'" ·~ Entergy 

PNP 2013-038 

April 23, 2013 

U. S. Nuclear Regulatory Commission 

AnN: Document Control Desk 

Washington, DC 20555-0001 

Entergy Nuclear Operations, Inc. 

Palisades Nuclear Plant 

27780 Blue Star Memorial Highway 

Covert, MI 49043 

Tel 269 764 2000 

Otto W. Gustafson 

Licensing Manager 

10 CFR 50.36a 

Subject: 2012 Annual Radioactive Effluent Release and Waste Disposal Report 

Palisades Nuclear Plant 

Docket 50-255 

License No. DPR-20 

Dear Sir or Madam: 

Big Rock Point 

Dockets 50-155 and 72-043 

License No. DPR-6 

Attached are the Entergy Nuclear Operations, Inc. 2012 Annual Radioactive Effluent 

Release and Waste Disposal Reports for Palisades Nuclear Plant (PNP) and Big Rock 

Point (BRP) Independent Spent Fuel Storage Installation (ISFSI). These reports are 

submitted in accordance with 10 CFR 50.36a(a)(2). 

Attachment 1 contains the report for PNP. Attachment 2 contains the report for the 

BRP ISFSI. 

These reports provide a summary of the quantities of radioactive liquid and gaseous 

effluent releases and solid radioactive waste processed during the period of 

January 1,2012, through December 31,2012. 
Document Control Desk 

Page 2 

This letter contains no new commitments and no revision to existing commitments. 

Sincerely, 

OWG/bed 

Attachment 1: Palisades Nuclear Plant 2012 Radioactive Effluent Release Report 

Attachment 2: Big Rock Point Independent Spent Fuel Storage Installation 2012 

Radioactive Effluent Release Report 

CC Administrator, Region III, USNRC 

Project Manager, Palisades, USNRC 

Resident Inspector, Palisades, USNRC 

NRC NMSS Project Manager 

American Nuclear Insurers (ANI) 
Attachment 1 

Palisades Nuclear Plant 2012 Radioactive Effluent Release Report 

2012 Plant Operating History 

Palisades Nuclear Plant (PNP) entered the reporting period on line on January 1, 2012, 

at nominal full power (NFP). PNP performed a planned shutdown on January 5,2012, 

to address primary coolant system leakage through a control rod drive mechanism 

mechanical seal and leak-by of a pressurizer vent valve. The unit attained criticality on 

January 8, 2012, and returned to NFP on January 11, 2012. PNP performed a planned 

shutdown on April 8, 2012, to enter 1 R22 refueling outage. The unit attained criticality 

on May 10,2012, and returned to NFP on May 18, 2012. PNP performed a planned 

shutdown on June 12, 2012, to perform repairs on the safety injection refueling water 

tank. The unit attained criticality on July 10, 2012, and returned to NFP on July 15, 

2012. PNP performed a planned shutdown on August 12, 2012, to locate and repair 

primary system leakage on control rod drive (CRD-24) upper housing. The unit attained 

criticality on August 29,2012, and returned to NFP on August 31,2012. PNP 

performed a planned shutdown on November 4, 2012, to repair a main steam leak. 

The unit attained criticality on November 7,2012, and returned to NFP on November 8, 

2012. PNP remained on line for the remainder of 2012. The unit generated 5,178,213 

MWHrs of net electrical energy during 2012. 

A. Gaseous Effluents 

Tables A-1, "Gaseous Effluents - Summation of All Discharges," A-1A, "Gaseous 

Effluents - Ground-Level Release - Batch Mode," and A-1 B, "Gaseous EffluentsGround-Level Release - Continuous Mode," list and summarize gaseous effluents 

released during this reporting period. 

B. Liquid Effluents 

Tables A-2, "Liquid Effluents - Summation of All Discharges," A-2A, "Liquid 

Effluents - Batch Mode," and A-2B, "Liquid Effluents - Continuous Mode," list and 

summarize liquid effluents released during this reporting period. 

C. Solid Waste Storage and Shipments 

Table A-3, "Low-Level Waste for Waste Classification A, Band C, summarizes 

solid radioactive waste shipped for processing or burial in 2012 for the following 

waste streams: resins, filters and evaporator bottoms, dry active waste, irradiated 

components, other waste, and sum of all waste. 

D. Dose Assessments 

Tables A-4, "Dose Assessments, 10 CFR Part 50, Appendix 1," and A-5, "EPA 

40 CFR Part 190, Individual in the Unrestricted Area," lists annual dose to the 

members of the public. 

Page 1 of 5 
E. Supplemental Information 

1. Abnormal Discharges 

In December 2007, tritium was detected in a groundwater monitoring well at 

a level of 22,000 pCi/L. The source of the activity is leakage associated with 

T-91 , the utility water storage tank, and associated piping. T-91 is used to 

store processed liquid waste prior to discharge. No radionuclides other than 

tritium have been detected in the groundwater. 

Additional piping repair work of underground piping was performed during 

the spring of 2011. The overflow line to T-91 was sleeved to ensure piping 

integrity. This line was assumed to be dry, based on all indication, but 

contained highly tritiated water, of which a small amount was expelled during 

the sleeving operation. This resulted in an additional release of tritiated 

water to the groundwater which caused spiking in Monitoring Well 3. This 

event is further discussed under section 9, Other, Groundwater Monitoring, 

of this report. 

Monitoring of the groundwater tritium plume continues in order to determine 

effectiveness of the repairs, and to ensure the accuracy of the site 

hydrology. 

Depth to Local Water Table - The depth is approximately eight to nine feet. 

Classification of Subsurface Aquifers - Not used for drinking water. 

Expected Movement/Mobility of Groundwater Plume - Westerly direction 

down-gradient toward Lake Michigan at approximately two feet per day. 

Land Use Characteristics - PNP site property, water not used for drinking or 

irrigation. 

NRC Notification, Date and contact Organization - The NRC was notified on 

December 10,2007, by PNP. 

2. Non-Routine Planned Discharges 

None. 

3. Radioactive Waste Treatment System Changes 

None. 

Page 2 of 5 
4. Annual Land Use Census Changes 

The garden critical receptor remains located in the southeast sector at 1.01 

miles. The residence critical receptor is unchanged at 0.8 miles. Also 

unchanged is that there are no beef cattle or dairy cows located within five 

miles of the plant. There are goats located to the ENE at 2.62 miles. These 

goats are fed stored feed. 

5. Effluent Monitoring System Inoperability 

There was one effluent monitor that has been out of service for greater than 

30 days. RIA-2320, steam generator blowdown vent, was declared 

inoperable on November 6,2012, due to indicating failed. Technically, the 

pathway is not in service, but there is suspected valve leakage in the 

system, so compensatory samples are being obtained as a conservative 

measure as if it were in service. Work continues through the work control 

process to get the monitor returned to service. 

6. Offsite Dose Calculation Manual (aDeM) Changes 

There was no revision to the Offsite Dose Calculation Manual during the 

report period. 

7. Process Control Program Changes 

None. 

8. Errata/Corrections to Previous Reports 

None. 

9. Other 

Groundwater Monitoring 

PNP installed five groundwater monitoring wells in 2007, and added an 

additional nine wells in 2008. These wells were strategically placed within 

the owner controlled area, both inside and outside the protected area to 

allow detection of radioactive contamination of ground water due to leaks or 

spills from plant systems. Monitoring well (MW) 3 is most indicative of a 

historic leak that continues to be monitored and addressed through piping 

repairs. This leak is described in the Abnormal Discharges section. Tritium 

levels for 2012 in MW3 ranged from less than minimum detectable activity 

Page 3 of 5 
(MDA) to 5,233 pCi/L, down from 19,854 pCi/L in 2011. Monitoring well 

MW2 exhibited a spike to 8,952 in February 2012, which was caused by a 

leaking underground radwaste discharge line that was subsequently isolated 

and repaired, and levels dropped to nondetectable in June 2012. Monitoring 

well MW11 exhibited two detectable readings in 2012, with the highest being 

792 pCi/L. Values of this magnitude may be attributed to precipitation 

recapture of tritium. The remaining wells showed no activity throughout the 

year. Well locations are depicted in Figure 1. 

Carbon-14 

In 2010, PNP and other facilities participated in an EPRI task force to build a 

model to accurately estimate gaseous C-14 releases, given some key sitespecific plant parameters (mass of the primary coolant, average thermal 

neutron cross section, rated MW, etc). This work was completed in 

November 2010. The estimates for C-14 were constructed using the 

aforementioned EPRI methodology contained with EPRI 1021106, 

Estimation of Carbon-14 in Nuclear Power Plant Gaseous Effluents. Using 

the C-14 curie estimates, the annual dose to man was derived from 

guidance contained within Regulatory Guide 1.109. Because the dose 

contribution of C-14 from liquid radioactive waste is much less than that 

contributed by gaseous radioactive waste, evaluation of C-14 in liquid 

radioactive waste is not required. (Reg Guide 1.21 Rev 2) 

Annual C-14 release PNP and subsequent doses for 2012: 

Total Gaseous C-14 Released Curies = 6.39 

Gaseous C-14 as C02 Curies = 1.92 

Effective Child TB Dose, C-14 mrem = 0.0296 

Effective Child Bone Dose, C-14 mrem = 0.148 

The quarterly curies released are provided in Table A-1 B. Airborne doses 

due to C-14 are grouped under the category of Particulate, Iodine, and 

Tritium which are contained in Table A-4. 

Safety Injection Refueling Water (SIRW) Tank 

During the course of repairs to the SIRW tank during the forced outage from 

6/12 to 7/12/12 there was 1.5E-5 Curies of various particulate radionuclides 

released from tank repair activities. These releases were quantified from 

sampling during the course of this work and actions were taken to mitigate 

these releases. The activity released is included as part of the continuous 

gaseous release information contained in Table A-1 B. This data is also 

included for dose calculation purposes provided as Table A-4 of this report. 

Page 4 of 5 
a 

, 

FIGURE 1 

GROUNDWATER MONITORING WELL LOCATIONS 

~ ~ , ,- ..... I 

" 

/ 

--. IlIl'IS -

I 

_:>0111~ 1'CIR!l~ 

",""",J«JlOOU-lDl'"'--

OQ ~u:.::A1 t:l .. 

ffgure 4,1 

GROUNDWATER MONITORING WELL LOCATIONS 

PALISADES NUCLEAR POWER PLANT 

217BD8LUESTAR HWY, 

CmwIt MicI1ig6n 

Page 5 of 5 
Summation of 

All Releases 

Fission and 

Activation 

Gases 

Average 

Release Rate 

% of Limit 

Particulates 

Average 

Release Rate 

% of Limit 

Tritium 

Average 

Release Rate 

% of Limit 

Gross Alpha 

C-14 

Average 

Release Rate 

% of Limit 

ATTACHMENT 1 

Palisades - Table A-1 

2012 Gaseous Effluents - Sum of All Releases 

Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 

Ci 6.64E+OO 3.36E+OO 1.77E+OO 2.0BE+OO 

4.2BE-01 2.1BE-01 2.45E-01 

9.56E-06 1.64E-05 1.46E-05 B.76E-06 

1.15E-07 1.97E-07 1.76E-07 1.06E-07 

2.63E-07 2.54E-05 3.00E-04 3.74E-OB 

1.95E-06 3.4BE-05 O.OOE+OO 

1.47E-07 3.24E-06 1.75E-05 O.OOE+OO 

4.47E+OO 3.19E+OO 3.0BE+OO 

5.69E-01 4.02E-01 3.B7E-01 

1.11 E-03 1.37E-03 9.6BE-04 9.33E-04 

Ci 4.14E-07 4.02E-07 ND 6.34E-07 

Ci 2.02E+OO 8.04E-01 1.4BE+OO 2.09E+OO 

its 2.57E-01 1.02E-01 1.B6E-01 2.63E-01 

% 2.06E-06 B.21E-07 1.49E-06 2.12E-06 

Page 1 of 1 

Total Uncertainty 

(%) 

1.39E+01 4.17 

4.3BE-01 

1.23E-05 

1.4BE-07 

3.26E-04 

1.03E-05 

5.23E-06 

1.44E+01 

4.54E-01 

1.09E-03 

1.45E-06 

6.39E+OO 

2.02E-01 

1.62E-06 
ATTACHMENT 1 

Palisades - Table A-1A 

2012 Gaseous Effluents - Ground Level Release, Batch Mode 

Fission and Activation Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 

Gases 

Ar-41 Ci 6.99E-02 NO NO NO 

Kr-85 Ci NO NO NO NO 

Kr-85m Ci 8.30E-03 NO NO NO 

Kr-87 Ci NO NO NO NO 

Kr-88 Ci NO NO NO NO 

Xe-131m Ci 9.36E-03 1.40E-02 8.08E-03 7.39E-04 

Xe-133 Ci 1.67E+OO 1.46E+OO 6.73E-01 8.60E-03 

Xe-133m Ci 1.77E-02 5.41E-03 6.26E-04 

Xe-135 Ci 2.26E-01 2.22E-02 8.38E-03 4. 1 OE-05 

Xe-135m Ci NO NO NO NO 

Xe-138 Ci NO NO NO NO 

Total Ci 2.00E+OO 1.50E+OO 6.90E-01 9.38E-03 

lodines/Halogens Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 

1-131 Ci NO NO 9.54E-07 1.68E-06 

1-132 Ci NO NO NO NO 

1-133 Ci NO NO 9.21E-07 NO 

1-134 Ci NO NO NO NO 

1-135 Ci NO NO NO NO 

Total Ci O.OOE+OO O.OOE+OO 1.88E-06 1.68E-06 

Particulates Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 

Co-58 Ci NO NO 1.69E-04 NO 

Co-60 Ci NO NO 1.94E-05 NO 

Na-24 Ci NO NO 8.91E-06 NO 

Cr-51 Ci NO NO 6.23E-05 NO 

Mn-56 Ci NO NO 6.67E-06 NO 

Sr-92 Ci NO NO 7.54E-06 NO 

Nb-95 Ci NO NO 2.58E-05 NO 

Zr-95 Ci NO NO 1.24E-05 NO 

Ag-110m Ci NO NO 1.08E-05 NO 

Total Ci O.OOE+OO O.OOE+OO 3.23E-04 O.OOOE+OO 

I Tritium I Ci 1.34E-02 I 9.59E-02 1 3.99E-01 I NA 

I Gross Alpha I Ci I NA I NA 

I C-14 I Ci I NA I NA 

NO = Measurements performed but no activity detected. 

NA = Analysis not required and not performed 

Page 1 of 1 

I NA I NA 

I NA I NA 
ATTACHMENT 1 

Palisades - Table A-1 B 

2012 Gaseous Effluents - Ground Level Release, Continuous Mode 

Fission and Activation Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 

Gases 

Ar-41 Ci 2.20E+OO 6.16E-01 1.66E-01 3.1BE-01 

Kr-B5 Ci NO NO NO NO 

Kr-B5m Ci 1.69E-02 3.97E-03 1.77E-02 2.03E-02 

Kr-B7 Ci 1.49E-01 1.17E-02 5.33E-03 2.05E-02 

Kr-BB Ci 1.2BE-01 2.7BE-02 5.B1E-02 1.69E-01 

Xe-133 Ci 1.30E-01 B.07E-01 3.7BE-01 1.20E-02 

Xe-135 Ci 6.19E-01 2.44E-01 2.11E-01 5.B9E-01 

Xe-135m Ci 3.94E-01 5.41E-02 6.27E-02 2.34E-01 

Xe-13B Ci B.2BE-02 NO 4.07E-02 1.2BE-01 

Total Ci 4.64E+OO 1.B6E+OO 1.0BE+OO 2.07E+OO 

lodines/Halogens Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 

1-131 Ci 7.50E-05 1.2BE-04 1.05E-04 6.96E-05 

1-132 Ci NO 1.33E-03 NO NO 

1-133 Ci 1.57E-04 4.77E-05 1.50E-04 5.59E-05 

1-135 Ci NO NO NO NO 

Total Ci 2.32E-04 1.50E-03 2.55E-04 1.26E-04 

Particulates Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 

Co-58 Ci 2.36E-OB 7.03E-06 1.51E-07 NO 

Co-60 Ci 2.39E-07 4.B7E-06 1.B7E-07 NO 

Cr-51 Ci NO 1.21E-06 NO NO 

Mn-54 Ci NO 1.70E-07 NO NO 

Co-57 Ci NO 2.47E-OB NO NO 

Nb-95 Ci NO 2.01E-06 7.42E-OB NO 

Zr-95 Ci NO 1.03E-06 NO NO 

Ag-110m Ci NO 7.69E-06 4.31 E-B NO 

Sn-113 Ci NO 7.36E-OB NO NO 

Sb-125 Ci NO 1.95E-07 NO NO 

Cs-137 Ci NO 1.01E-06 2.66E-OB 3.74E-OB 

Ce-144 Ci NO 1.11E-07 NO NO 

Total Ci 2.63E-07 2.54E-05 4.B2E-07 3.74E-OB 

I Tritium 3.61E+OO 4.3BE+OO 2.79E+OO 3.0BE+OO 

I Gross Alpha I Ci 4.14E-07 4.02E-07 NO 6.34E-07 

I C-14 2.02E+OO B.04E-01 1.4BE+OO 2.09E+OO 

NO = Measurements performed but no activity detected. 

Page 1 of 1 
ATTACHMENT 1 

Palisades - Table A-2 

2012 Liquid Effluents - Sum of All Releases 

Summation of All Uncertainty Liquid Releases Units rter2 Quarter 3 Quarter 4 Total 

Fission and 

Activation 

Products 

(excluding tritium, 

gases, and gross 

ha Ci 3.22E-03 6.44E-03 6.24E-04 1.05E-03 1.13E-02 5.26 

Average 

Concentration Ci/ml 1.37E-10 2.45E-10 1.71E-11 2.77E-11 9.13E-11 

% of Limit 1.42E-03 4.06E-03 3.42E-04 6.21E-04 1.42E-03 

Tritium 9.69E+01 4.04E+01 3.20E+01 1.61E+02 3.31E+02 

Average 

Concentration Ci/ml 4.1 2E-06 1.53E-06 B.7BE-07 4.25E-06 2.66E-06 

% of Limit % 4.12E-01 1.53E-01 B.7BE-02 4.25E-01 2.66E-01 

Dissolved and 

Entrained Gases Ci 1.45E-03 1.0BE-03 O.OOE+OO B.16E-05 2.61E-03 

Average 

Concentration 6.15E-11 4.10E-11 O.OOE+OO 2.15E-12 2.10E-11 

% Of Limit 3.07E-05 2.05E-05 O.OOE+OO 1.0BE-06 1.05E-05 

Alpha O.OOE+OO 2.12E-OB O.OOE+OO O.OOE+OO 2.12E-OB 

Average 

Concentration O.OOE+OO B.04E-16 O.OOE+OO O.OOE+OO 1.70E-16 

Volume of 

Primary System 

Liquid Effluent 

Before Dilution Liters 1.09E+06 9.6BE+05 3.61E+05 7.1BE+05 3.13E+06 

Dilution Water 

Used for Above Liters 2.35E+10 2.63E+10 3.64E+10 3.79E+10 1.24E+11 

Volume of 

Secondary or 

Balance-of-Plant 

Liquid Effluent 

(e.g., low-activity 

or unprocessed) 

Before Dilution Liters 2.51E+06 3.47E+06 4.B7E+06 5.35E+06 1.62E+07 

Average Stream 

Flow m3

/s 2.99E+00 3.35E+00 4.5BE+00 4.77E+00 3.92E+00 

Dilution flow rate (gal/qtr) = # of Dilution pumps running x days running/qtr x 4000 gpm/pump x min/day 

Page 1 of 1 
Fission and Activation 

Products 

Cr-51 

Mn-54 

Fe-55 

Fe-59 

Co-57 

Co-5B 

Co-60 

Sr-B9 

Sr-90 

Nb-95 

Ag-110m 

Sn-113 

Sb-124 

Sb-125 

1-131 

1-133 

1-135 

Cs-134 

Cs-137 

Ni-63 

Zn-65 

Zr-95 

La-140 

Totals 

Dissolved and 

Entrained Gases 

Kr-B5 

Xe-131m 

Xe-133 

Xe-133m 

Xe-135 

Totals 

I Tritium 

I Gross Alpha 

NO = None Detected 

ATIACHMENT1 

Palisades· Table A·2A 

2012 Liquid Effluents - Batch Mode 

Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 

Ci ND ND ND ND 

Ci 2.63E-05 ND ND ND 

Ci ND 5.31 E-04 ND 1.0BE-04 

Ci ND ND ND ND 

Ci ND ND ND ND 

Ci 6.16E-04 1.17E-03 1.37E-04 2.03E-04 

Ci 5.60E-04 6.57E-04 2.20E-04 3.55E-04 

Ci ND ND ND ND 

Ci ND ND ND ND 

Ci ND 5.B3E-06 

Ci ND 3.77E-03 2.67E-04 2.59E-04 

Ci ND ND ND ND 

Ci ND ND ND ND 

Ci ND ND ND ND 

Ci ND 2.17E-05 ND ND 

Ci ND ND ND ND 

Ci ND ND ND ND 

Ci ND ND ND ND 

Ci 7.B7E-05 2.35E-05 ND 6.20E-05 

Ci 1.92E-03 1.16E-04 ND 6.51 E-05 

Ci ND ND ND ND 

Ci ND 2.99E-05 ND ND 

Ci ND ND ND ND 

Ci 3.20E-03 6.33E-03 6.24E-04 1.05E-03 

Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 

Ci ND ND ND ND 

Ci ND ND ND ND 

Ci 1.45E-03 1.0BE-03 B.16E-05 

Ci ND ND ND ND 

Ci ND ND ND ND 

1.45E-03 1.0BE-03 O.OOOE+OO B.16E-05 

Ci 9.69E+01 4.04E+01 3.20E+01 1.61 E+02 

I Ci ND 7.0BE-06 ND ND 

Page 1 of 2 
Fission and Activation 

Products 

Cr-51 

Mn-54 

Fe-55 

Co-58 

Co-60 

Sr-89 

Sr-90 

Nb-95 

Ag-110m 

Sn-113 

Sb-124 

Sb-125 

1-131 

1-133 

1-135 

Cs-134 

Cs-137 

Ni-63 

Totals 

Oissolved and 

Entrained Gases 

Kr-85 

Xe-133 

Xe-133m 

Xe-135 

Xe-135m 

Totals 

I Tritium 

I Gross Alpha 

NO = None Oetected 

ATTACHMENT 1 

Palisades - Table A-2B 

2012 Liquid Effluents - Continuous Mode 

Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 

Ci NO NO NO NO 

Ci NO NO NO NO 

Ci NO NO NO NO 

Ci NO NO NO NO 

Ci 1.13E-05 NO NO NO 

Ci NO NO NO NO 

Ci NO NO NO NO 

Ci NO NO NO NO 

Ci NO NO NO NO 

Ci NO NO NO NO 

Ci NO NO NO NO 

Ci NO NO NO NO 

Ci NO NO NO NO 

Ci NO NO NO NO 

Ci NO NO NO NO 

Ci NO NO NO NO 

Ci 1.79E-05 1.07E-04 NO NO 

Ci NO NO NO NO 

Ci 1.79E-05 1.18E-04 O.OOE+OO O.OOE+OO 

Units Quarter 1 Quarter 2 Quarter 3 Quarter 4 

Ci NO NO NO NO 

Ci NO NO NO NO 

Ci NO NO NO NO 

Ci NO NO NO NO 

Ci NO NO NO NO 

O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO 

2.60E-03 4.90E-03 1.26E-02 4.10E-02 

NO NO NO NO 

Page 2 of 2 
Resins, Filters, and 

Evaporator Bottoms 

Waste Class 

A 

B 

C 

ALL 

ATTACHMENT 1 

Palisades - Table A-3 

2012 Low Level Waste 

Volume 

ft;j m;j 

6.64E+02 1.88E+01 

O.OOE+OO O.OOE+OO 

6.40E+01 1.81E+00 

7.28E+02 2.06E+01 

Curies Shipped 

Curies 

3.28E-02 

O.OOE+OO 

1.83E+01 

1.83E+01 

Major Nuclides for the Above Table: H-3 (2%), Fe-55 (37%), Co-60 (43%), 

Ni-63 (17%), Ce-144 (1 %) 

Dry Active Waste Volume Curies Shipped 

Waste Class ft;j m;j Curies 

A 1.37E+04 3.89E+02 2.46E+00 

B O.OOE+OO O.OOE+OO O.OOE+OO 

C O.OOE+OO O.OOE+OO O.OOE+OO 

ALL 1.37E+04 3.89E+02 2.46E+00 

Major Nuclides for the Above Table: H-3 (1%), C-14 (6%), Cr-51 (6%), Mn-54 (1%), 

Fe-55 (9%), Co-58 (20%), Co-60 (17%), Ni-63 (7%), Zr-95 (6%), Ag-110m (22%), Sb-125 

(2%), Cs-134 (1%),Cs-137 (2%) 

Irradiated Components Volume Curies Shipped 

Waste Class W m;j Curies 

A O.OOE+OO O.OOE+OO O.OOE+OO 

B O.OOE+OO O.OOE+OO O.OOE+OO 

C O.OOE+OO O.OOE+OO O.OOE+OO 

ALL O.OOE+OO O.OOE+OO O.OOE+OO 

Major Nuclides for the Above Table: 

Other Waste: Used oil & soil Volume Curies Shipped 

Waste Class W m;j Curies 

A 8.82E+02 2.50E+01 1.73E+00 

B O.OOE+OO O.OOE+OO O.OOE+OO 

C O.OOE+OO O.OOE+OO O.OOE+OO 

ALL 8.82E+02 2.50E+01 1.73E+00 

Major Nuclides for the Above Table: H-3 (1%), Mn-54 (1%), Fe-55 (8%), Co-58 (58%), 

Co-60 (13%), Ni-63 (13%), Ag-110m (1), Sb-125 (2%), Cs-134 (1%), Cs-137 (2%) 

Page 1 of 2 
Sum of All Low-Level 

Waste Shipped from 

Site 

Waste Class 

A 

B 

C 

ALL 

ATTACHMENT 1 

Palisades - Table A-3 

2012 Low Level Waste 

Volume 

fe m3 

1.53E+04 4.33E+02 

O.OOE+OO O.OOE+OO 

6.40E+01 1.81E+OO 

1.53E+04 4.35E+02 

Curies Shipped 

Curies 

4.22E+OO 

O.OOE+OO 

1.83E+01 

2.25E+01 

Major Nuclides for the Above Table: H-3 (2%). C-14 (1%). Cr-51 (1%). Fe-55 (32%). 

Co-58 (7%). Co-60 (38%). Ni-63 (16%). Zr-95 (1%). Ag110m (2%) 

Page 2 of2 
ATTACHMENT 1 

Palisades· Table A·4 

2012 Dose Assessments, 10 CFR Part 50, Appendix I 

Quarter 1 Quarter 2 Quarter 3 Quarter 4 Yearly 

Liquid Effluent Dose Limit, Total 1.5 mrem 1.5 mrem 1.5 mrem 1.5 mrem 3 mrem 

Body 

Total Body Dose 6.26E-04 9.52E-04 1.32E-04 3.18E-04 2.03E-03 

% Of Limit 0.04% 0.06% 0.01% 0.02% 0.07% 

Liquid Effluent Dose Limit, Any 5 mrem 5 mrem 5 mrem 5 mrem 10 mrem 

Organ 

Organ Dose 1.04E-03 1.21E-03 1.35E-04 4.03E-04 2.79E-03 

% of Limit 0.02% 0.02% 0.00% 0.01% 0.03% 

Gaseous Effluent Dose Limit, 5 mrad 5 mrad 5 mrad 5 mrad 10 mrad 

Gamma Air 

Gamma Air Dose 2.76E-03 6.58E-04 3.71 E-04 1.00E-03 4.79E-03 

% of Limit 0.06% 0.01% 0.01% 0.02% 0.05% 

Gaseous Effluent Dose Limit, 10 mrad 10 mrad 10 mrad 10 mrad 20 mrad 

Beta Air 

Beta Air Dose 1.46E-03 4.42E-04 2.82E-04 5.95E-04 2.78E-03 

% of Limit 0.015% 0.004% 0.003% 0.006% 0.014% 

Gaseous Effluent Dose Limit, Any 7.5 mrem 7.5 mrem 7.5 mrem 7.5 mrem 15 mrem 

Organ (Iodine, Tritium, 

Particulates with >8 day half-life) 

Gaseous Effluent Organ Dose 4.72E-02 1.88E-02 3.45E-02 4.87E-02 1.49E-01 

(Iodine, Tritium, Particulates with 

>8-Day half-life) 

% of Limit 0.63% 0.25% 0.46% 0.65% 0.99% 

Palisades· Table A·5 

2012 EPA 40 CFR Part 190, Individual in the Unrestricted Area 

Whole Body Thyroid Any Other Organ 

Dose Limit 25 mrem 75 mrem 25 mrem 

Dose 8.53E-02 1.39E-02 2.79E-03 

% of Limit 0.34% 0.02% 0.01% 

Page 1 of 1 
ATTACHMENT 2 

BIG ROCK POINT INDEPENDENT SPENT FUEL STORAGE INSTALLATION 

2012 RADIOACTIVE EFFLUENT RELEASE REPORT 

This report provides information relating to radioactive effluent releases and solid 

radioactive waste disposal at Big Rock Point (BRP) for the year 2012. The report 

format is detailed in the BRP Offsite Dose Calculation Manual (ODCM). Effluent 

releases from BRP are controlled by the Defueled Technical Specifications and the 

ODCM requirements. The ODCM was not revised in 2012. 

2012 Operating History 

On January 8,2007, the Nuclear Regulatory Commission (NRC) approved release of 

the former BRP Nuclear Plant property for unrestricted use in accordance with the BRP 

License Termination Plan 1. On April 11, 2007, the license for BRP, DPR-06, was 

transferred to Entergy Nuclear Operations, Inc. 

During 2012, normal Independent Spent Fuel Storage Installation (ISFSI) operations 

continued. There were no operational activities that generated any solid radioactive 

waste. 

Liquid and gaseous effluent monitoring is no longer conducted as the former BRP 

nuclear plant property has been released from the license. Short-lived radionuclides, 

including iodines and noble gas, are neither expected nor reported. 

1. Supplemental Information 

A. Batch Releases 

There were no batch releases of gaseous or liquid effluents during 

2012. All batch releases of radioactive liquids as described in the 

ODCM ceased in 2004. 

B. Abnormal Releases 

There were no abnormal releases from BRP during 2012. 

C. Radioactive Effluent Monitoring Instrumentation 

BRP ODCM currently specifies required actions when less than the 

minimum number of radioactive effluent monitoring instrument 

channels are operable. The ODCM also specifies these actions be 

taken when installed effluent monitoring systems are removed from 

service for decommissioning. 

All plant-installed liquid and gaseous radioactive effluent monitOring 

instrument channels have been permanently removed and dismantled. 

1 Letter from the USNRC dated January8, 2007, "Release of Land from Part 50 License br Unrestricted Use" 

Page 1 of 8 
2. Gaseous Effluents 

Although there were no gaseous effluents released during 2012, Table 2 

provides a summary of all gaseous radioactive effluent monitoring conducted 

during the reporting period as required by the aDCM. 

3. Liquid Effluents 

There were no liquid effluent batch releases during 2012. Table 3 lists and 

summarizes liquid effluent releases in accordance with the aDCM. 

4. Solid Waste 

There was no solid radioactive waste generated or shipped during 2012. 

5. Summary of Radiological Impact on Man 

The aDCM specifies that the annual effluent release report provide potential dose 

calculations based on measured effluent to liquid and gaseous pathways, if 

estimates of dose exceed one millirem to an organ or total body of any individual or 

more than one person-rem to the population within 50 miles. During 2012, there 

were no releases. Therefore, no calculations were required. 

6. affsite Dose Calculation Manual 

The aDCM describes the radiological release requirements for the BRP site. 

There were no revisions to the aDCM in 2012. 

7. Process Control Program (PCP) 

The Process Control Program (PCP) describes solid waste processing and 

disposal methods utilized at the BRP site. The PCP was not revised during 2012. 

Page 2 of 8 
A. GASEOUS 

B. LIQUID 

Number af Releases 

T atal Release Time 

Maximum Release Time 

Average Release Time 

Minimum Release Time 

TABLE 1 

Big Rock Point 

Batch Releases 

January 1, 2012 to December 31 , 2012 

Units 1STQTR 2NDQTR 3RDQTR 

N/A N/A N/A 

Minutes N/A N/A N/A 

Minutes N/A N/A N/A 

Minutes N/A N/A N/A 

Minutes N/A N/A N/A 

Page 3 of 8 

4TH QTR 

N/A 

N/A 

N/A 

N/A 

N/A 
TABLE 2 

Big Rock Point 

Gaseous Effluent Releases 

January 1,2012 to December 31,2012 

1ST 2ND 

A. FISSION AND ACTIVATION GASES Units OTR OTR 

1. Total release Ci N/A N/A 

2. AveraQe release rate for period ~Cilsec N/A N/A 

3. Percent of annual avg EC % N/A N/A 

B IODINES 

1. Total iodine Ci N/A N/A 

2. AveraQe release rate for period ~Ci/sec N/A N/A 

3. Percent of annual avg EC % N/A N/A 

C PARTICULATES 

1. Particulates with haW-life >8 day Ci N/A N/A 

2. Average release rate for period ~Ci/sec N/A N/A 

3. Percent of annual avg EC % N/A N/A 

4. Gross alpha radioactivity Ci N/A N/A 

D TRITIUM 

1. Total Release Ci N/A N/A 

2. Average release rate for period \.lCi/sec N/A N/A 

3. Percent of annual aVQ EC % N/A N/A 

E WHOLE BODY DOSE 

1. Beta Air dose at Site Boundary due to Noble Gases 

(ODCM Section 1 1.3.2 a (1) (2)) mrads N/A N/A 

2. Percent limit % N/A N/A 

3. Gamma Air dose at Site Boundary due to Noble 

Gas lODCM Section 1 1.3.2 a (1 )(2)) mrads N/A N/A 

4. Percent limit % N/A NlA 

F. ORGAN DOSE (ODCM Section 1, 1.3.2b (1) (2)) 

1. Maximum organ dose to pubic based on Critical 

Receptors (child bone) mrem N/A N/A 

2. Percent of limit (7.5 mremlquarter) % N/A N/A 

Page 4 of 8 

3RD 4TH Est Total 

OTR OTR Error % 

N/A N/A 

N/A N/A N/A 

N/A N/A 

N/A N/A 

N/A N/A N/A 

N/A N/A 

N/A N/A 

N/A N/A N/A 

NlA N/A 

N/A N/A 

N/A N/A 

N/A N/A 

N/A N/A 

N/A N/A 

N/A N/A 

N/A N/A 

N/A N/A 

N/A N/A 

N/A N/A 
1. FISSION GASES 

~plon-85m 

Kryplon-87 

Kryplon-88 

Xenon-133 

Xenon-133m 

Xenon-135 

Xenon-135m 

Xenon-138 

T olal for Period 

2. IODINES 

lodine-131 

lodine-132 

lodine-133 

lodine-134 

lodine-135 

T olal for Period 

TABLE 2 

Big Rock Point 

Gaseous Effluent Releases 

January 1,2012 to December 31,2012 

Unils 1STOTR 2NOOTR 3ROOTR 

Ci N/A N/A N/A 

Ci N/A N/A N/A 

Ci N/A N/A N/A 

Ci N/A N/A N/A 

Ci N/A N/A N/A 

Ci N/A N/A N/A 

Ci N/A N/A N/A 

Ci N/A N/A N/A 

Ci N/A N/A N/A 

Ci N/A N/A N/A 

Ci N/A N/A N/A 

Ci N/A N/A N/A 

Ci N/A N/A N/A 

Ci N/A N/A N/A 

Ci N/A N/A N/A 

Page 5 of 8 

4TH OTR 

N/A 

N/A 

N/A 

N/A 

N/A 

N/A 

N/A 

N/A 

N/A 

N/A 

N/A 

N/A 

N/A 

N/A 

N/A 
3. PARTICULATES* 

Chromium-51 

Manganese-54 

Cobalt-58 

Iron-59 

Cobalt-60 

Zinc-65 

Silver -110m 

Cesium-134 

Cesium-137 

Barium-140 

Europium-152 

Strontium-89 

Strontium-90 

Net unidentified beta 

Total 

TABLE 2 

Big Rock Point 

Gaseous Effluent Releases 

January 1,2012 to December 31,2012 

Units 1STOTR 2ND OTR 3RDOTR 

Ci N/A N/A N/A 

Ci N/A N/A N/A 

Ci N/A N/A N/A 

Ci N/A N/A N/A 

Ci N/A N/A N/A 

Ci N/A N/A N/A 

Ci N/A N/A N/A 

Ci N/A N/A N/A 

Ci N/A N/A N/A 

Ci N/A N/A N/A 

Ci N/A N/A N/A 

Ci N/A N/A N/A 

Ci N/A N/A N/A 

Ci N/A N/A N/A 

Ci N/A N/A N/A 

* Particulates with half-life >8 days 

Page 6 of 8 

4TH OTR 

N/A 

N/A 

N/A 

N/A 

N/A 

N/A 

N/A 

N/A 

N/A 

N/A 

N/A 

N/A 

N/A 

N/A 

N/A 
TABLE 3 

Big Rock Point 

Liquid Effluent Releases 

January 1,2012 to December 31,2012 

A. FISSION AND ACTIVATION PRODUCTS Units 1ST OTR 2NDOTR 

1. Total release (not including tritium. gases, alpha) Ci N/A N/A 

2. Average diluted concentration during period uCi/ml N/A N/A 

3. Percent of EC % N/A N/A 

B TRITIUM 

1. Total release Ci N/A N/A 

2. Average diluted concentration during period j!Cilml N/A N/A 

3. Percent of EC % N/A N/A 

C DISSOLVED AND ENTRAINED GASES 

1. Total release Ci N/A N/A 

2. Average diluted concentration during period uCi/ml N/A N/A 

3. Percent of EC % N/A N/A 

D. GROSS ALPHA RADIOACTIVITY 

E. VOLUME OF WASTE RELEASED 

(Prior to dilution) Liters N/A N/A 

F. VOLUME OF DILUTION WATER USED DURING 

PERIOD Liters N/A N/A 

G. MAXIMUM DOSE COMMITMENT WHOLEBODY mrem N/A N/A 

Percent of aDCM Section 1, 2.3.2 a (1.5 mrem) % N/A N/A 

H. MAXIMUM DOSE COMMITMENT - ORGAN Mrem N/A N/A 

Percent of aDCM Section 1, 2.3.2 b (3.0 mrem) % N/A N/A 

Page 7 of 8 

Est Total 

3RDOTR 4TH OTR Error % 

N/A N/A 

N/A 

N/A N/A 

N/A N/A 

N/A N/A 

N/A 

N/A N/A 

N/A N/A 

N/A N/A 

N/A 

N/A N/A 

N/A N/A 

N/A N/A 

N/A N/A 

N/A N/A 

N/A N/A 

N/A N/A 

N/A N/A 
1. NUCLIDES 

RELEASED 

Chromium-51 

Manganese 54 

Cobalt-58 

Iron-59 

Cobalt-60 

Zinc-65 

Strontium-89 

Strontium-90 

Molybdenum-99 

Silver-110m 

lodine-131 

Cesium-134 

Cesium-137 

Antimony-125 

Tin-113 

Net Unidentified Beta 

Fission & Activation 

Product Total 

Xenon-133 

Tritium 

Grand Total 

TABLE 3 

Big Rock Point 

Liquid Effluent Releases 

January 1,2012 to December 31,2012 

Units 1STOTR 2ND OTR 3RDOTR 

Ci - - -

Ci - - -

Ci - - -

Ci - - -

Ci - - -

Ci - - -

Ci - - -

Ci - - -

Ci - - -

Ci - - -

Ci - - -

Ci - - -

Ci - - -

Ci - - -

Ci - - -

Ci - - -

Ci - - -

Ci - - -

Ci - - -

Ci - - -

Page 8 of 8 

4THOTR 

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-

-