOE/W IPP02-3122, Appendix A. The system ’s actual capabili ty to achieve a particular MDC can be

estim ated from these m e asurem ents. The data in Tables 2 and 3 below rep r esent the 239 

# Pu MDA

and MDC values that w e re obtained for the combustibles drum using the segm ented assay

protoco l and the m u lti-cu rve density ( s ummed spectrum ) m o de, respe c tiv e l y, both bas e d on a

drum weight of 54.4 kg.

31

# Table 2. LLD/MDC Segmented Analysis Results

Ma trix Onl y Drum With ou t R a di oa ctive Source s

Run # 239 

# Pu LLD ( μ Ci) 239 

# Pu LLD (mg ) 239 

# Pu M D C (n Ci/g)

1 1 2 7 2. 0 5 2. 3 3

2 1 0 6 1. 7 1 1. 9 5

3 1 0 2 1. 6 4 1. 8 8

4 1 0 2 1. 6 4 1. 8 8

5 1 0 2 1. 6 4 1. 8 8

6 1 2 3 1. 9 8 2. 2 6

Ave r a g e 1 1 0 1. 7 8 2. 0 3



# These resu lts for the seg m ented m o de represent a best cas e sc enario s i nce the m a trix attenuation

is not taken into account. For an actual waste dr um where the nuclear m a terial content is treated

as unknown prospectively, the MDC and MDA determ ined from the segmented results m u st be

multiplied b y the ave r ag e m a trix cor r ection f act o r dete rm ined f r om the average trans m ission

through the drum . For e x am ple, this com bustible drum had an average transm ission correction

factor of approxim a tely 1.75 at the 414 keV energy of 239 

# Pu. This produces an MDA and MDC

value of 3.1 mg and 3.6 nCi/g, respectively, for this drum . The data in Table 3 below represent

the 239 

# Pu MDA and MDC values that were obtai ned for the com bustibles drum using the

summed spectrum analysis m ode based on a drum weight of 54.4 kg.

Table 3. LLD/MDC Summed Spectrum A n alysis Results

Ma trix Onl y Drum With ou t R a di oa ctive Source s

Run # 239 

# Pu LLD ( μ Ci) 239 

# Pu LLD (mg ) 239 

# Pu M D C (n Ci/g)

1 2 8 4 4. 5 8 5. 2 2

2 2 5 5 4. 1 1 4. 6 9

3 2 4 0 3. 8 7 4. 4 1

4 2 5 1 4. 0 5 4. 6 1

5 2 5 4 4. 0 9 4. 6 7

6 2 9 2 4. 7 1 5. 3 7

Ave r a g e 2 6 3 4. 2 3 4. 8 3



# The system ’s ability to discrim i nate at or below the 100 nCi/g criterion was adequately

docum ented for both ass a y m odes and the LLD values were technically acceptab l e an d

appropriately docum ent e d.

(6) Replicate testing of the IQ 3 was perform e d and evaluated.

Replicate testing is perf orm e d in accord ance with the p r otocol described in EPA Replicate

Testing for WIPP Nondestruc tive Assay (NDA) Systems , Rev. 2, June 2002. The purpose of the

replicate testing performed as part of this in spection was to provide EPA with an independent

m eans to verify that the MCS IQ3 can provi de consistent, reproducible results for the

determ inatio n of the quantity of 10 W I PP-track ed radionu clides ( 241 

# Am

, 137 

# Cs, 238 

# Pu, 239 

# Pu,

240 

# Pu, 242 

# Pu, 90 

# Sr, 233 

# U, 234 

# U, and 238 

# U) and the TR U alpha activity concentration. This is

32

# accom p lished by reassay i ng drum s that were p r ev iously ch aracterized on the sam e system or

instrum e nt in order to d e monstrate th e f o llowing:

• The instrument produces results consistent with the reported TMU by comparing the

sam p le standard deviation for a number of replicate m easurem ents taken over several

hours or days to the reported TMU.

• The instrument provides reproducible results over longer periods of tim e, such as weeks

or m onths, by com p aring the results of the replicate m easurement( s ) to the origin al

reported values.

As with all s t atistical eva l uations, the r e ar e lim ita tions inherent in this protocol. The value or

usefulness of the results with resp ect to the two objectives stated above depends in large part to

the degree to which the conditions encountered are consistent with th e assum p tions upon which

the statistical tes t s are predicated. Our experien ce to date has indicate d that the containers

chosen at random do not always provide inform a tion best suited for th e ap plication of these

statistical protocols. For exam ple:

• An NDA system m a y ha ve been recalibrated in th e tim e perio d between th e orig inal

assay and the reassay perform e d during an inspection and the new calibration m a y have

different values for som e of the calibration algorithm ’s term s

• The containers chosen at random for repli cate analysis m a y lack sufficient nuclear

m a terial content to provide useable data f

o r all th e W I PP-tr acked radionuclides

• High precision for the five replicate assays m a y yield an average value that differs

slightly from the original assay value but pr oduces results that the statistical analysis

i ndi cat e s ar e Significant or Highly Significant . H o wever, these differences m a y be s m all

variations that are inhe re nt in th e sta t istical p r otocols and do not indicate true

m easure m ent trends or problem s

• Since som e radionuclides are quantif ied base d on the m e asurem ent of a si ngle other

radionuclide, i.e., values for 238 

# Pu and 240 

# Pu are derived by applying an isotopic ratio to a

m easured 239 

# Pu value, a Significant or Highly Significant ind i cator f o r the single

m easured entity will be r e f l ected in th e other two, indica ting a larg er pote n tia l

m easure m ent trend or problem than m a y exist

It is im portant to keep these in m i nd when evaluating replicate data and to realize that Significant

or Highly Significant results m a y not in fact be repr esentative of m easurem ent issues.

As part of the inspection to certify the MCS IQ3, EPA requested that SRS-CCP reassay six

drum s that EPA random l y selected from a list of drum s previously assayed on the IQ3. Drum

Nos. MDL0506073, MDL0506146, MDL0506241, SR123477, SR546270 and SR611807 were

reassayed five tim es, for a total of six (6) valu es, and the results of the five reassays were

com p ared to the original assay data. Two statistical tests, a chi-squared ( χ 2 

# ) test and a t test, were

perform e d. Data and results of the statistical analys is are included in Attachm e nts B.7 through

B.18 and are discussed in detail below. There we re no issues relative to replicate testing for the

IQ3 system at SRS-CCP.

33

# Container N o s. MDL0506073, MDL0506146, MDL 0506241 contained essentially only 238 

# Pu.

The χ 2 

# test for all three containers sh owed that within the s t atistical lim its of the test the observed

varian ces in the rep licate m easurem ents are less th an or equal to the reported uncertainties. The t

test for Container Nos. MDL0506073 and MD L0506146 did not show any statistically

significan t d i fferences b e tween the o r igin al m easurem ent assay values an d the averag e of the

five replicate m easure m ents fo r the activities of a ll reported radionuclides and the TR U Alpha

Activity Concentration. The t test results for Contai ner No. MDL0506241 showed a Significant

flag for the plutonium radionuclides m easured ( 238 

# Pu and 242 

# Pu) but not for 241 

# Am and this is

reflected in the TRU Alpha Activity Concentration that also showed a Significant flag. The five

replicates for 238 

# Pu determ ination are tightly grouped and all five valu es are greater than the

original m easurem ent, although the m a gn itude of the difference is sm all.

Container N o s. SR123477 and SR546270 contained predom inantly 239 

# Pu with sm all amounts of

238 

# Pu, 240 

# Pu, 242 

# Pu and 241 

# Am , and m o re closely resem b led the profile of WG Pu. The χ 2 

# tes t f o r

both containers showed that the observed variance s in the replicate m e asurem ents are less than o r

equal to the reported unc erta inties within th e sta t istic al lim its of the test. The t test for SR123477

showed a Highly Significant differen ces between the original m easure m ent assay values and the

average of the five replicate m easurem ents for 240 

# Pu, 242 

# Pu and TRU Alp h a Activity

Concentration. The five replicates for 240 

# Pu determ ination are tightly grouped and all five values

are greater than the original m easurem ent. The de viations in the replicate data suggest that assay

results m a y vary m o re over long periods relative to shorter tim e periods. W h ile this is not

entirely unexpected due to fluc tuations in environm ental bac kgrounds, the observed deviations

that are greater than the reported TM U also s ugg est th at th e TMU for these analys es m a y be

som e what underestim ated. The t test for SR546270 showed no statistically significant

differences between the origin al m easurem ent assa y values and the average of the five replicate

m easure m ents for all individual radionuclides but did show a Highly Significant di fference for

TRU Alpha Activity Concentration. The exact reason for this flag is not clear.

Container N o. SR611807 contained predom inantly 238 

# Pu as well as sm all am ounts of 239 

# Pu, 242 

# Pu

and 241 

# Am . The χ 2 

# test for this container showed that the observed variances in the replicate

m easurem ents are less th an or equal to the repo rt e d uncertainties within the statistica l lim its of

the te st. Th e t te st f o r th is cont ainer showed no statistically si gnificant d i fferences between the

origin al m easurem ent assay values and the av erage of the five replicate m easure m ents.

Waste Characteriz a tion Elemen t Description: IPAN System

The IPAN-GEA NDA s y stem is housed in a trailer located at TRU Pad 4 of E-Area of the Solid

Waste Managem e nt Area of SRS adj acent to the MCS IQ3 described p r ev iously. This system

had been ev aluated prev iously by EP A on seve ral occasions, most recen tly EPA Inspection

No.CCP-SRS-09-04.24, EPA Docket A-98-49, II -A4-50, and had been approved for W I PP

assays prior to this inspection. The IPAN had no t been relocated since EP A certified it initially

although there had been som e system changes all of which had been evaluated and approved for

use in cha r a c ter i zing TR U wastes f o r W I PP. The IPAN is a multi-de tec t or system that cons ists

of the following:

34

# • A shielded assay cham ber that surrounds the waste container on all four sides, top, and

bottom ; one side of the enclosure contains a 14 MeV neutron genera tor lo cated inside a

moderator a ssem b ly

• Shielded detector p ackag es com p risin g a num ber of 3 

# He neutron detectors em bedded

within blocks of polyethylene

• Individual electronic counting units cons isting of pre-am plifiers, am plifiers,

discrim i nators and other supporting hardware

• An internal HP Ge detector for the determ ination of isotopic distribution

The system operates in both active and passive m odes, and provides values for 239 

# Pu effective

m a ss ( 239 

# Pu Ef f 

# ) and 240 

# Pu effective m a ss ( 240 

# Pu Ef f 

# ), respec tive l y. The IPAN/GEA is currently

configured to m easure one of these two quantit ies depending on the nuclear m a terial (plutonium )

loading of a specific container. Values for ot her W I PP-tracked are quantified based on known or

estab lished r e lationship s with th e m easured quantity or by using com putational techniques as in

the cas e of 242 

# Pu. Typical SRS wastes assayed on the IPAN/GEA consist predom inantly of WG

Pu, and containers with signifi cant contribution from HS Pu a r e not am enable to the IPAN/GEA

at th is tim e

.

Technical Evaluation

(1) The design of the IPAN was assessed.

The IPAN/GEA syste m uses active and passive mode determ inations to pr ovide two independent

m easures of the plutonium content of a waste cont ainer. The activ e m ode result is exp r essed in

term s of 239 

# Pu Ef f 

# and the passive m ode result is expressed in term s of 240 

# Pu Ef f 

# . The system makes

a selection to use the active or passive resu lts based prim arily on the number of m easured

coincidence neutrons and the m a gnitude of the abso rber and/or m oderator co rrection factors, i.e.,

the MOD and/or ABS-MOD indi ces discussed below.

The system ’s single gamm a-ray detector co lle cts data ove r its ca librated range, i.e.,

approxim a tely 50 to 1500 keV. The container is rota ted dur ing the assay inte rval to r e duce the

error assoc i a t ed with d i f f erent loca tio ns of nucle a r m a terial within th e container and corrections

for detecto r efficiency and gamma-ray attenuation are containe r and assay event specific.

Gamm a data are co rrelated to active and/or passive m ode neutron data.

(2) The calib ration of the IPAN/GEA was evalu a ted

.

The IPAN/GEA calibration of record was unchange d from previous EPA Inspections (see EPA

Inspection No. EPA-SRS-CCP-10-03.24 of the Central Characterization Program as

Implemented at the Savannah River Site , EPA Docket A-98-49, II-A4-40 ). The system ’s

calibration is docum ented in the BII report Mobile Assay System Calibration Test Report for SRS

Operations , BII-5104-C T R-001, Revision 3, August 2001. This calibration continues to be

appropriate f o r the wastes the IPAN/GEA has a ssayed sinc e that tim e until the tim e of this

35

# inspection. There are no techni cal issues with the IPAN/GEA’s calibration or the docum e ntation

thereof.

(3) The calibrated range and operational range of the IPAN had been established and

docum ented.

The IPAN/GEA is calibrated for assays of W I PP c ontainers from the system detection lim it to a

m a xi m u m of 120g of WG Pu. The calibration in the active m ode is valid for m a trices with

ABSMOD (absorber-m o derator) indices betw een 11.96 and 341.65. The ABSMOD index is a

m easure of the neutron absorption and m oderatio n properties of the waste m a trix and is a

function of both the m a trix m a ss and the elem ental com position of the waste m a terial itself. For

a given m a trix com position, the ABSMOD index is e xpected to increase w ith increasing m a trix

m a ss. In the passive m ode, the calibration is va lid f o r m a tric es with MO D (m oderato r) ind i ces

between 1.89 and 13.94, where the MOD index is a m easure of the neutron m oderation

properties of the waste m a trix. The system ’s calibration range is docum ented in the BII repor t

Mobile Assay System Calibration Test Report for SRS Operations , BII-51 04-CTR-001, Revision

3, August 2001. For the IPAN/GEA the calibrate d and operational ranges are synonymous.

There are no issues relative to the calibrated or op erational ran g e of the IPAN/GEA f r om this

inspection.

(4) The TMU for assays perform e d on the IPAN had been determined and docum ented.

The TMU for the IPAN/GEA syste m was found to be unchanged from the previous EP A

inspec tions when it was evalua ted. TM U is docum ented in the BII report Total M e as urement

Uncertain ty for the BNF L

Instrumen t s Mobile As say System , BII-5104-T M U-001, Revision 1,

August 2001. There are no issues relative to TMU for the IPAN/GEA fr om this inspection.

(5) The Lower Lim it of Det ection (LLD) of the IPAN/GEA had been determined and

docum ented.

The LLD for the IPAN/GEA had been evaluate d previously during EP A Inspection No. EPACCP-SRS-09.04-24 during which a concern was rais ed regarding the use of the IPAN/GEA for

assays belo w 100 nCi/g. Because o f the m a nner in which th e IPAN/GEA determ ined the LLD,

EPA was concerned abo u t the technical bas i s for assays of lo wer m a trix m a ss drum s with low

ABSMOD indices where the differen ces in the MDC were not prim ar ily due to differences in the

MDA, but resulted from differences when the M DA was divided by the net weight of the drum

. Origina lly, SRS CCP estim ated the m i nim u m de tectable activity (MDA) and m i ni m u m

detec t able c oncentr ation (MDC) f o r three su rro g a te waste matrices a nd assigned the MDC of

each surrogate container to the three regions of th e ABSMOD range assu m i ng it was

representative of all containers a nd m a trices within tha t rang e. In additio n to the thre e orig inal

m easurem ents, SRS CCP included d a ta f r om an addition a l e i g h t (8) su rrog a te waste matr ices,

divided the ABSMOD range into four regions and assigned the hi ghest of the observed MDCs to

that part of the ABSMOD range. SRS-CCP ma de these changes in resp onse to the EPA concern

to better ch aracterize th is region of the syst em ’s operating range. These changes adequately

addressed E P A’s concern and are reflected in the report B II Mobile Assay System Quality

Assurance Objective Compliance , BII-5104-Q AO-001, Re vision 7, from January 2005 and the

operating procedure CCP Mobile IP AN/GEA Ex pert Analysis Procedure , CCP-TP-025, Revision

36

# 10, from Se ptem ber 7, 2005. There are no issues relative to the LLD for the IPAN/GEA from

this inspection.

(6) Replicate testing of the IPAN/ GEA was performed and evaluated.

Replicate testing is perf orm e d in accord ance with the p r otocol described in EPA Replicate

Testing for WIPP Nondestruc tive Assay (NDA) Systems , Rev. 2, June 2002. The purpose of the

replicate testing performed as part of this in spection was to provide EPA with an independent

m eans to verify that the IPAN/GEA can provi de consistent, reproduc ible results for the

determ inatio n of the quantity of 10 W I PP-track ed radionu clides ( 241 

# Am

, 137 

# Cs, 238 

# Pu, 239 

# Pu,

240 

# Pu, 242 

# Pu, 90 

# Sr, 233 

# U, 234 

# U, and 238 

# U) and the TR U alpha activity concentration. This is

accom p lished by reassay i ng drum s that were p r ev iously ch aracterized on the sam e system or

instrum e nt in order to d e monstrate th e f o llowing:

• The instrument produces results consistent with the reported TMU by comparing the

sam p le standard deviation for a number of replicate m easurem ents taken over several

hours or days to the reported TMU.

• The instrument provides reproducible results over longer periods of tim e, such as weeks

or m onths, by com p aring the results of the replicate m easurement( s ) to the origin al

reported values.

As with all s t atistical eva l uations, the r e ar e lim ita tions inherent in this protocol. The value or

usefulness of the results with resp ect to the objectives stated above depends in large part to the

degree to which the con d itions enco untered are c onsistent w ith the assumptions upon which the

statistical tests are pred icated. Our experien ce to date has ind i cated that the containers chosen at

random do not always provide inform ation best su ited for the application of these statistical

protocols. For exam ple:

• An NDA system m a y ha ve been recalibrated in th e tim e perio d between th e orig inal

assay and the reassay perform e d during an inspection and the new calibration m a y have

different values for som e of the calibration algorithm ’s term s.

• The containers chosen at random for repli cate analysis m a y lack sufficient nuclear

m a terial content to provide useable data fo r som e or all the WIPP tracked radionuclides.

• High precision for the five replicates assays m a y yield an average value that differs

slightly from the original assay value but pr oduces results that the statistical analysis

i ndi cat e s ar e Significant or Highly Significant . H o wever, these differences m a y be s m all

variations th at are m o re a f unction of the statistical protoc ols and do not indicate true

m easure m ent trends or problem s.

• Since som e radionuclides are quantif ied base d on the m e asurem ent of a si ngle other

radionuclide, i.e., values for 238 

# Pu and 240 

# Pu are derived by applying an isotopic ratio to a

m easured 239 

# Pu value, a Significant or Highly Significant ind i cator f o r the single

m easured entity will be r e f l ected in the other thre e, indic a ting a larg er potentia l

m easure m ent trend or problem than m a y exist.

37

# It is im portant to keep these in m i nd when evaluating replicate data and to realize that Significant

or Highly Significant results m a y not in fact be repr esentative of m easurem ent issues.

As part of the inspection to certify the IPAN/GEA system , EP A re quested that SRS-CCP reassay

three drum s that EPA random l y selected from a list of drum s previously assayed on the IPAN.

Drum Nos. FBL04011, SR144771 and SR138868 were rea ssayed five tim e s and the results were

com p ared to the original assay data. Two statistical tests, a chi-squared ( χ 2 

# ) test and a t test, were

perform e d. Data and results of the statistical analys is are included in Attachm e nts B.1 through

B.6 and are discussed below. There were no i ssues relative to repl icate tes ting f o r the

IPAN/GEA system at SRS-CCP.

The χ 2 

# test for all three containers assayed on the IPAN/GEA system indicated that th e observed

varian ces in the rep licate m easurem ents are less th an or equal to the reported uncertainties within

the statistica l lim its of th e tes t . Additionally, the t tests for these containers did not show any

statistically significan t d i fferences b e tween th e o r igin al m easurem ent assay values an d the

average of the five replicate m easurem ents.

Inspection Issues

Findings

The EPA inspection team did not identify a ny findings relative to the MCS IQ3 or the

IPAN/GEA system s during this inspection.

Concerns

The EPA inspection team identified one concern th at did not require a re sponse in the area of

NDA during this inspection; however subsequent to the inspection, CBFO supplied inform ation

addressing this concern, as described below.

EPA Inspec tion Issue T r acking Form, Issue No. SRS-CCP- NDA-05-006CR: Def a ult

isotopics based on AK are docum ented on a wast e stream basis and are co ntained in th e

appropriate AK-NDA Mem o randum for each waste stream . However, there is no formal

instruction for the NDA Expert Analysts (EA) re garding the use of AK b a sed default isotopics.

Additionally, CCP Procedure CCP-TP-048 does contai n directions to the EA regarding other

aspects of the radioaassay process. E x am in ation of NDA BDRs by the EPA inspection team

indicates that on several occasions th e NDA EA has applied AK-based isotopics.

Resolution of NDA Issue

A step was added to CCP-TP-048, Section 4.1.2 to clarify that the EA shall refer to the

appropriate NDA/AK mem o randu m when assigni ng default isotopic values. A copy of the

changed page from the procedure is include d in the CBFO re sponse in Attachm e nt D.

Proposed Baseline Approval

The baseline conditions that the EPA inspection team evaluated during this baseline inspection

consist of the two NDA system s described in this report:

38

# • MCS IQ3 Gamma Ray System used for gamm a–based determ inations of isotopic

distributions and quantitative assa ys as described above and de tailed in the IQ3 checklist

(Attachm e nt A.6) over the cal ibrated energy and efficiency ranges of photon em ission

from 59 keV to 1,408 keV.

• IPAN/GEA system used for neutron–based a ssays of fissile radionuclides using active

and/or passive m ode m e asurem ents consis tent w ith the system ’s operating range

expressed in ABS and ABS-MOD indices, re spectively, as represented in the IPAN

Calibration Test Report and refl ected in the IPAN/GEA che c k lis t (Attac hm ent A.5) with

gamma or AK–based isot opics, as appropriate.

Each system , along with its range of applicability for disintegration rate (a ctivity) and m a trix,

and any lim itations, is approved as described in th is report and detailed in the NDA che c klists

(Attachm e nt A5 and A.6). Each system is curren tly configured to assay retrievably-stored or

newly-generated so il/g ravel (S4000) and debris (S5000) wastes.

Proposed NDA Tiers

Based on the inspection and the results discu ssed above, EPA proposes to assign the following

tie rs:

Tier 1 NDA changes tha t will require EPA review and approval pr ior to implem e ntation are th e

following:

• New NDA e quipm ent; 8



# • Physical m odifications to approved equipm ent; 9 

# and

• Extension or changes of an approved ca libration range(s) for approved equipm ent

For purposes of clarification, the last bullet above refers to the extension of a system ’ s approved

calibration range with respect to determ ination of disintegrati on rate (activity) or physical

characteristics (m atrix) of any of the thr ee NDA system s proposed for approval during this

inspection During an EPA technical inspection, several characteris tics of a m easurement system

are evaluated. A key characteristic is the rang e of conditions for which the instrum e nt is capable

of producing technically defensible da ta with respect to two aspects:

• Activity – the nuclear disintegration rate of specif i c radiations types (neutron or gamma),

typically Special Nuclear Mate rial or Transuranic radionuc lides; units of activity and

m a ss are interchangeable;

8 

# New NDA equip m en t re fers t o a sy st em or c o m pone nt n o t pre v i o usl y eval uat e d by E P A

. Speci fi cal l y , t h i s

i s defi ned as a phy si cal l y di st i n ct o r di f f ere n t sy st em or a pparatus; a n assa y syste m th at is rep o rted to be th e

equi val e nt of o r i d e n t i cal t o a pre v i o usl y ap p r o v e d sy st em but w h i c h ha s n o t bee n f o rm al ly i n spect e d a n d a p p r ove d

by EP A i s a ne w sy st em and m u st be ap pr o v ed by EP A pr i o r t o i m pl em ent a t i on t o c h ar act eri ze WIPP wast es.

9 

# C h a nges t o e x i s t i ng ND A e q ui pm ent i n cl u d e al l cha nges a n d o r m odi fi ca t i ons t o a p p r o v e d e qui pm ent t h at

h a v e th e po ten t ial to affect th e qu ality o f NDA d a ta used fo r th e p u rp o s es of waste ch aract erizatio n and / or waste

iso l atio n

. Th is do es no t in clud e m i n o r ch ang e s o r safety-related ch ang e s (e.g ., add itio n o f h a nd rails) th at do no t

h a v e th e po ten t ial to affect wa ste characte r ization data.

39

# • Physical Characteristics – the physical attributes of waste m a trices as they relate to a

radiom etric system , i.e., how the m a t r ix’s physi cal properties interact with the radiations

that o r igin ate within the sam p le and af f ect th e sy stem ’s ability to detect them . Examples

include attenuation of photons (gam m a ), a nd m o deration and abso rption of neutrons.

During the inspection, the system ’s technical capabilities that are evaluated represent the

conditions o b served and they define the operatio n a l envelope in which W I PP m easurem ents will

occur. Chan ges to a sys t em ’s calibrated rang e wi th respe c t to disintegra tion rate and/or m a trix

m a y represent an essentially different set of conditions from those evaluated during the

inspection. For this reason, a ch ange to a system ’s calibrated range is considered a Tier 1

change. A system ’s operating range is generall y, although not always, a subset of a calibration

range, i.e., system s that are calib rated to m a ke valid m easurem en ts from 0 to 200 gram s of WG

Pu or Total Pu typically operate in a sm aller range, the system ’s LLD to <200 g for W I PP.

Provided the system ’s calibrated range is valid, a site is free to designate a different operating

range(s ) within the c a lib rated range as a Tier 2 change.

Sim ilarly, for physical characteristics NDA system s are often calibrated with respect to a range

of sa m p le attributes, e.g., a m a trix density range upper lim it of 2.2 g/cm 3 

# for the IQ3 s y stem

discussed in this report. This range m a y include m a terials that are commonly referred to using

term s such as debris (S5000) and soils & gravel s (S4000), both of which ar e within the calibrated

density range. Actual w a ste assays m a y be restricted to a portion or subset of this range, i.e.,

debris only, for a variety of t echnical and/or adm i nistrative re asons. Changing the calibrated

range by extending it beyond 2.2 g/cm 3 

# for the IQ3 system would constitute a Tier 1 change.

Provided the original density ra nge is valid, changing the operati onal range(s) of an approved

NDA system is a Tier 2 cha nge, as discussed below.

Tier 1 chang e s will b e re ported and d o cum e ntation will be su bm itted whe n SRS-CCP is ready

for EPA review. In case of the first two T1 N DA changes listed above, DOE should assum e that

an EPA inspection is likely. In the case of a last T 1 NDA change, EPA will inform SRS-CCP

and CBFO whether a site inspection is necessa ry. EPA m a y r e quest add i tional information,

choose to conduct a desktop review, and/or confer with SRS-CCP NDA personnel. U pon

evaluation (with or with out site insp ection )

, EPA will issue an approval letter and on ly upon

receiving the EPA approval can SRS-CCP continue to use the equipm ent affected by the change.

Tier 2 NDA Changes that do not require EPA approval pr ior to im ple m entation but require

reporting an d subm itting docum entation di scus sing changes by SRS-CCP are:

• Changes to software for approved equipm ent; and

• Changes to approved operating range(s) of approved NDA sy stem s upon CBFO appr oval

(see discussion, above)

• Changes to procedures that require CBFO appr oval

For purposes of clarification, exam ples of the first bullet above would include:

• Changing a system ’s operating system , e.g., first use of Canberra NDA 2000

40

# • Identification of a system atic problem w ith a software package and subsequent

modifications to address the problem

, e.g., us e of an incorrect value for a radionuclide’s

transition probability in NDA 2000

• Introduction of a new version of an existing software package beyond what is in current

use

Regarding the second bullet above, reducing a syst em ’s operating range because of perform a ncerelated problem s or equipm ent failures would be Ti er 2 changes. For example, if, the IQ3 were

to not pass a PDP cycle for a specif ic m a trix or ac tivity range and its use for those were for m ally

restricted by the site or C B FO, this would be a Tier 2 change.

Every thr ee months f r om the date o f EPA approval, SRS-CCP will prov ide inf o rm ation

concern i ng T2 changes. EPA will evaluate chan ges and communicate with SRS-CCP whether

changes raise any concerns and SRS-CCP res ponse is necessary or whether SRS-CCP can

continue to implem e nt c h anges.

8.3 Real-Time Radiography (RTR)

Waste Characteriz a tion Element Description

At the tim e of the inspection, only on e m obile RTR unit (RTR#1) was on site.

As part of th e inspec tion of the RTR activ ities, th e team revie w ed the ele m ents of the RTR

process listed below:

• Docum e ntation of RTR activities th rough use of an approved procedure

• Proper execution of RTR activities

• Managem e nt oversight and indepe nd ent rev i ew o f RTR activities

• Statistical verification of RTR ac tivities through VE (see Section 8.4.2)

• Training of RTR personnel

Em phasis was placed on overall procedural technical adequacy and im plem entation, as well as

the iden tif ic ation of W M Ps and pro h ibited items.

The RTR fa cility uses radiography to help determine the following aspects of TRU WC:

• Types and amounts of WMP

• Presence o r absence of p r ohibited item s

• Testing for new operators on the RT R sy stem using specifically placed item s

Documents Review ed

The following docum ents were am ong those exam ined to assess whether all RTR operations

f o llow the a ppropria te approved procedures:

• CCP-TP-011, Revision 16, Radiography Inspection Operating Procedure

, May 2, 2005

41

# • CCP-TP-028, Revision 2, CCP Ra di ographic Test and Training Drum Re quirem e nts,

February 4, 2005

• CCP-QP-002, Revision 16, Tr aining & Qualifica tion Plan, June 6, 2005

• CCP-PO-002, Revision 13, CCP Tra n su ranic W a ste Certification Plan

, effective May 9,

2005

• RTR BDRs: SRRTR1724, SRRTR1728, SRRTR1732 (S5000, debris w a ste)

• Training records for RTR operator/ITR/TS/F QAO and RTR subject m a tter expert (S ME)

Technical Evaluation

During the inspection, the following elem ents of the RTR process were investigated using the

checklist contained in Attachm e nt A.3:

(1) Overall p r ocedural techn i cal adequa cy and im plem entation were evaluated.

Prior to the inspection, the RTR procedure was revi ewed for technical adequacy. The procedure,

docum ented in CCP-TP-011, contains specific instruc tions for perform i ng nonintrusive

radiography, including operati onal setup and checkout , identification of prohibited item s,

assignm ent of W M Ps and estim ation of weights and volum es, confirm a tion of W M Cs, input of

data, issuance of NCRs, and technical review of radiography results. No technical adequacy

issues wer e identif ied f o r

this pro ced ure.

QC exa m inations were perform e d as required. For exam ple, in batch SR RTR1278, a n

independent observation was perform e d on c ont ainer SR85815 and a rep licate scan was

perform e d on container SR506717. In batch SR RTR1732, a n independent observation was

perform e d on container 235F01073 and a replicat e scan was perform e d on container SR519787.

Both of the QC sa m p les were perform e d by a different operator from the original.

Corrective action is im plem ented as neede d. NCR-SRS-1273-05 was initiated for drum

SR118958, batch SRRTR1728, because it contained greate r than 1 inch o f liquid. In the sam e

batch, containers 772F020054, FBL03144, and SR529802 contained greater than 20% inorganic

waste. The disposition f o r these containers was docum e nted in NCR-SRS-1272-05 as “use as

is.” The verification of NCRs associated with specific drum s is a checklist item in the FQAO

checklist for each BDR.

(2) Characterization of W M Ps and prohibited item s were evaluated.

WMPs and their es tim ated weights, the pr esen ce or absence o f prohibited item s , and

confirm a tion of the WMC were re corded in the BDRs and audio/ visual tapes reviewed. The

following process is used to perform the RTR ex am ination of containers at SRS-CCP. At the

beginning of a shift, and prior to exam ining any waste containers, the operator perform s a linespair (LP) res o lution tes t to ensure th at im ages are clearly visible. The procedure requires an

im age resolution of at le ast 5 LP/cm

, and the r e su lt of the test im age is docum ented in

Attachm e nt 8, “CCP Ra diography Measurem ent Control R e port.”

42

# For each RTR event, two audio/v i deo record ings are sim u ltan e ously m a de. The first n o tations

on the audio/video recording, m a de by the ope rator, are the contai ner number and the

exam ination date and tim e . The exam ination begi ns at the top of the drum , where the operator

determ ines if a rigid liner is pr esent and if this liner is vent ed. The drum is rotated through

360 degrees so that all o b jects can b e viewed fro m all sides. The operato r has the ability to zoom

both in and out and increase or d ecrease th e scan energy in orde r to compensate for varying

densities of the waste m a terial exam ined. Duri ng the exam ination, the operator also rocks the

drum from s i de to side to determ ine the presence of free liquids. A second operator

elec tronically records ite m s identif ied by the ope ra tor scanning the container on Attachm e nt 3 to

the procedure.

During exam ination of the cont ainer, the operator determ ines the presen ce or abs e nc e of

prohibited item s , and this determ ination is docum ented on Attachm e nt 3, as well as on the

audio/visual recording. Standa rdized weights for W M Ps are contained in the RTR procedure

(Tables 1 and 2) and are used by the operators, in conjunction w ith an operator aid that also

contains standardized WMP weig hts, to calcu l ate W M P weights imm e diately after th e scan is

com p leted. Layers of confinem ent a nd volum e u tilization of the drum are also recorded on

Attachm e nt 3.

During the onsite inspection, EPA observed the RT R event for a debris (S5000) drum , num b er

SR515960 (batch SRRTR1749). The dem onstration took place on Pad 4 of SRS. Perfor m a nce

of

the LP resolution tes t

, as well as the opera to r’s system atic exam ination of the subject drum

, was observed. RTR data, including WMP descrip tion and estim a ted weights, and the presence

or absence of prohibited item s we re electronic a lly enter e d into th e data sheet (Attachment 3 of

procedure CCP-TP-011).

Through interviews with operational personnel, review of BDRs, and observation of an RTR

event, EPA determ ined that SRS-CCP successfully characterizes W M Ps a nd prohibited item s for

debris waste.

(3) Docum e ntation of radiography activities was exam ined.

EPA reviewed both the written reco rd (BDR) and audio/visual reco rding for containers

SR100137 and SR118958. The data recorded in th e BDR and on the tape were consistent.

During the RTR de m o nstration, EP A observed that da ta were recorded on the audio/visual tape

and in Attachm e nt 3. RTR data are entered electronically into A ttachm e nts 3 and 8 of procedure

CCP-TP-011. The review of the audio/visual recordings and BDRs de m o nstrated that

docum entation of RTR events by SRS-CCP was com p lete.

(4) Training of radiogra phy personnel w a s adequate.

During the inspection, EPA reviewed docum ent a tion of the capability d e m onstratio n for

radiography personnel. The test drum tapes and associated docu m e ntation for one operator and

one SME were reviewed:

• Training drum (SRS-NDE-TEST-12B) audio/ video recording for SME, August 25, 2005

43

# • Training drum (SRS-NDE-TEST-13B) audio/vi deo recording for operator, October 19,

2005

Although the drum inventory includ ed a horsetail, the SME did not identify this and the SME

reviewing the tape did not recognize this om ission. EPA Concern SRS-CCP-RTR-05-003CR

was written because the review pro c ess used by CCP did not identify this problem and provide

adequate training feedback to RTR personnel.

The training records rev i ewed indicate that only trained personnel were operating the R T R

equipm ent. RTR operators are required to revi ew the results of the RTR/VE com p arisons, and

significant issues are discussed. Training docum entation was com p lete and f iled cor r e c tly f o r

viewing and reference. The docum e n ts rev i ewed include the f o llowing:

• Training records for RTR opera tor (ITR/TS/FQAO) and SME

• VE/RTR comparison report, May 25, 2005

Inspection Issues

Findings

The EPA inspection team did not identify any findi ngs in th e area of RTR during this inspection.

Concerns

The EPA inspection team identified one concer n in the area of RTR during this inspection.

EPA Inspec tion Issue T r acking Form, Issue No . SRS-CCP- R TR-05-003CR: In the process

of RTR train i ng in accordance with CCP-TP-02 8, Revision 2, an operato r did not identify a

required item in the training drum . Although a qualified RT R operator reviewed this training

tape, it appears that the CCP NDE Test Drum Inventory Sheet, CCP-TP-028-A1, Revision 0, was

not used as a basis for this rev i ew because th e reviewer d i d not docum ent that a req u ired item

was m i ssed. The process in place res u lts in a lack of identification of pr oblem s associated with

the re-qualification of RTR operators and does no t provide the opportunity for feedback to the

operator undergoing RT R ope rator re-qualification.

Resolution of Issue: This issue was discussed with CCP managem e nt during the on-site

inspection and CCP provided docum ented eviden ce that the issue had b een approp riately

addressed. The docum e n tation that supported th e successful im ple m entation of appropriate

corrective action consisted of a written descripti on of training provided to the RTR operators and

a signed attendance sheet dem onstrat ing that the training was given to the applicable personnel.

This issue w a s successfully resolved

, during th e o n -site insp ection, by CCP.

Proposed Baseline Approval

The baseline conditions that the EPA inspection team evaluated during this baseline inspection

consisted of the f o llowin g :

44

# • Trained personnel: operator/ITR/TS/FQAO and SME

• Approved and controlled operating proce dures: CCP-TP-011, CCP-TP- 028, and CCPQP-002

• CCP Mobile RTR Unit No. RTR 1

• RTR records and supporting data: C C P-TP- 011, Revision 16, Attachm e nts 3 and 8, and

RTR BDRs

This system is approved for RTR of S5000 (debris) wastes.

Proposed RTR Tiers

Based on the inspection and the results discu ssed above, EPA proposes to assign the following

tie rs.

Tier 1 RTR changes: none at th is tim e.

Tier 2 RTR changes tha t do not require EPA approval prior to im plem entation bu t req u ire

reporting and subm ission of docum e n tation di scussing changes by SRS-CCP include the

following:

• New RTR equipm ent or change s to approved equipm ent

• Changes m a de to RTR procedure( s) that require CBFO appr oval

Every thr ee months f r om the date o f EPA approval, SRS-CCP will prov ide inf o rm ation

concerning T2 changes. If new RTR equipm ent is in use, EP A inspection m a y be necessary.

EPA will evaluate chang e s and communicate with SRS-CCP whether th e changes raise any

concerns and require SRS-CCP re sponse, or whether SRS-CCP can continue to im plem ent the

changes.

8.4 Visual Examination

Waste Characteriz a tion Element Description

Three VE processes were assessed as part of the inspec tion a c tiv ities:

(1) VET for ne wly-generated waste

(2) VE in lieu o f RTR f o r retrievably-stored waste

(3) VE as a QC check for RTR for retrievably-s t ored waste

The two VE processes are com b ined in the s a m e section of this report because the operational

processes used are the sam e

. These processes are discu ssed in Sections 8.4.1 and 8.4.2,

respectively, below.

As part of the inspecti on of the VE activitie s, the inspector rev i ewed the elem ents of the VE

processes listed below:

45

# • Characterization of W M Ps and prohibited item s

• Technical adequacy of VE procedures

• Docum e ntation of VE activities

• Training of VE personnel

Em phasis was placed on overall procedural technical adequacy and im plem entation, as well as

the iden tif ic ation of W M Ps and pro h ibited items.

8.4.1 Visual Examination T echnique for New l y-generated Waste

Waste Characteriz a tion Element Description

The VET process for newly-generated waste consis ts of rem oving the w a ste from the container

in order to determ ine the following aspects of TRU WC:

• Confir m a tion of W M Ps and W M C

• Confir m a tion of presence or absence of prohibited item s

Documents Review ed

The following docum ents were am ong those review ed to assess whether VET operations follow

the appropriate approved procedur es and m eet VET requirem e nts:

• CCP-TP-113, Revision 3, CCP St andard W a ste Visual Exam ination, January 25, 2005

• CCP-QP-002, Training & Qualificat ion Plan, Revision 16, June 6, 2005

• Training records for VEE a nd VE o p erator/ITR/TS/FQAO

• BDRs: SRVETXxxx1, SRVETXxxx2, S5000, debris (Note: these BDRs were generated

by SRS-CCP for de m o nstration purposes only)

Technical Evaluation

During the inspection, the technical elem ents of CCP’s VET process were evaluated using the

checklist contained in Attachm e nt A.2. These aspects are summarized below:

(1) Overall p r ocedural techn i cal adequacy was evalu a ted.

Prior to the onsite inspection, procedure CCP-TP- 113 was reviewed for technical adequacy and

no issues were identified. The proced ure contains specific inst ructions for perform i ng VET in

Section 4.2, including iden tification of prohibited item s and WMPs, and confirm a tion of W M Cs.

(2) Characterization of W M Ps a nd prohibited item s was evaluated.

VET for ne wly-generated waste does not require ge neration of an audio/vi sual reco rding of the

VET event. The contents of the container are removed and sorted by WMP. Bags are

sequentially num b ered and opened, and the cont ents identified and weighed. Both of the

containers in the dem o nstration BDRs contai ned num e rous bags and a variety of WMPs.

46

# Operators receive trainin g on specific waste generating pr oces ses, typical packaging

configuratio ns, and W M Ps expected to be f ound in each W M C. After the waste has b een

identified, weighed, and docum ented, it is loaded into a preweighed drum and the volum e

utilization percentage of the outpu t container is estim ated. The fi nal weight of the loaded drum

is determ ined after the drum has been closed.

Section 5 of Attachm e nt 1 is used to record th e presence o r ab sence of pro h ibited items. If

found, an NCR is initiated and the p r ohibited item is processed in acco rd ance with th e

disposition specified in the NCR or as di rected by the VE t echnical supervisor.

Through interviews with operational personnel, review of BDRs, and observation of a VET

event, it was determ ined that SRS-CCP successf ully characterizes W M Ps and prohibited item s

by this technique for debris waste.

(3) Im ple m entation of the procedure and docum entation of VET activ ities wer e exam ined.

Section 1 of Attachm e nt 1 records general information for the container undergoing V ET

exam ination. Section 2 records W M C and layers of confine m ent, Section 3 records waste

packaging data, and Section 4 records packagi ng m a terial and W M Ps. Se ction 5 records the

presence or absence of prohibited item s. In both of the BDRs reviewed, all of the required

inform ation was entered into Attachm e nt 1.

During the onsite dem o nstration, two operators worked in a glovebox and a VEE was outside of

the rad i ation containm ent area reco rd ing all VET data as they were generated. Data entry is

m a de by hand. All drum contents are rem oved, s o rted by WMP, and weighed. The scale

calibration verification w a s observed by EPA a nd correctly docum e nted by the VEE. To

facilitate operations, the ope rators use Operator Aid No. E-03-0006 when they are working

inside the glovebox. This aid docum ents the scal e identification num b er and calibration date.

The dem ons tration drum SR233850 contained a hut th at was tightly packed in the drum. The

operato rs cu t the hu t into pieces to remove it from the drum . The drum also contained two

prohibited item s , and the VEE initia ted an NCR as required by the proc e dure.

By interviews with VE personnel, observation of the dem o nstration VE T event, and review of

the dem onstration BDRs, it was de ter m ined th at the VET procedure for debris waste was

im ple m ented and docum ented as required.

(4) Calculation of m i scertification rates is not applicable becau se all newly

- generated waste

will undergo VET.

(5) Training of VET personnel was evaluated.

The site m a intains a list of qualif ied individu als, which is used to ensure that all training is

current. CCP uses qualif ication cards to docum ent training received by CCP personnel. The

appointm e nt of VEEs by the SPM is docum ented in a letter that is in cluded in the VE E’s

qualification card. Training on specific wast e-generating processes, typical packaging

configuratio ns, and W M Ps expected to be f ound in each W M C is provided to VE personnel.

47

# During the inspection, the qualific ation cards for a VE operato r/ITR/TS/F QAO were reviewed

and found to be com p lete and current. Also, th e qualification card for a VEE was reviewed and

found to be com p lete and current, and cont ained the letter appoin ting him as a VEE.

The following docum ents were reviewed:

• Qualificatio n card for VEE/SME

• Qualification card for VE operator

Training docum e ntation was com p le te and file d correctly for viewing and reference.

8.4.2 Visual Examination as a QC Check of RTR and VE in lieu of RTR

Waste Characteriz a tion Element Description

The operational VE process used for VE as a QC ch eck of RTR is the sam e as that for VE in lieu

of RTR; hence, these tw o VE processes are repor ted together. Both types of VE are perform e d

in a glovebox located on Area 4, Pad 6, at SRS. The EPA inspector observed VE in lieu of RTR

for container SR597472 (S4000, soil/gravel), BDR SRVEP60162. The drum was from waste

stream SR-W027-221H-HET. Although the EPA inspector did not observe VE as QC check of

RTR, two BDRs, SRVEP60037 and SRVEP60132, were rev i ewed. Additionally, EP A reviewed

the audio/visual recording for VE of drum SR100052, BDR SRVEP60037. The drum s in both

BDRs contained S5000, debris waste.

Documents Review ed

The following docum ents were am ong those reviewed to assess whether VE as a QC check of

RTR and VE in lieu of RTR operations follow the appropriate approved pr ocedures and m eet the

appropriate technica l req u irem ents:

• CCP-TP-113, Revision 3, CCP St andard W a ste Visual Exam ination, effective January

25, 2005

• CCP-QP-002, Revision 17, Tr aining & Qualifica tion Plan, June 6, 2005

• Training records for VEE a nd VE o p erator/ITR/TS/FQAO

• VE as a QC check of RTR BDRs SRVEP60037, SRVEP60132 (S5000, debris waste)

• VE in lieu of RTR BDRs SRVEP60 019, SRVEP60029 (S5000, debris), SRVEMS0001,

SRVEMS0002, SRVEMS0003 (S4000, soil/g rav e l waste)

• Posted Operator Aid No. E-03-0006

• VE/RTR comparison em ail and report, May 25, 2005

48

# Technical Evaluation

During the inspection, the technical elem ents of the VE process as a QC check of RTR and VE

in lieu of RTR were evaluated using the checklis t contained in Attachm e nt A.2. These areas are

summarized below:

(1) Overall p r ocedural techn i cal adequacy was evalu a ted

The VE procedure, CCP-TP-113, is well defined, a nd the docum ent is controlled. The procedure

contains complete and detailed instructions for perform i ng VE as a QC check of RTR and VE in

lieu of RTR. These two types of VE are perfor med in exactly the sam e manner, and both are

included in Section 4.1 of the procedure. Th e procedure requires identification of W I PP

prohibited item s , a description of layers of c onfinem ent, determ ination of WMPs and their

weights, and confirm a tion of the WMC. Table 4 in the procedure provides standard weights for

item s , and Attachm e nt 1 is used to record all VE data

.

(2) Characterization of W M Ps a nd prohibited item s was evaluated.

For each co ntainer undergoing exam ination, an audio/ vid e o recording of the event is m a de. For

VE as a QC check of RTR and VE in lieu of RT R for S5000 debris waste, the operators rem ove

all of the waste item s from the drum , open pack ages, sort and identify the WMPs, and weigh the

packages. T h e VEE docum ents the item s and their weights on Attachm e nt 1 and m a kes voice

entr ies of th e sam e on th e audio/visual recording.

When perform i ng VE in lieu of RTR for S4000 so il/g ravel waste, only the top of the waste is

investigated. Any W M Ps found ar e inventoried and weighed, but only if they are contained in

the top 6–8 inches of the waste. EPA Concer n SRS-CCP-VE- 05-001F was written in response to

this lim ited VE process.

Section 5 of Attachm e nt 1 is used to record th e presence o r ab sence of pro h ibited items. If

found, an NCR is initiated and the p r ohibited item is processed in acco rd ance with th e

disposition specified in the NCR or as di rected by the VE t echnical supervisor.

Through interviews with operational personnel, revi ew of BDRs, and observation of a VE in lieu

of

RTR event, EPA dete rm ined that SRS-CCP s u ccessfully characterizes W M Ps and prohibited

item s by this technique and VE as a QC ch eck for RTR for S4000 (soil/gravel) and S 5000

(debris) was t e.

(3) Docum e ntation of VE activities was exam ined.

Section 1 of Attachm e nt 1 records general information for the container undergoing V ET

exam ination. Section 2 records W M C and layers of confine m ent, Section 3 records waste

packaging data, and Section 4 records packagi ng m a terial and W M Ps. Se ction 5 records the

presence or absence of prohibited item s. In th e BDRs reviewed, all of the required infor m ation

was entered into Attachm e nt 1.

49

# The EPA inspector reviewed f our audio/video recordings for VE in lieu of RTR:

SRVEMS0001, SRVEM S 0002, SRVEMS0003 (S4000, so il/gravel), and SRVEP60029 (S5000,

debris). The inform ation contained in the BDRs corresponded to that recorded on the

audio/visual tapes.

One audio/video recording for VE as a QC check of RTR was reviewed an d com p ared to the

written inform ation in BDR SRVEP60132. The audi o/visual record did not m a tch the written

record in the BDR for drum SR100052. Changes ha d been m a de to the written record, and the

original record was not retained as re quired. EP A concern SRS-CCP-VE-06-002CR was

initiated to a ddress th is issue.

During the inspection, EPA observed VE in lieu of RTR for debr is (S5000) drum SR597472,

BDR SRVEP60162. The drum was fr om waste stream SR- W 027-221H-HET

. 

# During the

dem onstration, two operators worked inside a glovebox, and the VEE was outside of the

radiation co ntainm ent area reco rding all VE data as they were generated. Data entry is m a de by

hand. All drum contents are rem oved, sorted by WMP, and weighed. The scale calibration

verif i ca tion was observe d by EPA and corre ctly d o cum e nted by the VEE. To f acilitate

operations the operators use Operator Aid N o. E-03-0006 when working inside the glovebox.

This aid docum ents the s cale identification num ber and calibration date . The dem ons tration

drum , SR597472, contained a hut that was tightly p acked in the drum . Th e operators cut the hut

into pieces to rem ove it from the drum and weigh the ind i vid u al pieces. The drum also contained

two prohibited item s , and the VEE initiated an NCR as required by the procedure.

(4) Calculation of m i scertif ication rates was exam ined.

At the tim e of the inspection, SRS-CCP had cal culated a m i scertificat ion rate for Category

Group S5000 (debris). Inter-office m e morandum “Savannah River Site Category Group S5000

Specific Mis certification Rate,” repo rts the m i scertif ication rate calculations and results. Sixteen

drum s were selected and visually exam ined between October 4, 2004, and May 3, 2005. These

drum s were added to the 141 drum s processed in pr evious years, and a m i scertification rate of

3% was calculated. The algorithm used for the calculation was appropriate.

(5) Training of VE personnel was evaluated.

The site m a intains a list of qualif ied individu als, which is used to ensure that all training is

current. CCP uses qualif ication cards to docum ent training received by CCP personnel. The

appointm e nt of VEEs by the SPM is docum ented in a letter that is in cluded in the VE E’s

qualification card. Training on specific wast e-generating processes, typical packaging

configuratio ns, and W M Ps that are expected to b e found in each W M C is provided to VE

personnel.

During the inspection, the qualific ation cards for a VE operato r/ITR/TS/F QAO were reviewed

and found to be com p lete and current. Also, th e qualification card for a VEE was reviewed and

found to be com p lete and current, and cont ained the letter appoin ting him as a VEE.

50

# The following docum ents were reviewed:

• Qualificatio n card for VEE/SME

• Qualification card for VE operator

Training docum e ntation was com p le te and file d correctly for viewing and reference.

Inspection Issues

Findings

VE for Newly-generated W a ste : The EPA inspection team did not identify any findings in the

area of VE of newly-generate d waste during this inspection.

VE as a QC Check of RTR : The EPA inspection team identified one finding, summarized

below, in the area of VE as QC check of RTR.

EPA Inspec tion Issue T r acking Form, Issue No . SRS-CCP- V E-05-001F: W h en perform i ng

VE on S4000 soils drums from the Mound soil waste stream described in AK-8 for BDRs

SRVEMS0001 through SRVEMS0003, operators c onducted visual inspection that w a s not

consistent w ith procedure CCP-TP-113, Revision 3. The VE event did not assess the drum s’

contents but focused solely on the top layer of waste. The BDRs reported that no prohibited

item s were found, but this could not be asce rtained based on the VE that was performed.

Resolution of Issue: T h is issue was discussed at leng th with CCP’s m a nagem e nt and was

resolved based on the following inform ation:

• Only 19 containers of this waste were at SR S, including 14 drum s. Of thes e drum s, only

2 had not been investigated by a WC t echniqu e at the tim e of t h e inspectio n.

• All of the W C activitie s f o r these d r u m s di d not result in any prohibited item s being

identified.

• The AK record for the waste did not indi cate th e presen ce o f prohibited item s in

containers.

• CBFO appr oved procedure CCP-TP-113, Revision 3, section 4.1.4, Note below [D],

allows for lim ited VE, “ F or containers whose co ntents are to larger or heavy to m ove

(e.g., solidified m a ss or sludge), the VE m a y be perform e d with the m a terial in place”.

• ALARA concerns associated with remova l of sludge/soil m a trices for full VE.

EPA accepted CCP’s explanation for the lim ited VE for these specific co ntainers and the issu e

was successfully reso lved during th e on-site insp ection.

VE in Lieu of RTR : The EPA inspection team did not identi fy any findings in the area of VE in

lieu of RTR.

51

# Concerns

VET for Ne wly-generated W a ste : T h e EPA inspection team did not identify any concerns in the

area of VET for newly-generated waste during this inspection.

VE as a QC Check of RTR : The EPA inspection team did not iden tify an y concerns in the area

of VE as a QC check of RTR during this inspection.

VE in Lieu of RTR : The EPA inspection team identif ied on e concern, s u mm arized below, in th e

area of VE in lieu of RTR during this inspection.

EPA Inspec tion Issue T r acking Form, Issue No . SRS-CCP- V E-06-002CR: The W a ste

Visual Exam ination Data Form (Attachm e nt 1) from procedure CCP-TP-113 contains data that

does not m a tch what actually transpired duri ng V E of Drum SR100052. The videotape record

shows a problem with the VE data for this drum that was initially re corded in the hard-copy

record. Sub s equently, th e orig inal record was dis carded and replaced with one that do es not

m a tch the videotaped event. C onsequently, the hard-copy record that rem a ins does not represent

what transpired during V E of this drum.

Resolution of Issue: T h e cause of this concern was that the VE operator di d not recognize the

origin al reco rd as an in -p rocess quality assuranc e record and d i scard e d it. The corrective action

that CCP implem ented consisted of providing VE operators with Lessons Learned CCP-LL-QA0001-06. This training described how records may be corrected and required operators to retain

all in-process record s. This issue was successfully reso lved, during the on -site inspection, by

CCP.

Proposed Baseline Approval

VET for Ne wly-generated W a ste : T h e VET system for newly-generated waste that the EPA

inspection team evaluated during this baseli ne inspection consisted of the f o llowing:

• Trained personnel: operators, VEEs, SPM, and SPQAO

• Approved and controlled operating procedur es: CCP-TP-113, Revision 3, and CCP-QP002, Revision 17

• VET records and supporting data: C C P-TP -113, Revision 3, Attachm e nt 1, and VET

BDRs

This VET process is approved for char acterization of S5000 de bris wastes.

VE as a QC Check of RTR and VE in lieu of RTR : The system for VE as a QC check for RTR

and VE in lieu of RTR t h at the EPA inspection team evaluated during this baseline inspection

consisted of the f o llowin g :

• Trained personnel: operators, VEE, SPM, and SPQAO

52

# • Approved and controlled operating procedur es: CCP-TP-113, Revision 3, and CCP-QP002, Revision 17

• VE records and supporting data: CC P-TP-113, Revision 3, A ttachm e nt 1, and VE BDRs

This system is approved for VE as a QC ch eck of RTR and VE in lieu of RTR for S4000

(soil/gravel) and S5000 (debris) wastes.

Proposed VE and VET Tiers

Based on the inspection and the results discu ssed above, EPA proposes to assign the following

tie rs.

• Changes in vendor perf orm i ng VE and/or VET

Tier 2 VE and VET changes that do not require EPA appr oval prior to implem e ntation but

requir e repo rting and su bm itting doc um entation include th e f o llowing:

• Changes m a de to VE or VET procedur e(s) that require CBFO approval.

Every thr ee months f r om the date o f EPA approval, SRS-CCP will prov ide inf o rm ation

concern i ng T2 changes. EPA will evaluate chan ges and communicate with SRS-CCP whether

the changes raise any concerns and require SRS-CCP response, or whether SRS-CCP can

continue to implem e nt the changes.

8.5 WIPP Waste Information System

Waste Characteriz a tion Element Description

SRS-CCP has succes sfully subm itte d data, for b o th characte r iza tion and certification, from

num e rous containers to the WW I S in the past . The CCP pr ocedures, practices, and personnel

who process contain e r d a ta are the s a m e as those used at other approved sites.

Documents Review ed

The following docum ents were reviewed prior to or during the inspection to guide inv e stig ation

and questions:

• 

# CCP-TP-030, Revision 16, TRU Waste Certific ation and W W I S Data Entry, April 22,

2005

• 

# CCP-TP-086, Revision 8, TRUP ACT-II Shipp i n g Payload Assem b ly, July 11, 2005

• 

# CCP-PO-002, Revision 13, CCP Tra n suranic W a ste Certification Plan, May 9, 2005

• 

# CCP-QP-002, Revision 17, Tr aining and Qualification P l an, June 6, 2005

• 

# Waste Container Data Report fo r Containers SR544742 and SRTP01413

53

# • 

# WW IS Data Entry Summ ary—Char acteriz ation and Certification for Drum

MDL0506073

Technical Evaluation

During the inspection, the technical elem ents of the SRS-CCP WW I S process (see Attachm e nts

A.8 and A.9) were evaluated:

(1) Overall p r ocedural techn i cal adequacy was evalu a ted.

The WW IS procedure, docum e nted in CCP-TP-0 30, Revision 16, is well defined and controlled

and contains com p lete instructions fo r ente ring, reviewing, an d transm ittin g data. Adequate

reviews are incorporated into th e WW I S data entry procedure to m i ni m i ze the transm ittal of

noncom pliant or incorrect data. The Excel spread sheet, used for data entry, was also adequate

and controlled. No adequacy issues were iden tified for the procedure o r s p readsheet.

(2) Im ple m entation and docum entation of W W I S activitie s were exam ined.

Personnel entering data into th e WW I S can only do so after being gran ted access by the WW I S

Adm i nistrator, and access is password protected. After the data have been through every level of

review and approval, they are com p iled into a d r u m f ile and entered into a contro lled Excel

spreadsheet by the waste certification assis t ant (WCA). The waste certif ication official (WCO)

reviews th e data to ensure that they are W I PP co mplaint and signs the spr eadshee t to accept the

data. At this point, data are converted into ASCII form at file s and transmitted to the WW IS.

The inf o rm ation con t ain e d in the d r u m f ile is subsequently used for tr ansp orta tion ac tivities.

Data storage and retrieval were dem onstrated. C C P personnel were able to retrieve and print

requested records, inclu d ing WWIS access reque sts and waste container data reports for

containers S R 544742 and SRTP0141 3.



# (3) Training of WW IS pers onnel was reviewed.

The actual job perform a nce of a W C O was obser ved to verify training and qualification.

Training and qualifications pack ages were reviewed for WCA (data entry personnel) and the

WCO who perform e d the data entry dem onstrat ion. Required training included use of the

WW IS User’s Manual, and the re quired reading list included the W I PP Waste Analys is Plan

(W AP) and DOE/CBFO Quality Ass u rance Prog ram Document (QAPD). Training

docum entation was complete and filed co rrectly for viewing and reference.

(4) Load m a nagem e nt was evaluated.

The following docum ents were reviewed prior to or during the inspection to guide inv e stig ation

and questions:

• CCP-TP-030, Revision 16, TRU Waste Certific ation and W W I S Data Entry, April 22,

2005

• CCP-PO-002, Revision 13, CCP Tra n suranic W a ste Certification Plan, May 9, 2005

54

# • DOE/ W IPP- 02-3122, Revision 3.0, C ontact-Hand l ed Transu ranic W a ste Acceptan ce

Criteria for the W a ste Isolati on Pilot Plant, April 25, 2005

Attachm e nt 8 of the certification plan (CCP -PO-002, Revision 13) and procedure CCP-TP-030,

Revision 16, contain the sam e re quirem e nts for load m a nage m e nt as those found in Appendix E

of the CH-WAC. CCP-TP-030 and CCP-TP-08 6, containing CCP’s load m a nagem e nt

procedures and practices, are approved procedures . SRS-CCP had previously been approved for

load m a nagem e nt of debr is waste. The pro cess u s ed is th e sam e as that successfully

im ple m ented at other sites.

The SPM assesses drums for load managem e nt, en suring that all candidate drum s are from the

sam e waste stream . For the purpose of de m onstr ation, a W C O entered data into the WW IS test

module as if drum s were candidates for load m a nagem e nt. The dem onstration included the

WCO trying to include a containe r from a different waste stream into a payload container. The

WW IS rejected the container and the software gave an error m e ssage. The W C O als o added

contain e rs to a payload to dem onstrate th at th e WW IS recalculates the average TRU activ ity as

new drum s a r e added to the payload. The WW IS al so recalculated oth e r crite ria that m u st be m e t

for shipping, i.e., requirem ents from t h e U.S. Nuc l ear Regulatory Comm ission docum ent

“Contact-Handled Transuranic W a ste Author ized Methods for Payload Control (CHTRAMPAC)”. The weight used to calculate the TRU alpha activity of the drum s in the payload

include s dru m s, waste, and line r s. SRS-CCP w ill use approv ed 10-drum overpacks o r SW Bs as

load-m anaged containers.

The EPA inspector v e rified that the p r oce dure and process used by SRS-CCP for load

m a nage m e nt confor m to the requirem ents contained in Appendix E of the CH- W AC.

Inspection Issues

Findings

The EPA inspection team did not identify a ny findings related to the W W I S during this

inspection.

Concerns

The EPA inspection team did not identify any concerns related to the WW I S during this

inspection.

Proposed Baseline Approval

The system used for container ce rtification and load m a nage m e nt that was evalu a ted during th is

baseline inspection consisted of the f o llowing:

• Trained personnel: WWIS W C A ( f orm e rl y data entry personnel) and W C O

• Approved and controlled operating procedur es: CCP-TP-030, Re vision 16, and CCP-QP002, Revision 17

55

# • Approved and controlled Excel spreadsheet: WW I S Data Entry Summ a r y—

Characte r iz a tion and Cer tif ica tion

This system is approved for subm itting data to th e WW IS for contain e r characterization,

certification, and payload m a nagem e nt for waste summ ary category groups S4000 and S5000.

Proposed WWIS Tiers

Based on the inspection and the results discu ssed above, EPA proposes to assign the following

changes.

Tier 1 WWIS changes that require EPA review and appr ova l prio r to implem entatio n include

the f o llowin g :

• Changes to WW IS algorithm s specific to load managem e nt

This Tier 1 change will be repor ted and docum entation will be subm itted when SRS-CCP is

ready for EPA review. Upon review, EPA may re quest additional inform ation, choose to inspect

or conduct a desktop review, and/or confer w ith SRS-CCP WW IS pers onnel. Upon evaluation,

EPA will iss u e an appro v al letter. Only upon receiving the E P A approval can SRS-CCP use the

changed algorithm s

.

Tier 2 WWIS changes that do not require EPA approval pr ior to im plem e n tation but require

reporting an d subm itting docum entation discus sing changes by SRS-CCP include th e f o llowing:

• Changes m a de to WW I S procedure(s) that require CBFO approval

• Changes in load m a nage m e nt status of approved waste category(s)

Every thr ee months f r om the date o f EPA approval, SRS-CCP will prov ide inf o rm ation

concern i ng T2 changes to EPA. EPA will eval u a te th e chan ges and will inf o rm SRS-CCP

whether the changes raise any concerns and re quire SRS-CCP response, or whether SRS-CCP

can continue to im ple m ent the proposed changes.

9.0 RESPONSE TO COMMENTS

This section is reserved f o r comm ent s in re sponse to the EPA ’ s proposed approval decision.

10.0 SUMMARY OF RESULTS

10.1 Findings

During this inspection of SRS-CCP, t h e EPA inspec tion team identified one finding in the area

of VE as QC check of RTR. This is cont ained on the EPA Inspecti on Issue Tracking Form

(Attachm e nt C.5) and is summarized below.

EPA Inspec tion Issue T r acking Form, Issue No . SRS-CCP- V E-05-001F: W h en perform i ng

VE on S4000 soils drums from the Mound soil waste stream described in AK-8 for BDRs

56

# SRVEMS0001 through SRVEMS0003, operators c onducted visual inspection that w a s not

consistent w ith procedure CCP-TP-113, Revision 3. The VE event did not assess the drum s’

contents but focused solely on the top layer of waste. The BDRs reported that no prohibited

item s were found, but this could not be asce rtained based on the VE that was performed.

10.2 Concerns

During this inspection of SRS-CCP, t h e EPA inspec tion team identified five concerns: two in

the area of AK, one in the area of NDA, one in RTR, and o n e in the area of VE. Al l concerns are

addressed on the Inspection Issue T r acking Form s (Attachm e nts C.1 through C.4 and C.6) and

are summ arized below.

The EPA inspection team identified two concer ns in the area of AK during this inspection.

EPA Inspec tion Issue T r acking Form, Issue No . SRS-CCP- A K-05-004 C: AK reference

D152 indicates that wastes in SR-SRS- W 027- 773A-HET include large item s , such as boxed

wastes. This waste stream is class i fied as j ob co ntrol was t e that typ i cally excludes large m e tal

item s like those found in SR-SRS- W 027-773A-HET. The AK Summary (AK-7) does not yet

address the boxed waste com ponent and CCP is en couraged to assess whether the boxed waste

belongs in S R -SRS- W 027-773A-HET based on the si m ilarity of processes, physical form and

m a terial typ e

.

EPA Inspec tion Issue T r acking Form, Issue No . SRS-CCP- A K-05-005 C: Several AK

references (e.g., C040) indicate that the Sava nnah River Technology Center generates W a ste

Stream SR- S RS- W 027- 773A-HET (debris) that m a y contain m a terials identified as High-Level

Waste (HLW ). An earlier revision of AK-7 (SR-SRS- W 0 27 -773A-HET) included the HLW

com ponent that has since been rem oved in th e latest revision of the AK s u mm ary. The AK

record m u st include why this inform ation was removed from AK-7. Also, in the future, CCP

must adequately docum ent and justif y the inclusi on of any waste in AK-7 pr eviously or currently

identified as being high-level.

The EPA inspection team identified one concer n in the area of NDA during this inspection.

EPA Inspec tion Issue T r acking Form, Issue No. SRS-CCP- NDA-05-006CR: Def a ult

isotopics based on AK are docum ented on a wast e stream basis and are co ntained in th e

appropriate AK-NDA Mem o randum for each waste stream . However, there is no formal

instruction for the NDA Expert Analysts (EA) re garding the use of AK b a sed default isotopics.

Additionally, CCP Procedure CCP-TP-048 does contai n directions to the EA regarding other

aspects of the radioaassay process. E x am in ation of NDA BDRs by the EPA inspection team

indicates that on several occasions th e NDA EA has applied AK-based isotopics.

The EPA inspection team identified one concer n in the area of RTR during this inspection.

EPA Inspec tion Issue T r acking Form, Issue No . SRS-CCP- R TR-05-003CR: In the process

of RTR train i ng in accordance with CCP-TP-02 8, Revision 2, an operato r did not identify a

required item in the training drum . Although a qualified RT R operator reviewed this training

tape, it appears that the CCP NDE Test Drum Inventory Sheet, CCP-TP-028-A1, Revision 0, was

not used as a basis for this rev i ew because th e reviewer d i d not docum ent that a req u ired item

57

# was m i ssed. The process in place res u lts in a lack of identification of pr oblem s associated with

the re-qualification of RTR operators and does no t provide the opportunity for feedback to the

operator undergoing RT R ope rator re-qualification.

The EPA inspection tea m identif ied one concern in the area of VE in lieu of RTR during this

inspection.

EPA Inspec tion Issue T r acking Form, Issue No . SRS-CCP- V E-06-002CR: The W a ste

Visual Exam ination Data Form (Attachm e nt 1) from procedure CCP-TP-113 contains data that

does not m a tch what actually transpired duri ng V E of Drum SR100052. The videotape record

shows a problem with the VE data for this drum that was initially r ecorded in the hard-copy

record. Sub s equently, th e orig inal record was dis carded and replaced with one that do es not

m a tch the videotaped event. C onsequently, the hard-copy record that rem a ins does not represent

what transpired during V E of this drum.

10.3 Response to Inspection Issues

Personnel from the site and the Carlsbad Field O ffice (CBFO) provided info r m ation relative to

the one finding and two of the concerns that re qu ired a respo n se to th e EPA inspection team

prior to the inspection closeout on site. The fi nding and two concerns th at requ ired a written

response were also addressed by a form al su bm ittal prov ided by CBFO to EPA on Novem b er 22,

2005, included as Attachm e nt D. CBFO’s subm it tal included inform ation related to the NDA

concern that did not require a written response. T h e EPA inspection team m e mbers evaluated

the responses for com p le teness and adequacy, an d concluded that each had been resolved

satisfactorily. As a result of th e inform ation provided by these two sources, all issu es identified

by EPA during the inspection were adequately addressed. EP A considers all concerns and

findings to be resolved, and there are no open issues resulting from this inspection.

10.4 Conclusions

EPA’s inspe c tion team determ ined th at SRS-CCP’s W C program activities were techn i cally

adequate. E P A is proposing to approve the fo llowing scope of WC activ ities for SRS-CCP:

• Acceptable knowledge (AK) and load m a nagem e nt for contact-hand led (C H) retrievab l ystored and newly-generated TRU debris waste (S5000) and soils/gravel (S4000)

• Visual exam ination technique (VET) for CH newly-generated debris waste (S5000) and

soils/gravel (S4000)

• Visual exam ination (VE) as quality contro l (QC) check of real-tim e radiography (RTR)

for CH retrievably-stored TRU debris wa ste (S5000) and soil/gravel wastes (S4000)

• RTR for CH retrievab l y-stored TRU debris was t e (S5000) an d soil/g ravel waste (S40 00)

• Nondestructive assay (NDA) and the W I PP W a st e Inform ation System ( W W I S) for CH

retrievably-stored and newl y-generated TRU debris waste (S 5000) and soils/gravel

(S4000)

58

# Any changes to the W C activ ities f r o m the date o f the baseline inspection must be reported to

and, if applicable, app r o v ed by EPA accord ing to the followin g table.

Proposed Tiering of TRU WC Pr ocesses Implemented by SRS-CCP

(Based on October 31–Novemb er 3, 2005, Baseline Inspection)

WC Proces s

Elements S R S- CC P WC P r o c e s s

Specific T1 Changes SRS-CCP W C Pr ocess

Specific T2 Changes * SRS

- CCP Ge neral T 2

Ch an ges*

AK in clud ing

Loa d M a na ge m e nt Any ne w wast e category

Ch ang e s to WW IS

algorithm s specific to loa d

m a nagem e nt WSP F s, i n cl u d i ng u pdat e s

or

ad di t i ons t o wast e

stream (s) withi n a n

approve d wast e category

(see Sect i o n 8. 1)

Ch ang e s i n lo ad

m a nagem e nt st at us of

approve d wast e stream (s) Changes t o site

pr oce d u r es req u i r i n g

CBFO ap pro v a ls

and ot her cha n ges as

di scuss e d i n Se ct i on 8. 1

o f

th is repo rt

NDA New equipm ent or physical

m odi fi cat i ons t o a p p r ove d

equi pm ent **

C h an ges t o a p pr o v ed

calibration ra n g e fo r

app r ove d e q ui pm ent (see

Sect i on 8. 2 ) Chan ges t o s o f t ware fo r

app r ove d e q ui pm ent (see

Sect i on 8. 2 )

Changes t o operating

r a ng e(s) up on CBFO

app r oval Changes t o site

pr oce d u r es req u i r i n g

CBFO ap pro v a ls

and ot her cha n ges as

di scuss e d i n Se ct i on 8. 2

o f

th is repo rt

R T R N / A New eq ui pm ent or

ch ang e s to appr ov ed

equi pm ent Changes t o site

pr oce d u r es req u i r i n g

CBFO ap pro v a ls

and ot her cha n ges as

di scuss e d i n Se ct i on 8. 3

o f

th is repo rt

VE a n d VET C h an ges i n ve nd o r

per f o r m i ng VE an d/ o r VE T N/A Chan ges t o site

pr oce d u r es req u i r i n g

CBFO ap pro v a ls

and ot her cha n ges as

di scuss e d i n Se ct i on 8. 4

o f

th is repo rt

WWI S N/A N/A Chan ges t o site

pr oce d u r es req u i r i n g

CBFO ap pro v a ls

and ot her cha n ges as

di scuss e d i n Se ct i on 8. 5

o f

th is repo rt

* Upon receivi ng EPA a p proval, SR S-CCP will repo rt all T2 c h a nges to EPA eve r y three m onths.

** M o d i ficatio n s to app r ov ed eq u i p m en t in clu d e all ch an ges with th e po ten tial to affect NDA d a ta relativ e to

wast e i s ol at i o n an d e x cl u d e m i no r c h an ges, s u ch as t h e a ddi t i on of safet y

- r e l a t e d eq ui pm ent

.

59

# 11.0 REFERENCES

U.S. Departm e nt of Energy, Carlsbad Area Fiel d Office, “Contact-Handled Transuranic W a ste

Acceptance Criteria for the W a ste Is olation P ilo t Plant (CH-WAC),” Revision 3, D O E/ W I PP-02-

3122, Carlsbad, New Mexico, April 25, 2005.

New Mexico Environment Department, W a ste Is olation Pilot Plant Hazardous W a ste Facility

Perm it, NM 48901 139088-TSDF, Santa Fe, New Mexico, 1989.

U.S. Environm ental Protection Agency, “Criteria fo r the Cer tif ica tion an d Recertif ic ation of the

W a ste Isolation Pilo t Pla n t’s Com p liance with th e Disposal R e gulations: Certif ica tion Decision ;

Final Rule,” Federal Register , Vol. 63, No. 95, May 18, 1998, pp. 27354, 27405.

U.S. Code of Federal Regulations, Title 40

, Protection of Environment , Part 191, “Environm ental

Radiation P r otection Standards for Managem e nt a nd Disposal of Spent Nuclear Fuel, High-Level

and Transuranic Radioactive W a stes.”

U.S. Code of Federal Regulations, Title 40

, Protection of Environment , Part 194, “Criteria for the

Certif ica tion and Re-Certif i cation of the W a st e Is olation Pilo t Plant’s Co mpliance with the

40 CFR Part 191 Disposal Regulations.”

U.S. Departm e nt of Energy, Title 40 CFR Part 191, Com p liance Certificati on Application for the

Waste Isolation Pilot Plant, DOE/C AO 1996-2184, Carlsbad, New Mexico, 1996.

U.S. Departm e nt of Energy, Title 40 CF R Part 191, SUBPART D AND C, Com p liance

Recertification Applica tion 2004, DOE/ W IPP/2004-3231.

U.S. Departm e nt of Energy, Carlsbad Area Field Office, “Quality Assurance Program

Description (QAPD)”, DOE/ CBFO-94-1012, Revision 7, Carlsb ad, New Mexico, July 2005.

U.S. Nuclear Regulatory Comm ission, “Contact-Handled Transuranic W a ste Authorized

Methods for Payload C ontrol (CH-TRAMPAC).”

60

# Attachments A.1 thr ough A.8ATTACHMENT A.1:ACCEPTABLE KNOWLEDGE (AK) CHECKLISTEPA Inspection No.: EPA-SRS-10.05-8Inspection Date: 10/31/2005–11/03/2005Required Technical ElementsProcedure Location/AdequacyVerificationofActivityExamples of ObjectiveEvidenceGeneralAK-1Is the waste TRU bydefinition aspresentedin theLWA?(P.L.102-579)CCP-TP-005,Revision15; CHWACRev.3;P.L. 102-579YesCCP-AK-SRS7Rev.1;CCP-AK-SRS-8Rev.2.Notethatload managementisbeing performed forSRS-7 waste,andanalytical data suggest it maybenecessaryfor SRS-8waste see ItemAK-29).AK-2Do thepresentedvolumes comport with LWA capacityrestrictions?(P.L.102-579)CCP-TP-005,Revision15; CHWACRev.3;P.L. 102-579YesCCP-AK-SRS7Rev.1;CCP-AK-SRS-8Rev.2;CCP-AK-SRS-1 Rev11, CCP-AKSRS-2Rev 8, CCP-AK-SRS-3Rev 3,CCP-AK-SRS-4Rev3,CCP-AK-SRS-5,Rev 2,CCP-AK-SRS-6Rev 1, TWBIR2004forSRS waste, D152.Nodataexaminedidentifiedany issues with respecttowaste volume.AK-3Areanywastesconsidered (or previously considered)HLW?HLW are prohibited.(P.L.102-579)CCP-TP-005,Revision15; CHWACRev.3;P.L. 102-579Partial Verification;seeObjective EvidenceCCP-AK-SRS7 Rev.1 andRev0;CCP-AK-SRS-8Rev.2;D122;D077;D062;D020;C068. PreviousrevisionofSRS-7(rev.0)indicated thatHLWwas generatedat the facility; CCP must ensure that allwaste subsequently includedin wastestreams doesnotmeetthe definitionofHLW.AK-4Areanywastesconsidered (or previously considered)Spent NuclearFuel?(P.L.102-579)CCP-TP-005,Revision15; CHWACRev.3;P.L. 102-579YesCCP-AK-SRS7Rev.1;CCP-AK-SRS-8Rev.2;D122;D077;See commentaryabove.AK-5Arethese defense wastes?(P.L.102-579)CCP-TP-005,Revision15; CHWACRev.3;P.L. 102-579YesCCP-AK-SRS7Rev.1;CCP-AK-SRS-8Rev.2;P010, P006, P001, C003,D077.Waste appearstobedefenserelated baseduponconsiderationspresented inreferenceddocuments examined.RevisionNo.:1AK-1DateofRevision:11/01/05ATTACHMENT A.1:ACCEPTABLE KNOWLEDGE (AK) CHECKLISTEPA Inspection No.: EPA-SRS-10.05-8Inspection Date: 10/31/2005–11/03/2005Required Technical ElementsProcedure Location/AdequacyVerificationofActivityExamples of ObjectiveEvidenceAK-6Whatisthe scopeofauthorization sought(i.e., SCG,newlygenerated vs. retrievablystored, other site-specificbreakdowns)CCP-TP-005, Revision15;CRA 2002Partial Verification;seeObjective EvidenceCCP-AK-SRS7Rev.1;CCP-AK-SRS-8Rev.2;TWBIR2002; CRA,2002. CCPprovideda definition ofnewlygeneratedthat did not comport withDOE’sdefinitioninthe CRA.Thisaffected theproposedscopeof the authorizationsought,inthatthe scopeneeded to beexpanded to includenewlygenerated soilanddebris, notjustretrievably storeddebris and soil.AK-7IsAK being used thatwasassembled prior toanEPAapprovedQAprogram(retrievablystored).If so,whatqualificationprocess isused?Is thiswasteundergoingconfirmation asper theCCA/CRA(100%sampling)[194.24(c)(2)-(5),194.22(a)]CCP-TP-005,Revision15; CHWACRev.3;P.L. 102-579YesCCP-AK-SRS7Rev.1;CCP-AK-SRS-8Rev.2;BDRsforcontainers773A020021,SR570782, SR98079, MDL0506241,MDL0506073.Waste undergoes100%NDA andNDE.AK-8IsAKbeingassembled as waste isgenerated after EPAapprovaloftheQAprogram(newlygenerated)?Isthiswasteundergoingconfirmation asper theCCA/CRA(100% sampling)?[194.24(c)(2)-(5)]CCP-TP-005,Revision15; CHWACRev.3;P.L. 102-579Partial Verification;seeObjective EvidenceCCP-AK-SRS7Rev.1;CCP-AK-SRS-8Rev.2;BDRsforcontainers773A020021,SR570782, SR98079, MDL0506241,MDL0506073.See scope ofauthorizationissue, itemAK-6.Althoughdefinition ofwaste (retrievably storedvs.newlygenerated),all waste regardless of typeisbeing100%characterized asper theCCA/CRA.Personnel TrainingRequirementsAK-9Proceduresrequire staff tobequalifiedtoassemble,compile andconfirmAK data, includingbutnotlimitedto:Identification of requiredreadinglist and successfulcompletionofall requiredreadingincluding, but notCCP-TP-005, Revision15;CCP-QP-002Partial Verification,seeObjective EvidenceCCP-AK-SRS7Rev.1;CCP-AK-SRS-8Rev.2; TrainingRecordsfor JeffHarrison,Kevin Peters,Steve Rose.ExtensiveRCRA training wasexamined, butnotrainingwithrespecttoEPA requirementswasobserved.Itisrecommended thatEPArequirements as perCCA/CRAand 194.8RevisionNo.:1AK-2DateofRevision:11/01/05ATTACHMENT A.1:ACCEPTABLE KNOWLEDGE (AK) CHECKLISTEPA Inspection No.: EPA-SRS-10.05-8Inspection Date: 10/31/2005–11/03/2005Required Technical ElementsProcedure Location/AdequacyVerificationofActivityExamples of ObjectiveEvidencelimitedto:•Applicable portionsofthe WIPP WAPandTSDFWAC•WIPP Compliance Certification DecisionConditions2 and3•State and Federal RCRAregulationsassociatedwithsolidand hazardous wastecharacterization•Discrepancyresolution and reportingprocesses•Site-specific proceduresassociated withwastecharacterizationusing acceptable knowledge•Successful completion of testing to demonstrateunderstandingofrequiredreading list•Completionofinternal and/orexternal trainingprogramspertinent toAK•Participation in internal audits toassessAKprogram•Othermethodologies for demonstratingAKproficiencyas developed onasite-specificbasis(WAPB4, B4-3a)be included inAKEandSPMtrainingprograms. Notethat noEPA-relatedtestingor trainingwasobserved inpersonnelfiles.Procedure ScopeAK-10a.Areproceduresadequate toencompass the spectrumofwastesforwhich authorization issought?b.Aretheredifferentproceduresfornewlygeneratedvs.retrievably storedwaste?Aretheredifferentprocedures for solid,debris, orsoilwaste?Shouldthere be?c.Fornewlygenerated waste, haveadequateproceduresCCP-TP-005,Revision15; CCP-TP066,SW13.3-SOP-CAND-01,ManualIS Rev.5;SRS Procedure6.24;Partial Verification;seeObjective EvidenceCCP-AK-SRS7Rev.1;CCP-AK-SRS-8Rev.2;DR005,DR006, M064.Information fromMoundhadoriginallyidentified Mound Soil waste,butRTRandFastScan of the waste showedmost (i.e.,40ofthe53) toactually bedebris waste.Itdoesnotappearthattherearedifferentprocedures for retrievablystored vs.newlygenerated for the example waste observed(i.e., SRS-7),but site hadalso misidentifiedRevisionNo.:1AK-3DateofRevision:11/01/05ATTACHMENT A.1:ACCEPTABLE KNOWLEDGE (AK) CHECKLISTEPA Inspection No.: EPA-SRS-10.05-8Inspection Date: 10/31/2005–11/03/2005Required Technical ElementsProcedure Location/AdequacyVerificationofActivityExamples of ObjectiveEvidencebeendeveloped andimplemented tocharacterizewasteusing acceptableknowledgeprior topackaging?(WAPB4, B4-3b)the waste asbeing entirelyretrievablystored.Note that SRS-specific wastepackagingprocedures tocharacterizenewlygenerated waste priortopackagingwereexamined, but CCPrepresentativefeltthat this informationmay belacking,sothey did notrely onthis informationandinsteadperformed100% RTR/Assay ofeach container.AssemblingAKInformationand CompilingAKDocumentationinto anauditablerecordAK-11What is thebreakdown of thetypes andquantities ofTRU waste generated/storedatthesite?(WAPB4, B4-2a)CCP-TP-005, Revision15YesCCP-AK-SRS-7 Rev.1;CCP-AK-SRS-8Rev.2;CCP-AK-SRS-1 Rev11, CCP-AKSRS-2Rev 8, CCP-AK-SRS-3Rev 3,CCP-AK-SRS-4Rev3,CCP-AK-SRS-5,Rev.2, CCP-AK-SRS-6 Rev1,TWBIR2004forSRS waste, D152.Dataincludedinthe abovereferences covered thebreakdownand quantity of TRUwastegenerated/storedatthesite.AK-12Do procedurescall for AK informationto be collectedfor:a.241Am,238Pu,239Pu,240Pu,242Pu,233U,234U,238U,90Sr,137Cs+ unexpectedradionuclidesb.ferrous metals(in containers)c. cellulosics,plastics,rubberd.nonferrous metals(in containers)(CRA/CCACh4 andAttachments/Appendices)CCP-TP-005, Revision15;ManualIS Rev.5;SRS Procedure6.24Partial Verification;seeObjective EvidenceCCP-AK-SRS7Rev.1;CCP-AK-SRS-8Rev.2; WSPFsforW027-773A-HETandSR-SD-SOIL, M024, D061,D020,C003,C019,M022,NDA-AKmemoWSW027-773A-HET andSR-SD-SOIL; D152;C074,M025, CCP-TP-005Attachments6,7,and 8 for W027-773A-HETand SR-SDSOIL; P028, P040, P054, P086,WCP9-20.Radionuclide data were adequatelyassembled. CCO representatives expressedlittle confidence inSRS-generatedAKdatapertainingtoWMPs,soAKSummaries didnotinclude any percentagebreakdownorother detailedidentificationofWMPsincludingferrous andnon-ferrousmetals.RevisionNo.:1AK-4DateofRevision:11/01/05ATTACHMENT A.1:ACCEPTABLE KNOWLEDGE (AK) CHECKLISTEPA Inspection No.: EPA-SRS-10.05-8Inspection Date: 10/31/2005–11/03/2005Required Technical ElementsProcedure Location/AdequacyVerificationofActivityExamples of ObjectiveEvidenceAK-13Doproceduresrequire documentation ofradionuclideprocess origin?Are thefacilityandTRUwaste managementoperationscorrelated tospecificwaste streaminformation?(AttachmentB4;CHWACAppendixA.2.2)CCP-TP-005,Revision15YesCCP-AK-SRS7Rev.1;CCP-AK-SRS-8Rev.2;M024,P001, P010,D122,D061,D020, C003, C019, C023, C040, C037,P028, P040, P054, P056, P058,P064,P120.Radionuclide processoriginwasadequately researched, noting that thegenerationofHLW atSRSinBuilding773was notedand shouldbeevaluated whenassigning wastes to this waste stream. SeeItemAK-3.AK-14Arecorrelations between waste streams, with regard totimeof generation,waste generatingprocesses, andsitespecificfacilities clearly described?For newlygeneratedwastes, therate andquantity of waste tobegeneratedshallbedefined.(Attachment B4, B4-3c; CHWACAppendixA,SectionA.2)CCP-TP-005,Revision15Partial Verification,seeObjective EvidenceCCP-AK-SRS7Rev.1;CCP-AK-SRS-8Rev.2;TWBIR;WSPFs forW027-773AHET andSR-MD-Soil; D122.Note thatW027-773A-HET actuallycomprised ofthree separatewaste streams identifiedinthe TWBIR,combined basedon chemicaldata/information.Alsonote that while thesite identified thewaste to begeneratedwithinthe 773A waste streamexamined,CCPhadnotidentified thismaterialasnewlygeneratedwaste (this shouldbedone).See ItemAK-6.AK-15Arewastesstreams appropriately identifiedand arewastes characterizedon awaste streambasis?Arewastesgroupedonawaste streambasis usingAcceptable Knowledgeand are they characterizedinthesamemanner(i.e.,by visual examination) asa newlygeneratedwaste ifawastedoes nothaveallmandatoryAK documentationrequirements?(Attachment B4,Section B-1a)CCP-TP-005,Revision15Partial Verification,seeObjective EvidenceCCP-AK-SRS7Rev.1;CCP-AK-SRS-8Rev.2;TWBIR;WSPFs forW027-773AHET andSR-MD-Soil; D122.SeeAK-14for discussion regardingwastestreamcombination.Note that the 773Awasidentified asbeing“jobcontrol” waste,butTWBIRdescriptions also indicated thatthiswaste mightcontainverylarge,boxeditems. It is ofquestionswhether thiswastewouldbeconsideredjobcontrol,andCCPmust carefully evaluate theboxed materialtoensure it meets all requirements forinclusion inany773waste streams.RevisionNo.:1AK-5DateofRevision:11/01/05ATTACHMENT A.1:ACCEPTABLE KNOWLEDGE (AK) CHECKLISTEPA Inspection No.: EPA-SRS-10.05-8Inspection Date: 10/31/2005–11/03/2005Required Technical ElementsProcedure Location/AdequacyVerificationofActivityExamples of ObjectiveEvidenceAK-16Doproceduresdemonstrate a logicalprogressionfromgeneral facilityinformationto more detailedwastestream-specific information?CCP-TP-005,Revision15YesCCP-AK-SRS7Rev.1;CCP-AK-SRS-8Rev.2;D152,D061,D037, P028, P040,U018.Datawere available to showprogrammatic towaste streaminformation.AK-17Doestheprocess includereviewofAKinformation toevaluateanddocumentAK-AKinformationdiscrepancies?(CH WACSection A.2.2.3, AttachmentB4, SectionB4-3)CCP-TP-005,Revision15YesCCP-AK-SRS7Rev.1;CCP-AK-SRS-8Rev.2;DR005,DR006, M064. Thediscrepancies examine dealt withtheincorrectidentificationofmound soilvs.mound debris.Moundhadindicatedthatsoil was present incertain drums, butFastScan showed thesedrumsto actuallybecomprised ofdebris.TheDRs werepreparedtodocumentthisincidence.AK-18Doproceduresrequire collection ofinformation regardinghowwaste is tracked and managed at thegenerator site(includinghistoricalandcurrentoperations)?(ChWACSectionA.2;AttachmentB4Section B4-2a)CCP-TP-005,Revision15YesCCP-AK-SRS7Rev.1;CCP-AK-SRS-8Rev.2;G-WestdatabaseQuery;Transuranic WasteCharacterizationDatabase,29-90 Forms;CTS/PTSprintouts. CCP acquiresdrum-specific AK(i.e., historic information)into theTransuranic WasteCharacterizationDatabase, whichisfurther queriedtoobtainthe WIPP-specific Go-Westinformation.This AK informationisusedto assignwastestreams, etc.Measurementdata obtainedby CCP is enteredintotheCTS/PTS system, which alsotracksNCRs.Data entry fromthis systemintotheWWISwasnotexamined.AK-19IsAK informationcompiledinanauditablerecord,includingaroadmapfor all applicable information?CCP-TP-005,Revision15YesCCP-AK-SRS7Rev.1;CCP-AK-SRS-8Rev.2;CCP-TP-005Attachments1 and4,waste streams W027-773A-HET; SR-MDSOIL.Attachments correlate mandatoryprogramandwaste streaminformationwithreferences tosupport theRevisionNo.:1AK-6DateofRevision:11/01/05ATTACHMENT A.1:ACCEPTABLE KNOWLEDGE (AK) CHECKLISTEPA Inspection No.: EPA-SRS-10.05-8Inspection Date: 10/31/2005–11/03/2005Required Technical ElementsProcedure Location/AdequacyVerificationofActivityExamples of ObjectiveEvidencedetermination;Attachment4isa completereferencelist.AK-20Has a reference list been providedthat identifiesdocuments, databases, Quality Assurance protocols, andother sourcesofinformation that supportAKinformation?(Attachment B4,Section B4-3c)CCP-TP-005,Revision15YesCCP-AK-SRS7Rev.1;CCP-AK-SRS-8Rev.2;Attachment4forwaste streamsW027-773A-HETand SR-MD-SOIL.Reference lists were sufficient. It isrecommended,however, thatsomesortofuniqueidentifierbe added toeachreference indicatingthe waste streamitapplies to, asthe samereference listnumbers areused indifferentreportstoidentifydifferentreferences,whichcanlead toconfusion.AK-21Havethefollowingmandatoryinformation requirementsbeen identified?Mapofthe site that identifiesthe areas andfacilitiesinvolvedinTRUwastegeneration, treatment, and storageFacilitymissiondescription relatedtoTRUwastegeneration andmanagementDescription ofthe operationsthat generateTRU waste atthe site andprocess information,including:•Area(s)or building(s)fromwhichthe waste streamwasorisgenerated•Estimated waste streamvolume and time periodofgeneration•Wastegeneratingprocessdescription for eachbuilding orarea•Process flowdiagrams,ifappropriate•Generalizedmaterial inputsorother informationthatCCP-TP-005, Revision15CCP-AK-SRS7 Rev.1;CCP-AK-SRS-8Rev.2;P001, P006, M024,D152,D122,D077, D061, D020, D001, D074, D037,M025, SCO8-20, IO31, IO82,P028,P040,P054, P058, P064,P120,U018.Informationpresented identifiedthespecific programmaticand wastestreaminformationrequired inthis checklist item.Thephysical/chemical informationthatcould affectisotopicdistribution are mostthoroughly presentedinAK-NDAmemosforwaste streamW027-773A-HETandSR-MD-SOIL, as arenumeric adjustmentsmade.Isotopicratios arepresentedwhenavailable for specific componentsofthewaste (e.g.,SR-MD-SOIL),but couldnotbe presentedforwastes originating fromexperimental activities (e.g.,W027-773AHET).For both, historicGo-West datawereusedtocalculate the radionuclidedistribution ona waste streambasis, andwere alsousedtoidentify the“toptwo”RevisionNo.:1AK-7DateofRevision:11/01/05ATTACHMENT A.1:ACCEPTABLE KNOWLEDGE (AK) CHECKLISTEPA Inspection No.: EPA-SRS-10.05-8Inspection Date: 10/31/2005–11/03/2005Required Technical ElementsProcedure Location/AdequacyVerificationofActivityExamples of ObjectiveEvidenceidentifies the radionuclide contentof thewaste streamand thephysical waste form•Types and quantities ofTRUwastegenerated,includinghistoricalgeneration throughfutureprojections•Physical/chemical waste compositionthat couldaffectisotopicdistribution(i.e.,processestoremoveingrown241Am)•Statement of all numericaladjustments applied toderive thematerial’s isotopicdistribution,e.g.,scaling factors,decay/ingrowthcorrections andsecular equilibriumconsiderations•Specification ofisotopic ratiosforthe 10 WIPPtrackedradionuclides and,ifapplicable, theradionuclidesthat comprise95%of thehazard(CHWACSectionA.2.2;AttachmentB4, B4-2a,B4-2b)nuclidespresentinwaste bothbyweightand byactivity.It shouldbenotedthattherewere slightly conflicting conclusionspresented in the AK Summaries vs. theAK-NDA memos withrespect totopnuclides identified;it is recommendedthatthe site revisit bothto ensureconsistency.AK-22Does the site haveprocedures for the collection ofsupplemental information?Examples ofsupplementalinformation,fromCHWAC,include:•Safeguards andsecurityandothermaterialcontrolsystems/programs•Reports ofnuclearsafety orcriticality•Accidents involvingSNM waste packagingand wastedisposal•Buildingornuclear materialmanagementarea logsorinventoryrecords•Site databasesthatprovideSNM ornuclearmaterialCCP-TP-005,Revision15YesCCP-AK-SRS7Rev.1;CCP-AK-SRS-8Rev.2;BurialGroundandotherrecords;P006, P001,D122,D077, D061, D020,C003, C019, C023, C040, C068,D001,D037,IO31,IO82, P028, P040, P056,P058, P064, P086,U018,Go-WestDatabaseprintouts;various historicBurialGround datasheets.CCP has assembledsupplementalinformation (manyofwhichare examples fromthe example listingprovidedto the left).RevisionNo.:1AK-8DateofRevision:11/01/05ATTACHMENT A.1:ACCEPTABLE KNOWLEDGE (AK) CHECKLISTEPA Inspection No.: EPA-SRS-10.05-8Inspection Date: 10/31/2005–11/03/2005Required Technical ElementsProcedure Location/AdequacyVerificationofActivityExamples of ObjectiveEvidenceinformationtest plans•Research project reports,orlaboratorynotebooks thatdescribe theradionuclidecontentofmaterials usedinexperiments•Information fromsite personnel•Historical analytical data relevanttoisotopicdistribution inthe waste stream(CH-WACSectionA.2.2.2;AttachmentB4SectionB4-2c)AK-23Is all necessarysupplemental informationassembledandhas itbeen appropriately used?(SectionB4-2c)CCP-TP-005,Revision15Partial Verification,seeObjective EvidenceCCP-AK-SRS7Rev.1;CCP-AK-SRS-8Rev.2;Go-Westquery,varioushistoricdata informationsheets; M022.Itshouldbe notedthatthe physicalwastedescriptorassignmentofWMCwasnottechnicallycorrect based upondatareviewed (e.g.,M022,etc.)for WSW027-773A-HET (i.e.,a WMC ofS5300, notS5400isapparentlycorrect,basedondatareviewed).CCPdidnotchoose S5300becausetheyhadnoconfidence inSRS waste generating/identification process controls toensurethat the actualwaste contentswerecorrectly identified, so it chose thebroaderS5400category. Insodoing,the CCPelected to make all AK Accuracycalculations based on WMCsincorrectasthey arenot basedonwhat appearstobethe actualAK results.RevisionNo.:1AK-9DateofRevision:11/01/05ATTACHMENT A.1:ACCEPTABLE KNOWLEDGE (AK) CHECKLISTEPA Inspection No.: EPA-SRS-10.05-8Inspection Date: 10/31/2005–11/03/2005Required Technical ElementsProcedure Location/AdequacyVerificationofActivityExamples of ObjectiveEvidenceAK-24a.Arewaste categorization schemes presentedand arethey appropriate?b.Arewaste identification/categorization schemesrelevanttotheisotopic compositionofwaste?(AttachmentB4Section B1,CH-WACpageix,AppendixA.2)CCP-TP-005,Revision15; CHWACRev.3Partial, seeObjectiveEvidenceCCP-AK-SRS7Rev.1;CCP-AK-SRS-8Rev.2;M022.See ItemAK-23, above.Withrespectto categorization schemesassociatedwithisotopic distribution,neither of the two wastestreams examinedweresegregated based onisotopicdistribution/information, althoughinattemptingtofollow thedefinitionofwastestreampresented in the CH-WAC, Moundwastehad a relatively distinct isotopiccharacter.AK-25Havedatausesand limitations beenassembled andarethey technicallyadequate?(CRA/CCA;CH-WACAppendix A, Section A.2.2.3)CCP-TP-005,Revision15YesCCP-AK-SRS7Rev.1;CCP-AK-SRS-8Rev.2;CCP-TP-005Attachment3Acceptable KnowledgeSourceDocumentSummary. This attachmentis completedand placed atop eachreference; theattachment includesa location whereAKsourcedocument limitations aredocumented.Generatingan AK Summary/AK DocumentAK-26Site documents/procedures require the facility prepare anAK summary document thatsummarizes all informationcollected, including thebasis for all waste streamdesignations.IstheAKSummaryofsufficientscopeanddetail?(CH-WACAppendix A Section A.2.2;AttachmentB4Section B4-2b)CCP-TP-005, Revision15YesCCP-AK-SRS-7 Rev.1;CCP-AK-SRS-8Rev.2;CCP-AK-SRS-1 Rev11, CCP-AKSRS-2 Rev.8,CCP-AK-SRS-3 Rev.3,CCP-AK-SRS-4Rev.3,CCP-AK-SRS-5,Rev.2, CCP-AK-SRS-6 Rev.1.Scopeanddetail oftheseSummaries appears tobeadequate.AK-27Areconclusions and interpretationspresented intheAKSummary technically soundand supported by referencedCCP-TP-005,Revision15Partial Verification,seeObjective EvidenceCCP-AK-SRS7Rev.1;CCP-AK-SRS-8Rev.2.Documents mustbeperiodicallyupdatedtoensurethatloadmanagementdiscussion is accuratebasedon analyticalRevisionNo.:1AK-10DateofRevision:11/01/05ATTACHMENT A.1:ACCEPTABLE KNOWLEDGE (AK) CHECKLISTEPA Inspection No.: EPA-SRS-10.05-8Inspection Date: 10/31/2005–11/03/2005Required Technical ElementsProcedure Location/AdequacyVerificationofActivityExamples of ObjectiveEvidencemandatory and supplemental information?data (e.g.,AK-8),and to ensure that theradionuclideinformation (topnuclideidentification, etc.).inthe AK Summariesand theNDA-AK memocoincide.AK-28IfAKdata discrepancy is identified,sitewill evaluate thesourceofthe discrepancy todetermine ifdiscrepantinformationiscredible.Informationthat isnotcrediblewill beidentifiedas suchandreasons for dismissingwillbejustifiedinwriting.Limitationsconcerninginformationwill bedocumentedin theAKrecordandsummarized in theAK report.Ifadiscrepancy cannotberesolved, the site will perform direct measurements forthe impactedpopulation.(CHWACAppendixA.2,SectionA.2.2.3)CCP-TP-005,Revision15YesCCP-AK-SRS7Rev.1;CCP-AK-SRS-8Rev.2;DR005,DR006, M064.AspresentedinAK-10, AK-AK data(i.e.,Mound drumspecificdata and FastScan)showeddiscrepancies with respect toidentification of SCG.Thediscrepancy isadequately documented, and limitationofMound and othersite-specificdata (e.g.,Burial Groundrecords,etc.) was notedbyAKEs.It shouldbenoted that the AKEsexpressed hesitancyinusingpreviouslymeasurement data bythegenerator sites,but theAK-NDAmemoforW027-773AHET explicitlyindicates that thisinformation willbe providedtoNDAmeasurement personnel.The AK-NDAmemos document AKdata limitations.AK-29Is loadmanagementbeingproposed?DoestheAKSummary includethe followingfromthe CHWAC,Rev. 3 AppendixE?Each TRUwaste streamselected for payloadmanagement mustincludein its acceptableknowledgesummary report anestimate ofthe totalwaste volumeandthe percentageofthewastevolumethatisaboveandbelow 100 nCi/g.(Itshouldbenotedthatthisinformation, althoughbasedonthebestavailable AKinformation,ispreliminary andsubject totheperformance ofWIPP-certifiedNDA measurements andcannotandwillnotbeusedasa measureofAKCCP-TP-005,Revision15Partial Verification,seeObjective EvidenceCCP-AK-SRS7Rev.1;CCP-AK-SRS-8Rev.2.,M022,M028.Note that the AKSummaryfor SR-MD-SOIL does notanticipate loadmanagement, butmeasurement data apparently show theretobe atleastoncecontainerthatmightrequire loadmanagement. Modificationofthe AKSummarywouldbe inorderifloadmanagementofSR-MD-SOILwere tobeused.RevisionNo.:1AK-11DateofRevision:11/01/05ATTACHMENT A.1:ACCEPTABLE KNOWLEDGE (AK) CHECKLISTEPA Inspection No.: EPA-SRS-10.05-8Inspection Date: 10/31/2005–11/03/2005Required Technical ElementsProcedure Location/AdequacyVerificationofActivityExamples of ObjectiveEvidenceaccuracy.) (ReferenceE3)(CH-WAC, AppendixE)IdentifyingManagement Controls ForDiscrepant Items/Containers/Waste Streamsand Data Management/TrackingAK-30Arenonconforming wastes segregated?AreNCRsdisposition inanappropriate and technically defensiblemanner?(Attachment B4,Section B4-3b, AttachmentB3, SectionB3-13)CCP-TP-005,Revision15YesCCP-AK-SRS7Rev.1;CCP-AK-SRS-8Rev.2;NCR-SRS 0561, NCR-SRS-0289,CTS database.CCPtracks containerNCRsinthe CCP CTS database toensure thatNCRs areappropriately identified andaddressed.Nonconforming waste wouldbe segregatedas necessary.AK-31Do site procedures require that additional informationbecollectedbefore waste may beshippedif therequiredAKinformationisnotavailablefor awaste streamorifavailableAK ispooror unacceptable?(Attachment B4,Section B1)CCP-TP-005,Revision15YesCCP-AK-SRS7Rev.1;CCP-AK-SRS-8Rev.2.SeeAKItems 28and10.ConfirmingAK Information with OtherAnalyticalResultsAK-32Do theseproceduresfacilitatethe mandatory traceabilityanalysisperformed for eachSummaryWasteCategoryGroupexaminedduringthe audit,noting that EPA willdetermine whether the available waste streams adequatelydemonstrate the full characterization processfor theproposedscope?(Attachment B4,Section B4-2)CCP-TP-005,Revision15YesCCP-AK-SRS7Rev.1;CCP-AK-SRS-8Rev.2;BG RecordSR98079,TRUWastePackage Data/Burialgroundrecordfordrum570782;Retrievable AlphaWasteforPad and ConcreteDrum570782;TRUWaste Container CharacterizationformforDrum773A-02-0021;Go-WestQueryforcontainersSR570782,MDL0506073;MDL0506241;773A020021;SR98079;PTS/CTSPrintouts; BDRsfor containers773A020021, SR570782,SR98079,MDL0506241, MDL0506073.Traceability was demonstrated.RevisionNo.:1AK-12DateofRevision:11/01/05ATTACHMENT A.1:ACCEPTABLE KNOWLEDGE (AK) CHECKLISTEPA Inspection No.: EPA-SRS-10.05-8Inspection Date: 10/31/2005–11/03/2005Required Technical ElementsProcedure Location/AdequacyVerificationofActivityExamples of ObjectiveEvidenceAK-33If AKwas used(i.e.,datacollectedpriortoQAprogram),what methodwas employedtoqualify the information?Approvedmethodsorpeer review, corroboratingdata,confirmatory testing,andQA programequivalency?Ifconfirmatory testingisused,has the followingbeenconsidered(fromCH WAC)At a minimum,toconfirmexistingAKdata,it isnecessary to compare ratiosofthe two mostprevalentradionuclidesintheisotopicmixa. For238Pu,239Pu,240Pu,241Pu,242Pu and241Am:Confirmation canbe accomplishedvia comparisonofmeasured andAK valuesfor239Pu/240Pu forweapons gradeplutonium;238Pu/239Pu forheat sourceMeasured241Amcan be usedto calculate241Pu (forsubsequent AK comparison)if timeof chemicalseparation isknown (no241Amattimeof separationassumed)241Pu canbe compared (by ratio) toconfirmAK ofany Pu isotopeassociatedwith WG/RG(i.e.,239Pu or240Pu)238Pu fromAKforwg/rg Puisassumed tobevalidiftheAK values of239Pu and240Pu have beenconfirmedby measurement242Pu calculatedby correlation techniques, since itcan’tbe measuredb. For235U,233U, 238U,234U:Were they tracked or measuredin AK information?If novalidAK exists, datageneratedcanonlybeusedto detector calculate, or confirmabsenceratiosforCCP-TP-005,Revision15, CHWACRev.3Partial Verification,seeObjective EvidenceCCP-AK-SRS7Rev.1;CCP-AK-SRS-8Rev.2NDA-AK Memos forWaste StreamsW027-773A-HET andSR-MD-Soil.SRS-W027-773A.The AK-NDAmemostates “...thetwo most prevalentradionuclides,byweightexpected inSavannah River Sitewaste streamSRW027-773A-HET are238U and239Pu,followed by238Pu.”Note that wastefromthis streamareexperimental inorigin, sospecific confirmation ofplutoniumbyisotopicdistributionforweaponsgradevs.heatsource couldonlybe accomplishedona drumbydrumbasis. Tothisend, theAK-NDA memostates: “Thedrums inthiswaste streamcontain a mixture of Puratios...About300 drumsappeartocontainheatsource Puwithapproximately81.5%238Pu.Over800drums contain90% (byweight)239Puvalues.Afewdrumscontainover 99%239Pu. Both the238Pu and239Puratiosvarywidely for drums inthis wastestream. Isotopic ratios arepresented on adrum-by-drumbasisonthespreadsheetprovidedbyAKpersonnel...The242Puvalue iscalculated based on238Puand or239Pu weight.Ifheat source238Pu ispresent, the mass of the238Puismultipliedby a scaling constant tocalculate242Puvalues.Ifweapons-grade239Puispresent,the measuredmass of239Puis usedwiththemulti-groupanalysis value todetermine the242Puvalue. Thevalue is theisotopicdistribution orwt% for each isotope inaspecific mix. Tocalculate242Pu, themeasured239Pu (weapons-grade) mass ismultipliedbythe242Pu/239Puwt% ratio”.RevisionNo.:1AK-13DateofRevision:11/01/05ATTACHMENT A.1:ACCEPTABLE KNOWLEDGE (AK) CHECKLISTEPA Inspection No.: EPA-SRS-10.05-8Inspection Date: 10/31/2005–11/03/2005Required Technical ElementsProcedure Location/AdequacyVerificationofActivityExamples of ObjectiveEvidence234U calculated from235U enrichmentIfvalidAK exists canconfirmwithcertifiedsystems234U calculated by235U enrichment, because234Ucan’t bemeasuredc. For137Csand90Sr:ConfirmedbyWIPP-certified system(directmeasurement or comparison of241Ampeak at662keVtoother241Ampeaks(disproportionate241Ampeak at 662keV could mean presenceof137Cs)90Sr calculated from137Csusingscaling factorsOtherradionuclides – must identify viaNDAandshouldidentify viaAK(40 CFR149.22(b), CHWAC,AppendixA,SectionA.2.1)TheNDA memos states that U234will bequantified by“calculation,” but does notprovideorreferencetheformula tobeused.The AK-NDA memofurtherstatesthat “quantificationof236U is fromprevious assayat SRS; therefore,236Uvaluescan bescaled fromparent ordaughter.”The AK-NDAmemogoesontonote that252Cf,244Cm, and238U maybepresentinseveraldrums, anddrum-specificAK will beusedto identify thesecontainerspriorto assay.Inshort,NDArelies heavily onAK for preliminary drumcontents,but NDA will attempt tomeasureall nuclides possible.SR-MD-SOIL:TheAK-NDA memostates“The predominantradionuclides, byweight% are238Pu and237Np.The predominantradionuclidesby activity % are238Pu and241Am(decay correctedfor46 years). Thememoprovidedplutoniumisotopicdistributionsforheat grade,war reserve(weaponsgrade)and neutronsourceplutonium.WithregardtohowAK will beusedbyNDApersonnel,the memostates“Radioassayperformedfor confirmationofthis wastestreamwillconsistofgammaanalysis usingthe IQ3gammaspectroscopysystemsupplemented,asneeded,by"neutrononly" datafromtheMobile IPANsystem.” TheAK-NDAmemogoesonto state that the242Pu valueiscalculatedbasedon238Pu and/or239Puweight %. Ifheat sourcePu is present, themass of the238Puis multipliedbythescaling factor2.5xl0-3...to calculate the242Pu mass. Ifwar reservePuis present,RevisionNo.:1AK-14DateofRevision:11/01/05ATTACHMENT A.1:ACCEPTABLE KNOWLEDGE (AK) CHECKLISTEPA Inspection No.: EPA-SRS-10.05-8Inspection Date: 10/31/2005–11/03/2005Required Technical ElementsProcedure Location/AdequacyVerificationofActivityExamples of ObjectiveEvidencethe measuredmass of239Puis usedwithascalingfactor providedbythemulti-groupanalysis (MGA) isotopicsoftwaretodetermine the242Pu mass. Ifagivendrumcontainsa mixtureofplutoniumgrades, thewar reserve Pu compositionwill beusedtoscale242Pu.This will provideaconservativelylowresult so as not tooverestimate the amountof242Pu,whichmightresult inmisclassification of a LLWas TRU. Thememogoesonto state, “The234U value is calculatedbased on238Puand/or239Pu weight%.IfheatsourcePuispresent, the mass of the238Puismultipliedbya scaling constant(0.44for46yearold238Pu) tocalculate the234U mass.IfwarreservePu is present, the measuredmass of239Puisusedwitha scalingfactorprovidedbythe multi-groupanalysis (MGA)isotopic software to determine the234Umass. Ifagivendrumcontainsa mixtureofplutoniumgrades,theheatsource Pucompositionwill beusedtoscale234U.The quantification of90Sr isperformed byusing thedirectlymeasured137Cs activityvalue inthe calculation.90Sr isdeterminedbyassumingan activity ratioof137Cs /90Sr= 1.4,althoughthe IQ3uses a1:1activity ratio.”Summary. The process iswelldescribedinNDA memos, but theoriginofallscaling factors mustbebetter referenced.For W027-773A-HET,the234U calculationshouldbespecified.Inall instances“conservative” assumptionsmust takeintoaccountrequirements of theCRA.RevisionNo.:1AK-15DateofRevision:11/01/05ATTACHMENT A.1:ACCEPTABLE KNOWLEDGE (AK) CHECKLISTEPA Inspection No.: EPA-SRS-10.05-8Inspection Date: 10/31/2005–11/03/2005Required Technical ElementsProcedure Location/AdequacyVerificationofActivityExamples of ObjectiveEvidenceAK-34Ifwasteis generatedafteranEPAapproved QAprogram,are radioassayand NDEresults compared tothe dataassembly process as acrossreference toverifyimplementationofthe as-generated characterizationprogram?(194.24 (c)(3);194.22(b))CCP-TP-005, Revision15CCP-AK-SRS7 Rev.1;CCP-AK-SRS-8Rev.2;TWBIR2002,D152, CRA, ManualNumber 1s;SRSProcedure 6.24.See ItemAK-6, above.Note that CCPexpressedlittle confidence insomeaspects ofthenewlygenerated waste dataassemblyprocessat SRS, which coloredhow theyinterpreteddata(e.g.,WMP,WMC data).AK-35Thisprocedurerequiresa reevaluation ofAKifNDEidentifies it tobeadifferentwaste matrixcode.Thisprocedure describes howthe wastemustbe reassigned,based onthe AKreevaluation.(Attachment B4,Section B4-3d)CCP-TP-005, Revision15YesCCP-AK-SRS 7Rev. 1;CCP-AK-SRS-8Rev..2;M064, DR005, DR006.Notethatthe misidentificationofWMCvia RTRperformed outside oftheprogram(FastScan, etc.) was considered anAK-AKdiscrepancyandwasnotcataloged asanNDEdeterminationofpoor AK. Whileprocedurally correct, this does givetheimpressionthatAKwas adequate, when inactualitypost AKNDE was usedtoidentify the issue.AK-36Does the generator sitehavewrittenprocedures for newlygenerated waste todocument the confirmationofacceptable knowledgeinformation with visualexaminationpriortoor duringwaste packaging?Dotheseprocedures address therequiredelementsin3.4-3d?(AttachmentB4, Section B4-3d)CCP-TP-005,Revision15YesCCP-AK-SRS7Rev.1;CCP-AK-SRS-8Rev.2.CCPhas elected to RTR all waste,includingnewlygeneratedandretrievablystoredwaste.AK-37Procedures require the followingsteps tobefollowedifwastes are reassigned toadifferentwaste matrixcodebased onNDE:•Review existinginformationbasedonthe containerCCP-TP-005,Revision15YesCCP-AK-SRS7Rev.1;CCP-AK-SRS-8Rev.2.Noexamples of thisprocess wereprovided;see itemAK-35, above.RevisionNo.:1AK-16DateofRevision:11/01/05ATTACHMENT A.1:ACCEPTABLE KNOWLEDGE (AK) CHECKLISTEPA Inspection No.: EPA-SRS-10.05-8Inspection Date: 10/31/2005–11/03/2005Required Technical ElementsProcedure Location/AdequacyVerificationofActivityExamples of ObjectiveEvidenceidentification number anddocumentall differences•Reassess and document all analytical data associatedwiththe waste•Reevaluatewaste material parameter determinationsand documentany changes•Reevaluatetheradionuclidecontentanddocumentany changes•Verify anddocument that thereassignedwastematrixcodewasgeneratedwithin the specifiedtime period,area and buildings,wastegenerating process,and thatthe process material inputs are consistentwiththewaste materialparameters identifiedduringradiographyorvisualexamination•Record all changes to acceptable knowledgerecords•Ifdiscrepancies exist in theacceptableknowledgeinformationfor thereassigned waste matrixcode,complete a nonconformance report,document thesegregation ofthiscontainer,and definethecorrectiveactionsnecessary tofully characterize thewaste(Attachment B4,Section B4-3d)AK-38Has the acceptable knowledge expert calculated thepercent changes inmatrixparameter categories (MPCs)basedon AK and NDE/VE?Wereaccuracyevaluationsassigned?Are theseacceptable?(AttachmentB4,SectionB4-3e;CH-WACAppendixA,Section A.6.5)CCP-TP-005,Revision15Partial Verification,seeObjective EvidenceCCP-AK-SRS7Rev.1;CCP-AK-SRS-8Rev.2;MiscertificationRateCalculation,M022, CCP-TP-005Attachment14.Moundwaste, Lot 1 AKAccuracyCalculationswere examined and appearedadequate, althoughthe documentincludedno supportinganalytical data. AKAccuracy calculationsareoflittle valuebecause they arenon-specificwithrespecttonuclidecalculations. TheWMCaccuracy for both soil and Building773debriswas compromised in that an NDERevisionNo.:1AK-17DateofRevision:11/01/05ATTACHMENT A.1:ACCEPTABLE KNOWLEDGE (AK) CHECKLISTEPA Inspection No.: EPA-SRS-10.05-8Inspection Date: 10/31/2005–11/03/2005Required Technical ElementsProcedure Location/AdequacyVerificationofActivityExamples of ObjectiveEvidencetechniquewasusedtoprescreen soildata,and a too-broadWMC assignment wasassigned byAKtoW027-773A-HET.NDA-AKDataSharingandCommunication/ProceduralizationAK-39Are thefollowingbullets addressedwithrespect toAKNDA communication anduseofAKdatabyNDApersonnel?Do proceduresrequire the identificationofAK datalimitations?AreAKdata and associated limitations communicated toNDApersonnel and is thisrequiredbyprocedure?Howis AKusedbyNDA?Do AK andNDA personnelcommunicate and agreeabout the useofAK?Is thisagreement proceduralized?(CH-WAC, AppendixA)CCP-TP-005, Revision15.Section 4.4.20YesCCP-AK-SRS7Rev.1;CCP-AK-SRS-8Rev.2; AK-NDA memos forwaste streamsSR-MD-SOILandW027-773A-HET.CCPhasproceduralizeda requirement thatNDA andAKpersonnelcommunicate withrespecttouse ofAKdatabyNDApersonnel.The memocommunicatesdatalimitationsand how AKwill beusedbyNDApersonnel. SeeItemAK-33, above.Auditing of AKRecords andAK DiscrepancyIdentification/ResolutionAK-40Haveinternalauditsbeenperformed?(Attachment B4,Section B4-3e)CCP-TP-005,Revision15YesCCP-AK-SRS7Rev.1;CCP-AK-SRS-8Rev.2;SRS CCP Project SurveillanceReport.Internalauditsareperformed,butthis audit apparently tookplace inCarlsbadrather thanthesite. It isrecommendedthataninternal audit atSRS beperformed withrespect toAK.RevisionNo.:1AK-18DateofRevision:11/01/05ATTACHMENT A.1:ACCEPTABLE KNOWLEDGE (AK) CHECKLISTEPA Inspection No.: EPA-SRS-10.05-8Inspection Date: 10/31/2005–11/03/2005Required Technical ElementsProcedure Location/AdequacyVerificationofActivityExamples of ObjectiveEvidenceAK-41Has awastestreambeenrevokedbasedeitheronAKinformationorreassessment as part ofreconfirmation?Ifso, wasthe procedure(s) followed?(Attachment B4,Section B4-4)CCP-TP-005,Revision15YesCCP-AK-SRS7Rev.1;CCP-AK-SRS-8Rev.2.Noexample available todate.AK-42Ifdata consistently indicatediscrepancies withacceptableknowledge information,the site increases sampling,reassessesthematerials andprocesses thatgenerate thewaste, and resubmits waste streamprofileinformation.(CH-WACSectionA.2.2.3;AttachmentB4,SectionsB4-3b, B4-3d)CCP-TP-005,Revision15YesCCP-AK-SRS7Rev.1;CCP-AK-SRS-8Rev.2.Noexample available todate.QA Objectivesfor AK and OtherElementsAK-43Areacceptable knowledgeprocessesconsistently appliedamongallgeneratorsites, anddoes eachgeneratorsitecomply withthe followingdataquality requirements foracceptable knowledge documentation:a.Precision- Precisionisnot applicable to AK(seeAttachment B4)b.Accuracy - Accuracy is thedegreeof agreementbetweenanobservedsample result and the truevalue.Thepercentageofwaste containerswhichrequirereassignmenttoa new waste matrixcode based onthereevaluation of acceptable knowledgeandsamplingand analysisdata will bereportedas a measure ofacceptableknowledge accuracy. Accuracybasedonradionuclide contentistypicallyassessedbycomparingmeasuredresults withAKdata.c.Completeness - Completeness is an assessment of theCCP-TP-005,Revision15Partial Verification,seeObjective EvidenceCCP-AK-SRS7Rev.1;CCP-AK-SRS-8Rev.2.AcceptableKnowledge AccuracyReport, MoundWaste.AKaccuracycalculations were baseduponCCP-TP-005requirements, andarenot ofenoughdetailtobeusefulwithrespecttoradionuclidecomparisons. Further,accuracywithrespect toWMC assignment wascompromisedfor theW027-773A-HETwaste streambecause theWMC assignedwasbroaderthan couldbe assignedbasedonavailable data; the SR-MD-SOILAKAccuracydidnot take into account thefactthat every drumofthe soil matrixhad tobeFastScanned toassessdrumcontents.Because each containerundergoesRTR/VE andNDA,EPAbelieves that thewastes arebeing appropriatelycharacterized regardless ofanyRevisionNo.:1AK-19DateofRevision:11/01/05ATTACHMENT A.1:ACCEPTABLE KNOWLEDGE (AK) CHECKLISTEPA Inspection No.: EPA-SRS-10.05-8Inspection Date: 10/31/2005–11/03/2005Required Technical ElementsProcedure Location/AdequacyVerificationofActivityExamples of ObjectiveEvidencenumberofwaste streams or number ofsamplescollectedto the number of samples determined tobeuseable through thedatavalidationprocess.Theacceptable knowledge record mustcontain 100percentofthe informationspecifiedin SectionB4-2.Theusability of theacceptable knowledgeinformationwill beassessedfor completeness duringaudits.d.Comparability - Data are consideredcomparablewhenone setofdata can becompared toanother setofdata. Comparability is ensured throughsitesmeetingthe trainingrequirements and complyingwiththe minimumstandardsoutlinedforproceduresthat areusedtoimplement the acceptable knowledgeprocess. CH-WACSectionA.6.5:Additionally,comparison ofmeasured data withAK-derivedor-basedvalues,asapplicable,provides ameans toassess comparability onawaste streambasis.e.Representativeness- Representativenessexpresses thedegree towhich sample dataaccurately andpreciselyrepresent characteristics ofapopulation.Representativeness isaqualitative parameter thatwillbesatisfiedbyensuringthattheprocess ofobtaining,evaluating, and documenting acceptable knowledgeinformationisperformedinaccordancewith theminimumstandards establishedin SectionB3.Sitesalsomust assess anddocumentthe limitations of theacceptableknowledge informationusedto assignwaste parameters.(Attachment B4,Section B4-3e)miscalculationormisrepresentationwithrespecttoAK Accuracy.AK-44Does the generator site address quality control bytrackingitsperformance withregard totheuse ofacceptable knowledge by:1)assessing thefrequencyofCCP-TP-005,Revision15YesCCP-AK-SRS7Rev.1;CCP-AK-SRS-8Rev.2;AKConfirmation Checklist(Attachment13). Thesite documentedthemound AKissues withrespecttoidentification of SCG, andconfirmationisRevisionNo.:1AK-20DateofRevision:11/01/05ATTACHMENT A.1:ACCEPTABLE KNOWLEDGE (AK) CHECKLISTEPA Inspection No.: EPA-SRS-10.05-8Inspection Date: 10/31/2005–11/03/2005Required Technical ElementsProcedure Location/AdequacyVerificationofActivityExamples of ObjectiveEvidenceinconsistenciesamong information, and2)documentingthe resultsof acceptableknowledge confirmation throughradiographyorvisualexamination?Inaddition,theacceptable knowledge processand wastestreamdocumentation must beevaluatedthrough internalassessments byquality assuranceorganizationsandassessments byauditors orobservers external totheorganization(i.e., CBFO,NMED,EPA).(SectionB4-3e)performed usingVE and/orRTR.Internalassessments are performed (see ItemAK40,above).AK-45Didthegenerator site implement,ordoes it currentlyimplement, process controls toensure that prohibiteditemsare documented and managed inaccordancewithsite-specific certificationplans and that thefollowingminimumsitespecific controls:•Identifythe organization(s) responsibleforcompliance withadministrative controls•Identify theoversightprocedures andfrequency ofactionstoverify compliance withadministrativecontrols•Develop on-the-job training specific to administrativecontrolprocedures•Ensurethatpersonnelmaystopworkifnoncompliance withadministrative controlsisidentified•Develop anonconformance process that complieswiththe requirements inSection B3-13oftheWAPto document and establish correctiveactions•Address controlled changes toWAP-relatedplansorproceduresaspart ofthe nonconformanceandCCP-TP-005,Revision15Partial Verification,seeObjective EvidenceCCP-AK-SRS7Rev.1;CCP-AK-SRS-8Rev.2;SRSprocedures ManualNo1s, andSRS Procedure6.24;SW15.3-SOPCAND-01, Rev15;CCP-TP-066;P001,P006, P010,NCR-SRS-0561, 0289. Thegenerator site,SRS, implementsprocedurestocontrol the inclusion ofprohibiteditemsinwaste as it is generated,and hashistorically implemented procedures tocontrolwaste content.NoSRS-CCPprocedures tocontrolnewlygeneratedwaste contentwereexamined aspartof theAKportion ofthe EPAinspection.Itisrecognized that SRS-CCP implementscharacterizationprocedure CCP-TP-066 toperform“FastScan”on containersas awayto quickly assess wastecontent and mayconsider this atypeof administrativecontrol.Also, CCP-SRSimplementsprocedures togenerateNCRs, someofwhichare createdwithrespecttoAK.Further,themanagementofprohibiteditemsdetected via AK, RTR,or VEwasnotexamined excepttounderstand thatdrums containingprohibited items aresegregated fromthe waste streampopulationfor laterdisposition(e.g.,RevisionNo.:1AK-21DateofRevision:11/01/05ATTACHMENT A.1:ACCEPTABLE KNOWLEDGE (AK) CHECKLISTEPA Inspection No.: EPA-SRS-10.05-8Inspection Date: 10/31/2005–11/03/2005Required Technical ElementsProcedure Location/AdequacyVerificationofActivityExamples of ObjectiveEvidencecorrective action process•As part ofthecorrectiveaction process, assess thepotential timeframeofthenoncompliance, thepotentially affectedwaste population(s), andthereassessment and recertification ofthose wastes(Attachment B4,Section B4-3b)treatment). Therefore,whilediscussedintheWAPAppendix B4(AK),administrative controlsareprogrammaticand better addressedoutsideofAKexceptwhere processcontrolscurrentlyorhistorically control waste content as it isbeing generated.AK-46Does the generator sitedocument, justify, andconsistently delineate waste streams... based onsitespecific permitrequirements orstate-enforcedagreements?How dotheseagreements impact wastecharacterization?(SectionB4-4)CCP-TP-005,Revision15YesCCP-AK-SRS7Rev.1;CCP-AK-SRS-8Rev.2;TWBIR2004.D152,C074. TheTWBIRdelineatesWaste Profiles that aresometimes used asa startingpointforassigninganddeterminingwaste streams.No state-enforced agreements orpermitrequirements were identified duringtheinspection thatimpact waste streamdetermination.RevisionNo.:1AK-22DateofRevision:11/01/05ATTACHMENT A.2:VISUAL EXAMINATION (VE) CHECKLISTEPA Inspection No.: EPA-SRS-10.05-8Inspection Date: 10/31/2005–11/03/2005Establishment of RequiredTechnical Elements inProceduresY/NLocationExecution of ProceduresY/NObjective Evidence/CommentVE-1Site procedures identifyrequiredtrainingandqualificationsforVEpersonnel.CCP-QP-002,Revision17Visual Examination Expert’s(VEE)explanationofjobdutieswas consistentwithapplicableprocedures.VE personnel’strainingwas consistentwithapplicableprocedures.VEpersonnel’s certification is current.VEpersonnelare re-qualified every twoyears.•VEpersonnel received trainingon specificwastegenerating processes, typicalpackagingconfigurations, WMPsexpectedto befound ineachWaste Matrix CodeYCCPusesQualification CardstodocumentandrecordtrainingreceivedbyCCPpersonnel.The SiteProjectManager appointsVisualExamination Experts (VEE),whichis documentedina letter that isincludedin the VEE’strainingfile. Trainingonspecific wastegenerating processes,typical packaging configurations,WMPsexpected tobefound ineachWaste MatrixCodeis providedto theVEpersonnel.The site maintains a ListofQualifiedIndividuals, which isusedto ensureall trainingis current.Duringthe inspection, theQualificationCardsfor a VEoperator/ITR/TS/FQAOwasreviewedandfound tobecomplete andcurrent.Also, theQualificationCardfor a VEEwasreviewedand found tobe complete and current, andcontained the letter appointinghimas a VEE.Objective evidence reviewed:VE operator QualificationCardVEE QualificationCardListofQualified Individualsfor VEVE-2Proceduresand technicalguidancedocuments providecomplete instructions forperforming VE.CCP-TP-113,Revision3•The siteusesAK to identify the wastematrixcodecategory andtoestimatewaste materialparameters present•Procedures are sufficiently detailedtoenable theoperator todetermine if awastecontainer meets the criteria of '194.24withregard toidentifying applicableparameterswithwaste limits•Establishstandardnomenclature,based oncurrentsite practice, so that all staffrecognize waste by thesamedescriptorsYTwotypes ofVE wereassessed duringthe inspection ofSRSCCP, namelyVE inlieuofRTRandVE asa QCcheckofRTR.Procedure CCP-TP-113containscompleteand detailedinstructionsforperformingVEas aQCcheckofRTRandVE inlieuofRTR.These two typesofVEareperformed inexactlythe samemanner andboth are coveredinsection4.1oftheprocedure. Theprocedurealso includes a listofWIPPprohibiteditems, adescription of layersofconfinement, adescriptionofWaste Material Parameters (WMP),a lookuptable forwasteitemweights, and a tableexplaining thecodesusedto recordsomeof theVEdata.RevisionNo.:1VE-1DateofRevision:11/01/05ATTACHMENT A.2:VISUAL EXAMINATION (VE) CHECKLISTEPA Inspection No.: EPA-SRS-10.05-8Inspection Date: 10/31/2005–11/03/2005Establishment of RequiredTechnical Elements inProceduresY/NLocationExecution of ProceduresY/NObjective Evidence/CommentWhenanewAK summary becomes available, theoperatorsreceive documentedtraining with regardto expectedWMPsandpackagingconfigurationsinthat wastestream.VE-3CCP-TP-113,Revision3,s.3.2.3Prior to startingthe VE, theVEEreviews alldocumenteddata relatedto the wastecontainer and its contentsto ensure that thereare nosafety hazardsforthe VE operatorsAlldrums gothroughfastscanRTRpriortoVE. TheVEEisinformed by the VPM ifthereare anydangerousitemsidentified inthe drums.AK summaries for thewaste streams beingprocessed areavailable to the VEE andVEoperators inthe facility whereVE takesplace.Objective evidence reviewed:1.VE inlieuofRTRBDRs:SRVEP60019, SRVEP60029(S5000)SRVEMS0001, SRVEMS0002,SRVEMS0003(S4000)2.VE asaQC checkof RTR BDRs:SRVEP60037, SRVEP60132(S5000)VE-4Procedurerequires anaudio/visualrecordingoftheVEevent tobemade.CCP-TP-113,Revision3,s.4.1.2•VEE/operator’sexplanation of howtooperatethedatarecording systemwasconsistentwith applicable procedures•The videocamera was focused priortothestart ofVEAnaudio/videotape ismade ofthewastecontainer exam and maintained asanonpermanentrecord•Data on the audio/visual recording isconsistentwith documentationYDuringthe inspection, EPA observedVE inlieuof RTRfor adebris(S5000) drum. The drum#was SR597472 andtheBDR # was SRVEP60162.Thedrumwas fromwaste streamSR-W027-221H-HET.At the timeofthe inspection,VEoperations wereoperating ona24/7basis.The VEeventtook placein building TVEFonPad 6 ofSRS.VE was performedby2 operators,witha VEErecording VEdataandcontrolling which cameraswere usedtoproduce thevisualrecordings.AnRCTisalsopresent intheradiationcontainment area and isresponsible for operatinga hand-heldcamera.Other cameras are in fixedpositions intheVE area.Twotapes aremadeof the VE event and the EPA inspectorobservedthattherequiredaudio/visualcheckswereperformedasrequired.TheEPAinspectoralsoobservedtheRevisionNo.:1VE-2DateofRevision:11/01/05ATTACHMENT A.2:VISUAL EXAMINATION (VE) CHECKLISTEPA Inspection No.: EPA-SRS-10.05-8Inspection Date: 10/31/2005–11/03/2005Establishment of RequiredTechnical Elements inProceduresY/NLocationExecution of ProceduresY/NObjective Evidence/Commentscale check.ForthisVEevent,thedrumcontentsareremoved fromthedrum, sortedin accordancewith WMPs, weighed,and putinto anewdrum. All data are recorded byhand. The emptycandidatedrumissealed anddisposedofaslow-levelwaste.BDR SRVEP60029,VEinlieuofRTR for debris(S5000)drum#SR557498andaudio/visualrecordingwerereviewedduringthe on-siteinspection.AlsoBDRs SRVEMS0001,SRVEMS0002, andBDR SRVEMS0003for soil/gravelwaste and their associated audio/visualrecordingswerereviewed.In all cases, thewrittenrecordedcorresponded tothe taperecord.During the inspection ofVEas aQC checkof RTR, EPAreviewed BDRSRVEP60037and both the BDR andaudio/visual tapeforBDR SRVEP60132to ensurethat CCPperformed VEas aQC checkfor RTR inaccordancewithprocedure.The drums inbothBDRscontainedS5000debriswaste.The writtenrecordfor BDR SRVEP60132,drumSR100052 and the audio/visual tapedidnotcontain the sameinformation and EPAInspection IssueTrackingFormNo.SRS-CCP-VE-06-002CR wasinitiatedtoaddress this issue.Concern SRS-CCP-VE-06-002CR:TheWasteVisual ExaminationData Form(Attachment 1)fromprocedure CCP-TP-113,containsdatathatdoesnotmatchwhatactually transpiredduring visualexamination ofDrumNo.SR100052.Thevideotaperecordshows aproblemwiththe VEdata for this drumthat was initially recorded inthe hardcopyrecord.Subsequently, theoriginalrecordwasdiscardedand replaced withonethat does notmatchthevideotapedevent.Consequently, the hardcopyrecordthatremains does not representwhat transpiredduringVEof thisdrum.RevisionNo.:1VE-3DateofRevision:11/01/05ATTACHMENT A.2:VISUAL EXAMINATION (VE) CHECKLISTEPA Inspection No.: EPA-SRS-10.05-8Inspection Date: 10/31/2005–11/03/2005Establishment of RequiredTechnical Elements inProceduresY/NLocationExecution of ProceduresY/NObjective Evidence/CommentObjective evidence reviewed:VE inlieuofRTR BDRs:SRVEP60019, SRVEP60029(S5000)SRVEMS0001, SRVEMS0002,SRVEMS0003 (S4000)VE asaQC checkof RTR BDRs:SRVEP60037, SRVEP60132(S5000)VE-5Thereis aprocedureforhandlinginstances whentheVE Expert isunable toseethroughthe innerplasticbags/packages/containers ofwaste.CCP-TP-113,Revision3,s.3.2, 4.1.4,[F3],(b)TheVEEhasdecision makingcriteria forassessingtheneed toopenthebags/packagesinorder toidentify all oftheircontents.Ifthe bagsare notopened,a brief writtendescriptionofthe contentsof thebagsispreparedwithestimates of the amountofeachwastetypeinthebags.YItis CCP’spolicy toopen allbagsduringVE.For VE asaQC checkof RTR, a full VE took placefordrums inthereviewedBDRs.For the drums containingsoil/gravel waste,a limitedVE wasperformed anddocumented inthe commentsectionoftheCCP-Waste VisualExamination DataForminthe aboveBDRs.Thetop ofthe waste wasexamined inplace andthesoil/ gravelwas not removedfromthe drum. EPAInspectionIssueTracking FormNo.SRS-CCP-VE-05-001Fwasinitiatedtoaddress this issue.FindingSRS-CCP-VE-05-001F:WhenperformingVEonS4000soilsdrums fromthe Moundsoil wastestreamdescribed inAK-8 for BDRsSRVEMS0001 throughSRVEMS0003, operators conductedvisual inspection thatwasnot consistentwithProcedureCCP-TP-113,Revision3.TheVE eventdidnotassess thedrums’ contentsbutfocused solelyonthetop layerofwaste.The BDRsreportedthatnoprohibited itemswerefoundbutthiscouldnotbe ascertainedbasedontheVEthatwasperformed.Objective evidence reviewed:VE inlieuofRTR BDRs:RevisionNo.:1VE-4DateofRevision:11/01/05ATTACHMENT A.2:VISUAL EXAMINATION (VE) CHECKLISTEPA Inspection No.: EPA-SRS-10.05-8Inspection Date: 10/31/2005–11/03/2005Establishment of RequiredTechnical Elements inProceduresY/NLocationExecution of ProceduresY/NObjective Evidence/CommentSRVEP60019, SRVEP60029(S5000)SRVEMS0001, SRVEMS0002,SRVEMS0003 (S4000)VE asaQC checkof RTR BDRs:SRVEP60037, SRVEP60132(S5000)VE-6The VE procedurerequiresverificationofWasteMatrixCodeandWMP weights.CCP-TP-113,Revision3,Attachment1,Tables 1-4•If anautomateddata entry systemis used,dataentryVEpersonnelcouldnavigatethroughthevariousscreens•AVEdata formis used todocument thewaste matrixcodeandestimatedWMPweights ofthe waste•VEstaff have accessto standardizedchartsortables to aid inthe consistentestimation/assignmentofweights,wastematerial parameters, and waste matrixcodes•The estimated orweighedWMP weightsaredetermined bycompilingan inventoryof waste items, residual materials andpackaging materials•The itemsonthe inventory list are sortedbyWMP and combinedwith astandardweightlook-up table toprovide anestimateofWMPweights•References tables areupdated as site gainsinformationfromVE•VEE verifies WasteMatrixCodeandrecommends changesasneededYAll data sheetsare completedbyhand.Operatorssignthedata sheets foreachdrumprocessedbyVE inlieuof RTRatthe endoftheday (they donot comeoutofthe radiationcontainment area as eachdrumis completed).Thewaste matrixcode isrecordedinquestion#s18and19onthe CCPWaste VisualExaminationData Form.WMPsare recordedinsection 3 of the CCPWasteVisualExamination DataFormand inquestion#s42-43of the sameform.Procedure CCP-TP-113, Revision3,includes a list ofWIPPprohibiteditems, adescription of layersofconfinement, adescriptionofWaste Material Parameters (WMP),a lookuptable forwasteitemweights, and a tableexplaining thecodesusedto recordsomeof theVEdata.Forsoildrums,WMPsweights are estimated and theweightofthe soil/gravel is calculated fromthe gross weightofthedrumminus the estimated weightofotherWMPs present.WhenperformingVEas aQCcheckofRTR,waste issortedbyWMP and actualweightsarerecorded.Thewaste matrixcode isrecordedinquestion#s18and19onthe CCPWaste VisualExaminationData Form.TheVEEinterviewedhadneverrequested anupdatetotheWMPreference table.Occasionally itemsare identified thatarenot contained in thereference tablebutnot at a sufficientfrequencytorequireupdatingthe reference table.RevisionNo.:1VE-5DateofRevision:11/01/05ATTACHMENT A.2:VISUAL EXAMINATION (VE) CHECKLISTEPA Inspection No.: EPA-SRS-10.05-8Inspection Date: 10/31/2005–11/03/2005Establishment of RequiredTechnical Elements inProceduresY/NLocationExecution of ProceduresY/NObjective Evidence/CommentObjective evidence reviewed:VE inlieuofRTR BDRs:SRVEP60019, SRVEP60029(S5000)SRVEMS0001, SRVEMS0002,SRVEMS0003(S4000)VE asaQC checkof RTR BDRs:SRVEP60037, SRVEP60132(S5000)VE-7Procedureprovides instructionsfor processingofcontainerswithprohibiteditems.CCP-TP-113,Revision3,s.4.3, Attachment1, s.5VE expertcouldnameprohibited items.VE expert’sexplanationofrequiredactionsifprohibiteditems were encountered wasconsistentwith procedure.TheVEEdescribes anyliquidsfound,includingadescriptionof their location inthecontainer and estimated volume.Otherprohibited items, includingsealedcontainers are identified and segregated.YEPA interview of aVEEdemonstrated that theVEEwasabletoidentify prohibiteditemsand howthey are processed iffound.Theprocessdescribedwas inaccordancewithprocedure CCP-TP-113, Revision3.Prohibited itemsfoundare eitherremediatedor removed and theVE event iscontinued.If anitemis found that cannotbedealt withinthisway,theVEeventwouldbe stop, anNCRwouldbeinitiatedandthe VPMwouldbeinformed.At the time oftheinspectionnodrumhadbeenencountered thatcouldnotbeprocessed.Volumeutilizationisrecordedin question# 28ofAttachment1, CCPWasteVisualExaminationDataFormand thegrossweightofthe container inquestion#20of the sameform.This information was presentinall the BDRsreviewed.Objective evidence reviewed:VE inlieuofRTR BDRs:SRVEP60019, SRVEP60029(S5000)SRVEMS0001, SRVEMS0002,SRVEMS0003(S4000)VE asaQC checkof RTR BDRs:SRVEP60037, SRVEP60132(S5000)RevisionNo.:1VE-6DateofRevision:11/01/05ATTACHMENT A.2:VISUAL EXAMINATION (VE) CHECKLISTEPA Inspection No.: EPA-SRS-10.05-8Inspection Date: 10/31/2005–11/03/2005Establishment of RequiredTechnical Elements inProceduresY/NLocationExecution of ProceduresY/NObjective Evidence/CommentVE-8CCP-TP-113,Revision3,s.4.1.4, [C.1]&[C.8]Attachment1,s. 2Thegrossweightofthewastecontainer(container pluscontents) is recordedontheVE dataform.Volumeutilizationofthe container isdocumented.YVolumeutilizationisrecordedin question# 28ofAttachment1, CCPWasteVisualExaminationDataFormand thegrossweightofthe container inquestion#20of the sameform.This information was presentinall the BDRsreviewed.Objective evidence reviewed:1.VE inlieuofRTRBDRs:SRVEP60019, SRVEP60029(S5000)SRVEMS0001, SRVEMS0002,SRVEMS0003 (S4000)2.VE asaQC checkof RTR BDRs:SRVEP60037, SRVEP60132(S5000)VE-9CCP-TP-113,Revision3,s.4.3.2CCP-QP-005,Revision10The procedure isadequatelyimplemented•Corrective actionsaretakenwhennecessaryYThe demonstration observedduringthe on-siteinspection wasperformed inaccordancewithprocedure CCP-TP-113,Revision3.The BDRsandtapereviewedwerecompleteandcontainedalloftherequiredinformation (referenceFindingSRS-CCP-VE-06-002CR).NCRs NCR-SRS-0901-05andNCR-SRS-0904-05werereviewed duringthe inspection.TheseNCRs were initiatedbecause the waste indrumsFBL01216 andSR544842 didnotmatchthe waste streamdescription.The final disposition ofthe drums was“use asis” and were correctly signed by theresponsible manager andtheSite ProjectQuality AssuranceOfficer /Facility Quality AssuranceOfficer.Objective evidence reviewed:1.VE inlieuofRTRBDRs:SRVEP60019, SRVEP60029(S5000)SRVEMS0001, SRVEMS0002,SRVEMS0003(S4000)2.VE asaQC checkof RTR BDRs:SRVEP60037, SRVEP60132(S5000)3.NCRs NCR-SRS-0901-05andNCR-SRS-0904-05RevisionNo.:1VE-7DateofRevision:11/01/05ATTACHMENT A.2:VISUAL EXAMINATION (VE) CHECKLISTEPA Inspection No.: EPA-SRS-10.05-8Inspection Date: 10/31/2005–11/03/2005Establishment of RequiredTechnical Elements inProceduresY/NLocationExecution of ProceduresY/NObjective Evidence/CommentVE-10Site procedure(s) requiredatageneration andprojectlevelreviews ofBatch DataReports(BDRs).CCP-TP-113,Revision113,s.4.6-4.8,Attachments 2-4CCP-TP-001,Revision11,Attachment2&5•BDRs containall requiredinformation(seetable below)•Datageneration andprojectlevelreviewsare completeYThe BDRsreviewed for VE in lieu of RTRand VE as aQCcheckofRTRcontainedalloftherequiredinformation.TheBDRscontained completed and signeddatageneration levelreviewchecklists (IndependentTechnicalReviewer,Technical Supervisor, FacilityQuality Assurance Officer)and completedand signedproject levelreview checklists(Site Project Manager andSiteProject Quality AssuranceOfficer).Objective evidence reviewed:VE inlieuofRTR BDRs:SRVEP60019, SRVEP60029(S5000)SRVEMS0001, SRVEMS0002,SRVEMS0003 (S4000)VE asaQC checkof RTR BDRs:SRVEP60037, SRVEP60132(S5000)VE-11Thesitehasaprocedure forusingthe dataobtained fromVE asaQC checkof RTR tocalculatethe percentage ofmiscertified waste containers.Thefacility has aprocedure forrandomly selectingwastecontainers.CCP-TP-113,Revision113,s.4.1CCP-TP-003,Revision14,s.4.9 - 4.10, 4.12,Table1Thenumberof waste containersto undergoVE is appropriately calculated.The siteuses aninitial miscertificationrateof11%.Miscertificationrate is calculated for eachapplicable Summary Category Groupafter6months or50%oftheSCGhaveundergoneRTR.Site uses1%miscertificationrate if calculatedvalue is <1%.Rate is reassessedannually using adrumweighed average.Aninter-officememorandum“Savannah River SiteCategoryGroupS5000Specific Miscertification Rate”, reports theS5000(debris) miscertificationrate calculationsand results.Sixteendrums wereselected and visually examined betweenOctober 4,2004and May 3,2005. Thesedrums wereaddedtothe141 drums processedinpreviousyears and amiscertificationrateof 3%was calculated.Thenumber ofwaste containers to undergoVEwas calculated appropriately.Objective evidence reviewed:VE asaQC checkof RTR BDRs:SRVEP60037, SRVEP60132(S5000)Inter-office memo, “SavannahRiverSiteCategoryGroupS5000Specific Miscertification Rate”Inter-office memo, “Waste Material ParameterWeightComparisonReportfor Savannah RiverSiteOctober2004throughMay 2005(Relative PercentDifferenceComparisonReportfor RadiographyandVisualExamination”RevisionNo.:1VE-8DateofRevision:11/01/05ATTACHMENT A.2:VISUAL EXAMINATION (VE) CHECKLISTEPA Inspection No.: EPA-SRS-10.05-8Inspection Date: 10/31/2005–11/03/2005Establishment of RequiredTechnical Elements inProceduresY/NLocationExecution of ProceduresY/NObjective Evidence/CommentVE-12The sitehas adocumentedstratagemforselectingreplacement waste containers.CCP-TP-003,Revision14,s4.12&4.13Iffewer containerswerevisuallyexaminedthan weresampled,the reason forexcluding the containers isdocumentedThereplacement stratagemis restricted tocontainersfromthe samewaste streamVEisperformed onthe replacementcontainersYContainers usedforcalculation ofmiscertification ratearechosenrandomly, byExcel software,froma master list andaredocumented ina “VE RandomlySelected ContainerReport”.Thisreport alsodocuments the reasonforanycontainerreplacementfromthose initially chosen.Asimilarreport is generatedfor selection of containers forsolidssampling.Objective evidence reviewed:VE asaQC checkof RTR BDRs:SRVEP60037, SRVEP60132(S5000)Inter-office memorandum, “2005 RandomlySelectedContainersforSolidsSampling attheSavannah RiverSite”VE-13The calculationusedfor themiscertificationrateisdocumented.CCP-TP-003,Revision14,s.4.9Aftertherequirednumber ofcontainershavebeen visually examined, theUCL90for theproportion miscertifiedis calculatedThe sitehasusedthe appropriate distributionfor theUCL90calculationtodetermine N.YAninter-officememorandum“Savannah River SiteCategoryGroupS5000Specific Miscertification Rate”, reports theS5000(debris) miscertifcationrate calculationsand results.Sixteendrums wereselected and visually examined betweenOctober 4,2004and May 3,2005. Thesedrums wereaddedtothe141 drums processedinpreviousyears and amiscertificationrate of3%was calculated.The table usedfordeterminingthe number of containers requiring VE is aduplicate of that inWAP, Table B2-1.Objective evidence reviewed:VE asaQC checkof RTR BDRs:SRVEP60037, SRVEP60132(S5000)Inter-office memo, “SavannahRiverSiteCategoryGroupS5000Specific Miscertification Rate”Inter-office memo, “Waste Material ParameterWeightComparisonReportfor Savannah RiverSiteOctober2004throughMay 2005(Relative PercentDifferenceComparisonReportfor RadiographyandVisualExamination”RevisionNo.:1VE-9DateofRevision:11/01/05ATTACHMENT A.2:VISUAL EXAMINATION (VE) CHECKLISTEPA Inspection No.: EPA-SRS-10.05-8Inspection Date: 10/31/2005–11/03/2005Establishment of RequiredTechnical Elements inProceduresY/NLocationExecution of ProceduresY/NObjective Evidence/CommentVE-14Resultsof VE asa QCcheck ofRTR areforwardedtotheradiography facility.RTR operatorsreceiveresultsof RTR/VEcomparisonYRTR personnel arerequiredtoreadWaste Material ParameterComparison Reports asare they are issued and they areavailable electronically for their review.Anysignificantissuesare discussed withtheSME.Objective evidence reviewed:1.Inter-office memo, “Waste Material ParameterWeightComparisonReportfor Savannah RiverSiteOctober2004throughMay 2005(Relative PercentDifferenceComparisonReportfor RadiographyandVisualExamination”Information Included inBDR–VE in LieuofRTR, Soils andDebrisRequired Testing Batch ContentPresentY or NRequired Testing Batch ContentPresentY or NRequired Testing Batch ContentPresentY or NBatchDateYDescriptionof linersYVerificationofWasteMatrixCodeYReportdateYLayersof confinementYReference toorcopiesofanyNCRsYWastecontainer numberYIndicationofvented rigidlinersYVEE decisionsYWaste MatrixCodeYDescriptionofcontainer contentsYOperatorsignature and testdateYImplementing procedurenameor#YIndicationofsealed containers>4LYVEEsignatureandtestdateYVideotapereferenceYAmountoffreeliquidYCompleted datageneration checklistsYQCdocumentationYContainergross weightYCompleted projectlevelchecklistsVerification that waste matches wastestreamdescriptionYWaste Material Parameters weightsYRevisionNo.:1VE-10DateofRevision:11/01/05ATTACHMENT A.2:VISUAL EXAMINATION (VE) CHECKLISTEPA Inspection No.: EPA-SRS-10.05-8Inspection Date: 10/31/2005–11/03/2005InformationIncluded inBDR–VE asa QCCheckforRTR,DebrisRequired Testing Batch ContentPresentY or NRequired Testing Batch ContentPresentY or NRequired Testing Batch ContentPresentY or NBatchDateYDescriptionof linersYVerificationofWasteMatrixCodeYReportdateYLayersof confinementYReference toorcopiesofanyNCRsYWastecontainer numberYIndicationofvented rigidlinersYVEE decisionsYWaste MatrixCodeYDescriptionofcontainer contentsYOperatorsignature and testdateYImplementing procedurenameor#YIndicationofsealed containers>4LYVEEsignatureandtestdateYVideotapereferenceYAmountoffreeliquidYCompleted datageneration checklistsYQCdocumentationYContainergross weightYCompleted projectlevelchecklistsYVerification that waste matches wastestreamdescriptionYWaste Material Parameters weightsYRevisionNo.:1VE-11DateofRevision:11/01/05ATTACHMENT A.3:VISUAL EXAMINATION TECHNIQUE (VET) CHECKLISTEPA Inspection No.: EPA-SRS-10.05-8Inspection Date: 10/31/2005–11/03/2005Establishment ofRequiredTechnicalElements inProceduresY/NLocationExecution of ProceduresY/NObjective Evidence/CommentVET-1Site procedures identifyrequiredtrainingandqualificationsforVETpersonnel.CCP-QP-002,Revision17VE personnel’strainingwas consistentwithapplicableprocedures.VEpersonnel’s certification is current.VEpersonnelare re-qualified every twoyears.•VEpersonnel received trainingon specificwastegenerating processes, typicalpackaging configurations,WMPsexpectedtobefound in eachWaste MatrixCodeYCCP usesQualification Cardstodocument training received by CCPpersonnel. The letter fromSiteProject Manager appointing aVisualExaminationExpert (VEE) isincludedinthe VEE’sQualificationCard.Trainingonspecificwaste generatingprocesses,typicalpackaging configurations,WMPs expectedto befound ineachWasteMatrixCodeis providedtothe VE personnel.The site maintains a ListofQualifiedIndividuals, which is usedtoensure all trainingis current.Duringthe inspection, theQualificationCardsfor a VEoperator/ITR/TS/FQAOwasreviewedandfound tobe completeandcurrent.Also, theQualificationCard fora VEE wasreviewedandfound tobecomplete, current, andcontained the letter appointinghimas aVEE.Objective evidence reviewed:VE operator Qualification CardVEEQualificationCardListofQualifiedIndividuals forVEVET-2Proceduresand technicalguidancedocumentsprovide completeinstructionsforperformingVET.CCP-TP-113,Revision3,s.4.2•Twotrained operatorsperformVET•Procedures are sufficiently detailedtoenable theoperator todetermine if awastecontainer meets the criteria of '194.24withregard toidentifying applicableparameters withwaste limits•Establishstandardnomenclature,based oncurrentsite practice, so that all staffrecognize waste by thesamedescriptorsYProcedure CCP-TP-113containscompleteand detailed instructionsforperforming VET.Theprocedure alsoincludesa list ofWIPPprohibiteditems, adescription of layersofconfinement, a descriptionofWaste Material Parameters (WMP),a lookuptableforwaste itemweights, and atable explainingthecodesusedtorecordsomeof theVE data.Duringthe on-siteinspection EPA observedVET ondrum#SR233850 (S5440, debris)fromwaste streamSR-W027-221H-HET.Two operators performedthe VETandthe VEErecordedthedatagenerated.The drumcontained ahutthatwas tightlypacked andtheoperatorshad tocut thehutout of thedrumpiece bypiece. A smallamountofresidualliquidwasfoundinthefoldsoftheplastic.Operatoraid #E-03-0006, Revision4lists information,suchas thescale ID #, calibrationdate, and isused by theoperators.The EPAinspectorobserved the calibration check of thebalanceusedto weighRevisionNo.:1VET-1DateofRevision:11/01/05ATTACHMENT A.3:VISUAL EXAMINATION TECHNIQUE (VET) CHECKLISTEPA Inspection No.: EPA-SRS-10.05-8Inspection Date: 10/31/2005–11/03/2005Establishment ofRequiredTechnicalElements inProceduresY/NLocationExecution of ProceduresY/NObjective Evidence/CommentWMPs.Twocans(prohibiteditems) werefound inthedrum. Thecanswereremoved,afterweighing, andbaggedoutoftheglove-box.An NCRwas initiatedasrequired.NOTE: this was fordemonstration purposesonlyandthe datawillnotbe usedbySRS/CCP.Two BDRsweregeneratedbySRS/CCPforthepurposeofdemonstrationduringthe inspection.Thedatageneratedfor thesubjectdrums, SR545235 and SR502501,will notbeusedfor wastecharacterization.Objective evidence reviewed:BDRs (S5000,debris):SRVETXxxx1,SRVETXxxx2VET-3The VETprocedurerequiresverificationofthephysical formof thewasteand presenceorabsence ofprohibiteditems.CCP-TP-113,Revision3,Attachment1•A VET dataformisusedtodocumentverificationofthe physical formof thewaste and theWaste MatrixCode•Packaging configuration, typeandnumberoffilters, andrigidlinerventhole(presence anddiameter) aredocumentedfor each container•Presenceorabsenceofprohibited itemsisdocumented onthe VET dataform•VET operatorsexplanation ofrequiredactionsif prohibiteditemswereencounteredwasconsistentwithprocedure•If anautomateddata entry systemis used,dataentryVET personnelcouldnavigatethroughthevariousscreens•A calibratedscale is usedtoweighWMPsVETstaff haveaccess to standardized chartsortables to aid inthe consistentestimation/assignmentofWMP weightsYAttachment1 fromprocedureCCP-TP-113isusedtorecordtheVETdata, whichincludes WasteMatrixCode, packaging configuration,rigidlinerventhole(presenceanddiameter),and presence orabsenceofprohibited items. Data areenteredintoAttachment1byhand, byaVEE, as thedata aregenerated.Thewaste itemsare sortedbyWMP,weighedand recorded.After weighing thewaste itemsare placed inthe outputwaste container.Prior toweighing itemsthe scalecalibration ischeckedandrecorded.Procedure CCP-TP-113,Table4providesstandardweightsforwaste itemsbutinthe twodemonstrationBDRsprovidedforreview, allwaste itemswereweighed.It isoptionalfor the VET event toberecorded onanaudio/visualtape.Objective evidence reviewed:1.BDRs(S5000, debris):SRVETXxxx1,SRVETXxxx2RevisionNo.:1VET-2DateofRevision:11/01/05ATTACHMENT A.3:VISUAL EXAMINATION TECHNIQUE (VET) CHECKLISTEPA Inspection No.: EPA-SRS-10.05-8Inspection Date: 10/31/2005–11/03/2005Establishment ofRequiredTechnicalElements inProceduresY/NLocationExecution of ProceduresY/NObjective Evidence/CommentVET-4CCP-TP-113,Revision3,Attachment1Thegrossweightofthewastecontainer(container pluscontents) is recordedontheVE dataformVolumeutilizationofthe container isdocumentedYTheforms usedto recordVET data are the sameas thoseusedforVEas aQC checkof RTR andVE in lieu of RTR (Attachment 1, CCPTP-113).Volume utilizationis recordedin question#28ofAttachment1, CCP Waste VisualExamination DataFormand thegrossweightofthecontainerinquestion#20ofthe sameform. Thisinformationwas present inallthe BDRs reviewed.Objective evidence reviewed:1.BDRs(S5000, debris):SRVETXxxx1,SRVETXxxx2VET-5Proceduresand technicalguidancedocumentsprovide completeinstructionsforperformingVET.CCP-TP-113,Revision3CCP-QP-005The procedure isadequatelyimplemented•Corrective actionsaretakenwhennecessaryYDuringthe demonstration VETevent,an NCR was initiatedbecauseprohibiteditems werefound inthe drum.NCRs NCR-SRS-0901-05andNCR-SRS-0904-05werereviewedduringthe inspection.TheseNCRs were initiatedbecausethe wasteindrums FBL01216and SR544842 didnotmatchthe waste streamdescription.Thefinaldispositionofthedrums was “use asis” andthe NCRswerecorrectly signedbytheresponsible managerand theSPQAO/FQAO.AlthoughtheseNCRswere notassociated withVET, theydemonstratedthatVEpersonnelwere able toinitiateNCRs asrequired andwerefamiliar with the process.Objective evidence reviewed:1.NCRs NCR-SRS-0901-05andNCR-SRS-0904-05VET-6Site procedure(s) requiredatagenerationandprojectlevel reviewsof BatchData Reports(BDRs).CCP-TP-113,Revision3,Attachments2-4CCP-TP-001,Revision11,Attachments2 &5•Datageneration levelreviewsareperformed anddocumented•Projectlevelreviewsareperformed anddocumentedYThe twoBDRsreviewedcontained alloftherequired informationandcontained completedand signed datagenerationlevelreviewchecklists(ITR,TS, and FQAO)and completed andsignedprojectlevel review checklists (SPMand SPQAO).Objective evidence reviewed:1.BDRs(S5000, debris):SRVETXxxx1,SRVETXxxx2RevisionNo.:1VET-3DateofRevision:11/01/05ATTACHMENT A.4:REAL-TIME RADIOGRAPHY (RTR) CHECKLISTEPA Inspection No.: EPA-SRS-10.05-8Inspection Date: 10/31/2005–11/03/2005Establishment of RequiredTechnical Elementsin ProceduresY/NLocationExecution of ProceduresY/NObjective Evidence/CommentRTR-1Site procedures identify requiredtrainingand qualificationsforRTRpersonnelCCP-TP-011,Revision16,s. 3.3CCP-QP-002,Revision17CCP-TP-028,Revision2,CCP-TP-028-A1, Revision0Operator trainingwas consistentwith applicableprocedures.Operator certificationis current.OJT was documentedforeach operator.Operators arere-qualified every two years.RTRoperatorspassed atrainingdrumtestthatincludes itemscommontothe waste streamsexamined at the site (biannually).Trainingdrumcontains all requireditems.RTR operatorsreceivetrainingon thewastematrixparameters and typicalpackagingconfigurationsexpectedtobefoundineachwastestream.YCCPusesQualification CardstodocumentandrecordtrainingreceivedbyCCPpersonnel.The SiteProjectManager appoints RTR Subject Matter Experts (SME)and this appointmentis documentedbya letter includedintheSME’s trainingfile.Training onspecific wastegenerating processes,typicalpackagingconfigurations,WMPs expected tobefound ineachWasteMatrixCodeis providedto the RTRpersonnel.The operatorsreceive trainingfor eachwaste streamthat they processand haveAK summaries available in thework area forreference.The site maintains a ListofQualifiedIndividuals,whichisusedtoensure all trainingis current.At thetimeof the inspection,onlyfour(4) individualswerequalifiedfor RTR.All four RTR personnelwerequalifiedonunitRTR#1forS5000,debriswaste.Duringthe inspection, theQualificationCardfor a RTRoperator/ITR/TS/FQAOwasreviewedandfound tobecomplete andcurrent.Also, theQualificationCardforan SMEwas reviewedandfound tobe completeandcurrent, andcontained the letter appointinghimas anSME.EPAreviewedthe latest competency demonstrationtape anddocumentation (required everysixmonths)foran RTRoperator. The testwas performed on10/19/05anddrumusedwas SRS-NDE-TEST-13B.Therewerenoproblems identifiedduringthis review.EPA also reviewedthelatestcompetencydemonstrationtape anddocumentation for anRTRSME.The testwasperformed on8/25/05 anddrumusedwasSRS-NDETEST-12B.Althoughthedruminventoryincluded ahorsetail, the SME did not identify this and the SMEreviewing thetapedidnotrecognize thisomission.TheRevisionNo.:1RTR-1DateofRevision:11/01/05ATTACHMENT A.4:REAL-TIME RADIOGRAPHY (RTR) CHECKLISTEPA Inspection No.: EPA-SRS-10.05-8Inspection Date: 10/31/2005–11/03/2005Establishment of RequiredTechnical Elementsin ProceduresY/NLocationExecution of ProceduresY/NObjective Evidence/Commentfollowing concern was writtenbecause thereviewprocessusedbyCCPdidnotidentifythisproblemandprovide adequatetrainingfeedback to RTRpersonnel.SRS-CCP-RTR-05-003CR:In theprocessofRTRtraininginaccordancewithCCP-TP-028, Revision2,anoperatordid not identify arequirediteminthetrainingdrum. Althoughaqualified RTRoperatorreviewed this trainingtape, itappears that the CCPNDETestDrumInventory Sheet CCP-TP-028-A1,Revision0 was not used as abasis forthis reviewbecausethereviewerdid not documentthat arequireditemwas missed.Theprocessinplace results in alackofidentificationofproblemsassociatedwith therequalificationofRTROperatorsanddoesnotprovidethe opportunityforfeedbacktotheoperatorundergoingRTR Operatorrequalification.Objective evidence reviewed:RTRoperator Qualification CardRTR SMEQualificationCardCompetencydemonstration audio/visualtapeandassociated documentation foroperator and SMEListofQualifiedIndividualsfor RTRRTR-2Siteprocedure(s)provide completeinstructionsfor operators toperformthe RTR examination andcompletion of the associateddocumentationCCP-TP-011,Revision16•RTR operatoradequately explained theprocessfollowed for examining adrumand enteringdataintodataforms(whether hardcopyorelectronicdata entry isused).YDuringtheon-site inspection,EPA observed the RTReventfora debris (S5000)drum, numberSR515960(batchSRRTR1749) onRTRunit#1.Thedemonstration took placeon Pad 4 ofSRS.Theoperator hada copyoftheapplicableprocedure(CCPTP-011) available in the RTRoperations areaandperformed theRTReventin accordancewith theprocedure instructions.RTRdata areelectronicallyentered intothe dataform(Attachment3 ofprocedureRevisionNo.:1RTR-2DateofRevision:11/01/05ATTACHMENT A.4:REAL-TIME RADIOGRAPHY (RTR) CHECKLISTEPA Inspection No.: EPA-SRS-10.05-8Inspection Date: 10/31/2005–11/03/2005Establishment of RequiredTechnical Elementsin ProceduresY/NLocationExecution of ProceduresY/NObjective Evidence/CommentCCP-TP-011).Anoperator aid is availableforWMPstandardweights thatareusedfor completing theRadiographyDataSheet(Attachment3).A 200lbweight isusedto check the calibration of thecontainerscale.A toleranceof±5 lbs isallowed.EPAobservedthe LinesPairResolution checkwhichwas acceptableand documentedon Attachment8oftheprocedure.Two audio/visualtapesaresimultaneouslymade oftheRTR event.Objective evidence reviewed:BDRs, debris,S5000:SRRTR1724, SRRTR1728, SRRTR1732Audio/visualrecordings for BDRsSRRTR1728andSRRTR1732RTR-3TheRTR procedure(s) requireanimage qualitycheck tobeperformedCCP-TP-011,Revision16,s.4.6•Operatoradequatelyexplainedhow theacceptability of animage is determined•Image quality check isperformedonceper day•Performance of the image quality checkisdocumented andrecordedYThe operator wasabletoexplain howtheRTRunitworkedandwhatactions aretakenfordensematerials.The image quality checkwasobserved byEPAduringthe demonstration RTReventfordrum# SR515960.Ineachof the BDRs reviewed, the image quality checkwasdocumentedon Attachment 8 of theprocedure(Radiography MeasurementControls).Objective evidence reviewed:BDRs, debris,S5000:SRRTR1724, SRRTR1728, SRRTR1732RTR-4The procedure allowsthe operatortoadjust the RTR toaccommodatethe physical properties of thewasteand waste containers likely tobeCCP-TP-011,Revision16,s.4.7.4•Operator could identify applicable policies andprocedures governingthe operationofRTRequipment•The RTRsystemcould beadjustedYDuringthedemonstration RTRevent,theoperatoradjustedtheKvof theunit toaccommodate varyingdensities ofthe material encountered.All containers atSRS-CCP undergo FastScanRTR,whichis notanapprovedprocess forWIPP,totryand identifyprohibiteditems prior to going throughthe approvedRevisionNo.:1RTR-3DateofRevision:11/01/05ATTACHMENT A.4:REAL-TIME RADIOGRAPHY (RTR) CHECKLISTEPA Inspection No.: EPA-SRS-10.05-8Inspection Date: 10/31/2005–11/03/2005Establishment of RequiredTechnical Elementsin ProceduresY/NLocationExecution of ProceduresY/NObjective Evidence/Commentencountered atthe site•High-density material was examinedwith thex-raydevice setonthe maximumvoltage and lowdensitymaterialat a lowervoltage•Operator adequately explainedwhat isdoneif animage is unacceptable(e.g., thewaste issolidified or the container is lead-lined)RTR process.Ifprohibited itemsare identified,theyare returnedtoSRS forremediation.Afterremediation,the containersare sent for full RTR.If thefast scandoesnotidentifythepresenceofprohibited items, thecontainer issubjectedtofullRTR in accordancewithCCP-TP-011. Forthis pathway,if prohibiteditemsareidentified, theyareremediatedthroughCCP procedureCCP-TP-136.Containers mayberejectedafter fullRTR due to thepresenceofimpenetrable items, suchasleadlinedgloves.If a container isrejectedin thiswayit will beexaminedbythe VE inlieuof RTRprocess(CCP-TP-113).Objective evidence reviewed:BDRs, debris,S5000:SRRTR1724, SRRTR1728, SRRTR1732RTR-5CCP-TP-011,Revision16,s.4.3RTR tapeishighquality, thesoundtrackisaudible, andthe required information iscontainedonthe audibleportionof the tape.The RTR tapeis consistentwiththedatapackagefor thesamedrum.YAspartof the inspection, the tapes andBDRsfordrum#sSR100137 (BDR# SRRTR1732)andSR118958(BDR SRRTR1728) werereviewed. Thedata recordedonthe audio/visualtapesandBDRsforthese twodrumswereconsistent. The audio/visualtapeswereaudibleandof goodquality.Objective evidence reviewed:BDRs, debris,S5000:SRRTR1724, SRRTR1728, SRRTR1732RTR-6Thereis aprocedurefordeterminingwhether thewastematches thewaste streamdescription andWaste MatrixCode, and fordeterminingWasteCCP-TP-011,Revision16,s.4.7.12[P]&[Q],Attachment1-3The procedure isadequatelyimplementedOperatorsverify that thewaste matches thewastestreamdescription.Waste MatrixCodeis verified.Ifnot, correctiveactionis taken.YAttachment 3,CCP-TP-011,Waste Formsection,documents that thephysicalformof thewaste matchesthe waste streamdescriptionandthe waste matrixcode.During the RTR event theWMPs arerecorded andweights areestimated for these items. Anoperator aidcontainsstandardweightsbutoperator experience isRevisionNo.:1RTR-4DateofRevision:11/01/05ATTACHMENT A.4:REAL-TIME RADIOGRAPHY (RTR) CHECKLISTEPA Inspection No.: EPA-SRS-10.05-8Inspection Date: 10/31/2005–11/03/2005Establishment of RequiredTechnical Elementsin ProceduresY/NLocationExecution of ProceduresY/NObjective Evidence/CommentMaterial Parameters andWeightsWMPweightsare estimated by compiling aninventoryofwaste itemsandresidual/packagingmaterials.DoestheRTRoperatoruse astandardweightlookuptable to provide an estimate ofWMPweights?If so, has thetablebeen updated toreflect additional informationgainedthroughprevious RTR/VE exams orupdatedAKinformation?criticalwhenassigningWPMweights.Attachments 1and 2 ofprocedure CCP-TP-011include some basicstandard weights for containers andHEPAfilters.Objective evidence reviewed:BDRs, debris,S5000:SRRTR1724, SRRTR1728, SRRTR1732RTR-7TheRTR procedure providesinstructionsfor identifyingprohibited itemsandforprocessingdrums containingprohibitedCCP-TP-011,Revision16,s.4.7.12, [J],Attachment3Operatorcouldnameprohibited itemsOperator adequately explainedhow thepresenceoffree liquids isdeterminedOperator’s explanationof requiredactionsifprohibiteditems were encountered was consistentwithprocedureCorrective actionsaretakenwhennecessaryYTheoperatorwas able toname prohibited itemsanddemonstrated how thepresenceof free liquids isdetermined (rockingthecontainer).Whena prohibiteditemis identified,an NCR is issued.Liquidgreater than1”wasfoundindrum#SR118958,batch SRRTR1728and NCR# NCR-SRS-1273-05wasinitiated.Thisdrumwas rejectedbyCCP.Inthe samebatch,containers772F020054,FBL03144andSR529802 containedgreaterthan 20% inorganic waste.The dispositionforthesecontainers, documentedinNCR # NCR-SRS-1272-05was “use as is”.Objective evidence reviewed:BDRs, debris,S5000:SRRTR1724, SRRTR1728, SRRTR1732RTR-8RTR procedures include therequiredQCexaminations,evaluation accuracy andreproducibility of the RTR processCCP-TP-011,Revision16,s.4.9 &4.10•Anindependentreplicate scanisperformed ononewaste containerperdayoronone containerpertestingbatch(whicheverisless frequent)•Anindependentobservationofonescan(notthereplicate)isperformed, bya qualifiedRTRoperator(anyonebutthe initial RTR operator)YInbatch SRRTR1278, anindependentobservationwasperformed oncontainerSR85815and areplicate scanwasperformed oncontainerSR506717.InbatchSRRTR1732, anindependentobservationwasperformedoncontainer235F01073and areplicate scanwas performedoncontainer SR519787.A differentoperator fromthe originalperformedboth ofthe QCsamples. Thereplicate scan and independentRevisionNo.:1RTR-5DateofRevision:11/01/05ATTACHMENT A.4:REAL-TIME RADIOGRAPHY (RTR) CHECKLISTEPA Inspection No.: EPA-SRS-10.05-8Inspection Date: 10/31/2005–11/03/2005Establishment of RequiredTechnical Elementsin ProceduresY/NLocationExecution of ProceduresY/NObjective Evidence/Commentobservation for batch SRRTR1724wasdocumentedinbatch SRRTR1723.Objective evidence reviewed:BDRs, debris,S5000:SRRTR1728,SRRTR1732RTR-9Procedure(s)contain standardizedforms forrecording RTRdataCCP-TP-011,Revision16,Attachment3•RTR operatoradequately explained theprocessfollowed for examining adrumand enteringdataintodataforms(whether hardcopyorelectronicdata entry isused).•Directdataentryintoanelectronic formisdonebythe RTRoperator usinga computerwhiletheoperator is still inthe RTRbooth.•The electronicdatafileundergoes thesamequality control(QC) checks usedforhand-writtendata entriesYDuringtheon-site inspection,EPA observed the RTReventfora debris (S5000)drum, numberSR515960(batchSRRTR1749) onRTRunit RTR#1. Thedemonstration took placeon Pad 4 ofSRS.Theoperator hada copyoftheapplicableprocedure(CCPTP-011) available in the RTRoperations areaandperformed theRTReventin accordancewith theinstructionscontainedinthatprocedure.RTRdataareelectronically enteredintothedata form(Attachment3ofprocedureCCP-TP-011).Anoperatoraid isavailable forWMP standardweights that are usedforcompleting theRadiographyDataSheet(Attachment3).The BDRsaresubjecttobothdatagenerationandproject levelreviews.The checklists for theBDRsreviewedwerecomplete, signed anddated.Objective evidence reviewed:BDRs, debris,S5000:SRRTR1724, SRRTR1728, SRRTR1732RTR-10Siteproceduresrequire reviewofBatchData Reports(BDRs) at thedatagenerationandprojectlevelCCP-TP-011,Revision16,Attachment4-7CCP-TP-001,Revision11Datageneration levelreviewsareperformed anddocumentedProjectlevelreviewsareperformed anddocumentedYBDRs SRRTR1724,SRRTR1728, andSRRTR1732werereviewedduringthe on-siteinspection.AllBDRscontainedcompleteand signeddatagenerationlevelreviewchecklists (IndependentTechnicalReviewer,Technical Supervisor, Facility Quality AssuranceOfficer).TheBDRs also contained complete andsignedSite Project QualityAssurance Officer reviewRevisionNo.:1RTR-6DateofRevision:11/01/05ATTACHMENT A.4:REAL-TIME RADIOGRAPHY (RTR) CHECKLISTEPA Inspection No.: EPA-SRS-10.05-8Inspection Date: 10/31/2005–11/03/2005Establishment of RequiredTechnical Elementsin ProceduresY/NLocationExecution of ProceduresY/NObjective Evidence/Commentchecklists.TheSiteProject Manager data validationsummary for these BDRshadnotbeenperformed at thetimeofthe inspection.Objective evidence reviewed:BDRs, debris,S5000:SRRTR1724, SRRTR1728, SRRTR1732RTR-11RTR operatorsreceivetheresultsof theVE/RTRcomparisonRTR operatorsreceivetheresults of theVE/RTRcomparisonRTR operatorsreceivelessons learned informationbasedonthe comparisonofRTRandVEdataYRTR personnel arerequiredtoreadWaste MaterialParameter Comparison Reports as they are issued.RTRoperators can access thereports electronically. Anysignificant issues arediscussedwith theSME.Objective evidence reviewed:Inter-office memo, “Waste Material ParameterWeightComparisonReportfor Savannah RiverSiteOctober2004throughMay 2005(Relative PercentDifferenceComparisonReportfor RadiographyandVisualExamination”, datedMay25, 2005.RevisionNo.:1RTR-7DateofRevision:11/01/05ATTACHMENT A.4:REAL-TIME RADIOGRAPHY (RTR) CHECKLISTEPA Inspection No.: EPA-SRS-10.05-8Inspection Date: 10/31/2005–11/03/2005Information Included in BDRRequired Testing Batch ContentPresentYorNRequired Testing Batch ContentPresentY or NRequired Testing Batch ContentPresentY or NBatchDateYDescriptionof linersYVerificationofWasteMatrixCodeYReportdateYLayersof confinementYReference toorcopiesofanyNCRsYWaste containernumberYIndicationofventedrigid linersYOperatorsignature and testdateYWaste MatrixCodeYDescription ofcontainer contentsYData generationchecklistsYImplementing procedurenameor#YIndicationofsealed containers>4LYProjectlevelchecklistsYVideotape referenceYAmountoffreeliquidYQCdocumentationYContainergross weightYVerification that waste matches wastestreamdescriptionYEstimatedweights forWasteMaterial ParametersYRevisionNo.:1RTR-8DateofRevision:11/01/05ATTACHMENT A.5:NONDESTRUCTIVE ASSAY (NDA) CHECKLIST—IPANEPA Inspection No.: EPA-SRS-10.05-8Inspection Date: 10/31/2005–11/03/2005Required Technical ElementsY/NLocationVerificationofActivityY/NObjective EvidenceSystem DescriptionIdentify theNDA systembyname, locationand number, asappropriate.YCCP-PO-002,Revision13TheIPAN/GEsystemaddressed inthischecklist is identifiedanddescribed.YThere isone(1) Imaging PassiveActive Neutron Assay/GammaEnergyAnalysis(IPAN/GEA)systemusedbyCCP at theSavannah River Site(SRS).Itishousedina trailer onTRUPAD4within the SWMF at the EAreaofSRS and isidentified asID#B9F402S3TI4II10.Describe thesystem’s operationalhistoryincludingdeploymentatother DOEsites.NANotApplicableThesystem’soperationalhistoryforTRU wastes for WIPPis restrictedtoSRS.NAFor the purposes ofcharacterizing TRU wastes forWIPP thissystemhasnotbeenoperationalatanyotherDOEsiteForsystems thathavebeendeployedatmultiple DOEsites document pertinentaspectsof each system’sdevelopment, e.g.,installation ofnewordifferentdetectors,softwareorother relevantfeatures.NANotApplicableThissystemhas notbeendeployed atother DOEsitesfor assaying TRUwastes for WIPP.NAThis systemhas notbeendeployed atotherDOE sitesforassaying TRU wastes for WIPP.System PerformanceIdentifythe periodof performancerelevanttothis inspectionand if this NDA systemhasprior EPAapproval(s).NAEPA InspectionNotificationLetter forEPA-SRS-10.05-8and InspectionReportforEPA-CCP-SRS-09.04.24This inspection focusesonIPAN/GEAoperationsover thepastyear.PriorIPAN/GEA approvals arethosedeterminedbyEPA.YThis is a baselineinspection.The conditionsevaluatedconsistofthe current statusof theIPAN/GEA system. PriorIPAN/GEA approval was limitedtodebris wastes.RevisionNo.:1NDA-IPAN-1DateofRevision:11/01/05ATTACHMENT A.5:NONDESTRUCTIVE ASSAY (NDA) CHECKLIST—IPANEPA Inspection No.: EPA-SRS-10.05-8Inspection Date: 10/31/2005–11/03/2005Required Technical ElementsY/NLocationVerificationofActivityY/NObjective EvidenceIdentifythe numberof waste containersthissystemassayed duringtheperiodofperformance.Of these, indicate how manyBatch Data Reports(BDRs)wereassembled,andhow manyhavebeenpromoted throughProject LevelReview and are availableforevaluationduringthis inspection.NANotApplicableCCPdocuments indicate thenumber ofIPAN/GEA assays, thenumberofcompleted BDRsandhow manyBDRshavebeenpromotedthroughProjectLevel Reviewand areavailable forevaluationduringthis inspection.YApproximately440 IPAN/GEAassayswereperformed from10-22-04through10-23-05,whichresultedinthe generationof36BDRs.General ReportingRequirementsAssay systemsmust report quantitativevaluesanduncertainties for238Pu,239Pu,240Pu,242Pu,241Am,233U,234U,238U,90Sr,and137Cs.YCCP-PO-002,Revision13;CCP-TP-025, Revision10;CCP-TP-026, Revision6The IPAN/GEA provides quantitativevalues anduncertainties for all 10WIPP-trackedradionuclides.YThe combination of activeneutron (AN), passiveneutron(PN)and theHPGe(gamma)modes provides quantitativevaluesanduncertainties for238Pu,239Pu,240Pu,242Pu,241Am,233U,234U,238U,90Sr, and137Cs.235U isalsoprovidedfordeterminingFGE. See B11-5104-CTR-001Revision3 and BII-5104-QAO001,Revision7.Each container characterized andintendedfor disposalat WIPP must contain TRUwaste.YCCP-PO-002,Revision13;CCP-TP-025, Revision10;CCP-TP-026, Revision6Containers tobedisposedofatWIPPmeetthe definitionofTRUwaste.YSeeB11-5104-CTR-001Revision3 and BII-5104-QAO001,Revision7.NDA instruments andproceduresareappropriate for thewaste streams beingassayed.YCCP-PO-002,Revision13;CCP-TP-025, Revision10;CCP-TP-024, Revision20TheIPAN/GEA and associatedprocedures areappropriate for thewastematrices beingassayed.YTheABS/MOD andMODrangesfor the IPAN/GEA adequatelycoverthe range ofwastematrices. SeeB11-5104-CTR001Revision3 andBII-5104-QAO-001, Revision7.NDA instruments andproceduresresultinunbiasedvalues for the cumulative activity oftheWIPP radionuclide inventory.YCCP-PO-002,Revision13;CCP-TP-025, Revision10;CCP-TP-024, Revision20The IPAN/GEA operationresultsinunbiasedvalues for the cumulativeactivity oftheWIPPradionuclideinventory.YSeeB11-5104-CTR-001Revision3 and BII-5104-QAO001,Revision7.RevisionNo.:1NDA-IPAN-2DateofRevision:11/01/05ATTACHMENT A.5:NONDESTRUCTIVE ASSAY (NDA) CHECKLIST—IPANEPA Inspection No.: EPA-SRS-10.05-8Inspection Date: 10/31/2005–11/03/2005Required Technical ElementsY/NLocationVerificationofActivityY/NObjective EvidenceSomeradionuclides arederivedbytheapplication of scaling factors orcorrelationtechniques.Identify all radionuclides that arequantified inthis manner.YCCP-PO-002,Revision13;CCP-TP-024, Revision20;CCP-TP-025, Revision10Allradionuclides derivedbytheapplication of scaling factors orcorrelation techniques are identified.YValuesaredetermined for234Ubyscalingto235U and/or238U;90Srbyscaling to137Cs;and,242Pu viathe Efficiency–Times–Attenuation (ETA) MethoddevelopedbyBII.SeeB11-5104-CTR-001 Revision3andBII-5104-QAO-001, Revision7.Assessthe technical adequacy of thecalculations involvingtheapplicationofscaling factors and/orcorrelationtechniques.YCCP-PO-002,Revision13;CCP-TP-025, Revision10The technical adequacyof thecalculations involvingtheapplicationofscaling factors and/orcorrelationtechniquesis appropriate anddocumented.YThe basis forthescaling/correlation factorsusedistechnicallyadequateand isdocumented. SeeB11-5104-CTR-001 Revision3;BII-5104-QAO-001, Revision7;and BII5104-ADD-001, MobileSystemWaste Assay Algorithms,Revision0,August2000.Identify theprocedures thatgovernthisfunctionand where theresults of thesecalculations are documented.YCCP-PO-002,Revision13;CCP-TP-025, Revision10The CCP procedures that governtheapplication of scaling factors areidentified andresults of thesecalculations are documented.YCCP-TP-025, Section 4.3.4 Noteprovidesspecific directions inthis regard. The results of thecalculation arecontained intheIPAN/GEA BDRs.Acceptable Knowledge(AK)If isotopicratiosbasedonAKareusedthevalues arequalifiedbyconfirmatory testing.YCCP-PO-002,Revision13;CCP-TP-025, Revision10Isotopic ratios usedinquantifyingradionuclidesare qualified byconfirmatory testingwhen AK isused.YCCP-TP-025, Section 4.3describes the relationshipbetween measuredandAKbaseddefaultisotopics.RevisionNo.:1NDA-IPAN-3DateofRevision:11/01/05ATTACHMENT A.5:NONDESTRUCTIVE ASSAY (NDA) CHECKLIST—IPANEPA Inspection No.: EPA-SRS-10.05-8Inspection Date: 10/31/2005–11/03/2005Required Technical ElementsY/NLocationVerificationofActivityY/NObjective EvidenceDoNDApersonneluseAKderivedisotopicvalues tocalculate radionuclidevalues?Ifso, isthisfunctionperformedaccording toaformalprocedure?Assessthetechnicaladequacyof this process(s).YCCP-PO-002,Revision13;CCP-TP-025, Revision10NDA personnelusing AKderivedisotopic values tocalculateradionuclidevaluesdo soaccording toaformalprocedure thetechnical adequacy ofwhich is acceptable.YApprovedisotopicsforspecificwaste streams aredocumented inCCP-AK-SRS-1,CCP-AK-SRS2,CCP-AK-SRS-3 andCCP-AKSRS-4.CCP-TP-025, Section 4.3provides instructionregardingtheuse ofAKbasedisotopics.Identify theprocedureand where theresultsof these calculations aredocumented.YCCP-PO-002,Revision13;CCP-TP-025, Revision10The procedure for AKrelatedcalculations andwhere the results ofthese calculationsarerecordedaredocumented.YCCP-TP-025,Attachment1-CCP ExpertAnalysis Reportdocumentsthe use ofAKisotopics.Isotopic DeterminationIdentify theradionuclidesthatare measureddirectly and the specific radiationtype (",AN or PN) thatis measured.YCCP-PO-002,Revision13;CCP-TP-025, Revision10Theradionuclides thattheIPAN/GEAmeasuresdirectly andthe specificradiation type(AN,PNofgamma) thatis measured are documented.YThe combination ofAN, PNandgammaallowsdirectmeasurement of the following:238Pu,239Pu,240Pu,241Am,233U,238U and137Cs.Identify the method(s)usedto derivetheisotopiccontributionfor theunmeasuredradionuclides,e.g., MGA,PCFRAMorother technique.YCCP-PO-002,Revision13;CCP-TP-025, Revision10TheIPAN/GEA methodsusedtoderivethe isotopic contribution for theunmeasuredradionuclidesareidentified.YEfficiency–Times–Attenuation(ETA) MethoddevelopedbyBII.See B11-5104-CTR-001Revision3 and BII-5104-QAO001,Revision7.Lower Levelof Detection (LLD)The LLD for eachNDA systemmust bedetermined.For multimodalsystems thismayrequirea separatedeterminationfor eachmode, i.e., activeneutron,passiveneutronand gamma.YCCP-PO-002,Revision13;CCP-TP-026, Revision6The LLD for theIPAN/GEAhasbeendeterminedfor bothoperationalmodes(active neutronand passiveneutron)over arangeofwaste-related indices,i.e.,ABS/MOD &MOD indices.YThe LLD for each assay event isexpressed asaMinimumDetectable Concentration (MDC)value innCi/g. MDCs arederivedbydividingthebythecontainer’sweight.The LLDforpassivemode assayshasbeendeterminedasrequired, althoughis not routinelyuseddue to theRevisionNo.:1NDA-IPAN-4DateofRevision:11/01/05ATTACHMENT A.5:NONDESTRUCTIVE ASSAY (NDA) CHECKLIST—IPANEPA Inspection No.: EPA-SRS-10.05-8Inspection Date: 10/31/2005–11/03/2005Required Technical ElementsY/NLocationVerificationofActivityY/NObjective Evidenceinherently different sensitivitiesbetween thetwo modes.SeeBII5104-QAO-001, Revision7.Site-specific environmental backgrounds andcontainer-specific interferences must beaccounted for inLLDdeterminations.YCCP-PO-002,Revision13;CCP-TP-026, Revision6Site-specific environmentalbackgroundsand container specificinterferencesareconsidered.YSeeB11-5104-CTR-001Revision3 and BII-5104-QAO001,Revision7.NDA instrumentsperforming TRU/NonTRU waste discriminationmeasurementsarerequiredto have a LLDnogreater than100nCi/g.YCCP-PO-002,Revision13;CCP-TP-025, Revision10;CCP-TP-026, Revision6The IPAN/GEA performsTRU/NonTRU waste discriminationand hasaLLD oflessthan100nCi/gforallpertinentoperationalmodes.YThe IPAN/GEA hasadequatesensitivity toperformTRU/NonTRUdiscrimination atthe100nCi/gcriterion.See B11-5104-CTR-001 Revision3 andBII5104-QAO-001, Revision7.The technicalbasis andderivationfor LLDsmust beadequate and appropriatelydocumented.YCCP-PO-002,Revision13;CCP-TP-025, Revision10;CCP-TP-026, Revision6The technicalbasis andderivationforthe IPAN/GEA’s LLDsare adequateand appropriately documented.YThetechnical basis fortheIPAN/GEA’s LLD wasthe focusofEPA scrutinyduringpreviousinspections. Revisionsweremadetothe LLDmethodology,see BII-5104-QAO-001,Revision4 (6/18/04), 6 (1-21-05)and 7(1-25-05).For radionuclides that arenotdeterminedprimarily bymeasurement anLLD analog,i.e., areportingthreshold mustbeusedwhenit is technically feasible.Identify allinstances whenthis occursandthe formofthe documentationof these activities.YCCP-PO-002,Revision13;CCP-TP-025, Revision10For all radionuclides that arenotdeterminedprimarily bymeasurementanLLD analog is usedwhen it istechnically feasible.All instanceswhenthisoccursaredocumentedappropriately.YLLD analogsaredetermined forthenon-measuredradionuclides234U,90Sr and242Pu.SeeIPAN/GEA BDRs listedinthischecklist.Identify any/all instanceswhere anLLDvalue foranon-measuredradionuclide is notprovidedbasisona lackoftechnicalfeasibility.YCCP-PO-002,Revision13;CCP-TP-025, Revision10Thereareno instanceswherean LLDvalue (analog)foranon-measuredradionuclide isnotprovidedbasedonalackof technical feasibility.YCCPIPAN/GEA personnel statedthat therearenoinstances ofthisapproach for the IPAN/GEA.RevisionNo.:1NDA-IPAN-5DateofRevision:11/01/05ATTACHMENT A.5:NONDESTRUCTIVE ASSAY (NDA) CHECKLIST—IPANEPA Inspection No.: EPA-SRS-10.05-8Inspection Date: 10/31/2005–11/03/2005Required Technical ElementsY/NLocationVerificationofActivityY/NObjective EvidenceAreLLDvaluescontainer/assay eventspecificor aretypical LLDvalues applied toa class or typeof wastes, i.e.,those withsimilar attributes?IfLLDvalues arenotcontainer/assay eventspecific identify theattributesor characteristics wherebywastecontainers aregrouped.YCCP-PO-002,Revision13;CCP-TP-025, Revision10The technicalbasisfor theIPAN/GEA’sLLD valueshasbeendeterminedandisdocumented appropriately.YIPAN/GEA LLDvaluesaredeterminedonthe basis of agraphicalcorrelation determinedas a function of a container’sABS/MOD index.This iscorrectedfor the container’smasstoproduce theequivalentofacontainer-specific LLD.SeeB11-5104-CTR-001 Rev.3andBII-5104-QAO-001Rev.7.TotalMeasurement Uncertainty (TMU)The method used to calculatethe TMU for allrequiredquantitiesmustbe documentedandtechnically justified.YCCP-PO-002,Revision13The methodused tocalculatethe TMUfor all required quantities isdocumentedand technically justified.YTheIPAN/GEA’sTMUisdocumented inBII-5104-TMU001,Revision0,July2001. ThisdocumenthadbeenevaluatedbyEPAduringprevious inspectionsand remains unchanged.TMUdeterminationaccountsfor all sourcesofuncertainty,specifically:•Randomerrors•Calibration•Isotopic determination•Matrixinhomogeneity•Difference betweencalibrationassumptions and actualwaste•Nonuniformsource distribution•End effects•Self absorption•Transmission source•Self shielding•NeutronmultiplicationYCCP-PO-002,Revision13The TMUdetermination accountsforthe followingsourcesofuncertainty:•Randomerrors•Calibration•Isotopic determination•Matrix effects•Presenceofneutron&gammainterferents•Sourcedistribution•Self shielding•NeutronmultiplicationYSeeBII-5104-TMU-001,Revision0,July2001.RevisionNo.:1NDA-IPAN-6DateofRevision:11/01/05ATTACHMENT A.5:NONDESTRUCTIVE ASSAY (NDA) CHECKLIST—IPANEPA Inspection No.: EPA-SRS-10.05-8Inspection Date: 10/31/2005–11/03/2005Required Technical ElementsY/NLocationVerificationofActivityY/NObjective EvidenceMethods to determine TMUmust bedocumented,reviewedandapprovedbyCBFOforeach NDA instrument.YCCP-PO-002,Revision13Methods todetermine TMU havebeenreviewedand approvedbyCBFOforeach NDAinstrument.YBII-5104-TMU-001,Revision0,July2001has beenreviewedandapproved byCBFO.System CalibrationEachNDA instrumentmust becalibratedbefore its initial use.Determine the date ofthe system’s calibration ofrecordandwherethis is documented.YCCP-PO-002,Revision13;CCP-TP-026, Revision6The IPAN/GEA wascalibrated beforeits initial use and thesystem’scalibrationof recordhas beendetermined anddocumented.YTheIPAN’s calibration isdocumented inB11-5104-CTR001Revision3 andBII-5104-QAO-001 Revision7.Therangeof applicability ofthe system‘scalibration(s)must bespecifiedin siteprocedures orotherformaldocumentation.Identify the manner inwhichtherange isexpressed, i.e., curiesorPu/SNM mass foractivity and salient physical characteristicsfor matrix.YCCP-PO-002,Revision13;CCP-TP-026, Revision6Therangeof applicability for theIPAN/GEA’scalibrationshas beenspecified and isdocumentedappropriately.YThe range ofapplicabilityisexpressed interms of anABS/MOD indexfor activemodeassays (11.96– 341.65)and aMOD indexforpassivemodeassays (1.89 –13.94).The rangeofPu is statedas detectionlimitto120g.See B11-5104-CTR001 Revision3.Any matrix/source surrogatewastecombinationsmust be representativeof theactivity rangesand relevantwaste matrixcharacteristics currentlyinuseorplannedforuseby thesystem. Thesystemmust becalibrated to100%recovery.YCCP-PO-002,Revision13;CCP-TP-026, Revision6Matrix/source surrogate wastecombinations usedare representativeofthe activity ranges andrelevantphysicalcharacteristics (matrices) of thewastecontainers currentlymeasuredbytheIPAN/GEA. The systemis calibratedto100%recovery.YThe matrix/source combinationsusedfor theIPAN’s calibrationincludeanemptydrum, paper&plastics, glass,Ethafoam, drycombustibles and a mixture thatsimulates a lightsludge.Theseprovide theABS/MOD andMODrangescited above.SeeB11-5104-CTR-001, Revision3.The use ofconsensusstandards forcalibration is required,whensuchstandardsexist.If consensus standardsdonot exist, thecalibrationtechniquemustbeapprovedbyCBFO.Identify the specific consensusstandards thatwereusedfor the systemcalibration or, intheir absence, the alternateYCCP-PO-002,Revision13;CCP-TP-026, Revision6Aconsensus standardhas beenusedforthe IPAN/GEA’s calibration and is citedinthe CCP documentation.YBII-5104-QAO-001,Revision7cites ASTM C1493-01,StandardTest Method for Non-DestructiveAssayof Nuclear Material inWasteby Passive and ActiveNeutron CountingUsingaDifferential Die-AwaySystem.RevisionNo.:1NDA-IPAN-7DateofRevision:11/01/05ATTACHMENT A.5:NONDESTRUCTIVE ASSAY (NDA) CHECKLIST—IPANEPA Inspection No.: EPA-SRS-10.05-8Inspection Date: 10/31/2005–11/03/2005Required Technical ElementsY/NLocationVerificationofActivityY/NObjective Evidencecalibration technique.Evaluate the CBFOapprovalof thealternate technique.This standard is comparablebutthe imaging aspect is addresseddifferently. The system’scalibration ofrecord predates theexplicit requirement for aconsensus standardinDOE/WIPP-02-3122.Primarystandardsmustbeobtainedfromsuppliersmaintaininga nationallyaccreditedmeasurement program.Identify thenationally accredited measurement program.YCCP-PO-002,Revision13;CCP-TP-026, Revision6Primarystandardshavebeenobtainedfromsuppliersmaintaininganationallyaccredited measurement program.Theprogramhasbeenidentifiedandappropriately documented.YT. Petersonprovideda BNFLletter datedAugust16,2004fromR. HansontitledTraceability ofsources/standardstoNISTandvendorevaluation.List the standards usedfor calibrationandverifythepedigreeofeach standard.YCCP-PO-002,Revision13;CCP-TP-026, Revision6The calibration standards are listed andthe pedigreeof eachhasbeenverified.YCalibration standards consist ofPu,252Cf and238U (DU)sources.Standards are listedinB11-5104-CTR-001, Revision3.Calibration Verification&ConfirmationVerification ofan NDAinstrument’scalibration must beperformedafter any ofthe followingoccurrences: major systemrepairs and/ormodifications, replacementofthe system’s components, significantchangestothesystem’s software, andrelocationofthe system.YCCP-PO-002,Revision13;CCP-TP-026, Revision6Verificationofthe instrument’scalibrationhasbeenperformed anddocumented asrequired.YT. Petersonprovideda listofeighteen (18)calibrationverifications thatwereperformedfrom1-05-05 through9-22-05.Recalibration of the systemmustoccur if thecalibration verificationdemonstrates that thesystem’s responsehas significantly changed.YCCP-PO-002,Revision13;CCP-TP-026, Revision6Recalibration of the IPAN/GEA systemhasnotbeenrequiredwithinthe lastyear.NACCP personnel stated thatrecalibrationofthe IPAN/GEAhadnotbeenrequired.The systemcalibration must be confirmed byperforming replicatemeasurements of anoninterferingmatrix.YCCP-PO-002,Revision13;CCP-TP-026, Revision6The calibrationhasbeenconfirmed byperforming replicatemeasurements of anon-interfering matrix.YSeeBII-5104-QAO-001Revision7.RevisionNo.:1NDA-IPAN-8DateofRevision:11/01/05ATTACHMENT A.5:NONDESTRUCTIVE ASSAY (NDA) CHECKLIST—IPANEPA Inspection No.: EPA-SRS-10.05-8Inspection Date: 10/31/2005–11/03/2005Required Technical ElementsY/NLocationVerificationofActivityY/NObjective EvidenceReplicatemeasurements must beperformedwithcontainersofthesamenominalsize andaccording tothe sameproceduresused foractual waste assays.YCCP-PO-002,Revision13;CCP-TP-026, Revision6Replicate measurementshavebeenperformed withcontainersofthe samesize using the sameproceduresas thoseusedfor actualwaste assays.YSeeBII-5104-QAO-001Revision7.Replicatemeasurements must beperformedusingnationallyrecognized standardsorstandards derived fromnationallyrecognizedstandards thatspantherangeofuseoftheinstrumentwithrespecttodisintegration rateand/ormatrixeffects. Identify all standardsthatwere used andindicate their application(verification or confirmation).YCCP-PO-002,Revision13;CCP-TP-026, Revision6Replicate measurementshavebeenperformed usingnationallyrecognizedstandards thatspantherangeofuseofthe instrumentwithrespect todisintegration rateand/ormatrixeffects.Allstandards thatwereusedhavebeenidentified and their specific applicationdocumented.YSeeB11-5104-CTR-001Revision3,Appendix8and BII5104-QAO-001Revision7.Identify thenationally accreditedmeasurement program.List the standardsusedforverification/confirmation andverifythe pedigreeof eachstandard.YCCP-PO-002,Revision13Thenationally accredited measurementprogramsfor the three typesofstandards used areidentifiedallowingthepedigree ofeach standard tobeverified.YSee BNFLInstruments letter ofAugust 16,2004, RobertHansontoTomPeterson, that documentstraceability for LANL, FrontierTechnologyCorporation,NorthAmerican Scientific andIsotopeProducts Laboratories.The standardsusedfor calibrationconfirmationmustnotbethesamesourcesasthoseusedfor the system’s calibrationofrecord.YCCP-PO-002,Revision13;CCP-TP-026, Revision6The standardsusedfor calibrationconfirmationare differentfromthoseusedfor the IPAN/GEA’s calibrationofrecord.YInitial calibration was performedusing252Cfand238U (DU)sources. ConfirmatorymeasurementswereperformedusingPu sources. See B11-5104-CTR-001 Revision3 andBII5104-QAO-001Revision7.Requirements for accuracy, expressed as %R,and precision,expressed as%RSD, must bemet as specifiedin DOE/WIPP-02-3122,Appendix A, TableA-3.2for precisionand"30% for accuracy.YCCP-PO-002,Revision13;CCP-TP-026, Revision6Requirements for accuracy andprecisionhavebeen met as specified inDOE/WIPP-02-3122, AppendixA,Table A-3.2 for precisionand"30% foraccuracy.YCompliance withtherequirements for precision andaccuracy arefound inB11-5104-CTR-001 Revision3 andBII5104-QAO-001Revision7.RevisionNo.:1NDA-IPAN-9DateofRevision:11/01/05ATTACHMENT A.5:NONDESTRUCTIVE ASSAY (NDA) CHECKLIST—IPANEPA Inspection No.: EPA-SRS-10.05-8Inspection Date: 10/31/2005–11/03/2005Required Technical ElementsY/NLocationVerificationofActivityY/NObjective EvidenceQualityControlAllradioassayanddatavalidation mustbeperformed byappropriatelytrained andqualified personnel.YCCP-PO-002,Revision13;CCP-QP-002Reviewand validation ofIPANdataareperformed byappropriatelytrained andqualified personnel.YT. Petersonprovideda listofalldatareviewandvalidationpersonnel.See“SRS– ListofQualified Individuals,10/31/2005.”Identify thename, title andfunction of allpersonnelperforming NDA datavalidation.YCCP-PO-002,Revision13;CCP-QP-002;CCP-TP024,Revision20;CCP-TP025,Revision10The name,titleandfunctionofallpersonnelperforming IPAN/GEAdatavalidation aredocumented.YThe name,titleandfunctionofall data reviewand validationpersonnel areprovidedin“SRS–ListofQualifiedIndividuals,10/31/2005.”Requalificationofpersonnelmustbe basedon evidenceofcontinued satisfactoryperformance and must beperformed at leastevery two years.YCCP-PO-002,Revision13;CCP-QP-002;CCP-TP024,Revision20;CCP-TP025,Revision10Requalification ofpersonnelisbased onevidence ofcontinued satisfactoryperformance is performed at least everytwoyears.YThe “SRS–List ofQualifiedIndividuals,10/31/2005”providedthe trainingstatusof allIPAN/GEApersonnel.All computerprograms, includingspreadsheets used for datareduction oranalysis, must meet the applicablerequirements inthe CBFO QAPD.NAThis aspectwas notevaluated duringtheinspection.This aspectwas not evaluated duringthe inspection.NAThis aspectwas not evaluatedduringthe inspection.The site must participate inrelevantmeasurement comparison programssponsoredorapprovedbyCBFO,includingthe NDAPDP.YCCP-PO-002,Revision13The IPAN/GEA has participatedsuccessfully in the CBFO sponsoredNDA PDP.YThe IPAN/GEA participatedinNDAPDP Cycle 12Abysuccessfully assaying aglassmatrixwithWG Pu(239Pu). See“Scoring Results – Cycle 12ANondestructive AssayPDP,”July 8,2005,Michael BrowntoKerry Watson.RevisionNo.:1NDA-IPAN-10DateofRevision:11/01/05ATTACHMENT A.5:NONDESTRUCTIVE ASSAY (NDA) CHECKLIST—IPANEPA Inspection No.: EPA-SRS-10.05-8Inspection Date: 10/31/2005–11/03/2005Required Technical ElementsY/NLocationVerificationofActivityY/NObjective EvidenceBackgroundand Performance ChecksAssay systembackground measurementsmustbe takendaily, unlessotherwiseapprovedbyCBFO.Determine theformofthe documentationof CBFO’sapproval, ifapplicable. Contributionsto backgroundsfromnearbyradiationsourcesmustbecarefullycontrolled,ormorefrequentbackgroundsmustbe measured.YCCP-PO-002,Revision13;CCP-TP-024, Revision20;CCP-TP-025, Revision10Daily background measurementshavebeen taken and recorded overtheappropriate periodsofperformance.Contributionstobackgroundfromnearby radiation sourcesandwastehandling activities are controlled.YThe BDRsevaluatedduringthisinspection contain evidenceofdailybackgrounds. SeeIPAN/GEA BDRs: SRS-NDA050815, SRS-NDA-050412;SRS-NDA-050721and SRSNDA-050912.Assesshowoftenbackgroundradiationwasproblematic tothe extentthatmeasurementpersonnelhad tomake adjustments.YCCP-TP-002,Revision13;CCP-TP-024, Revision20Control chartsthat documentthesystem’s performance over time aremaintained.YExcessive backgrounds donotappeartobe amajorproblemforthe IPAN/GEA.Identify thecriteria usedto evaluateinstrument backgrounds and assess thetechnical adequacy of this criterion, i.e.,statistical oradministrative.YCCP-TP-002,Revision13;CCP-TP-024, Revision20Backgrounds have beenevaluatedandthe resultsof these evaluationshavebeen documented.YSee copyof CCP-TP-024,AttachmentAinIPAN/GEABDRs: SRS-NDA-050815,SRSNDA-050412; SRS-NDA050721and SRS-NDA-050912.Systemperformance checksmustbeperformed atleastonceperoperationalday.YCCP-TP-002,Revision13;CCP-TP-024, Revision20Performance checkshavebeenperformed atleastonceperoperationaldayand allcheckshavebeendocumented inIPAN/GEA BDRs.YSee IPAN/GEABDRs:SRSNDA-050815,SRS-NDA050412; SRS-NDA-050721andSRS-NDA-050912.Systemperformance checksmustinclude, asapplicable, efficiency, matrixcorrectionchecks, and systems peakposition andresolution for spectrometric systems.YCCP-TP-002,Revision13;CCP-TP-024, Revision20Performance checks include:No-SourceBackgrounds, Imaged Active Mass,CorrectedPassive Multiplicity Mass,137Cs Energy& Resolution (FWHM)YThe BDR’srevieweddocumentall applicableperformancechecks.See IPAN/GEABDRs:SRS-NDA-050815, SRS-NDA050412; SRS-NDA-050721andSRS-NDA-050912.Ata minimumofonceperoperationalweekaninterferingmatrixmust beassayedtoassess the longtermstability oftheNDAinstrumentand its matrixcorrections.Howisthisperformancedocumented?YCCP-TP-002,Revision13;CCP-TP-024, Revision20An interferingmatrixis usedtoassessthe longtermstability oftheIQ3 anditsmatrix correctionsat least onceperoperational week.This activity isreviewed anddocumented at theYTheBDRsexamineddocumentedthe executionof weeklyinterferingmatrixchecks.Seethe “Mobile Assay System(IPAN/GEA)6MonthInterferingRevisionNo.:1NDA-IPAN-11DateofRevision:11/01/05ATTACHMENT A.5:NONDESTRUCTIVE ASSAY (NDA) CHECKLIST—IPANEPA Inspection No.: EPA-SRS-10.05-8Inspection Date: 10/31/2005–11/03/2005Required Technical ElementsY/NLocationVerificationofActivityY/NObjective EvidencerequiredintervalsMatrixEvaluationReportforSRS Operations(11/14/2004to5/14/2005)” and “MobileAssaySystem(IPAN/GEA)6 MonthInterfering MatrixEvaluationReportforSRS Operations(5/16/2004to11/13/2004).”Interfering surrogatewaste matrices must beconstructedina way that thesalientmatrixcharacteristics do not changeover time.YCCP-TP-002,Revision13Interfering surrogatewaste matriceshavebeenconstructedsuchthatthesalientmatrixcharacteristics donotchange overtime.YSurrogatewaste matrixdrums arethe equivalentofPDP matrixdrums andaresufficiently stablefor this application.Theradionuclide sourcesusedforperformance checks mustbelong-livedandofsufficient strength(activity)toprovidestatistically sufficientresultsover a shortmeasurement time.YCCP-TP-002,Revision13;CCP-TP-024, Revision20Theradionuclide sourcesusedforperformance checks are long-livedandare ofsufficientstrength(activity)toprovide statistically sufficientresultsover ashort measurement time.YRadionuclidesources usedforperformance checks consistofcommercially availablegammaandneutron standards andcustommadePuO2standards;allare acceptable.Radioactive sourcesaredecaycorrected as afunctionoftheir physical half life, asappropriate, specifically133Ba,252Cf,137Cs,75Se and109Cd.YCCP-TP-002,Revision13;CCP-TP-024, Revision20Documentationexists toindicate thatradioactive sourcesare decay correctedas a function of their physical half life,as appropriate.YThe252Cf and137Cs sourcesaredecay corrected commensuratewiththeirphysical half lives.Decay correction is addressed inCCP-TP-024, Section 4.6.3.Performance checks must bequantitative andbasedon2and3 sigma limits.YCCP-TP-002,Revision13;CCP-TP-024, Revision20Performance checks are quantitative andbasedon2and3 sigma limits.YCCP-TP-024, Section 4.4provides direction for using2and3 sigma warningand controllimits, respectively.Identify howmanydata points are used forthe initial evaluation ofWeekly InterferingMatrix Checksand atwhat interval(s)newlimits are calculated.NACCP-TP-002,Revision13Theacceptancecriterion isnotcalculatedusinga collection ofdatapoints, therefore thisquestionis notapplicable.YThe control limit is definedasachievinga result wherethePutagvalue iswithin±95% oftheTMU confidence interval foreach measurement.RevisionNo.:1NDA-IPAN-12DateofRevision:11/01/05ATTACHMENT A.5:NONDESTRUCTIVE ASSAY (NDA) CHECKLIST—IPANEPA Inspection No.: EPA-SRS-10.05-8Inspection Date: 10/31/2005–11/03/2005Required Technical ElementsY/NLocationVerificationofActivityY/NObjective EvidenceDataManagementAllradioassaydatamustbereviewedandapproved byqualified personnelbefore beingreportedtoWWIS.YCCP-PO-002,Revision13;CCP-TP-024, Revision20;CCP-TP-025, Revision10IPAN/GEAdatahavebeenreviewedand approvedbyqualified personnelbeforebeingreportedtoWWIS.YTheIPAN/GEA BDRsreviewedcontain evidence ofappropriatereviews and approvals.SeeIPAN/GEA BDRs: SRS-NDA050815, SRS-NDA-050412;SRS-NDA-050721and SRSNDA-050912;also“SRS – ListofQualifiedIndividuals,10/31/2005.”Identify thename, title andfunction of theindividual(s)performing technicalreviewand approvalofNDABRDs.YCCP-PO-002,Revision13;CCP-TP-024, Revision20;CCP-TP-025, Revision10The name,titleandfunctionoftheindividual(s)performing technicalreviewand approvalofIPAN/GEABRDsare documented.YSee IPAN/GEABDRs:SRSNDA-050815,SRS-NDA050412; SRS-NDA-050721andSRS-NDA-050912; also“SRS –ListofQualifiedIndividuals,10/31/2005.”RadioassayBDRsmustconsistof thefollowingelements:•Testingfacilityname, testingbatchnumber, container numbers, and signatureof theSite Project Officer(SPO)ordesignee(s)•Table ofContents•Background andperformance check dataorcontrol charts for the relevanttimeperiod.•Data validation per the QAPD andsiteprocedures•Separatetesting report sheets foreachcontainer.YCCP-PO-002,Revision13;CCP-TP-024, Revision20;CCP-TP-025, Revision10IPAN/GEA BRDs consistofthefollowing elements, at aminimum:•Testingfacilityname, testingbatchnumber,containernumbers, andsignatureof the Site ProjectOfficer(SPO) ordesignee(s)•Table ofContents•Background andperformance checkdata or controlchartsfor therelevanttimeperiod.•Data validation per the QAPD andsite procedures•Separatetesting report sheets foreach container.YSee IPAN/GEABDRs:SRSNDA-050815,SRS-NDA050412; SRS-NDA-050721andSRS-NDA-050912.RevisionNo.:1NDA-IPAN-13DateofRevision:11/01/05ATTACHMENT A.5:NONDESTRUCTIVE ASSAY (NDA) CHECKLIST—IPANEPA Inspection No.: EPA-SRS-10.05-8Inspection Date: 10/31/2005–11/03/2005Required Technical ElementsY/NLocationVerificationofActivityY/NObjective EvidenceRadioassaydatasheets must include:•Title “Radioassay Data Sheet”•Method/procedure used•Dateofradioassay•ActivitiesandassociatedTMUforindividualradionuclides•TRU alpha concentration anditsassociated TMU•Operatorsignature•Reviewer signatureYCCP-PO-002,Revision13;CCP-TP-024, Revision20;CCP-TP-025, Revision10Radioassaydatasheets included, ataminimum:•Title “Radioassay Data Sheet”•Method/procedure used•Dateofradioassay•ActivitiesandassociatedTMUforindividualradionuclides•TRU alpha concentration anditsassociated TMU•Operatorsignature•Reviewer signatureYThe followingindividualradioasaydatasheets fromthree(3) ofthe four BDRslistedabovewereevaluated:SRS-NDA-050912: FBL04058&FBL04062SRS-NDA-050825: FBL03161,FBL03160&FBL04017SRS-NDA-050721: SR518613,SR5101102& SR5100218The followingnonpermanentrecords must bemaintainedat theradioassay-testingfacilityorforwarded tothesiteprojectoffice:•Testing batchreports•All rawdata, includinginstrumentreadouts, calculation records,andradioassay QC results•All applicableinstrumentcalibrationreportsYCCP-PO-002,Revision13;CCP-QP-008The followingnonpermanent recordsare maintained at theradioassay-testingfacility orforwardedtothe site projectoffice:•Testing batchreports•All rawdata, includinginstrumentreadouts, calculation records,andradioassay QC results•All applicableinstrumentcalibrationreportsYIPAN/GEArecordswereobserved inelectronic formintheIPAN/GEA trailer. Formalrecords arestored at CCPofficesoff site in Carlsbad,NM.RevisionNo.:1NDA-IPAN-14DateofRevision:11/01/05ATTACHMENT A.6:NONDESTRUCTIVE ASSAY (NDA) CHECKLIST—IQ3EPA Inspection No.: EPA-SRS-10.05-8Inspection Date: 10/31/2005–11/03/2005Required Technical ElementsY/NLocationVerificationofActivityY/NObjective EvidenceSystem DescriptionIdentify theNDA systembyname, locationand number, asappropriate.YCCP-PO-002,Revision13TheNDAsystemaddressed inthischecklist is the MCS IQ3 gammasystemhousedina trailer thatis locatedat the SavannahRiver Site,Area E,Pad 4.YPhysical observation ofsystememplaced at the Savannah River Site,AreaE,SWMF, Pad4,withintheIQ3trailer andCCP documentation tothesameeffect.Describe thesystem’s operationalhistoryincludingdeploymentatother DOEsites.NANotApplicableTheMCSIQ3has beendeployedonlyat SRSwithrespect toWIPPrelatedassays.NATheMCSIQ3has beendeployedonlyat SRSwithrespect toWIPPrelatedassays.Forsystems thathavebeendeployedatmultiple DOEsites document pertinentaspectsof each system’sdevelopment, e.g.,installation ofnewordifferentdetectors,softwareorother relevantfeatures.NANot ApplicableNotapplicable;theMCS IQ3 has onlybeendeployedatSRS forWIPP assayssince approximately March2003.NANot applicable; the MCSIQ3hasonlybeendeployedatSRS forWIPP assayssince approximately March2003.System PerformanceIdentifythe periodof performancerelevanttothis inspectionand if this NDA systemhasprior EPAapproval(s).YEPA InspectionNotificationLetter forEPA-SRS-10.05-8and InspectionReportforEPA-CCP-SRS-09.04.24This inspection focusesonIQ3operationsover thepastyear.PriorIQ3approvalsare thosedeterminedbyEPA.YThis is a baselineinspection.Theconditions evaluatedconsist of thecurrent status oftheIQ3 system. PriorIQ3 approvalwas limited todebriswastes.Identifythe numberof waste containersthissystemassayed duringtheperiodofperformance.Of these, indicate how manyBatch Data Reports(BDRs)wereassembled.Of the assembled BDRs, indicatehow manyhavebeenpromotedthroughProject LevelReview and are availableforevaluationduringthis inspection.YNot ApplicableThe numberof waste containers thissystemassayed duringtheperiodofperformance is identified.Ofthese, thenumberofBDRsthatwere assembledandhowmanyBDRshavebeenpromoted throughProjectLevelReviewand areavailable for evaluationduringthisinspectionare documented.YTherewere approximately2,772assays not including QCsamples forthe periodfrom10-15-04through10-06-05. Thesewere compiledinto200BDRs.RevisionNo.:1NDA-IQ3-1DateofRevision:11/01/05ATTACHMENT A.6:NONDESTRUCTIVE ASSAY (NDA) CHECKLIST—IQ3EPA Inspection No.: EPA-SRS-10.05-8Inspection Date: 10/31/2005–11/03/2005Required Technical ElementsY/NLocationVerificationofActivityY/NObjective EvidenceGeneral ReportingRequirementsAssay systemsmust report quantitativevaluesanduncertainties for238Pu,239Pu,240Pu,242Pu,241Am,233U,234U,238U,90Sr,and137Cs.YCCP-PO-002,Revision13;CCP-TP-047, Revision6;CCP-TP-048, Revision7Quantitative values and uncertaintiesfor238Pu,239Pu,240Pu,242Pu,241Am,233U,234U,238U,90Sr, and137Cs arereported.YThe IQ3provides quantitativevaluesfor all tenWIPP-trackedradionuclides,as documented in MCS-SRS-NDA0203, Revisions3and4 andMCSSRS-NDA-0504, Revision0.Each container characterized andintendedfor disposalat WIPP must contain TRUwaste.YCCP-PO-002,Revision13;CCP-TP-047, Revision6;CCP-TP-048, Revision7Containers tobedisposedofatWIPPmeetthe definitionofTRUwaste.YSee inMCS-SRS-NDA-0203,Revisions3 &4 andMCS-SRS-NDA0504, Revision 0.NDA instruments andproceduresareappropriate for thewaste streams beingassayed.YCCP-PO-002,Revision13;The IQ3 operationand proceduresareappropriate for thewaste streams beingassayed.YTheappropriatenessoftheIQ3for thewastes streambeing assayed isdescribed inMCS-SRS-NDA-0203,Revisions3 &4 andMCS-SRS-NDA0504, Revision 0.NDA instruments andproceduresresultinunbiasedvalues for the cumulative activity oftheWIPP radionuclide inventory.YCCP-PO-002,Revision13;TheIQ3operation results in unbiasedvalues for the cumulative activity oftheWIPP radionuclideinventory.YThe technicalbasisfor theIQ3’soperationin thisregardisdocumentedin MCS-SRS-NDA-0203,Revisions3& 4;MCS-SRS-NDA-0504,Revision0;and MCS-SRS-NDA-TMU-200,Revision1,June10,2004.Someradionuclides arederivedbytheapplication of scaling factors orcorrelationtechniques.Identify all radionuclides that arequantified inthis manner.YCCP-PO-002,Revision13;CCP-TP-048, Revision7Allradionuclides derivedbytheapplication of scaling factors orcorrelation techniques are identified.Y234U,242Puand90Sr aredeterminedbythe application ofscaling factorsorcorrelationtechniques. See MCS-SRSNDA-0203, Revisions3& 4;CCPTP-047,Revision5;and, CCP-TP048,Revision7.Assessthe technical adequacy of thecalculations involvingtheapplicationofscaling factors and/orcorrelationtechniques.YCCP-PO-002,Revision13;MCS-SRS-NDA-0203,Revisions3 &4;CCP-TP048,Revision7The technical adequacyof thecalculations involvingtheapplicationofscaling factors and/orcorrelationtechniquesis appropriate anddocumented.YMCS-SRS-NDA-0203Revisions3 and4 providethetechnical basis forthederivationof234U,242Pu and90Sr.RevisionNo.:1NDA-IQ3-2DateofRevision:11/01/05ATTACHMENT A.6:NONDESTRUCTIVE ASSAY (NDA) CHECKLIST—IQ3EPA Inspection No.: EPA-SRS-10.05-8Inspection Date: 10/31/2005–11/03/2005Required Technical ElementsY/NLocationVerificationofActivityY/NObjective EvidenceIdentify theprocedures thatgovernthisfunctionand where theresults of thesecalculations are documented.YCCP-PO-002,Revision13;CCP-TP-048, Revision7The proceduresthatgoverntheapplication of scaling factors areidentified andresults of thesecalculations are documented.YThe applicationofscaling factors isformalizedin CCP-TP-048, Revision7.Results aredocumentedwithinthesample’s BDR.Acceptable Knowledge(AK)If isotopicratiosbasedonAKareusedthevalues arequalifiedbyconfirmatory testing.YCCP-PO-002,Revision13;CCP-TP-048, Revision7Isotopic ratios usedinquantifyingradionuclidesare qualified byconfirmatory testingwhen AK isused.YSee theIQ3 BRDs listedinthischecklist thatwereevaluated duringthe inspection.DoNDApersonneluseAKderivedisotopicvalues tocalculate radionuclidevalues?Ifso, isthisfunctionperformedaccording toaformalprocedure?Assessthetechnicaladequacyof this process(s).NCCP-PO-002,Revision13;CCP-TP-048, Revision7NDA personnelusing AKderivedisotopic values tocalculateradionuclidevalues donot execute this taskaccording toaformal procedure.NApprovedisotopicsfor specific wastestreams are documented in CCP-AKSRS-1, CCP-AK-SRS-2, CCP-AKSRS-3 and CCP-AK-SRS-4.However,there is noformalinstructionfor theNDAExpertAnalysts (EA)regardingthe useofAKbased defaultisotopics.CCP-TP-048does containdirectionstotheEAregardingotheraspectsoftheradioaassayprocess.Examination ofBDRs indicates thatAK-basedisotopics havebeen applied by theNDA EA.SeeEPAInspectionIssueTracking FormNo.SRS-CCP-NDA05-006C.Identify theprocedureand where theresultsof these calculations aredocumented.YCCP-PO-002,Revision13;CCP-TP-048, Revision7The procedure for AKrelatedcalculations andwhere the results ofthese calculationsarerecordedaredocumented.YCCP-TP-048,Revision7 addresses theapplication of AK-basedisotopicsingeneral.Specific resultsarefound inthe IQ3BDRs.Isotopic DeterminationIdentify theradionuclidesthatare measureddirectly and the specific radiationtype (γ, ANor PN) that ismeasured.YCCP-PO-002,Revision13;CCP-TP-048, Revision7Theradionuclides thattheIQ3measuresdirectly are listed, all arephoton(gamma)emitters.YAllradionuclides arephoton(gamma)emitters. Dependingonnuclearmaterial content of aspecific containermeasuredradionuclidesinclude238Pu,239Pu,241Am,233U,235U and137Cs. SeeRevisionNo.:1NDA-IQ3-3DateofRevision:11/01/05ATTACHMENT A.6:NONDESTRUCTIVE ASSAY (NDA) CHECKLIST—IQ3EPA Inspection No.: EPA-SRS-10.05-8Inspection Date: 10/31/2005–11/03/2005Required Technical ElementsY/NLocationVerificationofActivityY/NObjective EvidenceMCS-SRS-NDA-0203, Revisions3and4and MCS-SRS-NDA-0504,Revision0.Identify the method(s)usedto derivetheisotopiccontributionfor theunmeasuredradionuclides,e.g., MGA,PCFRAMorother technique.YCCP-PO-002,Revision13;CCP-TP-048, Revision7The method(s)usedtoderive theisotopiccontributionfor theunmeasuredradionuclidesfortheIQ3are identified.YMGA isotopicsarebasedonmeasurement data fromthe LE Gedetector.In the absenceof validmeasured isotopics,AK isotopics areusedfor thosewaste streams that haveapproved AK-basedisotopics.Lower Levelof Detection (LLD)The LLD for eachNDA systemmust bedetermined.For multimodalsystems thismayrequirea separatedeterminationfor eachmode, i.e., activeneutron,passiveneutronand gamma.YCCP-PO-002,Revision13;CCP-TP-048, Revision7The LLD for eachNDA systemhasbeen determined, including alloperationalgamma(transmissioncorrectedand sum-of-segments) modesand detectorconfigurations (use ofendcaps).YThe system’s LLDhasbeendeterminedandtechnically justified.Systemisgammaonlybutusesmultiplemodesand/ordetectorconfigurationsthatare documentedin:MCS-SRS-NDA-0203, Revisions3and4and MCS-SRS-NDA-0504,Revision0.Site-specific environmental backgrounds andcontainer-specific interferences must beaccounted for inLLDdeterminations.YCCP-PO-002,Revision13;Site-specific and container specificbackgroundsand interferences areaddressed inLLD thedeterminationsfor all theIQ3’s operationalmodes.YThe system’s LLDdeterminationaccountsfor these potentialcontributions.See MCS-SRS-NDA0203, Revisions3and4.NDA instrumentsperforming TRU/NonTRU waste discriminationmeasurementsarerequiredto have a LLDnogreater than100nCi/g.YCCP-PO-002,Revision13The IQ3 does performTRU/Non-TRUwastediscrimination measurements anddoeshaveanLLD lessthan100nCi/g.The system’s LLD isadequate tosupportdecisionsat 100nCi/ g.Onlyassay values above the LLDwill bereportedfor the IQ3.See MCS-SRSNDA-0203, Revisions3and 4.The technicalbasis andderivationfor LLDsmust beadequate and appropriatelydocumented.YCCP-PO-002,Revision13;CCP-TP-047, Revision6;CCP-TP-048, Revision7The technicalbasis andderivationforIQ3 LLDsareadequate andappropriately documented.YThe technicalbasisfor the LLD istechnicallyadequateand isdocumented inMCS-SRS-NDA-0203,Revisions 3and 4.For radionuclides that arenotdeterminedprimarily bymeasurement anLLD analog,i.e., areportingthreshold mustbeusedwhenYCCP-PO-002,Revision13;CCP-TP-047, Revision6;CCP-TP-048, Revision7For radionuclides that arenotdeterminedprimarily bymeasurementan LLD analog, i.e., areportingYNon-measuredradionuclidesforwhichreporting thresholds areused:242Puand234U for238Pu wastes;234U forRevisionNo.:1NDA-IQ3-4DateofRevision:11/01/05ATTACHMENT A.6:NONDESTRUCTIVE ASSAY (NDA) CHECKLIST—IQ3EPA Inspection No.: EPA-SRS-10.05-8Inspection Date: 10/31/2005–11/03/2005Required Technical ElementsY/NLocationVerificationofActivityY/NObjective Evidenceit is technically feasible.Identify allinstances whenthis occursandthe formofthe documentationof these activities.thresholdisusedwhenit is technicallyfeasible.All instances whenthis occursfor theIQ3 aredocumentedappropriately.239Pu wastesusing adifferentfactorthanfor238Pu; and90Sr basedon137Cs.This isdocumentedinMCS-SRSNDA-0203, Revision4andproceduralized inCCP-TP-048.Identify any/all instanceswhere anLLDvalue foranon-measuredradionuclide is notprovidedonthe basisofa lackoftechnicalfeasibility.YCCP-PO-002,Revision13;CCP-TP-047, Revision6;CCP-TP-048, Revision7Any/all instances wherean LLDvaluefor anon-measuredradionuclide isnotprovidedbasedona lackoftechnicalfeasibility for theIQ3aredocumented.YA reportingthresholdisnotdeterminedfor242Pu in239Pu wastesbasedona lack of technical feasibilityas expressed by MCS personnel.Technical documentation for this isdocumented inMCS-NDA-0203,Revision4 and is formalizedinCCPTP-048,Revision7.AreLLDvaluescontainer/assay eventspecificor aretypical LLDvalues applied toa class or typeof wastes, i.e.,those withsimilar attributes?IfLLDvalues arenotcontainer/assay eventspecific identify theattributesor characteristics wherebywastecontainers aregrouped.YCCP-PO-002,Revision13;CCP-TP-047, Revision6;CCP-TP-048, Revision7The nature ofLLD valueshasbeendetermined and isdocumentedappropriately for theIQ3.YLLDvaluesare container and assayeventspecific,i.e., each assayeventfor thesamewaste container isexpectedtoyield an event-specificLLD value.SeeMCS-SRS-NDA0203, Revision3 and MCS-SRSNDA-0504, Revision0.TotalMeasurement Uncertainty (TMU)The method used to calculatethe TMU for allrequiredquantitiesmustbe documentedandtechnically justified.YCCP-PO-002,Revision13The methodused tocalculatethe TMUfor all required quantities isdocumentedandtechnically justifiedfor theIQ3.YTMU for thissystemhas beendetermined and isdocumented inMCS-SRS-NDA-TMU-200,Revision1,June10,2004.TMUdeterminationaccountsfor all sourcesofuncertainty,specifically•Randomerrors•Calibration•Isotopic determination•Matrixinhomogeneity•Difference betweencalibrationassumptions and actualwasteYCCP-PO-002,Revision13The TMUdetermination accountsforall sourcesofuncertainty, specifically:•Randomerrors•Calibration•Isotopic determination•Matrixinhomogeneity•Difference betweencalibrationassumptions and actualwasteYThe TMUdetermined for this systemand documentedin SRS-NDA-TMU200,Revision1 includes thecombineduncertaintiesdue to individual randomand systematicsourcesofmeasurement error.It includes thecontributionsfromthe following:countingstatistics, calibrationsourcestrengthandcurve fitting,isotopicdeterminations, self-absorptioneffects,RevisionNo.:1NDA-IQ3-5DateofRevision:11/01/05ATTACHMENT A.6:NONDESTRUCTIVE ASSAY (NDA) CHECKLIST—IQ3EPA Inspection No.: EPA-SRS-10.05-8Inspection Date: 10/31/2005–11/03/2005Required Technical ElementsY/NLocationVerificationofActivityY/NObjective Evidence•Nonuniformsource distribution•End effects•Self absorption•Transmission source•Attenuator caps•Nonuniformsource distribution•End effects•Self absorption•Transmission source•Attenuator capsmatrixnon-homogeneity, sourcedistribution,end effects,and attenuatorcaps. Uncertainties fromall identifiederror sources arepropagatedandreportedon radioassay datasheets as a1-sigma uncertainty.Methods to determine TMUmust bedocumented,reviewedandapprovedbyCBFOforeach NDA instrument.YCCP-PO-002,Revision13Methods todetermine TMU fortheIQ3havebeenreviewedand approvedbyCBFO.YThe TMUfor this systemis unchangedfromthe previousinspection.System CalibrationEachNDA instrumentmust becalibratedbefore its initial use.Determine the date ofthe system’s calibration ofrecordandwherethis is documented.YCCP-PO-002,Revision13;CCP-TP-047, Revision6The IQ3 hasbeencalibrated beforeitsinitial use andthe system’s calibrationofrecordhas been determinedanddocumented.YThe system’s calibration isdocumented inMCS-SRS-NDA-0203,Revisions 3and 4,MCS-SRS-NDA0504, Revision0 and MCS-SRSNDA-1000A, Revision1.Therangeof applicability ofthe system‘scalibration(s)must bespecifiedin siteprocedures orotherformaldocumentation.Identify the manner inwhichtherange isexpressed, i.e., curiesorPu/SNM mass foractivity and salient physical characteristicsfor matrix.YCCP-PO-002,Revision13;CCP-TP-047, Revision6Theranges ofapplicability oftheIQ3’scalibrationshavebeen specified and aredocumented appropriately.YMCS-SRS-NDA-0203, Revision 3provides a calibrationrangeexpressedinmass is0 to2.3gfor238Puand 0 to35g for239Pu.The upperends ofthese ranges are administrative. Thecalibration range isbest expressedinterms of Efficiency overtherangeof59keV to1408keV.MCS-SRS-NDA0504, Revision 0documents anextended modeoperationwith a rangeof0.1to7 g for238Puand1to211 gfor239Puusingattenuator capsonthethree LEGedetectors,asdescribed.RevisionNo.:1NDA-IQ3-6DateofRevision:11/01/05ATTACHMENT A.6:NONDESTRUCTIVE ASSAY (NDA) CHECKLIST—IQ3EPA Inspection No.: EPA-SRS-10.05-8Inspection Date: 10/31/2005–11/03/2005Required Technical ElementsY/NLocationVerificationofActivityY/NObjective EvidenceAny matrix/source surrogatewastecombinationsmust be representativeof theactivity rangesand relevantwaste matrixcharacteristics currentlyinuseorplannedforuseby thesystem. Thesystemmust becalibrated to100%recovery.YCCP-PO-002,Revision13;Matrix/source surrogate wastecombinations usedare representativeofthe activity ranges andrelevantphysical characteristics ofthe matricescurrentlymeasuredorplanned for use.TheIQ3is calibratedto 100%recovery.YMatrix/source surrogate wastecombinations aredocumented inMCS-SRS-NDA-0203, Revisions3and4and MCS-SRS-NDA-0504,Revision0.The use ofconsensusstandards forcalibration is required,whenapplicable.Ifconsensus standards do notexist,CBFOmustapprovethe calibration technique.YCCP-PO-002,Revision13Aconsensus standardhas beenusedforcalibrating theIQ3.YThe system’s calibration isbasedonanappropriate consensus standard,seenextchecklist item.Identify thespecific consensus standards thatwereusedfor the systemcalibrationor, intheir absence, the alternate calibrationtechnique.Evaluatethe CBFO approvalofthe alternate technique.YCCP-PO-002,Revision13The specific consensusstandardthatwasusedfor the IQ3’s calibrationisidentified anddocumented.YThe system’s calibration isbasedonStandardTestMethodsforNondestructive Assayof SpecialNuclearMaterialinLowDensityScrapandWaste bySegmentedPassive Gamma-Ray Scanning, ASTMC-1133-03. This standardwas revisedin2003 toallowforthe useofanefficiency calibration. PreviouslyASTM C-1133-96explicitly addressedonlya mass versuscountratecalibration technique.Primarystandardsmustbeobtainedfromsuppliersmaintaininga nationallyaccreditedmeasurement program.Identify thenationally accredited measurement program.YCCP-PO-002,Revision13Primarystandardshavebeenobtainedfromsuppliersmaintaininganationallyaccredited measurement program.Theprogramhasbeenidentifiedandappropriately documented.YCalibration sources are ModelENV4057 mixedgammasources fromNorth AmericanScientific,Inc.Certificates for calibrationsourceswereexamined andfound tobeacceptable. See MCS-SRS-NDA0203, Revisions3&4,Appendix1and SRS-NDA-0504,Revision0,Appendix 5.List the standards usedfor calibrationandverifythepedigreeofeach standard.YCCP-PO-002,Revision13The calibration standards are listed andthe pedigreeof eachhasbeenverified.YModelENV4057241Am/152Eu mixedgammaline sourceswereused, allofwhichwereNIST traceable asRevisionNo.:1NDA-IQ3-7DateofRevision:11/01/05ATTACHMENT A.6:NONDESTRUCTIVE ASSAY (NDA) CHECKLIST—IQ3EPA Inspection No.: EPA-SRS-10.05-8Inspection Date: 10/31/2005–11/03/2005Required Technical ElementsY/NLocationVerificationofActivityY/NObjective Evidenceindicated on the certificationsheets inMCS-SRS-NDA-0203, Revision 3,Appendix 1 whichalsoprovidesthe241Amand152Euactivity for eachsource andNDA-0504, Revision0,Appendix 5.Calibration Verification&ConfirmationVerification ofan NDAinstrument’scalibration must beperformedafter any ofthe followingoccurrences: major systemrepairs and/ormodifications, replacementofthe system’s components, significantchangestothesystem’s software, andrelocationofthe system.YCCP-PO-002,Revision13;CCP-TP-048, Revision7Verificationsof the IQ3’s calibrationhavebeenrequired,performed anddocumented asrequired.YTherewerefour(4) calibrationverificationsrequiredonthe followingdates:1-31-05followingreplacementofLEGeNo.6; 6-30-05 inresponseto3backgroundfailures; 8-26-05followinga softwareupgrade;and10-18-05 followingaproblemwithdetectorNo.1.Allpassed theacceptancecriterion and recalibrationwas notrequired.Allweredocumented inletter reports,copiesofwhichwereprovidedforeachinstance.Recalibration of the systemmustoccur if thecalibration verificationdemonstrates that thesystem’s responsehas significantly changed.NACCP-PO-002,Revision13;CCP-TP-048, Revision7Recalibration of the systemhas notbeen required inthe timeperiodrelevanttothis inspection.NARecalibrationwas notrequired foranyofthefour (4)calibration verificationsthatwereperformed.RevisionNo.:1NDA-IQ3-8DateofRevision:11/01/05ATTACHMENT A.6:NONDESTRUCTIVE ASSAY (NDA) CHECKLIST—IQ3EPA Inspection No.: EPA-SRS-10.05-8Inspection Date: 10/31/2005–11/03/2005Required Technical ElementsY/NLocationVerificationofActivityY/NObjective EvidenceThe systemcalibration must be confirmed byperforming replicatemeasurements of anoninterferingmatrix.YCCP-PO-002,Revision13TheIQ3’scalibrationwasconfirmed byperforming replicatemeasurements of anon-interfering matrix, asrequired.YTheApril 2003calibration wasconfirmed using combinationsofPDPtype sources to producegramloadingsof1.04, 3.35and 9.94grams239Pu inthe PDP combustible matrixdrum003.The January2005calibration wasconfirmed using thesametype of239Pustandards combinedtoyielda nominalvalueof24ginPDPCombustibles/Plastic Drum031.Extendedrange confirmationwasperformedinMarch 2005using 1 gand 4.8 g of238Pu and48gand144g239Pu. Calibrationconfirmationwasalsoperformed inSeptember2005followingthedensity extensionusing(nominal) 10gand24g239Pustandards.Allare documentedinMCS-SRS-NDA-0203, Revisions3 &4and SRS-NDA-0504, Revision0.Replicatemeasurements must beperformedwithcontainersofthesamenominalsize andaccording tothe sameproceduresused foractual waste assays.YCCP-PO-002,Revision13Replicatemeasurementshavebeenperformed withcontainersofthe samenominal size and according tothesameprocedures asthoseused for actualwaste assayson theIQ3.YAll confirmationswereperform-edusing55-gal(208l)drums withthesource/matrixcombinationsdescribedabove.All aredocumented in MCSSRS-NDA-0203,Revisions 3and4and SRS-NDA-0504,Revision0.Replicatemeasurements must beperformedusingnationallyrecognized standardsorstandards derived fromnationallyrecognizedstandards thatspantherangeofuseoftheinstrumentwithrespecttodisintegration rateand/ormatrixeffects. Identify all standardsthatwere used andindicate their application(verification or confirmation).YCCP-PO-002,Revision13Replicatemeasurementshavebeenperformed usingnationallyrecognizedstandards or standards derived fromnationallyrecognized standards thatspantherangeofuseofthe instrumentwithrespecttodisintegrationrateand/or matrix effects. All standards thatwereusedhavebeenidentified andtheir applicationdocumented.YAllstandards used for replicateanalyses werePDP-type Pustandardswith theappropriatepedigree. Eachconfirmation performed adequatelyspanned the rangeofusewithrespecttodisintegrationrate (mass) andmatrix.All are documentedinMCSSRS-NDA-0203,Revisions 3and4and SRS-NDA-0504,Revision0.RevisionNo.:1NDA-IQ3-9DateofRevision:11/01/05ATTACHMENT A.6:NONDESTRUCTIVE ASSAY (NDA) CHECKLIST—IQ3EPA Inspection No.: EPA-SRS-10.05-8Inspection Date: 10/31/2005–11/03/2005Required Technical ElementsY/NLocationVerificationofActivityY/NObjective EvidenceIdentify thenationally accreditedmeasurement program.List the standardsusedforverification/confirmation andverifythe pedigreeof eachstandard.YCCP-PO-002,Revision13Thenationally accredited measurementprogramhasbeenidentifiedand thepedigreeof theeachof standardsusedfor verification/confirmationhas beenverified.YPlutoniumstandardswere fabricated atLANL undera nationallyaccreditedprogram.SeeMCS-SRS-NDA-0203,Revisions3 and4, and SRS-NDA0504, Revision 0.The standardsusedfor calibrationconfirmationmustbe differentfromthesourcesthatwereused for the system’scalibration ofrecord.YCCP-PO-002,Revision13The standardsusedfor calibrationconfirmation arenotthe samesourcesas thoseusedfor theIQ3’s calibrationofrecord.YThe standardsusedfor confirmationweredistinctfromthose usedforinitial calibration. See MCS-SRSNDA-0203, Revisions3and 4 andSRS-NDA-0504,Revision0.Requirements for accuracy, expressed as %R,and precision,expressed as%RSD, must bemet as specifiedin DOE/WIPP-02-3122,Appendix A, TableA-3.2for precisionand"30% for accuracy.YCCP-PO-002,Revision13;CCP-TP-048, Revision7Requirements for accuracy andprecisionhavebeen met as specified inDOE/WIPP-02-3122, AppendixA,Table A-3.2 for precisionand"30% foraccuracy.YAccuracyand precision goalsweremet for all calibrationconfirmations.See MCS-SRS-NDA-0203, Revisions3and 4, and SRS-NDA-0504,Revision0.QualityControlAllradioassaydatareviewandvalidationmustbe performed byappropriatelytrainedand qualified personnel.YCCP-PO-002,Revision13;CCP-QP-002AllIQ3datareview andvalidationhavebeenperformed byappropriatelytrainedandqualified personnel.YA list of all qualifiedindividuals wasprovided. SeeSRS–List ofQualifiedIndividuals,10/31/2005.Identify thename, title andfunction of allpersonnelperforming NDA datavalidation.YCCP-PO-002,Revision13;CCP-QP-002The name,titleandfunctionofallpersonnelperformingIQ3 datavalidation aredocumented.YA list of all qualifiedindividuals wasprovided. SeeSRS–List ofQualifiedIndividuals,10/31/2005.Requalificationofpersonnelmustbe basedon evidenceofcontinued satisfactoryperformance and must beperformed at leastevery two years.YCCP-PO-002,Revision13;CCP-QP-002Requalification ofpersonnelisbasedon evidenceofcontinued satisfactoryperformance andhasbeenperformed atleast every two years.YTheSRS–ListofQualifiedIndividuals,10/31/2005providedthetrainingstatusofallIQ3personnel.All computerprograms, includingspreadsheets used for datareduction oranalysis, must meet the applicablerequirements inthe CBFO QAPD.NACCP-PO-002,Revision13This activity was not assessed duringthe inspection.NAThis activity was not assessed duringthe inspectionRevisionNo.:1NDA-IQ3-10DateofRevision:11/01/05ATTACHMENT A.6:NONDESTRUCTIVE ASSAY (NDA) CHECKLIST—IQ3EPA Inspection No.: EPA-SRS-10.05-8Inspection Date: 10/31/2005–11/03/2005Required Technical ElementsY/NLocationVerificationofActivityY/NObjective EvidenceThe site must participate inrelevantmeasurement comparison programssponsoredorapprovedbyCBFO,includingthe NDAPDP.YCCP-PO-002,Revision13The sitehasparticipated successfullyinthe CBFOsponsoredNDAPDP.YThe IQ3 participatedsuccessfullyinNDAPDP Cycle 12Abyassaying acombustiblematrixwithheat sourcePu (238Pu) anda glass matrixwithWGPu (239Pu).SeeScoring Results–Cycle 12 A Nondestructive Assay PDP,July 8,2005,Michael Brownto KerryWatson.Backgroundand Performance ChecksAssay systembackground measurementsmustbe takendaily, unlessotherwiseapprovedbyCBFO.Determine theformofCBFO approvaldocumentationofthealternate approach to backgrounds, ifapplicable. Contributionsto backgroundsfromnearbyradiationsourcesmustbecarefullycontrolled,ormorefrequentbackgroundsmustbe measured.YCCP-PO-002,Revision13;CCP-TP-047, Revision6Daily background measurementshavebeen taken and recorded overtheappropriate periodsofperformance.Contributionstobackgroundfromnearby radiation sourcesare controlled.YBackground measurements are takendaily at thebeginningof the countingsession,seeCCP-TP-047, Section 4.3.Backgrounds are takenwithout adruminthe counting chamberand last 300seconds.TheBDRsreviewedduringthe inspectiondocument adequatebackground performance.Assesshowoftenbackgroundradiationwasproblematic tothe extentthatmeasurementpersonnelhad tomake adjustments.YCCP-PO-002,Revision13;CCP-TP-047, Revision6Background records that documenttheIQ3’sperformanceover timearemaintained by CCPmeasurementpersonnel.YA calibrationverificationwasrequiredon6-30-05 inresponseto3successivebackground failures.DiscussionswithCCPNDApersonneland evaluationofNDABRDs did notindicatesignificantbackgroundproblems.Identify thecriteria usedto evaluateinstrument backgrounds and assess thetechnical adequacy of this criterion, i.e.,statistical oradministrative.YCCP-PO-002,Revision13;CCP-TP-047, Revision6;CCP-TP-048, Revision7Backgrounds for theIQ3have beenevaluated against a technicallyappropriate acceptancecriterion, andthe nature andresultsoftheseevaluations have beendocumented.YDaily backgroundsare evaluatedrelative toanadministrativelyderived,i.e.,nonstatistical, control limit withflagsforvaluesabove (Ab)orbelow(Be) the limit.RevisionNo.:1NDA-IQ3-11DateofRevision:11/01/05ATTACHMENT A.6:NONDESTRUCTIVE ASSAY (NDA) CHECKLIST—IQ3EPA Inspection No.: EPA-SRS-10.05-8Inspection Date: 10/31/2005–11/03/2005Required Technical ElementsY/NLocationVerificationofActivityY/NObjective EvidenceIdentifythe numberofdata points requiredtoderivethe initial control limit.At whatinterval(s)will new limits becalculated?YCCP-PO-002,Revision13Thenumber ofdatapoints requiredtoderivethe initial control limitandtheinterval(s) atwhichwill new limits becalculated aredocumented.YReview ofthe IQ3datalimitsisperformed everythree months.Routine limit reviews are typicallyperformed duringFebruary,May,August and November. Reportsdocumenting threeofthese reviewswereprovidedand examined:ReviewandRevisionofSRS IQ3QCLimits–2/15/2005,5/3/2005&10/4/2005.Thesereports contained the technicalbasisfor thederivationof eachQClimit.Systemperformance checksmustbeperformed atleastonceperoperationalday.YCCP-PO-002,Revision13;CCP-TP-047, Revision6Performance checkshavebeenperformed atleastonceperoperationaldayand have been documented.YThe BDRs examined documented theexecution of dailysystemperformancechecks.Systemperformance checksmustinclude, asapplicable, efficiency, matrixcorrectionchecks, and systems peakposition andresolution for spectrometric systems.YCCP-PO-002,Revision13;CCP-TP-047, Revision6Performance checks for the IQ3 includepeakcentroid at81&353keV,peakFWHMat81&356keV,and137CsefficiencyYThe BDRs examined documented theexecution of dailysystemperformancechecks asrequired.Ata minimumofonceperoperationalweekaninterferingmatrixmust beassayedtoassess the longtermstability oftheNDAinstrumentand its matrixcorrections.Howisthisperformancedocumented?YCCP-PO-002,Revision13;CCP-TP-047, Revision6An interferingmatrixis usedtoassessthe longtermstability oftheIQ3 anditsmatrixcorrectionsat leastonce peroperational week.This activity isreviewed anddocumented at therequiredintervals.YThe BDRs examined documented theexecutionof weeklyinterferingmatrixchecks.See theSummary ReportforWeekly Interfering MatrixStandardsfor the MCS IQ3 attheSavannahRiver Siteforperiods 8-16-04 to2-15-05(MCS-SRS-NDA-0305)and2-16-05to8-15-05(MCS-SRS-NDA-0905).Interfering surrogatewaste matrices must beconstructedina way that thesalientmatrixcharacteristics do not changeover time.YCCP-PO-002,Revision13Interferingsurrogatewaste matriceshavebeenconstructedsuchthatthesalientmatrixcharacteristics donotchange overtime.YSurrogatewaste matrix drums are theequivalentofPDP matrixdrums andare sufficiently stable for thisapplication.RevisionNo.:1NDA-IQ3-12DateofRevision:11/01/05ATTACHMENT A.6:NONDESTRUCTIVE ASSAY (NDA) CHECKLIST—IQ3EPA Inspection No.: EPA-SRS-10.05-8Inspection Date: 10/31/2005–11/03/2005Required Technical ElementsY/NLocationVerificationofActivityY/NObjective EvidenceTheradionuclide sourcesusedforperformance checks mustbelong-livedandofsufficient strength(activity)toprovidestatistically sufficientresultsover a shortmeasurement time.YCCP-PO-002,Revision13Theradionuclide sourcesusedforperformance checks are long-livedandare ofsufficientstrength(activity)toprovide statistically sufficientresultsover ashort measurement time.YRadionuclidesources usedforperformance checks consistofcommercially availablegammastandards andcustommade PuO2standards; both are acceptable.Radioactive sourcesaredecaycorrected as afunctionoftheir physical half life, asappropriate, specifically133Ba,252Cf,137Cs,75Se and109Cd.YCCP-PO-002,Revision13Documentation existstoindicate thatradioactive sourcesare decay correctedas a function of their physical half life,as appropriate,or that limits areadjustedto compensate fordecliningsource strength.YThe133Ba transmissionsource is notdecay correctedwhichrequires that thelimits beadjustedin a time framecompatible withthe source’sphysicalhalf life. The137Cs source isdecaycorrected. SeeReview and RevisionofSRSIQ3QCLimits –2/15/2005,5/3/2005&10/4/2005.Performance checks must bequantitative andbasedon2and3 sigma limits.YCCP-PO-002,Revision13Performance checks are quantitativeand based on2 and3sigma limits forall statisticalparameters. Nonstatistical parameters are establishedbyderived limits.YDerivation of control limits isdocumented inReview and RevisionofSRSIQ3QCLimits –2/15/2005,5/3/2005&10/4/2005.Identify howmanydata points are used forthe initial evaluation andatwhat interval(s)new limits are calculated.YCCP-PO-002,Revision13The numberofdatapoints used fortheinitial evaluation andatwhatinterval(s)new limits are calculated aredocumented asrequired.YAt least sixdatapoints areusedtoestablishinitial limits, IQ3performance data limits are reviewedevery three monthsand changes aremade as required.SeeReviewandRevision ofSRS IQ3 QCLimits–2/15/2005,5/3/2005&10/4/2005.DataManagementAllradioassaydatamustbereviewedandapproved byqualified personnelbefore beingreportedtoWWIS.YCCP-PO-002,Revision13;CCP-TP-048, Revision7Allradioassaydatahavebeenreviewedand approvedbyqualified personnelbeforebeingreportedtoWWIS.YThefollowingIQ3 BDRs thatwerereviewed documented review andapprovalofradioassaydata:SRNDA683,SRNDA917,SRNDA918, SRNDA715,SRNDA731, SRNDA788andSRNDA852.RevisionNo.:1NDA-IQ3-13DateofRevision:11/01/05ATTACHMENT A.6:NONDESTRUCTIVE ASSAY (NDA) CHECKLIST—IQ3EPA Inspection No.: EPA-SRS-10.05-8Inspection Date: 10/31/2005–11/03/2005Required Technical ElementsY/NLocationVerificationofActivityY/NObjective EvidenceIdentify thename, title andfunction of theindividual(s)performing technicalreviewand approvalofNDABRDs.YCCP-PO-002,Revision13;CCP-TP-048, Revision7The name,titleandfunctionoftheindividual(s)performing technicalreviewandapproval ofNDA BRDsaredocumented.YTheIQ3 BDRsthat werereviewedcontainedthename, title andfunctionofpersonnelperforming thesefunctions.SeeIQ3 BDRNos.SRNDA683, SRNDA715,SRNDA731,SRNDA917,SRNDA918, SRNDA788, andSRNDA852.RadioassayBDRsmustconsistof thefollowingelements:•Testingfacilityname, testingbatchnumber, container numbers, and signatureof theSite Project Officer(SPO)ordesignee(s)•Table ofContents•Background andperformance check dataorcontrol charts for the relevanttimeperiod.•Data validation per the QAPD andsiteprocedures•Separatetesting report sheets foreachcontainer.YCCP-PO-002,Revision13;CCP-TP-048, Revision7RadioassayBRDs consistedofthefollowing elements, at aminimum:•Testingfacilityname, testingbatchnumber,containernumbers, andsignatureof the Site ProjectOfficer(SPO) ordesignee(s)•Table ofContents•Background andperformance checkdata or controlchartsfor therelevanttimeperiod.•Data validation per the QAPD andsite procedures•A separate testingreport sheet foreach container.YThefollowingIQ3 BDRs thatwerereviewed documented thepresenceofall requiredelements: SRNDA683,SRNDA715, SRNDA917, RNDA918,SRNDA731, SRNDA788, andSRNDA852.Radioassaydatasheets must include:•Title “Radioassay Data Sheet”•Method/procedure used•Dateofradioassay•ActivitiesandassociatedTMUforindividualradionuclides•TRU alpha concentration anditsassociated TMU•Operatorsignature•Reviewer signatureYCCP-PO-002,Revision13Radioassaydatasheets include:•Title “Radioassay Data Sheet”•Method/procedure used•Dateofradioassay•ActivitiesandassociatedTMUforindividualradionuclides•TRU alpha concentration anditsassociated TMU•Operatorsignature•Reviewer signatureYThe followingindividualradioasaydata sheets fromthree (3)of the BDRslisted abovewere evaluated:BDRSRNDA683: HBL03104,SR608409, SR608404, SR608415, andSR608410BDRSRNDA917:MDL0506073,MDL0506135 andMDL0506146BDR SRNDA918:MDL0506095andMDL0506241RevisionNo.:1NDA-IQ3-14DateofRevision:11/01/05ATTACHMENT A.6:NONDESTRUCTIVE ASSAY (NDA) CHECKLIST—IQ3EPA Inspection No.: EPA-SRS-10.05-8Inspection Date: 10/31/2005–11/03/2005Required Technical ElementsY/NLocationVerificationofActivityY/NObjective EvidenceThe followingnonpermanentrecords must bemaintainedat theradioassay-testingfacilityorforwarded tothesiteprojectoffice:•Testing batchreports•All rawdata, includinginstrumentreadouts, calculation records,andradioassay QC results•All applicableinstrumentcalibrationreportsYCCP-PO-002,Revision13;CCP-QP-008The followingnonpermanent recordsare maintained at theradioassay-testingfacility orforwardedtothe site projectoffice:•Testing batchreports•All rawdata, includinginstrumentreadouts, calculation records,andradioassay QC results•All applicableinstrumentcalibrationreportsYIQ3 records were observedinelectronicform in theIQ3 trailer.Formal recordsare storedat CCPoffices offsite inCarlsbad, NM.RevisionNo.:1NDA-IQ3-15DateofRevision:11/01/05ATTACHMENT A.7:WIPP WASTE INFORMATION SYSTEM (WWIS) CHECKLISTEPA Inspection No.: EPA-SRS-10.05-8Inspection Date: 10/31/2005–11/03/2005Establishment of RequiredTechnical Elements in ProceduresY/NLocationExecution of ProceduresY/NObjective Evidence/CommentWWIS-1:WWIS and DataEntryPersonnelmustbe trained toassessdata andproperly enterdata intotheWWIS.CCP-QP-002,R. 17CCP-TP-030,R.16WCO andDataEntryPersonnel aretrainedtoassessdata and properly enterand transferalldata intheWWIS.TrainingforDataEntryPersonnelanddatareviewers/verifiers include theWIPPWasteInformation SystemUser’sManualand theapplicable site procedures.Trainingrecords are available forreview and arecomplete.YTrainingfor dataentrypersonnel(nowWCA,waste certification assistant) includes theWIPPWaste Information SystemUser’sManual and theapplicablesiteprocedures.WCO/WCAsarebasedin Carlsbad,NM andonly aWCO wasavailable atSRSto demonstratethe WWISprocesses used.All CCP data entry intoWWIS takesplace inCarlsbad.The trainingrecords contained in thepersonnelQualification Cardsfor aWCO and aWCAwere reviewed duringthe on-siteinspection.The trainingwas complete and appropriate forthese positions.TheWCOand/orWCAbuilda filethatcontains allcharacterizationdata for each container tobeenteredintoWWIS.TheWCO is able to accessBatchData Report (BDR) informationfor eachcontainerfromthe PTS(Project Office TrackingSystem) and uses this administrative systemtoidentify characterization/certificationdata.Objective evidence reviewed:QualificationCardfor WCOQualificationCardsfor WasteCertificationAssistant (WCA)WWIS-2:Security measuresforensuringdata integrity and accessingWWISaresufficient.CCP-TP-030,R.16, s.4.1Access toWWIS is controlled.WWIS accessrequests arerecordedin an access log,howevernamed, that isavailable for review.YTheWWISData Administrator controls access toWWIS. CCP requests accessforpersonnel and theapproval andpasswordis transmittedtoCCP via email. TheWWIS Data Administrator inCarlsbad,New Mexico,maintainsWWIS access log.Objective evidence reviewed:E-mail, dated 7/27/05, grantingWWIS access toWCARevisionNo.:1WWIS-1DateofRevision:11/01/05ATTACHMENT A.7:WIPP WASTE INFORMATION SYSTEM (WWIS) CHECKLISTEPA Inspection No.: EPA-SRS-10.05-8Inspection Date: 10/31/2005–11/03/2005Establishment of RequiredTechnical Elements in ProceduresY/NLocationExecution of ProceduresY/NObjective Evidence/CommentWWIS-3:There areadequateprocedures for enteringdataintotheWWIS andtransmittingdatatoWIPP.CCP-TP-030,R.16, s.4.0Employee’sexplanation ofjob duties wasconsistentwith applicable procedures. WWISandDataEntryPersonneladequatelyexplainedhowdata areassessed, input, and transferred intoWWIS.YData entry forall CCP sites takesplace in Carlsbad,NM.For thepurposeofdemonstration,aWCOwaspresent atSRS for this inspection.TheWWISData Entry Summary –CharacterizationandCertification,whichis anExcel spreadsheet, isusedtoentercharacterization/certificationdata. Aftercompletion, the spreadsheet isprinted andreviewed. Bysigningthissummary, theWCOaccepts thedataforsubmission toWWIS.Afterthe spreadsheetdatahave beenapproved bytheWCO, ASCII, tab-delimitedtextfiles aregenerated andthen submittedtoWWIS.The Excel spreadsheet is controlled by softwareQA.All NCRs must beclosed prior to data entry.DeanMooneyverifies NCR closure and informs theWCO of containers that are eligiblefordata entryintoWWIS.After acceptance byWWIS,container informationcan beaccessed bythe WasteContainer DataReport.Objectiveevidencereviewed:WWIS Data Entry Summary–Characterization andCertificationfor container MDL0506073Waste ContainerDataReport forcontainerSR544742E-mail, dated9/1/05,fromDean MooneywithregardtoNCR/CARdispositionsforcontainer lot537List of containers and associated NCRsRevisionNo.:1WWIS-2DateofRevision:11/01/05ATTACHMENT A.7:WIPP WASTE INFORMATION SYSTEM (WWIS) CHECKLISTEPA Inspection No.: EPA-SRS-10.05-8Inspection Date: 10/31/2005–11/03/2005Establishment of RequiredTechnical Elements in ProceduresY/NLocationExecution of ProceduresY/NObjective Evidence/CommentWWIS-4:Proceduresrequirethat onlyverifiedand validated data areenteredintoWWIS.CCP-TP-030,R.16, Table1Datageneration andprojectlevelreviewsofcontainer datafor WWISentryhavebeenperformed andreviewchecklists are complete.YWhenall reviews have beencompleted,the SiteProject Manager(SPM) notifies theWCO/WCAsthat a lot evaluationis complete byissuing aCIS(containerinformation summary).Theadministrative controlsusedby CCP ensurethatonlycontainersthathavebeenthroughbothlevelsofreview are available forWWISsubmission.As part ofthis inspection,the EPAinspectorreviewed RTRand VE BDRsall ofwhichcontainedcomplete review checklists.Objective evidence reviewed:Inter-office memorandum, Transmittal ofCharacterization Information SummaryforLot37SW026-772F-HET Waste Stream,dated9/2/05(CIS)WWIS-5:Procedures includeinstructionsfor submissionofdata intothe Characterization and theCertificationmodule ofWWIS.CCP-TP-030,R.16, s.4.3 &4.4To enableWaste StreamProfile FormapprovalData are enteredintothe CharacterizationmoduleofWWIS ona container basis.Toobtainshippingcertification of a containerdata are enteredintothe Certificationmodule ofWWIS.YCharacterizationdata areentered intotheCharacterization ModuleofWWIS sothat aWasteStreamProfileFormcanbe approved. Because thedata fieldsin the Characterization Module are asubset of those inthe CertificationModule,characterizationdata can be electronicallytransferred into the Certification Module.Spotchecksof electronically entereddata areperformedbut100%of manuallyentereddataare checkedforaccuracy. Thechecksuse thepaper copy ofBDRsand theWCO/WCA makes manual correctionstothe data.Anychangesmade are recordedintheBDR.AnExcel spreadsheet,WWISData EntrySummary–Characterization andCertification,is usedtoensure that alldata areentered and arecorrect priortouploadingtoWWIS.Thisspreadsheet containsmanyofthe samedatachecksasWWIS.BeforeWWIS submission theWCOmust accept the dataRevisionNo.:1WWIS-3DateofRevision:11/01/05ATTACHMENT A.7:WIPP WASTE INFORMATION SYSTEM (WWIS) CHECKLISTEPA Inspection No.: EPA-SRS-10.05-8Inspection Date: 10/31/2005–11/03/2005Establishment of RequiredTechnical Elements in ProceduresY/NLocationExecution of ProceduresY/NObjective Evidence/Commentby signing theExcel spreadsheet.Objective evidence reviewed:WWIS Data Entry Summary–Characterization andCertificationfor container MDL0506073Waste ContainerDataReport forcontainerSR544742WWIS-6:Procedures include arequirement for reviewofdatapriortosubmission toWWIS.CCP-TP-030,R.16, s.4.8-4.12ThereisanindependentreviewofdatapriortosubmissiontoWIPP viatheWWIS.Proceduresforresolution/correctionofnonconformingdataare adequately implemented.YCharacterizationdata areentered intotheCharacterization ModuleofWWIS sothat aWasteStreamProfileFormcanbe approved. Because thedata fieldsin the Characterization Module are asubset of those inthe CertificationModule,characterizationdata can be electronicallytransferred into the Certification Module.Spotchecksof electronically entereddata areperformedbut100%of manuallyentereddataare checkedforaccuracy. Thechecksuse thepaper copy ofBDRsand theWCO/WCA makes manual correctionstothe data.AnychangesmadearerecordedontheBDRs.TheWCO accepts dataforWWISsubmissionbysigningthe Excelspreadsheet.WWIS contains checks that donot allow incorrectorunusable datatobe uploaded.IfdataarerejectedbyWWIS,ane-mailissenttoCCPinformingtheWCO/WCA that the data arerejected. CCP issues anNCRfor therejected data,corrects it, and resubmits toWWIS.Objective evidence reviewed:E-mail, dated 12/6/04,fromWWIS returning datafor containerSR513189topre-submittalstatus.NCRsNCR-SRS-0508-05for containers772F020030 and SR556890RevisionNo.:1WWIS-4DateofRevision:11/01/05ATTACHMENT A.7:WIPP WASTE INFORMATION SYSTEM (WWIS) CHECKLISTEPA Inspection No.: EPA-SRS-10.05-8Inspection Date: 10/31/2005–11/03/2005Establishment of RequiredTechnical Elements in ProceduresY/NLocationExecution of ProceduresY/NObjective Evidence/CommentWWIS-7:There areadequateprocedures for enteringdataintotheWWIS andtransmittingthedata toWIPP.CCP-TP-030,R.16, s.4.0The sitehas successfully submittedcharacterization and certificationdata toWIPPvia WWIS.YCCP at SRShas successfully submittedcharacterization and certificationdatafor manycontainerstoWIPP via WWIS.The WCOwasable toaccess tomultiple certifiedcontainers todemonstrate CCP’sprocesses.Objective evidence reviewed:WWIS Data Entry Summary–Characterization andCertificationfor container MDL0506073Waste ContainerDataReport forcontainerSR544742WWIS Data Entry Summary–Characterization andCertificationfor container SR544742Filefor containerMDL5056095,SRSLot1,withanalytical BDRsWWIS-8:Procedures provideinstructionsfor data correctionif dataarerejectedby WWIS.CCP-TP-030,R.16, s.4.4.12CCP-QP-005,R. 10e-mail notificationsfromWWIS(acceptance/modification/rejection ofdata)Ifdata are rejected by theWWIS DataAdministrator,processesfordatareconciliation/correction are implementedYWWIS contains checks that donot allow incorrectorunusable datatobe uploaded.IfdataarerejectedbyWWIS,ane-mailissenttoCCPinformingtheWCO/WCA that the data arerejected.CCPissues anNCRfor therejected data,corrects it andresubmits toWWIS.Objective evidence reviewed:E-mail, dated 12/6/04,fromWWIS returning datafor containerSR513189topre-submittalstatus.NCRsNCR-SRS-0508-05for containers772F020030 and SR556890WWIS-9:Procedures for wastecontainer characterization/certificationdata submittal toWWISrequire theappropriate records toberetained.CCP-TP030,R.16,s.5.1.1WWIS data approval/rejectionreportsWWISDataSpreadsheetsWaste containerdatareportsWWIS accessrequestsYTheWCOdemonstratingCCP’sWWISprocesseswas able to retrieveall records requestedbyEPA.Objective evidence reviewed:E-mail, dated 12/6/04,fromWWIS returning datafor containerSR513189topre-submittalstatusRevisionNo.:1WWIS-5DateofRevision:11/01/05ATTACHMENT A.7:WIPP WASTE INFORMATION SYSTEM (WWIS) CHECKLISTEPA Inspection No.: EPA-SRS-10.05-8Inspection Date: 10/31/2005–11/03/2005Establishment of RequiredTechnical Elements in ProceduresY/NLocationExecution of ProceduresY/NObjective Evidence/CommentWWIS Data Entry Summary–Characterization andCertificationfor container MDL0506073Waste ContainerDataReport forcontainerSR544742WWIS Data Entry Summary–Characterization andCertificationfor container SR544742E-mail, dated 7/27/05, grantingWWIS access toWCAWWIS-10CCP-TP-030,R.16, s.4.7-4.13CCP-TP-086,R. 8CCP-PO-002,R.13,Attachment8Plansand procedures for payloadmanagementhavebeenapprovedbyCBFO.CBFO informedEPAprior toapprovingthesitetopayload managecontainers.TRU alpha activity concentrationis >100nCi/gfor theentirewaste stream.Onlywaste containersfromthe samewastestreamare payloadmanaged inthesamepayloadcontainer.Each wastecontainerselected for payloadmanagement contains at leastone TRU isotope.TRU alpha activity concentrationof thepayloadcontainer isdetermined and reported.YThe Certification Plan (Attachment8)andprocedure CCP-TP-030contain thesamerequirementsforpayload managementas thosefoundinAppendix EoftheCH-WAC. CCP-TP030 and CCP-TP-086,containingCCP’spayloadmanagement practices andprocedures, areapproved procedures.The proceduresand practices,usedfor payloadmanagement, at SRS arethesameas thoseused atother approvedCCPsites.At the time ofthe inspection,SRS-CCPwasapprovedtopayloadmanage debriswaste only.CBFOwill notify EPA whenCBFO approvessoils/gravelwastetobe payloadmanaged.TheSiteProjectManager(SPM) assessesdrumsfor loadmanagement, ensuring that all candidatedrums are fromthe samewaste stream. Aspartofthe demonstration,theWCOattemptedtoenter adrumfroma differentwaste streaminto thedemonstrationpayload butwas not allowed todoso by WWIS.The AKtrackingsheetisusedtoverifythateachdrumhas beenassigned toawastestream.Forthepurpose ofdemonstration, theWCOusedthe datafromSRS (site C1)drums, entered intotheRevisionNo.:1WWIS-6DateofRevision:11/01/05ATTACHMENT A.7:WIPP WASTE INFORMATION SYSTEM (WWIS) CHECKLISTEPA Inspection No.: EPA-SRS-10.05-8Inspection Date: 10/31/2005–11/03/2005Establishment of RequiredTechnical Elements in ProceduresY/NLocationExecution of ProceduresY/NObjective Evidence/CommentWWIStest module,toshowhowWWISrecalculates averageTRU activity as newdrums areaddedtothepayload. WWIS alsorecalculatesother criteria that must be met for shipping(CHTRAMPACrequirements). The internalchecks inWWISdoesnotallowfor containersfromdifferentwaste streams tobeputinthesamepayload.Theweightusedto calculate the alpha activity ofthe drums inthe payload includes thedrums, wasteand liners. CCP usesonly approved TCOPs orSWBsaspayload containers.The TransportationCertificationOfficial (TCO)will use theWWIStransportationmodule toensure thatthepayloadsassembled areWIPP compliant, asdemonstrated bytheWCO. Containersarenot available to the TCOfor shipmentuntil they havebeen certifiedbyWWIS.WWISchecksthateachdrum, forpayloadmanagement, contains at leastone isotope >LLD toqualifyasTRUwaste.Thewaste containerreport for containerSRTP01413lists all ofthedrums withinthatpayload(tendrumoverpack).Objective evidence reviewed:Waste ContainerReport for containerSRTP01413,ten-drumoverpack.RevisionNo.:1WWIS-7DateofRevision:11/01/05

# ATTACH MENT A.8: WIPP WASTE INFO RMATION SYSTEM (WWIS)

DAT A RE QUIREME N TS

EPA Inspec tion No.: EPA-SRS-10.05-8 Inspection Date: 10/31/2005–11/03/2005

WWIS Data Requirements

Characterization Module Data Fields

(not a comp lete lis t)

Container ID - present 239 

# Pu eq u i v a len t activ ity - p r esen t

Gene rato r E P A ID

– p r ese n t 239 

# Pu fi ssi l e gr am equi val e nt - prese n t

Site ID - presen t 239 

# Pu FG E un cer t ain t y - p r esen t

Waste Stream Profile Num b er - pr esen t Rad i on u c lid e na m e - presen t

Waste Matrix Co d e - presen t Rad i on u c lid e activ ity - p r esent

Wast e M a t r i x C ode G r o u p - prese n t R a di on u c lid e activ ity u n certai n ty - p r esen t

Wast e M a t e ri al W e i g ht - prese n t R a di o nucl i d e m a ss - prese n t

Waste Material Param e ter - p r esen t Rad i on u c lid e mass u n c ertainty - presen t

Hazardous Code - prese n t Radioassay m e thod - prese n t

Lay e rs of pac k agi n g - prese n t Assay dat e

- p r esent

Li ner e x i s t s - p r esent C h aract eri zat i o n m e t hod - pre s ent

Filter m odel - prese n t Characterization m e thod date

– prese n t

Num b er of filters installed - presen t A l p h a surface conce n tration - present

TRUCO N c o d e - pre s ent Dose rate

- pre s ent

Decay heat

– present Sam p le ID - present

Decay heat uncertainty - pre s ent Sam p le type - prese n t

TRU alpha acti v ity - pre s ent Sam p le date - prese n t

TRU alpha acti v ity unce r taint y - pre s ent Analyte - prese n t

TRU alpha acti v ity conce n trat ion

- pre s ent Analyte conce n tration - prese n t

TRU alpha acti v ity conce n trat ion uncertainty

-

prese n t Anal y t e det ect i o n m e t hod

- pr esent

Wast e t y pe c o de

- prese n t Anal y t e det ect i o n m e t hod

- pr esent



# Certificatio n Module Data Fields

C ont ai ne r ID - prese n t C ont ai ne r C e rt i f i cat i on dat e

- prese n t

C ont ai ne r Ty p e - pre s ent C ont ai ne r C l os ure dat e - prese n t

C ont ai ne r wei g ht

- p r ese n t Han d l i n g C ode

- pre s ent

C ont act DoseR a t e - prese n t

Revi si on N o .: 1 WWIS

- 8 Da te of Re vi si on: 11/ 0 1 / 0 5

# Attachments B.1 thr ough B.18B-1ATTACHMENT B.1 REPLICATE TESTING IPAN DATA FORCONTAINER SR144771Instrument: IPAN/GEA - SRSContainer: SR144771Original MeasurementReplicate #1Replicate #2Quantity ofReportedAbsoluteRelativeReportedAbsoluteRelativeReportedAbsoluteRelativeInterestValueUncertaintyUncertaintyValueUncertaintyUncertaintyValueUncertaintyUncertainty233U Activity (Ci)6.61E-05#VALUE!NA6.67E-05#VALUE!NA7.07E-06#VALUE!NA234U Activity (Ci)3.51E-05#VALUE!NA3.95E-05#VALUE!NA6.94E-05#VALUE!NA238U Activity (Ci)1.10E-05#VALUE!NA7.31E-06#VALUE!NA4.85E-07#VALUE!NA238Pu Activity (Ci)1.55E-041.10E-047.09E-011.37E-041.17E-048.54E-011.53E-041.23E-048.03E-01239Pu Activity (Ci)1.39E-039.80E-047.07E-011.23E-031.05E-038.53E-011.37E-031.10E-038.02E-01240Pu Activity (Ci)3.16E-042.32E-047.35E-012.81E-042.46E-048.76E-013.13E-042.59E-048.26E-01242Pu Activity (Ci)3.55E-082.51E-087.09E-013.15E-082.69E-088.54E-013.52E-082.82E-088.03E-01241Am Activity (Ci)9.43E-05#VALUE!NA1.34E-042.28E-041.71E+008.90E-057.97E-058.96E-0190Sr Activity (Ci)0.00E+00N/ANA0.00E+00N/ANA0.00E+00N/ANA137Cs Activity (Ci)0.00E+00N/ANA0.00E+00N/ANA0.00E+00N/ANATRU Alpha Conc. (nCi/g)1.12E+028.75E+017.80E-011.03E+029.44E+019.21E-011.11E+028.99E+018.10E-01Replicate #3Replicate #4Replicate #5Quantity ofReportedAbsoluteRelativeReportedAbsoluteRelativeReportedAbsoluteRelativeInterestValueUncertaintyUncertaintyValueUncertaintyUncertaintyValueUncertaintyUncertainty233U Activity (Ci)8.77E-07#VALUE!NA8.43E-05#VALUE!NA5.72E-05#VALUE!NA234U Activity (Ci)3.90E-04#VALUE!NA5.57E-05#VALUE!NA6.16E-05#VALUE!NA238U Activity (Ci)4.13E-08#VALUE!NA9.54E-06#VALUE!NA5.84E-06#VALUE!NA238Pu Activity (Ci)1.60E-041.24E-047.73E-011.66E-041.27E-047.67E-011.68E-041.23E-047.35E-01239Pu Activity (Ci)1.44E-031.11E-037.71E-011.49E-031.14E-037.65E-011.50E-031.10E-037.33E-01240Pu Activity (Ci)3.28E-042.61E-047.97E-013.39E-042.68E-047.91E-013.43E-042.61E-047.60E-01242Pu Activity (Ci)3.68E-082.85E-087.73E-013.80E-082.92E-087.67E-013.85E-082.83E-087.35E-01241Am Activity (Ci)9.32E-058.09E-058.69E-012.02E-043.85E-041.91E+004.06E-045.34E-041.32E+0090Sr Activity (Ci)0.00E+00N/ANA0.00E+00N/ANA0.00E+00N/ANA137Cs Activity (Ci)0.00E+00N/ANA0.00E+00N/ANA0.00E+00N/ANATRU Alpha Conc.(nCi/g)1.16E+029.06E+017.80E-011.26E+021.10E+028.74E-011.39E+021.16E+028.35E-01B-2ATTACHMENT B.2 REPLICATE TESTING IPAN RESULTS FOR CONTAINER SR144771Instrument: IPAN/GEA - SRSContainer: SR144771Original MeasurementQuantity ofReportedAbsoluteInterestValueUncertaintySampleMeanSampleStandardDeviationRelativeStandardDeviationχ2Pr(x<| 

# χ2|)tPr(x<|t|)233U Activity (Ci)6.61E-05#VALUE!4.32E-053.72E-058.61E-01#VALUE!#VALUE!5.62E-016.04E-01234U Activity (Ci)3.51E-05#VALUE!1.23E-041.50E-041.21E+00#VALUE!#VALUE!-5.38E-016.19E-01238U Activity (Ci)1.10E-05#VALUE!4.65E-064.21E-069.07E-01#VALUE!#VALUE!1.37E+002.44E-01238Pu Activity (Ci)1.55E-041.10E-041.57E-041.23E-057.81E-025.01E-021.00E+00-1.75E-018.69E-01239Pu Activity (Ci)1.39E-039.80E-041.41E-031.10E-047.81E-025.03E-021.00E+00-1.75E-018.69E-01240Pu Activity (Ci)3.16E-042.32E-043.21E-042.51E-057.81E-024.66E-021.00E+00-1.75E-018.69E-01242Pu Activity (Ci)3.55E-082.51E-083.60E-082.81E-097.81E-025.01E-021.00E+00-1.75E-018.69E-01241Am Activity (Ci)9.43E-05#VALUE!1.85E-041.32E-047.13E-01#VALUE!#VALUE!-6.27E-015.65E-0190Sr Activity (Ci)0.00E+00N/A0.00E+000.00E+00N/A#VALUE!#VALUE!N/AN/A137Cs Activity (Ci)0.00E+00N/A0.00E+000.00E+00N/A#VALUE!#VALUE!N/AN/ATRU Alpha Conc. (nCi/g)1.12E+028.75E+011.19E+021.41E+011.19E-011.04E-019.99E-01-4.40E-016.82E-01Quantity ofInterestχ2TesttTest233U Activity (Ci)#VALUE!Not Significant234U Activity (Ci)#VALUE!Not Significant238U Activity (Ci)#VALUE!Not Significant238Pu Activity (Ci)Not SignificantNot Significant239Pu Activity (Ci)Not SignificantNot Significant240Pu Activity (Ci)Not SignificantNot Significant242Pu Activity (Ci)Not SignificantNot Significant241Am Activity (Ci)#VALUE!Not Significant90Sr Activity (Ci)#VALUE!NotApplicable137Cs Activity (Ci)#VALUE!Not ApplicableTRU Alpha Conc. (nCi/g)#VALUE!Not SignificantB-3ATTACHMENT B.3 REPLICATE TESTING IPAN DATA FORCONTAINER FBL04011Instrument:IPAN/GEA - SRSContainer:FBL04011Original MeasurementReplicate #1Replicate #2Quantity ofReportedAbsoluteRelativeReportedAbsoluteRelativeReportedAbsoluteRelativeInterestValueUncertaintyUncertaintyValueUncertaintyUncertaintyValueUncertaintyUncertainty233U Activity (Ci)1.79E-04#VALUE!NA1.64E-04#VALUE!NA1.73E-04#VALUE!NA234U Activity (Ci)2.13E-051.02E-054.77E-011.82E-058.83E-064.85E-011.19E-056.46E-065.44E-01238U Activity (Ci)4.87E-06#VALUE!NA4.34E-06#VALUE!NA4.32E-06#VALUE!NA238Pu Activity (Ci)1.51E-021.43E-029.52E-018.96E-031.59E-021.77E+009.83E-031.72E-021.75E+00239Pu Activity (Ci)1.74E-017.76E-024.47E-011.68E-017.52E-024.47E-011.69E-017.54E-024.47E-01240Pu Activity (Ci)3.86E-023.46E-028.97E-016.15E-023.13E-025.09E-015.14E-022.65E-025.15E-01242Pu Activity (Ci)1.14E-055.12E-064.50E-011.03E-054.62E-064.50E-011.08E-054.86E-064.50E-01241Am Activity (Ci)4.86E-022.95E-026.06E-014.36E-022.63E-026.03E-014.63E-022.79E-026.03E-0190Sr Activity (Ci)0.00E+00N/ANA0.00E+00N/ANA0.00E+00N/ANA137Cs Activity (Ci)0.00E+00N/ANA0.00E+00N/ANA0.00E+00N/ANATRU Alpha Conc. (nCi/g)5.55E+033.14E+035.65E-015.68E+032.99E+035.27E-015.56E+032.96E+035.32E-01Replicate #3Replicate #4Replicate #5Quantity ofReportedAbsoluteRelativeReportedAbsoluteRelativeReportedAbsoluteRelativeInterestValueUncertaintyUncertaintyValueUncertaintyUncertaintyValueUncertaintyUncertainty233U Activity (Ci)1.78E-04#VALUE!NA1.71E-04#VALUE!NA1.64E-04#VALUE!NA234U Activity (Ci)1.55E-058.10E-065.22E-011.63E-058.33E-065.12E-011.69E-058.47E-065.00E-01238U Activity (Ci)4.38E-06#VALUE!NA4.41E-06#VALUE!NA4.27E-06#VALUE!NA238Pu Activity (Ci)1.25E-025.64E-034.50E-011.18E-025.31E-034.50E-011.18E-021.61E-021.36E+00239Pu Activity (Ci)1.72E-017.71E-024.47E-011.74E-017.77E-024.47E-011.72E-017.70E-024.48E-01240Pu Activity (Ci)5.17E-022.67E-025.16E-015.42E-022.77E-025.11E-016.50E-023.28E-025.05E-01242Pu Activity (Ci)1.14E-055.14E-064.50E-011.09E-054.90E-064.50E-011.22E-055.50E-064.50E-01241Am Activity (Ci)4.89E-022.95E-026.03E-014.68E-022.82E-026.03E-015.18E-023.12E-026.02E-0190Sr Activity (Ci)0.00E+00N/ANA0.00E+00N/ANA0.00E+00N/ANA137Cs Activity (Ci)0.00E+00N/ANA0.00E+00N/ANA0.00E+00N/ANATRU Alpha Conc. (nCi/g)5.75E+032.79E+034.86E-015.77E+032.80E+034.85E-016.05E+033.16E+035.23E-01B-4ATTACHMENT B.4 REPLICATE TESTING IPAN RESULTS FORCONTAINER FBL04011Instrument:IPAN/GEA - SRSContainer:FBL04011Original MeasurementQuantity ofReportedAbsoluteInterestValueUncertaintySampleMeanSampleStandardDeviationRelativeStandardDeviationχ2Pr(x<| 

# χ2|)tPr(x<|t|)233U Activity (Ci)1.79E-04#VALUE!1.70E-045.88E-063.46E-02#VALUE!#VALUE!1.47E+002.15E-01234U Activity (Ci)2.13E-051.02E-051.58E-052.38E-061.51E-012.19E-019.94E-012.14E+009.94E-02238U Activity (Ci)4.87E-06#VALUE!4.34E-065.58E-081.28E-02#VALUE!#VALUE!8.65E+009.83E-04238Pu Activity (Ci)1.51E-021.43E-021.10E-021.51E-031.38E-014.45E-021.00E+002.46E+006.94E-02239Pu Activity (Ci)1.74E-017.76E-021.71E-012.43E-031.42E-023.93E-031.00E+001.04E+003.56E-01240Pu Activity (Ci)3.86E-023.46E-025.68E-026.15E-031.08E-011.27E-019.98E-01-2.70E+005.39E-02242Pu Activity (Ci)1.14E-055.12E-061.11E-057.37E-076.62E-028.28E-029.99E-013.09E-017.73E-01241Am Activity (Ci)4.86E-022.95E-024.75E-023.08E-036.48E-024.36E-021.00E+003.37E-017.53E-0190Sr Activity (Ci)0.00E+00N/A0.00E+000.00E+00N/A#VALUE!#VALUE!N/AN/A137Cs Activity (Ci)0.00E+00N/A0.00E+000.00E+00N/A#VALUE!#VALUE!N/AN/ATRU Alpha Conc. (nCi/g)5.55E+033.14E+035.76E+031.80E+023.13E-021.32E-021.00E+00-1.04E+003.57E-01Quantity ofInterestχ2TesttTest233U Activity (Ci)#VALUE!Not Significant234U Activity (Ci)Not SignificantNot Significant238U Activity (Ci)#VALUE!Highly Significant238Pu Activity (Ci)Not SignificantNot Significant239Pu Activity (Ci)Not SignificantNot Significant240Pu Activity (Ci)Not SignificantNot Significant242Pu Activity (Ci)Not SignificantNot Significant241Am Activity (Ci)Not SignificantNot Significant90Sr Activity (Ci)#VALUE!Not Applicable137Cs Activity (Ci)#VALUE!Not ApplicableTRU Alpha Conc. (nCi/g)Not SignificantNot SignificantB-5ATTACHMENT B.5 REPLICATE TESTING IPAN DATA FORCONTAINER SR138868Instrument:IPAN/GEA - SRSContainer:SR138868Original MeasurementReplicate #1Replicate #2Quantity ofReportedAbsoluteRelativeReportedAbsoluteRelativeReportedAbsoluteRelativeInterestValueUncertaintyUncertaintyValueUncertaintyUncertaintyValueUncertaintyUncertainty233U Activity (Ci)3.16E-04#VALUE!NA1.21E-04#VALUE!NA1.53E-04#VALUE!NA234U Activity (Ci)2.94E-04#VALUE!NA1.67E-04#VALUE!NA1.89E-04#VALUE!NA238U Activity (Ci)5.18E-05#VALUE!NA1.05E-05#VALUE!NA1.24E-05#VALUE!NA238Pu Activity (Ci)1.20E-036.59E-045.49E-011.30E-037.66E-045.90E-011.23E-036.96E-045.64E-01239Pu Activity (Ci)2.87E-021.60E-025.57E-012.68E-021.59E-025.92E-013.07E-021.74E-025.67E-01240Pu Activity (Ci)6.93E-034.04E-035.83E-016.85E-035.18E-037.56E-016.77E-034.04E-035.97E-01242Pu Activity (Ci)1.11E-066.12E-075.49E-011.23E-067.25E-075.90E-011.13E-066.36E-075.64E-01241Am Activity (Ci)2.80E-032.57E-039.18E-016.14E-034.49E-037.32E-011.59E-032.06E-031.30E+0090Sr Activity (Ci)NA#VALUE!NA0.00E+00N/ANA0.00E+00N/ANA137Cs Activity (Ci)2.12E-07#VALUE!NA0.00E+00N/ANA0.00E+00N/ANATRU Alpha Conc. (nCi/g)2.25E+031.32E+035.87E-012.33E+031.49E+036.40E-012.29E+031.38E+036.01E-01Replicate #3Replicate #4Replicate #5Quantity ofReportedAbsoluteRelativeReportedAbsoluteRelativeReportedAbsoluteRelativeInterestValueUncertaintyUncertaintyValueUncertaintyUncertaintyValueUncertaintyUncertainty233U Activity (Ci)1.40E-04#VALUE!NA1.33E-04#VALUE!NA1.37E-04#VALUE!NA234U Activity (Ci)1.81E-04#VALUE!NA2.06E-04#VALUE!NA1.87E-04#VALUE!NA238U Activity (Ci)1.11E-05#VALUE!NA1.09E-05#VALUE!NA1.08E-05#VALUE!NA238Pu Activity (Ci)1.11E-036.60E-045.93E-011.41E-038.10E-045.74E-011.19E-036.95E-045.82E-01239Pu Activity (Ci)2.75E-021.64E-025.96E-012.91E-021.67E-025.75E-012.80E-021.64E-025.85E-01240Pu Activity (Ci)6.27E-033.87E-036.18E-016.47E-035.22E-038.07E-016.96E-034.27E-036.13E-01242Pu Activity (Ci)1.02E-066.05E-075.93E-011.34E-067.67E-075.74E-011.11E-066.49E-075.82E-01241Am Activity (Ci)1.72E-032.03E-031.18E+006.96E-035.03E-037.24E-013.74E-033.00E-038.02E-0190Sr Activity (Ci)0.00E+00N/ANA0.00E+00N/ANA0.00E+00N/ANA137Cs Activity (Ci)0.00E+00N/ANA0.00E+00N/ANA0.00E+00N/ANATRU Alpha Conc. (nCi/g)2.07E+031.30E+036.29E-012.50E+031.58E+036.33E-012.27E+031.38E+036.11E-01B-6ATTACHMENT B.6 REPLICATE TESTING IPAN RESULTS FOR CONTAINER SR138868Instrument:IPAN/GEA - SRSContainer:SR138868Original MeasurementQuantity ofReportedAbsoluteInterestPr(x<| 

# χ2|)ValueUncertaintySampleMeanSampleStandardDeviationRelativeStandardDeviationχ2tPr(x<|t|)233U Activity (Ci)3.16E-04#VALUE!1.37E-041.16E-058.52E-02#VALUE!#VALUE!1.41E+011.49E-04234U Activity (Ci)2.94E-04#VALUE!1.86E-041.43E-057.67E-02#VALUE!#VALUE!6.90E+002.31E-03238U Activity (Ci)5.18E-05#VALUE!1.11E-057.24E-076.50E-02#VALUE!#VALUE!5.12E+018.73E-07238Pu Activity (Ci)1.20E-036.59E-041.25E-031.13E-049.00E-021.17E-019.98E-01-4.02E-017.08E-01239Pu Activity (Ci)2.87E-021.60E-022.84E-021.53E-035.39E-023.67E-021.00E+001.74E-018.70E-01240Pu Activity (Ci)6.93E-034.04E-036.66E-032.86E-044.30E-022.01E-021.00E+008.48E-014.44E-01242Pu Activity (Ci)1.11E-066.12E-071.17E-061.21E-071.04E-011.56E-019.97E-01-3.85E-017.20E-01241Am Activity (Ci)2.80E-032.57E-034.03E-032.47E-036.13E-013.68E+004.50E-01-4.53E-016.74E-0190Sr Activity (Ci)NA#VALUE!0.00E+000.00E+00N/A#VALUE!#VALUE!N/AN/A137Cs Activity (Ci)2.12E-07#VALUE!0.00E+000.00E+00N/A#VALUE!#VALUE!N/AN/ATRU Alpha Conc. (nCi/g)2.25E+031.32E+032.29E+031.51E+026.60E-025.24E-021.00E+00-2.42E-018.21E-01Quantity ofInteresttTestχ2Test233U Activity (Ci)#VALUE!Highly Significant234U Activity (Ci)#VALUE!Highly Significant238U Activity (Ci)#VALUE!Highly Significant238Pu Activity (Ci)Not SignificantNot Significant239Pu Activity (Ci)Not SignificantNot Significant240Pu Activity (Ci)Not SignificantNot Significant242Pu Activity (Ci)Not SignificantNot Significant241Am Activity (Ci)Not SignificantNot Significant90Sr Activity (Ci)#VALUE!NotApplicable137Cs Activity (Ci)#VALUE!Not ApplicableTRU Alpha Conc. (nCi/g)Not SignificantNot SignificantB-7ATTACHMENT B.7 REPLICATE TESTING IQ3 DATA FOR CONTAINER MDL0506073Instrument:SRS IQ3Container:MDL0506073Original MeasurementReplicate #1Replicate #2Quantity ofReportedAbsoluteRelativeReportedAbsoluteRelativeReportedAbsoluteRelativeInterestUValueUncertaintyUncertaintyValueUncertaintyUncertaintyValueUncertaintyncertainty233U Activity (Ci)0.00E+00N/A0.00E+000.00E+00N/A0.00E+000.00E+00N/A0.00E+00234U Activity (Ci)0.00E+00N/A0.00E+000.00E+00N/A0.00E+000.00E+00N/A0.00E+00238U Activity (Ci)0.00E+00N/A0.00E+000.00E+00N/A0.00E+000.00E+00N/A0.00E+00238Pu Activity (Ci)7.92E-024.61E-025.82E-018.62E-024.87E-025.65E-017.24E-024.09E-025.65E-01239Pu Activity (Ci)0.00E+00N/A0.00E+000.00E+00N/A0.00E+000.00E+00N/A0.00E+00240Pu Activity (Ci)0.00E+00N/A0.00E+000.00E+00N/A0.00E+000.00E+00N/A0.00E+00242Pu Activity (Ci)4.55E-082.64E-085.80E-014.94E-082.79E-085.65E-014.16E-082.34E-085.63E-01241Am Activity (Ci)6.23E-053.30E-055.30E-015.98E-053.17E-055.30E-016.30E-053.34E-055.30E-0190Sr Activity (Ci)0.00E+00N/A0.00E+000.00E+00N/A0.00E+000.00E+00N/A0.00E+00137Cs Activity (Ci)0.00E+00N/A0.00E+000.00E+00N/A0.00E+000.00E+00N/A0.00E+00TRU Alpha Conc. (nCi/g)3.11E+021.81E+025.82E-013.38E+021.91E+025.65E-012.84E+021.60E+025.63E-01Replicate #3Replicate #4Replicate #5Quantity ofReportedAbsoluteRelativeReportedAbsoluteRelativeReportedAbsoluteRelativeInterestValueUncertaintyUncertaintyValueUncertaintyUncertaintyValueUncertaintyUncertainty233U Activity (Ci)0.00E+00N/A0.00E+000.00E+00N/A0.00E+000.00E+00N/A0.00E+00234U Activity (Ci)0.00E+00N/A0.00E+000.00E+00N/A0.00E+000.00E+00N/A0.00E+00238U Activity (Ci)0.00E+00N/A0.00E+000.00E+00N/A0.00E+000.00E+00N/A0.00E+00238Pu Activity (Ci)3.67E-021.97E-025.37E-017.70E-024.31E-025.60E-013.80E-022.01E-025.29E-01239Pu Activity (Ci)0.00E+00N/A0.00E+000.00E+00N/A0.00E+000.00E+00N/A0.00E+00240Pu Activity (Ci)0.00E+00N/A0.00E+000.00E+00N/A0.00E+000.00E+00N/A0.00E+00242Pu Activity (Ci)1.152.10E-081.13E-085.38E-014.42E-082.47E-085.59E-012.18E-08E-085.28E-01241Am Activity (Ci)5.88E-053.12E-055.31E-016.12E-053.24E-055.29E-016.00E-053.18E-055.30E-0190Sr Activity (Ci)0.00E+00N/A0.00E+000.00E+00N/A0.00E+000.00E+00N/A0.00E+00137Cs Activity (Ci)0.00E+00N/A0.00E+000.00E+00N/A0.00E+000.00E+00N/A0.00E+00TRU Alpha Conc. (nCi/g)1.44E+027.71E+015.35E-013.02E+021.69E+025.60E-011.49E+027.90E+015.30E-01B-8ATTACHMENT B.8 REPLICATE TESTING IQ3 RESULTS FORCONTAINER MDL0506073Instrument:SRS IQ3Container:MDL0506073Original MeasurementQuantity ofReportedAbsoluteInterestRelativePr(x<|t|)ValueUncertaintySampleMeanSampleStandardDeviationStandardDeviationχ2Pr(x<| 

# χ2|)t233U Activity (Ci)0.00E+00N/A0.00E+000.00E+00N/A#VALUE!#VALUE!N/AN/A234U Activity (Ci)0.00E+00N/A0.00E+000.00E+00N/A#VALUE!#VALUE!N/AN/A238U Activity (Ci)0.00E+00N/A0.00E+000.00E+00N/A#VALUE!#VALUE!N/AN/A238Pu Activity (Ci)7.92E-024.61E-026.21E-022.31E-023.72E-011.00E+009.09E-016.77E-015.35E-01239Pu Activity (Ci)0.00E+00N/A0.00E+000.00E+00N/A#VALUE!#VALUE!N/AN/A240Pu Activity (Ci)0.00E+00N/A0.00E+000.00E+00N/A#VALUE!#VALUE!N/AN/A242Pu Activity (Ci)4.55E-082.64E-083.56E-081.33E-083.73E-011.01E+009.08E-016.81E-015.33E-01241i)Am Activity (C6.23E-053.30E-056.06E-051.61E-062.66E-029.51E-031.00E+009.87E-013.79E-0190Sr Activity (Ci)0.00E+00N/A0.00E+000.00E+00N/A#VALUE!#VALUE!N/AN/A137Cs Activity (Ci)0.00E+00N/A0.00E+000.00E+00N/A#VALUE!#VALUE!N/AN/ATRU Alpha Conc. (nCi/g)3.11E+021.81E+022.43E+029.06E+013.72E-011.00E+009.10E-016.81E-015.33E-01Quantity ofInterestχ2TesttTest233U Activity (Ci)#VALUE!NotApplicable234U Activity (Ci)#VALUE! NotApplicable238U Activity (Ci)#VALUE!NotApplicable238Pu Activity (Ci)Not SignificantNot Significant239Pu Activity (Ci)#VALUE! NotApplicable240Pu Activity (Ci)#VALUE!NotApplicable242Pu Activity (Ci)Not SignificantNot Significant241Am Activity (Ci)Not SignificantNot Significant90Sr Activity (Ci)#VALUE!NotApplicable137Cs Activity (Ci)#VALUE!NotApplicableTRU Alpha Conc. (nCi/g)Not SignificantNot SignificantB-9Replicate #2ATTACHMENT B.9 REPLICATE TESTING IQ3 DATA FOR CONTAINER MDL0506146Instrument: SRS IQ3Container: MDL0506146Original MeasurementReplicate #1Quantity ofReporteReporteddAbsoluteRelativeReportedAbsoluteRelativeAbsoluteRelativeInterestValueValueUncertaintyUncertaintyValueUncertaintyUncertaintyUncertaintyUncertainty233U Activity (Ci)0.00E+00N/A0.00E+000.00E+00N/A0.00E+000.00E+00N/A0.00E+00234U Activity (Ci)0.00E+00N/A0.00E+000.00E+00N/A0.00E+000.00E+00N/A0.00E+00238U Activity (Ci)0.00E+00N/A0.00E+000.00E+00N/A0.00E+000.00E+00N/A0.00E+00238Pu Activity (Ci)1.701.683.16E-02E-025.38E-013.16E-021.70E-025.38E-013.12E-02E-025.38E-01239Pu Activity (Ci)0.00E+00N/A0.00E+000.00E+00N/A0.00E+000.00E+00N/A0.00E+00240Pu Activity (Ci)0.00E+00N/A0.00E+000.00E+00N/A0.00E+000.00E+00N/A0.00E+00242Pu Activity (Ci)9.771.82E-08E-095.37E-011.82E-089.98E-095.48E-011.79E-089.66E-095.40E-01241Am Activity (Ci)5.33E-052.87E-055.38E-015.54E-052.98E-055.38E-015.41E-052.91E-055.38E-0190Sr Activity (Ci)0.00E+00N/A0.00E+000.00E+00N/A0.00E+000.00E+00N/A0.00E+00137Cs Activity (Ci)0.00E+00N/A0.00E+000.00E+00N/A0.00E+000.00E+00N/A0.00E+00TRU Alpha Conc. (nCi/g)1.05E+025.62E+015.35E-011.04E+025.62E+015.40E-011.03E+025.55E+015.39E-01Replicate #3Replicate #4Replicate #5Quantity ofReportedAbsoluteRelativeReportedAbsoluteRelativeReportedAbsoluteRelativeInterestValueUncertaintyUncertaintyValueUncertaintyUncertaintyValueUncertaintyUncertainty233U Activity (Ci)0.00E+00N/A0.00E+000.00E+00N/A0.00E+000.00E+00N/A0.00E+00234U Activity (Ci)0.00E+00N/A0.00E+000.00E+00N/A0.00E+000.00E+00N/A0.00E+00238U Activity (Ci)0.00E+00N/A0.00E+000.00E+00N/A0.00E+000.00E+00N/A0.00E+00238Pu Activity (Ci)3.30E-021.78E-025.39E-013.39E-021.83E-025.40E-013.28E-021.77E-025.40E-01239Pu Activity (Ci)0.00E+00N/A0.00E+000.00E+00N/A0.00E+000.00E+00N/A0.00E+00240Pu Activity (Ci)0.00E+00N/A0.00E+000.00E+00N/A0.00E+000.00E+00N/A0.00E+00242Pu Activity (Ci)1.90E-081.02E-085.37E-011.95E-081.05E-085.38E-011.88E-081.01E-085.37E-01241Am Activity (Ci)5.53E-052.97E-055.37E-015.36E-052.88E-055.37E-015.48E-052.95E-055.38E-0190Sr Activity (Ci)0.00E+00N/A0.00E+000.00E+00N/A0.00E+000.00E+00N/A0.00E+00137Cs Activity (Ci)0.00E+00N/A0.00E+000.00E+00N/A0.00E+000.00E+00N/A0.00E+00TRU Alpha Conc. (nCi/g)1.09E+025.87E+015.39E-011.12E+026.03E+015.38E-011.08E+025.83E+015.40E-01B-10ATTACHMENT B.10 REPLICATE TESTINGIQ3 RESULTS FOR CONTAINER MDL0506146Instrument: SRS IQ3Container: MDL0506146Original MeasurementQuantity ofReportedAbsoluteInterestValueUncertaintySampleMeanSampleStandardDeviationRelativeStandardDeviationχ2Pr(x<| 

# χ2|)tPr(x<|t|)233U Activity (Ci)0.00E+00N/A0.00E+000.00E+00N/A#VALUE!#VALUE!N/AN/A234U Activity (Ci)0.00E+00N/A0.00E+000.00E+00N/A#VALUE!#VALUE!N/AN/A238U Activity (Ci)0.00E+00N/A0.00E+000.00E+00N/A#VALUE!#VALUE!N/AN/A238Pu Activity (Ci)3.16E-021.70E-023.25E-021.10E-033.37E-021.66E-021.00E+00-7.50E-014.95E-01239Pu Activity (Ci)0.00E+00N/A0.00E+000.00E+00N/A#VALUE!#VALUE!N/AN/A240Pu Activity (Ci)0.00E+00N/A0.00E+000.00E+00N/A#VALUE!#VALUE!N/AN/A242Pu Activity (Ci)1.82E-089.77E-091.87E-086.38E-103.42E-021.71E-021.00E+00-6.87E-015.30E-01241Am Activity (Ci)5.33E-052.87E-055.46E-057.77E-071.42E-022.93E-031.00E+00-1.58E+001.90E-0190Sr Activity (Ci)0.00E+00N/A0.00E+000.00E+00N/A#VALUE!#VALUE!N/AN/A137Cs Activity (Ci)0.00E+00N/A0.00E+000.00E+00N/A#VALUE!#VALUE!N/AN/ATRU Alpha Conc. (nCi/g)1.05E+025.626.16E+011.07E+023.70E+003.45E-021.74E-021.00E+00-5.43E-01E-01Quantity ofInterestχ2TesttTest233U Activity (Ci)#VALUE!Not Applicable234U Activity (Ci)#VALUE!Not Applicable238U Activity (Ci)#VALUE!Not Applicable238Pu Activity (Ci)Not SignificantNot Significant239Pu Activity (Ci)#VALUE!Not Applicable240Pu Activity (Ci)#VALUE!Not Applicable242Pu Activity (Ci)Not SignificantNot Significant241Am Activity (Ci)Not SignificantNot Significant90Sr Activity (Ci)#VALUE!NotApplicable137Cs Activity (Ci)#VALUE!Not ApplicableTRU Alpha Conc. (nCi/g)Not SignificantNot SignificantB-11ATTACHMENT B.11 REPLICATE TESTING IQ3 DATA FORCONTAINER SR123477Instrument: SRS IQ3Container: SR123477Original MeasurementReplicate #1Replicate #2Quantity ofReportedAbsoluteRelativeReportedAbsoluteRelativeReportedAbsoluteRelativeInterestUValueUncertaintyUncertaintyValueUncertaintyUncertaintyValuencertaintyUncertainty233U Activity (Ci)0.00E+00N/A0.00E+000.00E+00N/A0.00E+000.00E+00N/A0.00E+00234U Activity (Ci)0.00E+00N/A0.00E+000.00E+00N/A0.00E+000.00E+00N/A0.00E+00238U Activity (Ci)0.00E+00N/A0.00E+000.00E+00N/A0.00E+000.00E+00N/A0.00E+00238Pu Activity (Ci)5.44E-025.62E-021.03E+007.06E-021.65E-022.34E-018.26E-021.57E-021.90E-01239Pu Activity (Ci)1.97E+003.65E-011.85E-011.89E+003.49E-011.85E-011.89E+003.50E-011.85E-01240Pu Activity (Ci)8.17E-012.23E-012.73E-014.88E-019.21E-021.89E-014.46E-018.26E-021.85E-01242Pu Activity (Ci)3.23E-053.38E-051.05E+008.27E-062.01E-062.43E-017.67E-061.53E-061.99E-01241Am Activity (Ci)3.90E-017.42E-021.90E-013.78E-017.23E-021.91E-013.36E-016.39E-021.90E-0190Sr Activity (Ci)0.00E+00N/A0.00E+000.00E+00N/A0.00E+000.00E+00N/A0.00E+00137Cs Activity (Ci)0.00E+00N/A0.00E+000.00E+00N/A0.00E+000.00E+00N/A0.00E+00TRU Alpha Conc. (nCi/g)1.04E+051.40E+041.35E-019.05E+041.18E+041.30E-018.83E+041.17E+041.33E-01Replicate #3Replicate #4Replicate #5Quantity ofReportedAbsoluteRelativeReportedAbsoluteRelativeReportedAbsoluteRelativeInterestValueUncertaintyUncertaintyValueUncertaintyUncertaintyValueUncertaintyUncertainty233U Activity (Ci)0.00E+00N/A0.00E+000.00E+00N/A0.00E+000.00E+00N/A0.00E+00234U Activity (Ci)0.00E+00N/A0.00E+000.00E+00N/A0.00E+000.00E+00N/A0.00E+00238U Activity (Ci)0.00E+00N/A0.00E+000.00E+00N/A0.00E+000.00E+00N/A0.00E+00238Pu Activity (Ci)6.60E-021.57E-022.38E-017.07E-021.65E-022.33E-016.75E-021.60E-022.37E-01239Pu Activity (Ci)1.80E+003.34E-011.86E-011.88E+003.48E-011.85E-011.87E+003.46E-011.85E-01240Pu Activity (Ci)4.49E-018.48E-021.89E-015.16E-019.74E-021.89E-014.46E-018.41E-021.89E-01242Pu Activity (Ci)7.49E-061.89E-062.52E-018.35E-062.06E-062.47E-017.40E-061.86E-062.51E-01241Am Activity (Ci)3.62E-012.48E+006.85E+003.65E-019.28E-022.54E-013.73E-011.20E-013.22E-0190Sr Activity (Ci)0.00E+00N/A0.00E+000.00E+00N/A0.00E+000.00E+00N/A0.00E+00137Cs Activity (Ci)0.00E+00N/A0.00E+000.00E+00N/A0.00E+000.00E+00N/A0.00E+00TRU Alpha Conc. (nCi/g)8.59E+048.02E+049.34E-019.07E+041.20E+041.32E-018.83E+041.20E+041.36E-01B-12ATTACHMENT B.12 REPLICATE TESTING IQ3 RESULTS FOR CONTAINER SR123477Instrument: SRS IQ3Container: SR123477Original MeasurementQuantity ofReportedAbsoluteInteresttValueUncertaintySampleMeanSampleStandardDeviationRelativeStandardDeviationχ2Pr(x<| 

# χ2|)Pr(x<|t|)233U Activity (Ci)0.00E+00N/A0.00E+000.00E+00N/A#VALUE!#VALUE!N/AN/A234U Activity (Ci)0.00E+00N/A0.00E+000.00E+00N/A#VALUE!#VALUE!N/AN/A238U Activity (Ci)0.00E+00N/A0.00E+000.00E+00N/A#VALUE!#VALUE!N/AN/A238Pu Activity (Ci)5.44E-025.62E-027.15E-026.54E-039.14E-025.41E-021.00E+00-2.39E+007.56E-02239Pu Activity (Ci)1.97E+003.65E-011.87E+003.78E-022.03E-024.29E-021.00E+002.51E+006.60E-02240Pu Activity (Ci)8.17E-012.23E-014.69E-013.17E-026.77E-028.10E-029.99E-011.00E+015.60E-04242Pu Activity (Ci)3.23E-053.38E-057.84E-064.44E-075.67E-026.91E-041.00E+005.03E+019.38E-07241Am Activity (Ci)3.90E-017.42E-023.63E-011.63E-024.48E-021.92E-019.96E-011.53E+002.02E-0190Sr Activity (Ci)0.00E+00N/A0.00E+000.00E+00N/A#VALUE!#VALUE!N/AN/A137Cs Activity (Ci)0.00E+00N/A0.00E+000.00E+00N/A#VALUE!#VALUE!N/AN/ATRU Alpha Conc. (nCi/g)1.04E+051.40E+048.87E+041.96E+032.21E-027.85E-029.99E-017.10E+002.08E-03Quantity ofInterestχ2TesttTest233U Activity (Ci)#VALUE!Not Applicable234U Activity (Ci)#VALUE!Not Applicable238U Activity (Ci)#VALUE!Not Applicable238Pu Activity (Ci)Not SignificantNot Significant239Pu Activity (Ci)Not SignificantNot Significant240Pu Activity (Ci)Not SignificantHighly Significant242Pu Activity (Ci)Not SignificantHighly Significant241Am Activity (Ci)Not SignificantNot Significant90Sr Activity (Ci)#VALUE!NotApplicable137Cs Activity (Ci)#VALUE!Not ApplicableTRU Alpha Conc. (nCi/g)Not SignificantHighly SignificantB-13ATTACHMENT B.13 REPLICATE TESTING IQ3 DATA FORCONTAINER SR546270Instrument: SRS IQ3Container: SR546270Original MeasurementReplicate #1Replicate #2Quantity ofReportedAbsoluteRelativeReportedAbsoluteRelativeReportedAbsoluteRelativeInterestValueUncertaintyUncertaintyValueUncertaintyUncertaintyValueUncertaintyUncertainty233U Activity (Ci)0.00E+00N/A0.00E+000.00E+00N/A0.00E+000.00E+00N/A0.00E+00234U Activity (Ci)0.00E+00N/A0.00E+000.00E+00N/A0.00E+000.00E+00N/A0.00E+00238U Activity (Ci)0.00E+00N/A0.00E+000.00E+00N/A0.00E+000.00E+00N/A0.00E+00238Pu Activity (Ci)3.85E-018.36E-022.17E-013.59E-016.76E-021.88E-014.16E-011.83E-014.40E-01239Pu Activity (Ci)3.63E+007.68E-012.12E-013.68E+006.68E-011.82E-013.60E+006.55E-011.82E-01240Pu Activity (Ci)9.43E-012.01E-012.13E-019.12E-011.68E-011.84E-019.07E-011.67E-011.84E-01242Pu Activity (Ci)2.61E-055.94E-062.28E-012.42E-054.80E-061.98E-012.31E-051.03E-054.46E-01241Am Activity (Ci)5.75E-011.09E-011.90E-016.34E-011.18E-011.86E-016.25E-011.15E-011.84E-0190Sr Activity (Ci)0.00E+00N/A0.00E+000.00E+00N/A0.00E+000.00E+00N/A0.00E+00137Cs Activity (Ci)0.00E+00N/A0.00E+000.00E+00N/A0.00E+000.00E+00N/A0.00E+00TRU Alpha Conc. (nCi/g)2.74E+053.99E+041.46E-013.07E+053.86E+041.26E-013.05E+053.90E+041.28E-01Replicate #3Replicate #4Replicate #5Quantity ofReported RelativeReportedAbsoluteRelativeAbsoluteReportedAbsoluteRelativeInterestValueUncertaintyUncertaintyValueUncertaintyUncertaintyValueUncertaintyUncertainty233U Activity (Ci)0.00E+00N/A0.00E+000.00E+00N/A0.00E+000.00E+00N/A0.00E+00234U Activity (Ci)0.00E+00N/A0.00E+000.00E+00N/A0.00E+000.00E+00N/A0.00E+00238U Activity (Ci)0.00E+00N/A0.00E+000.00E+00N/A0.00E+000.00E+00N/A0.00E+00238Pu Activity (Ci)3.54E-019.71E-032.74E-023.63E-016.77E-021.87E-013.53E-017.60E-022.15E-01239Pu Activity (Ci)3.74E+006.78E-011.81E-013.62E+006.58E-011.82E-013.66E+006.64E-011.81E-01240Pu Activity (Ci)9.70E-011.78E-011.84E-018.88E-011.63E-011.84E-019.01E-011.66E-011.84E-01242Pu Activity (Ci)2.49E-057.03E-062.82E-012.30E-054.48E-061.95E-012.42E-055.45E-062.25E-01241Am Activity (Ci)5.59E-011.02E-011.82E-015.45E-019.91E-021.82E-015.44E-019.89E-021.82E-0190Sr Activity (Ci)0.00E+00N/A0.00E+000.00E+00N/A0.00E+000.00E+00N/A0.00E+00137Cs Activity (Ci)0.00E+00N/A0.00E+000.00E+00N/A0.00E+000.00E+00N/A0.00E+00TRU Alpha Conc. (nCi/g)3.09E+053.93E+041.27E-012.98E+053.78E+041.27E-013.00E+053.82E+041.27E-01B-14ATTACHMENT B.14 REPLICATE TESTING IQ3 RESULTS FOR CONTAINER SR546270Instrument: SRS IQ3Container: SR546270Original MeasurementQuantity ofReportedAbsoluteInterestValueUncertaintySampleMeanSampleStandardDeviationRelativeStandardDeviationχ2Pr(x<| 

# χ2|)tPr(x<|t|)233U Activity (Ci)0.00E+00N/A0.00E+000.00E+00N/A#VALUE!#VALUE!N/AN/A234U Activity (Ci)0.00E+00N/A0.00E+000.00E+00N/A#VALUE!#VALUE!N/AN/A238U Activity (Ci)0.00E+00N/A0.00E+000.00E+00N/A#VALUE!#VALUE!N/AN/A238Pu Activity (Ci)6.123.85E-018.36E-023.69E-012.66E-027.20E-024.04E-019.82E-015.50E-01E-01239Pu Activity (Ci)3.63E+007.68E-013.66E+005.48E-021.50E-022.03E-021.00E+00-5.00E-016.43E-01240Pu Activity (Ci)9.43E-012.01E-019.16E-013.17E-023.46E-029.95E-029.99E-017.89E-014.74E-01242Pu Activity (Ci)2.61E-055.94E-062.39E-058.11E-073.39E-027.45E-029.99E-012.50E+006.68E-02241Am Activity (Ci)5.75E-011.09E-015.81E-014.44E-027.64E-026.64E-019.56E-01-1.32E-019.02E-0190Sr Activity (Ci)0.00E+00N/A0.00E+000.00E+00N/A#VALUE!#VALUE!N/AN/A137Cs Activity (Ci)0.00E+00N/A0.00E+000.00E+00N/A#VALUE!#VALUE!N/AN/ATRU Alpha Conc. (nCi/g)2.74E+053.99E+043.04E+054.66E+031.53E-025.45E-021.00E+00-5.84E+004.29E-03Quantity ofInterestχ2TesttTest233U Activity (Ci)#VALUE!Not Applicable234U Activity (Ci)#VALUE!Not Applicable238U Activity (Ci)#VALUE!Not Applicable238Pu Activity (Ci)Not SignificantNot Significant239Pu Activity (Ci)Not SignificantNot Significant240Pu Activity (Ci)Not SignificantNot Significant242Pu Activity (Ci)Not SignificantNot Significant241Am Activity (Ci)Not SignificantNot Significant90Sr Activity (Ci)#VALUE! NotApplicable137Cs Activity (Ci)#VALUE!Not ApplicableTRU Alpha Conc. (nCi/g)Not SignificantHighly SignificantB-15ATTACHMENT B.15 REPLICATE TESTING IQ3 DATA FORCONTAINER SR611807Instrument: SRS IQ3Container: SR611807Original MeasurementReplicate #1Replicate #2Quantity ofReportedAbsoluteRelativeReportedAbsoluteRelativeReportedAbsoluteRelativeInterestValueUncertaintyUncertaintyValueUncertaintyUncertaintyValueUncertaintyUncertainty233U Activity (Ci)0.00E+00N/A0.00E+000.00E+00N/A0.00E+000.00E+00N/A0.00E+00234U Activity (Ci)0.00E+00N/A0.00E+000.00E+00N/A0.00E+000.00E+00N/A0.00E+00238U Activity (Ci)0.00E+00N/A0.00E+000.00E+00N/A0.00E+000.00E+00N/A0.00E+00238Pu Activity (Ci)1.86E+013.11E+001.67E-011.83E+013.05E+001.67E-011.86E+013.09E+001.66E-01239Pu Activity (Ci)1.45E-022.43E-031.68E-011.61E-022.61E-031.62E-011.56E-022.53E-031.62E-01240Pu Activity (Ci)0.00E+00N/A0.00E+000.00E+00N/A0.00E+000.00E+00N/A0.00E+00242Pu Activity (Ci)5.69E-069.52E-071.67E-015.59E-069.34E-071.67E-015.68E-069.46E-071.67E-01241Am Activity (Ci)5.34E-028.93E-031.67E-015.51E-029.25E-031.68E-015.31E-021.51E-022.84E-0190Sr Activity (Ci)0.00E+00N/A0.00E+000.00E+00N/A0.00E+000.00E+00N/A0.00E+00137Cs Activity (Ci)0.00E+00N/A0.00E+000.00E+00N/A0.00E+000.00E+00N/A0.00E+00TRU Alpha Conc. (nCi/g)1.47E+062.45E+051.67E-011.44E+062.41E+051.67E-011.47E+062.43E+051.65E-01Replicate #3Replicate #4Replicate #5Quantity ofReportedAbsoluteRelativeReportedAbsoluteRelativeReportedAbsoluteRelativeInterestValueUncertaintyUncertaintyValueUncertaintyUncertaintyValueUncertaintyUncertainty233U Activity (Ci)0.00E+00N/A0.00E+000.00E+00N/A0.00E+000.00E+00N/A0.00E+00234U Activity (Ci)0.00E+00N/A0.00E+000.00E+00N/A0.00E+000.00E+00N/A0.00E+00238U Activity (Ci)0.00E+00N/A0.00E+000.00E+00N/A0.00E+000.00E+00N/A0.00E+00238Pu Activity (Ci)1.87E+013.11E+001.66E-011.86E+013.10E+001.67E-011.87E+013.12E+001.67E-01239Pu Activity (Ci)1.59E-022.58E-031.62E-011.48E-022.45E-031.66E-011.60E-022.59E-031.62E-01240Pu Activity (Ci)0.00E+00N/A0.00E+000.00E+00N/A0.00E+000.00E+00N/A0.00E+00242Pu Activity (Ci)5.71E-069.52E-071.67E-015.69E-069.49E-071.67E-015.73E-069.54E-071.66E-01241Am Activity (Ci)5.30E-029.41E-031.78E-014.41E-027.48E-031.70E-013.46E-025.84E-031.69E-0190Sr Activity (Ci)0.00E+00N/A0.00E+000.00E+00N/A0.00E+000.00E+00N/A0.00E+00137Cs Activity (Ci)0.00E+00N/A0.00E+000.00E+00N/A0.00E+000.00E+00N/A0.00E+00TRU Alpha Conc. (nCi/g)1.48E+062.45E+051.66E-011.47E+062.44E+051.66E-011.48E+062.46E+051.66E-01B-16ATTACHMENT B.16 REPLICATE TESTING IQ3 RESULTS FOR CONTAINER SR611807Instrument: SRS IQ3Container: SR611807Original MeasurementQuantity ofInterestReportedValueAbsoluteUncertaintySampleMeanSampleStandardDeviationRelativeStandardDeviationχ2Pr(x<| 

# χ2|)tPr(x<|t|)233U Activity (Ci)0.00E+00N/A0.00E+000.00E+00N/A#VALUE!#VALUE!N/AN/A234U Activity (Ci)0.00E+00N/A0.00E+000.00E+00N/A#VALUE!#VALUE!N/AN/A238U Activity (Ci)0.00E+00N/A0.00E+000.00E+00N/A#VALUE!#VALUE!N/AN/A238Pu Activity (Ci)1.86E+013.11E+001.86E+011.64E-018.84E-031.12E-021.00E+001.11E-019.17E-01239Pu Activity (Ci)1.45E-022.43E-031.57E-025.26E-043.36E-021.88E-019.96E-01-2.05E+001.10E-01240Pu Activity (Ci)0.00E+00N/A0.00E+000.00E+00N/A#VALUE!#VALUE!N/AN/A242Pu Activity (Ci)5.69E-069.52E-075.68E-065.39E-089.48E-031.28E-021.00E+001.70E-018.74E-01241Am Activity (Ci)5.34E-028.93E-034.80E-028.61E-031.79E-013.71E+004.46E-015.75E-015.96E-0190Sr Activity (Ci)0.00E+00N/A0.00E+000.00E+00N/A#VALUE!#VALUE!N/AN/A137Cs Activity (Ci)0.00E+00N/A0.00E+000.00E+00N/A#VALUE!#VALUE!N/AN/ATRU Alpha Conc. (nCi/g)1.47E+062.45E+051.47E+061.64E+041.12E-021.80E-021.00E+001.11E-019.17E-01Quantity ofInterestχ2TesttTest233U Activity (Ci)#VALUE!Not Applicable234U Activity (Ci)#VALUE!Not Applicable238U Activity (Ci)#VALUE!Not Applicable238Pu Activity (Ci)Not SignificantNot Significant239Pu Activity (Ci)Not SignificantNot Significant240Pu Activity (Ci)#VALUE!Not Applicable242Pu Activity (Ci)Not SignificantNot Significant241Am Activity (Ci)Not SignificantNot Significant90Sr Activity (Ci)#VALUE!NotApplicable137Cs Activity (Ci)#VALUE!Not ApplicableTRU Alpha Conc. (nCi/g)Not SignificantNot SignificantB-17ATTACHMENT B.17 REPLICATE TESTING IQ3 DATA FORCONTAINER SR611807Instrument: SRS IQ3Container: MDL0506241Original MeasurementReplicate #1Replicate #2Quantity ofInterestReportedValueAbsoluteUncertaintyRelativeUncertaintyReportedValueAbsoluteUncertaintyRelativeUncertaintyReportedValueAbsoluteUncertaintyRelativeUncertainty233U Activity (Ci)0.00E+00N/AN/A0.00E+000.00E+00N/A0.00E+000.00E+000.00E+00234U Activity (Ci)0.00E+00N/A0.00E+000.00E+00N/A0.00E+000.00E+00N/A0.00E+00238U Activity (Ci)0.00E+00N/A0.00E+000.00E+00N/A0.00E+000.00E+00N/A0.00E+00238Pu Activity (Ci)3.22E-021.77E-025.50E-013.66E-022.02E-025.52E-013.74E-022.09E-025.59E-01239Pu Activity (Ci)0.00E+00N/A0.00E+000.00E+00N/A0.00E+000.00E+00N/A0.00E+00240Pu Activity (Ci)0.00E+00N/A0.00E+000.00E+00N/A0.00E+000.00E+00N/A0.00E+00242Pu Activity (Ci)1.85E-081.02E-085.51E-012.10E-081.16E-085.52E-012.14E-081.20E-085.61E-01241Am Activity (Ci)5.67E-053.12E-055.50E-015.93E-053.26E-055.50E-015.89E-053.24E-055.50E-0190Sr Activity (Ci)0.00E+000.00E+00N/A0.00E+000.00E+00N/A0.00E+00N/A0.00E+00137Cs Activity (Ci)0.00E+00N/A0.00E+000.00E+00N/A0.00E+000.00E+00N/A0.00E+00TRU Alpha Conc. (nCi/g)9.34E+015.13E+015.49E-011.06E+02015.83E+015.50E-011.08E+026.04E+015.59EReplicate #3Replicate #4Replicate #5Quantity ofInterestReportedValueAbsoluteUncertaintyRelativeUncertaintyReportedValueAbsoluteUncertaintyRelativeUncertaintyReportedValueAbsoluteUncertaintyRelativeUncertainty233U Activity (Ci)0.00E+00N/A0.00E+000.00E+00N/A0.00E+000.00E+00N/A0.00E+00234U Activity (Ci)0.00E+00N/A0.00E+000.00E+00N/A0.00E+000.00E+00N/A0.00E+00238U Activity (Ci)0.00E+00N/A0.00E+000.00E+00N/A0.00E+000.00E+00N/A0.00E+00238Pu Activity (Ci)2.143.74E-022.08E-025.56E-013.59E-022.01E-025.60E-013.86E-02E-025.54E-01239Pu Activity (Ci)0.00E+00N/A0.00E+000.00E+00N/A0.00E+000.00E+00N/A0.00E+00240Pu Activity (Ci)0.00E+00N/A0.00E+000.00E+00N/A0.00E+000.00E+00N/A0.00E+00242Pu Activity (Ci)2.14E-081.19E-085.56E-012.06E-081.15E-085.58E-012.21E-081.23E-085.57E-01241Am Activity (Ci)5.75E-053.16E-055.50E-015.72E-053.14E-055.49E-015.95E-053.27E-055.50E-0190Sr Activity (Ci)0.00E+00N/A0.00E+000.00E+00N/A0.00E+000.00E+00N/A0.00E+00137Cs Activity (Ci)0.00E+00N/AN/A0.00E+000.00E+00N/A0.00E+000.00E+000.00E+00TRU Alpha Conc. (nCi/g)1.08E+026.02E+015.57E-011.04E+025.82E+015.60E-011.12E+026.20E+015.54E-01B-18ATTACHMENT B.18 REPLICATE TESTING IQ3 RESULTS FOR CONTAINER SR611807Original MeasurementQuantity ofInterestReportedValueAbsoluteUncertaintyPr(x<|c2|)Pr(x<|t|)SampleMeanSampleStandardDeviationRelativeStandardDeviationc2t233U Activity (Ci)0.00E+00N/A0.00E+000.00E+00N/A#VALUE!#VALUE!N/AN/A234U Activity (Ci)0.00E+00N/A0.00E+000.00E+00N/A#VALUE!#VALUE!N/AN/A238U Activity (Ci)0.00E+00N/A0.00E+000.00E+00N/A#VALUE!#VALUE!N/AN/A238Pu Activity (Ci)3.22E-021.77E-021.30E-023.72E-021.01E-032.72E-021.00E+00-4.50E+001.08E-02239Pu Activity (Ci)0.00E+00N/A0.00E+000.00E+00N/A#VALUE!#VALUE!N/AN/A240Pu Activity (Ci)0.00E+00N/A0.00E+000.00E+00N/A#VALUE!#VALUE!N/AN/A242Pu Activity (Ci)1.85E-081.02E-082.13E-085.57E-102.61E-021.19E-021.00E+00-4.59E+001.01E-02241Am Activity (Ci)5.67E-053.12E-055.85E-051.06E-061.81E-024.61E-031.00E+00-1.53E+002.00E-0190Sr Activity (Ci)0.00E+00N/A0.00E+000.00E+00N/A#VALUE!#VALUE!N/AN/A137Cs Activity (Ci)0.00E+00N/A0.00E+000.00E+00N/A#VALUE!#VALUE!N/AN/ATRU Alpha Conc. (nCi/g)9.34E+015.13E+011.08E+022.97E+002.76E-021.34E-021.00E+00-4.37E+001.20E-02Quantity ofInterest2Testt Test233U Activity (Ci)#VALUE!Not Applicable234U Activity (Ci)#VALUE!Not Applicable238U Activity (Ci)#VALUE!Not Applicable238Pu Activity (Ci)Not SignificantSignificant239Pu Activity (Ci)#VALUE!Not Applicable240Pu Activity (Ci)#VALUE!Not Applicable242Pu Activity (Ci)Not SignificantSignificant241Am Activity (Ci)Not SignificantNot Significant90Sr Activity (Ci)#VALUE!NotApplicable137Cs Activity (Ci)#VALUE!Not ApplicableTRU Alpha Conc. (nCi/g)Not SignificantSignificant

# Attachments C.1 thr ough C.6

# ATT ACH MENT C.1: EPA INS P ECTION I SSUE TRACKING FORM,

EPA ISSUE No. SRS-CCP-AK-05-004C

Page 1 of 1



# ***DRAFT***

Upon further analysis, the EPA issue presen ted here may be

inclu ded in the EPA Inspection Report as an EPA Find ing or

Concern a nd can be the basis for EPA approval/disa p p r oval

Inspection No. EPA-SRS-CCP-10-05.8 Issue Number: SRS-CCP-AK-05-004C

Date: 11-01-05

Inspector: Connie W a l k er

Attachments? YES NO Sample Size: One W a ste Stream

Population siz e (if known): NA

A. Description of Issue: AK reference D152 indicates that wastes in SR- W 027-773A-HET include

large item s such as boxed wastes . This waste s t ream is classified as job control waste that typically

excludes large m e tal item s like those found in SR

- W 027-773A-HET. The AK Summ ary (AK-7) does not

yet address the boxed waste com ponent and CCP is encouraged to assess whether the boxed waste belongs

in SR- W 027-773A-HET based on the sim ilarity of processes, physical form and m a terial type.

B. Regulatory Reference:

40 CFR 194.24 (c)(3)

C. Site requirement(s):

CCP-TP-005, Revision 15

D. Discussed w i th:

Site Personnel: Kevin Peters, Jeff Harrison

DOE/CTAC Personnel: W a yne Ledford

Other Personnel:

E. Additional Comments:

None

F. Site Response Information :

Site Resp onse Required? YES NO

Site Resp onse Due Date: N/A

C- 1

# ATT ACH MENT C.2: EPA INS P ECTION I SSUE TRACKING FORM,

EPA ISSUE No. SRS-CCP-AK-05-005C

Page 1 of 1



# ***DRAFT***

Upon further analysis, the EPA issue presen ted here may be

inclu ded in the EPA Inspection Report as an EPA Find ing or

Concern a nd can be the basis for EPA approval/disa p p r oval

Inspection No. EPA-SRS-CCP-10-05.8 Issue Number: SRS-CCP-AK-05-005C

Date: 11-01-05

Inspector: Connie W a l k er

Attachments? YES NO Sample Size: One W a ste Stream

Population siz e (if known): NA

A. Description of Issue: Several AK references (e.g., C040 ) indicate that the Savannah River

Technology Center generates W a ste Stream SR- W 027- 773A-HET (debris) that m a y contain m a terials

identified as High Level Waste (HLW ). An earli er revision of AK-7 (SR- W 027-773A-HET) included the

HLW component that has si nce been rem oved in the latest revi sion of the AK summary. The AK record

must include why this infor m ation was rem ove d from AK-7. Also, in the future, CCP m u st adequately

docum ent and justify the inclusion of any waste in AK- 7 previously or currently identified as being high

level.

B. Regulatory Reference:

40 CFR 194.24 (c)(3)

C. Site requirement(s):

CCP-TP-005, Revision 15

D. Discussed w i th:

Site Personnel: Kevin Peters, Jeff Harrison

DOE/CTAC Personnel: W a yne Ledford

Other Personnel:

E. Additional Comments:

None

F. Site Response Information :

Site Response Required? YES NO

Site Resp onse Due Date: N/A

C- 2

# ATT ACH MENT C.3: EPA INS P ECTION I SSUE TRACKING FORM,

EPA ISSUE No. SRS-CCP-NDA- 05-006C

Page 1 of 1



# ***DRAFT***

Upon further analysis, the EPA issue presen ted here may be

inclu ded in the EPA Inspection Report as an EPA Find ing or

Concern a nd can be the basis for EPA approval/disa p p r oval

Inspection No. EPA-SRS-CCP-10-05.8 Issue Number: SRS-CCP-NDA-05-006C

Date: 11-01-05

Inspector: Patrick Kelly

Attachments? YES NO Sample Size: NA

Population siz e (if known): NA

A. Description of Issue: Default isotopics based on AK are docum ented on a waste stream basis and are

contained in AK-NDA Mem o randa. Th ere is no for m al instruction fo r the NDA Exp e rt Analysts (EA)

regarding the use of AK based defaul t isotopics. CCP-TP-048 does contain directions to the EA regarding

other aspects of the radioassay proc ess. Exam ination of NDA BDRs indi cates that AK-based isotopics have

been applied by the NDA EA.

B. Regulatory Reference:

40 CFR 194.24 (b)(2)

C. Site requirement(s):

CCP-TP-048

D. Discussed w i th:

Site Personnel: Rich T h om ason, Bruce Gillespie,

DOE/CTAC Personnel: Joe Harvill, David Drehr

Other Personnel:

E. Additional Comments:

None

F. Site Response Information :

Site Response Required? YES NO

Site Resp onse Due Date:

C- 3

# ATT ACH MENT C.4: EPA INS P ECTION I SSUE TRACKING FORM,

EPA ISSUE No. SRS-CCP-RTR-05-003CR

Page 1 of 1



# ***DRAFT***

Upon further analysis, the EPA issue presen ted here may be

inclu ded in the EPA Inspection Report as an EPA Find ing or

Concern a nd can be the basis for EPA approval/disa p p r oval

Inspection No. EPA-SRS-CCP-10-05.8 Issue Number: SRS-CCP-RTR-05

- 003CR

Date: 10-31-05

Inspector: Dorothy Gill

Attachments? YES NO Sample Size: Two (2)

Population siz e (if known): Four (4)

A. Description of Issue: In the p r ocess of RTR train i ng in accordan ce with CCP-TP-028, Revision 2, an

operator did not identify a required item in the training drum . A lthough a qualified RT R operator reviewed

this training tape, it appears that the CCP NDE Test Drum Inventory Sheet CCP-TP-028-A1

, Revision 0 was

not used as a basis for this rev i ew because the revi ewer d i d not docum ent tha t a req u ired item was m i ssed.

The process in plac e resu lts in a la ck of identif ica tion of problem s associated with the r e qualif ic atio n of

RTR Operators and does not provide the opportunity for feedback to th e operator undergoing RTR Operator

requalification.

B. Regulatory Reference:

40 CFR 194.24 (b)(2)

C. Site requirement(s):

CCP-TP-028, Revision 2

D. Discussed w i th:

Site Personn el: Lee Sm ith & Jam e s Mobley

DOE/CTAC Personnel: Annabelle Axinn, Wayne Ledford

Other Personnel:

E. Additional Comments:

None

F. Site Response Information :

Site Response Required? YES NO

Site Resp onse Due Date: 11-21-05

C- 4

# ATT ACH MENT C.5: EPA INS P ECTION I SSUE TRACKING FORM,

EPA ISSUE No. SRS-CCP-VE-05-001F

Page 1 of 1



# ***DRAFT***

Upon further analysis, the EPA issue presen ted here may be

inclu ded in the EPA Inspection Report as an EPA Find ing or

Concern a nd can be the basis for EPA approval/disa p p r oval

Inspection No. EPA-SRS-CCP-10-05.8 Issue Number: SRS-CCP-VE-05-001F

Date: 10-31-05

Inspector: Dorothy Gill

Attachments? YES NO Sample Size: Three (3)

Population siz e (if known): Five (5)

A. Description of Issue: W h en perform i ng VE on S4000 soils drum s from the Mound soil waste stream

described in AK-8 for BDRs SRVEMS0001 through SR VEMS0003, operators conduc ted visual inspection

that was not consistent w ith Procedure CCP-TP-113, Revi sion 3. The VE event did not assess the drum s’

contents but focused solely on the top layer of wast e. The BDRs reported that no prohibited item s were

found but this could not be ascertaine d based on the VE that was performed.

B. Regulatory Reference:

40 CFR 194.24 (b)(2)

C. Site requirement(s):

CCP-TP-113, Revision 3

D. Discussed w i th: Jam e s Mobley, CCP, Visual Exam ination Expert

Site Personn el:

DOE/CTAC Personnel: Annabelle Axinn

Other Personnel:

E. Additional Comments:

None

F. Site Response Information :

Site Response Required? YES NO

Site Resp onse Due Date: 11-21-05

C- 5

# ATT ACH MENT C.6: EPA INS P ECTION I SSUE TRACKING FORM,

EPA ISS U E No. SRS-CCP-VE-05 -002CR

Page 1 of 1



# ***DRAFT***

Upon further analysis, the EPA issue presen ted here may be

inclu ded in the EPA Inspection Report as an EPA Find ing or

Concern a nd can be the basis for EPA approval/disa p p r oval

Inspection No. EPA-SRS-CCP-10-05.8 Issue Number: SRS-CCP-VE-05-002CR

Date: 10-31-05

Inspector: Dorothy Gill

Attachments? YES NO Sample Size: One

Population siz e (if known): One

A. Description of Issue: The W a ste Visual E x am ination Data Form ( A ttachm e nt 1) from proc edure

CCP-TP-113 contains data th at does not m a tch what actually transpir ed during visual exam ination of Drum

No. SR100052. The videotape record shows a problem with the VE data for this drum that was initially

recorded in the hard copy record. Subsequently, the orig inal record was discar ded and replaced with one

that does not m a tch the videotaped event. Consequently, the hard copy record that rem a ins does not

represent w h at transpired during VE of this drum.

B. Regulatory Reference:

40 CFR 194.24 (b)(2)

C. Site requirement(s):

CCP-TP-113, Revision 3

D. Discussed w i th: Jam e s Mobley, CCP, Visual Exam ination Expert

Site Personnel:

DOE/CTAC Personnel: Annabelle Axinn

Other Personnel:

E. Additional Comments:

None

F. Site Response Information :

Site Response Required? YES NO

Site Resp onse Due Date: 11-21-05

C- 6

# Attachment D: Response to EP A

Inspection Issues

# APPE NDI X D: RES P ONSE TO EPA INS P ECTION I SSUES

Inspection No. EPA-SRS-CCP-10-05.8 In spection Date: 10/31/05-11/03/2005 APPE NDI X D: RES P ONSE TO EPA INS P ECTION I SSUES

Inspection No. EPA-SRS-CCP-10-05.8 In spection Date: 10/31/05-11/03/2005

D- 1

# APPE NDI X D: RES P ONSE TO EPA INS P ECTION I SSUES

Inspection No. EPA-SRS-CCP-10-05.8 In spection Date: 10/31/05-11/03/2005 APPE NDI X D: RES P ONSE TO EPA INS P ECTION I SSUES

Inspection No. EPA-SRS-CCP-10-05.8 In spection Date: 10/31/05-11/03/2005

D- 2

# APPE NDI X D: RES P ONSE TO EPA INS P ECTION I SSUES

Inspection No. EPA-SRS-CCP-10-05.8 In spection Date: 10/31/05-11/03/2005 APPE NDI X D: RES P ONSE TO EPA INS P ECTION I SSUES

Inspection No. EPA-SRS-CCP-10-05.8 In spection Date: 10/31/05-11/03/2005

D- 3

# APPE NDI X D: RES P ONSE TO EPA INS P ECTION I SSUES

Inspection No. EPA-SRS-CCP-10-05.8 In spection Date: 10/31/05-11/03/2005 APPE NDI X D: RES P ONSE TO EPA INS P ECTION I SSUES

Inspection No. EPA-SRS-CCP-10-05.8 In spection Date: 10/31/05-11/03/2005

D- 4

# APPE NDI X D: RES P ONSE TO EPA INS P ECTION I SSUES

Inspection No. EPA-SRS-CCP-10-05.8 In spection Date: 10/31/05-11/03/2005 APPE NDI X D: RES P ONSE TO EPA INS P ECTION I SSUES

Inspection No. EPA-SRS-CCP-10-05.8 In spection Date: 10/31/05-11/03/2005

D- 5

# APPE NDI X D: RES P ONSE TO EPA INS P ECTION I SSUES

Inspection No. EPA-SRS-CCP-10-05.8 In spection Date: 10/31/05-11/03/2005 APPE NDI X D: RES P ONSE TO EPA INS P ECTION I SSUES

Inspection No. EPA-SRS-CCP-10-05.8 In spection Date: 10/31/05-11/03/2005

D- 6

# APPE NDI X D: RES P ONSE TO EPA INS P ECTION I SSUES

Inspection No. EPA-SRS-CCP-10-05.8 In spection Date: 10/31/05-11/03/2005 APPE NDI X D: RES P ONSE TO EPA INS P ECTION I SSUES

Inspection No. EPA-SRS-CCP-10-05.8 In spection Date: 10/31/05-11/03/2005

D- 7

# APPE NDI X D: RES P ONSE TO EPA INS P ECTION I SSUES

Inspection No. EPA-SRS-CCP-10-05.8 In spection Date: 10/31/05-11/03/2005 APPE NDI X D: RES P ONSE TO EPA INS P ECTION I SSUES

Inspection No. EPA-SRS-CCP-10-05.8 In spection Date: 10/31/05-11/03/2005

D- 8

# APPE NDI X D: RES P ONSE TO EPA INS P ECTION I SSUES

Inspection No. EPA-SRS-CCP-10-05.8 In spection Date: 10/31/05-11/03/2005 APPE NDI X D: RES P ONSE TO EPA INS P ECTION I SSUES

Inspection No. EPA-SRS-CCP-10-05.8 In spection Date: 10/31/05-11/03/2005

D- 9

# APPE NDI X D: RES P ONSE TO EPA INS P ECTION I SSUES

Inspection No. EPA-SRS-CCP-10-05.8 In spection Date: 10/31/05-11/03/2005 APPE NDI X D: RES P ONSE TO EPA INS P ECTION I SSUES

Inspection No. EPA-SRS-CCP-10-05.8 In spection Date: 10/31/05-11/03/2005

D- 10

# APPE NDI X D: RES P ONSE TO EPA INS P ECTION I SSUES

Inspection No. EPA-SRS-CCP-10-05.8 In spection Date: 10/31/05-11/03/2005

D- 11