May 6, 2008 

MEMORANDUM TO: James W. Andersen, Chief 

 Performance Assessment Branch 

 Division of Inspection and Regional Support 

 Office of Nuclear Reactor Regulation 

FROM: Nathan Sanfilippo, Reactor Operations Engineer /RA/ 

 Performance Assessment Branch

 Division of Inspection and Regional Support 

 Office of Nuclear Reactor Regulation 

 

SUBJECT: SUMMARY OF THE REACTOR OVERSIGHT PROCESS WORKING 

 GROUP PUBLIC MEETING HELD ON APRIL 16 AND 17, 2008 

On April 16 and 17, 2008, the staff hosted the monthly Reactor Oversight Process (ROP) 

Working Group public meeting. The attendance list for the April 16 meeting is contained in 

Enclosure 1 and the agenda is contained in Enclosure 2. The attendance list for the April 17 

meeting is contained in Enclosure 3 and the agenda is contained in Enclosure 4. 

Summary of the April 16, 2008 Reactor Oversight Process Working Group Meeting

Discussions by the meeting attendees included: the safety culture lessons learned and the 

status of the NRC cross-cutting issue task force effort; potential non-safety culture related 

changes to Inspection Manual Chapter (IMC) 0305, “Operating Reactor Assessment Program;” 

an update on NRC actions regarding RIS 2007-21, “Adherence to Licensed Power Limits;” 

potential changes to IMC 0612, “Power Reactor Inspection Reports;” an upcoming Temporary 

Instruction on the Drill and Exercise Performance Performance Indicator (PI); and various 

proposed changes to Nuclear Energy Institute (NEI) 99-02, “Regulatory Assessment 

Performance Indicator Guidance.” 

The staff began the meeting by discussing logistics for the April 17, 2008, meeting on safety 

culture enhancements to the ROP. The staff then highlighted various non-safety culture related 

changes to IMC 0305. These included double counting in the action matrix, closing parallel 

white performance indicator and greater than green findings, the timing of findings leading to the 

repetitive degraded cornerstone column, and the timing of supplemental inspections. The staff 

is looking to make these changes in the August/September timeframe. 

CONTACT: Nathan Sanfilippo, NRR/DIRS 

 301-415-3951 
J. Andersen - 2 -

The staff also discussed some longer-term considerations for IMC 0305. These included: 

whether substantive cross cutting issues be accounted for in the action matrix; whether 

precursors should be used in the assessment process; the definition of column 4; whether 

greater than green PIs that go in and out should be held open until the supplemental inspection 

is completed; whether greater than green PIs can be closed after the supplemental inspection is 

complete; and the link between traditional enforcement and the action matrix. 

NRC staff provided a status update of activities surrounding RIS 2007-21. The staff continues 

to draft guidance for plants that go above the maximum thermal power limits. NEI submitted 

their draft guidance on this issue. The staff will present its draft guidance during the May ROP 

meeting. 

The staff discussed an effort to make changes and enhancements to IMC 0612. While no major 

changes are planned, the staff highlighted various updates to definitions, process 

improvements, and integration of the significant determination process/enforcement policy with 

IMC 0612. More specific proposed changes to IMC 0612 will be presented during the June 

ROP monthly meeting. 

The staff introduced an upcoming Temporary Instruction (TI) regarding the Drill and Exercise 

Performance (DEP) PI. This TI will ask inspectors, during the next emergency preparedness 

baseline inspection, to gather each licensee’s DEP PI data from the previous eight quarters and 

break the numbers down into opportunities for classifications, notifications, and protective action 

recommendations. Currently, DEP PI data is submitted summing all three areas together. The 

NRC staff is investigating whether poor performance in one area could be masked by increasing 

the opportunities in another area. Data collected will inform inspection practices going forward. 

This TI should be issued in May. 

Staff and industry then discussed various changes to NEI 99-02. The NRC provided Enclosure 

5 to propose clarifications to NEI 99-02 relating to the definition of “time of discovery” for the 

MSPI. NEI will consider this proposal and will further discuss these issues at the May ROP 

monthly meeting. Meeting participants also agreed to discuss the topics of emergency diesel 

generator test failures, mission times, and environmental unplanned power changes during the 

May ROP meeting. 

NEI provided Enclosure 6 to propose clarifications to NEI 99-02 relating to maintenance-induced 

damage/issues found during post-maintenance testing prior to returning the component to 

functional status. Discussion ensued and the staff provided Enclosure 7 to respond to the 

industry’s proposal. NEI will review the proposed changes and will further discuss these issues 

at the May ROP monthly meeting. 

NEI provided Enclosure 8 to introduce a proposed change to the Emergency Response 

Organization (ERO) PI. This whitepaper will be discussed in detail during the May ROP 

meeting. 

NEI provided Enclosure 9 to propose changes to IMC 0305 addressing protracted performance 

indicator results. The staff will consider this information as it moves forward with draft changes 

to IMC 0305. 
J. Andersen - 3 -

The staff and NEI discussed the logistics of implementing changes to NEI 99-02. As changes to 

the guidance are mutually agreed upon, they will be introduced and approved as frequently 

asked questions (FAQs) in order to be implemented prior to the next revision of NEI 99-02. 

Recently agreed upon changes will appear in the May FAQ package. 

The staff also described potential revisions to IMC 0608, “Performance Indicator Program,” 

regarding the application of PIs for plants restarting from extended shutdown or for newly built 

plants. The staff will present these draft revisions at future ROP meetings. 

A corrected FAQ Log from the March meeting is contained in Enclosure 10. The attendees then 

discussed open performance indicator FAQs as provided by NEI in Enclosure 11. FAQs 76.1, 

76.2, and 76.3 were given final approval. The staff and industry reached tentative approval on 

FAQs 76.0, 77.0, 78.1, 79.0, 79.2, and 79.3. FAQ 80.1 was introduced and no decision was 

made. The NRC staff’s proposed responses to FAQs 76.1, 76.2, 76.3, 79.0, and 79.3 are 

included as Enclosure 12. 

The status of the open draft FAQs are as follows: 

TempNo. PI Topic Status Plant/ Co. 

76.0 IE03 Discovery of an Off-normal 

condition 

Tentative 

Approval 

Quad Cities 

76.1 IE03 Cladophora Algae Intrusion 

Event on 10/13 

Final Approval FitzPatrick 

76.2 IE03 Cladophora Algae Intrusion 

Event on 11/6 

Final Approval FitzPatrick 

76.3 MS06 EDG Pressure Switch Failure Final Approval Byron 

77.0 IE03 Grassing Event Tentative 

Approval 

Salem 

78.1 IE03 Storm Induced 

Marine/Biological Intrusion 

Tentative 

Approval 

Diablo Canyon 

79.0 IE03 Over-Voltage due to 

Lightening 

Tentative 

Approval 

Robinson 

79.2 IE03 Threadfin Shad Run Tentative 

Approval 

Browns Ferry 

79.3 IE03 Historical Downpowers Tentative 

Approval 

Browns Ferry 

80.1 IE01 Reactor Power Indication Introduced 

and 

Discussed 

Columbia 

An action item list compiled by NEI for tracking various ongoing issues of the working group is 

included as Enclosure 13. 
J. Andersen - 4 -

Summary of the April 17, 2008 Meeting on Safety Culture Enhancements to the Reactor 

Oversight Process

The purpose of the meeting was for the staff to provide draft changes in safety culture related 

ROP guidance documents and to obtain initial external stakeholder questions and comments. 

The meeting slides are included as Enclosure 14. The staff provided working drafts of IMC 

0305, “Operating Reactor Assessment Program” and IP 95003, “Supplemental Inspection for 

Repetitive degraded Cornerstones, Multiple degraded Cornerstones, Multiple Yellow Inputs or 

One Red Input” (Enclosures 15 through 22). Enclosure 23 contains a staff provided summary of 

lessons learned inputs to the ROP safety culture assessment. The staff also provided an 

overview of intended safety culture related changes to IMC 0612, “Power Reactor Inspection 

Reports” and IP 71152, “Identification and Resolution of Problems.” The draft changes and the 

reasons for proposing the changes were discussed with the external stakeholders. 

Changes are proposed in IMC 0305 to provide for NRC consideration of additional follow-up 

actions in response to consecutive assessment letters issued with the same substantive crosscutting issue that has the same cross-cutting aspect. The more significant change to IP 95003 

involves the proposed approach for the NRC to conduct a graded safety culture assessment. 

The NRC assessment scope and depth would result from an evaluation of the licensee thirdparty safety culture assessment methodology, implementation, and results. 

NEI stated that the industry plans to develop a guidance document that will do the following: 1) 

capture the industry best practices for tracking and trending cross-cutting aspects, 2) provide 

guidance for licensees on what actions they should take when a substantive cross-cutting issue 

is identified at their plant, and 3) provide guidance for licensees on the methodology to conduct 

third party safety culture assessments and on the qualifications/independence of the assessors. 

NEI stated the desire to work with the staff as the guidance document is developed, in particular 

so that staff criteria and expectations for the third party safety culture assessment can be 

addressed. The goal is for the NRC to be able to endorse the guidance document. 

The NRC expressed that they will be willing to work with industry as the industry develops the 

methodology guidance document as the staff sees the benefits of having an endorsed guidance 

document. 

NEI expressed the belief that the use of focused problem identification and resolution 

inspections are an appropriate way to follow-up on substantive cross-cutting issues and to 

validate their closure. NEI questioned the appropriateness of assigning the safety culture 

components during supplemental inspection IP 95002, “Inspection of One Degraded 

Cornerstone or any Three White Inputs in a Strategic Performance Area,” given the small 

inspection sample. NEI recommended removing the safety culture reviews from both IP 95001 

and IP 95002. 

NEI provided a chart, included as Enclosure 24, depicting the historical trend in the number of 

plants receiving substantive cross-cutting issues (NRC note - the gross number of cross-cutting 

themes was actually depicted) in relationship to the number of plants in the various columns of 

the ROP action matrix. NEI expressed a concern in the most recent assessment cycle with the 

marked increase with the number of substantive cross-cutting issues while on a national basis 

the overall fleet performance as measured by the number of plants in the licensee response 
J. Andersen - 5 -

column has improved. NEI questioned whether the substantive cross-cutting issues are yielding 

the desired insights on plant performance. NEI recognizes that the intent is to try to preclude 

declining performance which is hard to correlate with the available data. The staff indicated that 

they routinely self-evaluate whether the assessment process is functioning as intended. 

Some of the initial comments on the IMC 0305 draft changes and the overview of the 

contemplated changes to the safety culture components included: 1) licensee causal analyses 

are typically carried out to the cross-cutting aspect level rather than at the cross-cutting 

component level, 2) the four “other” safety culture components were originally not included as 

cross-cutting components because of various constraints as described in Regulatory Issue 

Summary 2006-13, "Information on the Changes Made to the Reactor Oversight Process to 

More Fully Address Safety Culture,” 3) the staff needs to consider carefully the substantive 

cross-cutting issue threshold given the large number of plants now receiving them, 4) need to 

consider whether special substantive cross-cutting issue thresholds are needed for multi-unit 

sites (need to consider how cross-cutting aspects are compiled on a plant and site basis), 5) 

improving the component definitions by eliminating duplication could lead to an increase in the 

number of substantive cross-cutting issues, and 6) staff needs to consider the effect of changes 

to the components on existing substantive cross-cutting issues and how to handle continuing 

issues after revisions are made. 

The staff acknowledged that transition issues will need to be considered if a proposal is made to 

tag findings at the component level. If the staff develops approaches that are different from that 

described in RIS 2006-13, it is recognized that the changes in approach will need explanation. 

As part of its considerations the staff indicated that the threshold for a substantive cross-cutting 

issue would need to change if findings were tagged at the component level. 

Some of the initial comments on the IP 95003 draft changes included: 1) need for clarification 

on the staff expectations for the qualification of licensee third party safety culture assessors and 

whether it is appropriate to expect the same qualifications as for NRC safety culture assessors, 

2) given the large number of findings that can result from a typical IP 95003, participants 

questioned the appropriateness of assigning cross-cutting aspects to the large number of 

resultant findings, 3) a concern that licensees also need to perform safety culture assessments 

in accordance with INPO criteria and whether it was possible for the NRC and INPO to agree on 

the criteria to avoid duplication of effort, 4) if not well managed, the greater use of unresolved 

items could result in a lot of work for both the NRC and the industry, 5) the staff should consider 

the unintended consequences of allowing more unresolved items, 6) the staff should not 

implement a work around by allowing greater use of unresolved items, 7) suggested that the 

staff utilize information from licensee incentive programs to see if they encourage the 

appropriate behaviors instead of looking at individual performance appraisals to derive safety 

culture assessment insights, and 8) that the presence of inspectors and assessors, and their inprocess questions they ask of the licensee can add to the licensee burden and can influence the 

outcome of the licensee efforts and NRC conclusions/ assessments. 

Some general initial comments included: 1) need for the staff to roll out guidance document 

changes in a methodical manner with regional training, 2) need inspectors to describe the logic 

why they didn’t assign a cross-cutting aspect as stakeholders are owed that information, and 3) 

need for the staff to be very careful how NRC qualitative precursors are used in the assessment 

process as they are very subjective and can mean different things at different sites. 
J. Andersen - 6 -

The staff agreed that both internal inspector training and most likely workshops with the industry 

Regional Utility Groups will be appropriate for the next round of changes. 

The staff indicated their tentative plans to present the remaining ROP safety culture draft 

document changes (IMC 0305 safety culture components, IMC 0612, IP 95001, IP 95002, and 

IP 71152) during an ROP monthly public meeting on May 14, 2008. 

The staff agreed to extend the external stakeholder follow-up comment period for IP 95003 until 

May 23, 2008. The follow-up comment period for IMC 0305 (and the other safety culture related 

ROP guidance document changes) will be determined at the next public meeting when those 

draft changes will be discussed. 

The staff thanked the external stakeholders for their participation and constructive initial 

comments on the draft guidance document changes. 

The date for the next meeting of the ROP Working Group is May 14, 2008. Future ROP 

monthly meeting dates include June 18, 2008, July 16, 2008, and August 27, 2008. 

Enclosures: 

1. Attendance List – April 16, 2008 

2. Agenda – April 16, 2008 

3. Attendance List – April 17, 2008 

4. Agenda – April 17, 2008 

5. NRC Response to Proposed Change to NEI 99-02 to Address “time of discovery” 

6. Proposed Change to NEI 99-02 to Address Failures Identified During PMT 

7. NRC Response to Proposed Change to NEI 99-02 for PMT 

8. NEI Whitepaper Proposing a Change to NEI 99-02 for the ERO PI 

9. Proposed Guidance Change to IMC 0305 to Address Protracted PI Results 

10. Corrected FAQ Log from March 2008 

11. FAQ Log 

12. NRC Proposed Responses to Various FAQs 

13. NEI ROP Working Group Action List – April 2008 

14. April 17, 2008, Meeting Slides 

15. Proposed Markup to Inspection Procedure 95003 

16. Draft Enclosure 95003.02-A 

17. Draft Enclosure 95003.02-B 

18. Draft Enclosure 95003.02-C 

19. Draft Enclosure 95003.02-D 

20. Draft Enclosure 95003.02-E 

21. Draft Enclosure 95003.02-F 

22. Proposed Markup to Inspection Manual Chapter 0305 

23. Lessons Learned Input for the ROP Safety Culture Evaluation 

24. NEI ROP Action Matrix Placement 
J. Andersen - 6 -

The staff agreed that both internal inspector training and most likely workshops with the industry 

Regional Utility Groups will be appropriate for the next round of changes. 

The staff indicated their tentative plans to present the remaining ROP safety culture draft 

document changes (IMC 0305 safety culture components, IMC 0612, IP 95001, IP 95002, and IP 

71152) during an ROP monthly public meeting on May 14, 2008. 

The staff agreed to extend the external stakeholder follow-up comment period for IP 95003 until 

May 23, 2008. The follow-up comment period for IMC 0305 (and the other safety culture related 

ROP guidance document changes) will be determined at the next public meeting when those draft 

changes will be discussed. 

The staff thanked the external stakeholders for their participation and constructive initial 

comments on the draft guidance document changes. 

The date for the next meeting of the ROP Working Group is May 14, 2008. Future ROP monthly 

meeting dates include June 18, 2008, July 16, 2008, and August 27, 2008. 

Enclosures: 

1. Attendance List – April 16, 2008 

2. Agenda – April 16, 2008 

3. Attendance List – April 17, 2008 

4. Agenda – April 17, 2008 

5. NRC Response to Proposed Change to NEI 99-02 to Address “time of discovery” 

6. Proposed Change to NEI 99-02 to Address Failures Identified During PMT 

7. NRC Response to Proposed Change to NEI 99-02 for PMT 

8. NEI Whitepaper Proposing a Change to NEI 99-02 for the ERO PI 

9. Proposed Guidance Change to IMC 0305 to Address Protracted PI Results 

10. Corrected FAQ Log from March 2008 

11. FAQ Log 

12. NRC Proposed Responses to Various FAQs 

13. NEI ROP Working Group Action List – April 2008 

14. April 17, 2008, Meeting Slides 

15. Proposed Markup to Inspection Procedure 95003 

16. Draft Enclosure 95003.02-A 

17. Draft Enclosure 95003.02-B 

18. Draft Enclosure 95003.02-C 

19. Draft Enclosure 95003.02-D 

20. Draft Enclosure 95003.02-E 

21. Draft Enclosure 95003.02-F 

22. Proposed Markup to Inspection Manual Chapter 0305 

23. Lessons Learned Input for the ROP Safety Culture Evaluation 

24. NEI ROP Action Matrix Placement 

ADAMS Accession No.: Package - ML081200480 Memo - ML081190536 Enclosure 5 - ML081200512 

 Enclosure 6 - ML081200531 Enclosure 7 - ML081200567 Enclosure 8 - ML081200541 

 Enclosure 9 - ML081200593 Enclosure 10 - ML081200546 Enclosure 11 - ML081200551 

 Enclosure 12 - ML081200555 Enclosure 13 - ML081200440 Enclosure 14 - ML081120420 

 Enclosure 15 - ML081020491 Enclosure 16 - ML081020608 Enclosure 17 - ML081020675 

 Enclosure 18 - ML081020682 Enclosure 19 - ML081020688 Enclosure 20 - ML081020715 

 Enclosure 21 - ML081020821 Enclosure 22 - ML081010224 Enclosure 23 - ML081010229 

 Enclosure 24 - ML081200605 

OFFICE NRR/DIRS NRR/DIRS NRR/DIRS

NAME NSanfilippo TKobetz JAndersen

DATE 05/01/08 05/01/08 04/06/08

OFFICIAL RECORD COPY 
Memo to James W. Andersen from Nathan T. Sanfilippo dated _May 6, 2008_________ 

DISTRIBUTION: 

PUBLIC

DRoberts 

ABoland DDube 

AVegel ACampbell DAyres 

GShear PAppignani IPAB Distribution 

CPederson DLew IRIB Distribution 

DChamberlain HChristensen RCaniano 

ISchoenfeld LWert MGamberoni 

JClifford KKennedy SWest 

TPruett RCroteau
ENCLOSURE 1 

ATTENDANCE LIST 

INDUSTRY/STAFF ROP PUBLIC MEETING 

April 16, 2008 

NAME AFFILIATION 

1 John Butler NEI 

2 Sue Simpson NEI 

3 Lenny Sueper NMC 

4 Randy Hart Duke 

5 Duane Kanitz STARS 

6 Al Haeger Exelon 

7 Robin Ritzman FENOC 

8 Fred Mashburn TVA 

9 Bob Gramm NRC 

10 Jim Peschel FPL 

11 Bryan Ford Entergy 

12 Don Hickman NRC 

13 Tim Kobetz NRC 

14 Nathan Sanfilippo NRC 

15 Julie Keys NEI 

16 Ken Heffner Progress 

17 Jim Andersen NRC 

18 Bob Hanley Dominion 

19 Ned Tyler Constellation 

20 Brian McCabe Progress 

21 Fred Brown NRC 

22 Edward Weinkam NMC 

23 John Thompson NRC 

24 Mark Giles Entergy 

25 Bruce Thompson SCE&G 

26 Don Dube NRC 

27 Dave Midlik Southern Nuclear 

28 Rich Clemens OPPD – Fort Calhoun 

29 Zentan Yamashita NRC 

30 Dayne Brophy PPL Susquehanna 

31 Arthur Salomon NRC 

32 Steve LaVie NRC 

33 Ron Schmitt NRC 
ENCLOSURE 2 

REACTOR OVERSIGHT PROCESS (ROP) 

MONTHLY PUBLIC MEETING 

AGENDA

April 16, 2008 - 9:00 a.m. - 4:00 p.m. – NRC OWFN Commissioners’ Hearing Room 

 9:00 – 9:05 AM Introduction and Purpose of Meeting 

 9:05 – 9:45 AM Discussion of Performance Assessment Branch Topics 

1. Safety Culture (assessment status) 

2. Possible changes to Inspection Manual Chapter (IMC) 0305, 

“Operating Reactor Assessment Program” – non-safety culture 

3. Other 

 9:45 – 10:30 AM Reactor Inspection Branch Topics 

1. Regulatory Issue Summary (RIS) 2007-21 (update) 

2. General topics of interest in the inspection area 

3. Upcoming EP Temporary Instruction on DEP PI 

4. Other 

10:30 – 10:45 AM Public Input 

10:45 – 12:00 PM Discussion of Performance Indicator Topics 

1. MSPI Unavailability Reviews 

2. Potential NEI 99-02 guidance changes 

• MSPI time of discovery 

• MSPI EDG test failures 

• Maintenance-induced PMT issues 

• Environmental unplanned power changes 

• EP – Counting ERO participation for members in training 

3. Other 

12:00 – 1:00 PM Lunch 

1:00 – 2:30 PM Discussion of Open and New PI Frequently Asked Questions (FAQs) – 

Note topic may be moved before lunch if meeting is ahead of schedule 

The latest draft FAQs are located on the public web at 

http://www.nrc.gov/NRR/OVERSIGHT/ASSESS/draft_faqs.pdf 

This list is subject to change the day before the meeting based on 

availability of new draft FAQs provided by the Nuclear Energy Institute 

 2:30 – 2:45 PM Public Input 

 2:45 – 3:15 PM Continuation Discussion of Open and New PI FAQs 

 3:15 – 3:45 PM Future Meeting Dates, ROP Working Group Action List Status, and 

Future Topics 

 3:45 – 4:00 PM Public Input 

Meeting To Adjourn Following Public Input 
ENCLOSURE 3 

ATTENDANCE LIST 

SAFETY CULTURE ROP PUBLIC MEETING 

April 17, 2008 

NAME AFFILIATION 

1 John Butler NEI 

2 Sue Simpson NEI 

3 Lenny Sueper NMC 

4 Randy Hart Duke 

5 Duane Kanitz STARS 

6 Al Haeger Exelon 

7 Robin Ritzman FENOC 

8 Fred Mashburn TVA 

9 Bob Gramm NRC 

10 Jim Peschel FPL 

11 Bryan Ford Entergy 

12 Bruce Boger NRC 

13 Tim Kobetz NRC 

14 Nathan Sanfilippo NRC 

15 Julie Keys NEI 

16 Ken Heffner Progress 

17 Jim Andersen NRC 

18 Bob Hanley Dominion 

19 Ned Tyler Constellation 

20 Brian McCabe Progress Energy 

21 Fred Brown NRC 

22 Edward Weinkam NMC 

23 John Thompson NRC 

24 Mark Giles Entergy 

25 Bruce Thompson SCE&G 

26 June Cai NRC 

27 Dave Midlik Southern Nuclear 

28 Rich Clemens OPPD – Fort Calhoun 

29 Zentan Yamashita NRC 

30 Dayne Brophy PPL Susquehanna 

31 Ann Ramey-Smith NRC 

32 Robert Pascarelli NRC 

33 David Solorio NRC 

34 Paul Fleming NPPD 

35 Jeff Reinhart INPO 

36 Lou Larragoite Constellation 

37 Mike Shea APS 

38 Mark Rendmeyer Centrec Corporation 

39 Greag Halnon First Energy 

40 Steve Petzel Ameren UE 
- 2 - 

41 Jac Goodman ITTA, Inc. 

42 Tod Moser STARS 

43 Jerry Phifer Constellation 

44 Tony Harris STARS 

45 David Lochbaum UCS 

46 David Benyak Exelon 

47 Martin Ruscak DNV 

48 Jamie Mallon PSEG 

49 Patrick Boyle NRC 

50 Chuck Thebaud Morgan Lewis 

51 Isabelle Schoenfeld NRC 

52 Constance Perin MIT 

53 Diane Sieracki Dominion 

54 Time Hope Luminant 

55 Howard Levin Synergy 

56 Tony Pietrangelo NEI 

57 Deann Raleigh LIS Scientech 

58 Bill Nelson DNV 

59 Pete Wells FPL 

60 David Allsopp NRC 

61 David Desaulniers NRC 

62 Molly Keefe NRC 

63 Russ Bell NEI 

64 Paul Pieringer NRC 

65 Mike Headrick PSEG 

66 Jenny Weil McGraw-Hill 

67 Paul Bonnett NRC 

68 Henry Butterworth NRC 
ENCLOSURE 4 

DISCUSSION OF PROPOSED CHANGES TO REACTOR 

OVERSIGHT PROCESS SAFETY CULTURE GUIDANCE 

PUBLIC MEETING AGENDA

April 17, 2008 - 9:00 a.m. - 4:00 p.m. – TWFN Auditorium 

9:00 – 9:15 AM Introductions and Meeting Ground Rules 

9:15 – 9:30 AM Purpose of Meeting and Overview of Lessons Learned Process 

9:30 – 10:15 AM Discuss Draft Inspection Manual Chapter (IMC) 0305 Revisions and 

Initial External Stakeholder Comments 

10:15 – 10:30 AM Break 

10:30 – 11:30 AM IMC 0305 Discussion (continued) 

11:30 – 12:00 PM Discuss Draft Inspection Procedure (IP) 95003 Revisions and Initial 

External Stakeholder Comments 

12:00 – 1:00 PM Lunch 

1:00 – 1:45 PM IP 95003 Discussion (continued) 

1:45 – 2:15 PM Discuss Draft IMC 0612 Revisions and Initial External Stakeholder 

Comments 

2:15 – 2:30 PM Break 

2:30 – 3:00 PM Discuss Draft IP 71152 Revisions and Initial External Stakeholder 

Comments 

3:00 – 4:00 PM Opportunity for External Stakeholder Comments and Request for 

Written Comments on Draft Revisions