ML20206S674

Informs That During 980930-1002 ACRS 456th Meeting,Several Matters Discussed,Listed Repts & Ltrs Completed & Authorized Executive Director to Transmit Noted Memoranda

ML20206S674
Person / Time
Site:	Arkansas Nuclear
Issue date:	10/29/1998
From:	Seale R Advisory Committee on Reactor Safeguards
To:	Shirley Ann Jackson, The Chariman NRC COMMISSION (OCM)
References
ACRS-SL-0465, ACRS-SL-465, NUDOCS 9905210196
Download: ML20206S674 (7)

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• • • • • October 29,1998 The Honorable Shirley Ann Jackson Chairman U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001

SUMMARY

REPORT- FOUR HUNDRED FIFTY-SIXTH MEETING OF THE ADVISORY COMMITTEE ON REACTOR SAFEGUARDS, SEPTEMBER 30-OCTOBER 2,1998, AND OTHER RELATED ACTIVITIES OF THE COMMITTEE During its 456* meeting, September 30-October 2,1998, the Advisory Committee on Reactor Safeguards (ACRS) discussed several matters and completed the following reports and letters. In addition, the Committee authorized Dr. Larkins, Executive Director, to transmit the memoranda noted below.

REPORTS

- Imosct of Probabilistic Risk Assessment Results and insiahts on the Reaulatory System (Report to Shirley Ann Jackson, Chairman, NRC, from R. L. Seale, Chairman, ACRS, dated September 30,1998)

The Nuclear Enerav institute's Petition for Rulemakina to Amend Paraaraoh (a) of 10 CFR 50.54. Conditions of Licenses (Report to Shirley Ann Jackson, Chairman, NRC, from R. L. Seale, Chairman, ACRS, dated October 20,1998)

LETTERS

- Risk-Informed Pilot Acolication for Hydroaen Monitorina at Arkansas Nuclear One.

Units 1 and 2 (Letter to L. Joseph Callan, Executive Director for Operations, NRC, from R. L. Seale, Chairman, ACRS, dated October 14,1998)

- Proposed Priority Rankinos of Generic Safety issues: Tenth Group (Letter to L.

Joseph Callan, Executive Director for Operations, NRC, from R. L. Seale, Chairman, ACRS, dated October 16,1998)

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The Honorable Shirley Ann Jackson 2 MEMORANDA a

Proposed Rule "Chanoes to Reauirements for Environmental Review for Renewal of Nuclear Power Plant Operatina Licenses (10 CFR Part 51)"(Memorandum to L.

Joseph Callan, Executive Director for Operations, NRC, from John T. Larkins, Executive Director, ACRS, dated October 6,1998)

Proposed Final Amendment to 10 CFR Part 55. " Initial Licensed Operator Examination Reauirements"(Memorandum to L. Joseph Callan, Executive Director for Operations, NRC, from John T. Larkins, Executive Director, ACRS, dated October 6,1998)

Procosed Final Revisions to Reaulatorv Guide (RG) 1.84 (Desian and Fabrication Code Case Acceptabilitv). RG 1.85 (Materiais Code Case Acceptabilitv). and RG i

1.147 (Inservice inspection Code Case Acceptability) (Memorandum to L. Joseph Callan, Executive Director for Operations, NRC, from John T. Larkins, Executive Director, ACRS, dated October 7,1998)

Proposed Final Reaulatorv Guide DG-1029. Revision 1.7. " Guidelines for Evaluatina Electromaanetic and Radio-Freauency Interference in Safetv-Related Instrumentation and Control Systems" (Memorandum to L. Joseph Callan, Executive Director for Operations, NRC, from John T. Larkins, Executive Director, ACRS, dated October 8,1998)

HIGHLIGHTS OF KEY ISSUES CONSIDERED BY THE COMMITTEE

1. NEl Petition to Modify 10 CFR 50.54(a) Related to Quality Assurance Proarams The Committee heard presentations by and held discussions with representatives of the NRC staff and the Nuclear Energy Institute (NEI) regarding the NEl petition to modify 10 CFR 50.54(a) related to quality assurance (QA) programs. The petition sought to broaden the scope of allowed unilateral changes that would not require prior NRC review and approval. NEl proposed to amend 10 CFR 50.54(a) to make changes exempt if they do not involve an unreviewed safety question as defined in 10 CFR 50.59 (Changes, tests and experiments).

The NRC staff agreed that 10 CFR 50.54(a) should be revised to allow a broader scope of unilateral changes to QA programs without prior NRC review and approval, but the use of 10 CFR 50.59 criteria to make such changes is not appropriate. Instead, the staff has proposed a two-fold approach that consists of a direct final rulemaking to modify 10 CFR 50.54(a) and an alternate process for changes that the licensees could voluntarily implement for further relief. NEl

1 The Honorable Shirley Ann Jackson 3 gen'erally supports the NRC staff's proposed approach, but expresses concern about the staff's proposed monitoring of the performance of the QA programs.

Conclusion The Committee issued a report to Chairman Jackson, dated October 20,1998, on this issue.

2. Risk-Informed Pilot Acolication for Hydroaen Monitorina at Arkansas Nuclear One.

Units 1 and 2 The Committee heard presentations by and held discussions with representatives of the NRC staff and the nuclear industry regarding a pilot application of a risk-informed approach for post-accident hydrogen monitoring at Arkansas Nuclear One (ANO), Units 1 and 2. The staff stated that the Entergy Operations, Inc., ANO licensee, requested that the required time for activating the hydrogen monitoring system, after start of the safety injection, be changed from 30 minutes to 90 minutes to reduce burdens on operators at critical times. This request was made in accordance with the NEl Task Zero of the proposed Risk-Informed, Performance-Based Regulation Pilot Program. The staff has approved the licensee's proposed relief request by issuing a confirmatory order. The staff further stated that similar requests are expected from other plants. The Committee also discussed this issue with a representative from Performance Technology, Inc.

Conclusion The Committee issued a letter to the Executive Director for Operations, dated October 15,1998, on this matter.

3. Performance Technoloav. Inc.. Views on Criteria for Safety Decisions The Committee heard presentations by and held discussions with a representative of Performance Technology, Inc., on criteria for safety decisions. The Committee discussed Performance , Technology, Inc., views on Regulatory Guide 1.174 (formerly DG-1061) for risk-informed decisionmaking. The Committee also discussed issues contained in the ACRS report dated May 11,1998, regarding the elevation of core damage frequency (CDF) to a fundamental safety goal and possible revision to the Commission's Safety Goal Policy Statement.

Conclusion This briefing was for information only. No Committee action was required.

o The Honorable Shirley Ann Jackson 4

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4. Indostry Initiatives to Certifv Probabilistic Risk Assessments The Committee heard presentations by and held discussions with representatives of the NRC staff and NEl regarding the industry initiatives to certify probabilistic

- safety assessments (PSAs), otherwise known as probabilistic risk assessments (PRAs). The Committee discussed staff plans to consider certified PSAs in regulatory decisionmaking. The Committee also discussed the peer review process and possible integration of the certification process into the ASME/ANS Standard being developed for PSA quality.

Conclusion This briefing was for information only. The Committee plans to discuss the proposed ASME/ANS Standard on PSA quality during a future meeting.

5. Intearated Review of Assessment Processes and Proposed imorovements to the Senior Manaaement Meetina Process The Committee heard presentations by and held discussions with representatives of the NRC staff and the NEl conceming the status of activities associated with the integrated review of assessment processes and proposed improvements to the Senior Management Meeting (SMM) process. The staff presented an outline of the topdown approach for the SMM process and the initial results of the September 28-October 1,1998 public workshop. NEl expressed support for the staff's topdown approach and plans to work with the staff to furtherimprove the SMM process. NEl noted that the area of least agreement is related to the integration of performance indicators with inspection results.

1 The Committee discussed the logical consistency among the cornerstones i identified by the staff, the interrelationship among the crosscutting issues, and the associated regulatory inspection process.

Conclusion l This briefing was for information only. The Committee plans to continue its discussion of this matter during the December 1998 ACRS meeting.

RECONCILIATION OF ACRS COMMENTS AND RECOMMENDATIONS The Committee discussed the response from the NRC Executive Director for Operations dated September 14, 1998, responding to ACRS comments and recommendations included in the ACRS report dated July 24,1998, concerning

The Honorable Shirley Ann Jackson 5 Geheral Electric Nuclear Energy's extended power uprate program and Monticello Nuclear Generating Plant's power level increase request.

The Committee plans to continue its discussion of some of its recommendations associated with future power uprato applications during future meetings. .

The Committee discussed the response from the NRC Executive Director for ,

Operations dated September 29,1998, responding to ACRS comments and recommendations included in the ACRS report dated September 15, 1998, concerning the Edwin 1. Hatch Nuclear Plant, Units 1 & 2, application for extended

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power level increase.

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The Committee decided that it was satisfied with the EDO's response.

OTHER RELATED ACTIVITIES OF THE COMMITTEE During the period from September 8,1998 through September 29,1998, the following Subcommittee meetings were held:

Reliability and Probabilistic Risk Assessment - September 24,1998  ;

The Subcommittee discussed proposed options for developing a risk-informed  ;

approach to revising 10 CFR 50.59 (Changes, tests and experiments), options for l broader changes to 10 CFR Part 50, and industry initiatives to certify PRAs.

Plannina and Procedures - September 29,1998 The Subcommittee discussed proposed ACRS activities, practices, and procedures for conducting Committee business and organizational and personnel matters related to the ACRS and its staff.

LIST OF FOLLOW-UP MATTERS FOR THE EXECUTIVE DIRECTOR FOR OPERATIONS The Committee plans to continue its review of the industry initiatives to certify PRA after receiving the proposed ASME/ANS Standard on PRA quality.

The Committee plans to continue its review of the staffs integrated review of the l assessment processes and proposed improvements to the Senior Management Meeting Process at the December 1998 ACRS meeting.

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The Committee plans to continue its discussion of some of the recommendations associated with future power uprate applications, included in its July 24,1998 report on the GE extended power uprate program, during future meetings.

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The Honorable Shirley Ann Jackson 6 In the future, the Committee plans to inform the EDO representative regarding those ACRS letters and reports for which EDO response is not needed. This will also be documented in the ACRS summary report to the NRC Chairman. During this meeting, the Committee stated that no EDO response is needed for its October 14, 1998 letter to the EDO on Risk-Informed Pilot Application for Hydrogen Monitoring at Arkansas Nuclear One, Units 1 and 2.

PROPOSED SCHEDULE FOR THE 457 ACRS MEETING The Committee agreed to consider the following during the 457* ACRS Meeting, November 4-7,1998:

Procosed Rule on the Use of Revised Source Te'rm at Operatina Plants / Pilot Apolication of Revised Source Term at the Perrv Nuclear Plant (Open)

The Committee will hear presentations by and hold discussions with representatives of the NRC staff regarding the proposed rule on the use of the revised source term at operating I plants and the insights gained from the pilot application of the revised source term at the Perry Nuclear Power Plant.

Assessment of Pressurized Water Reactor (PWR) Primary Systems Leaks (Open)

The Committee will hear presentations by and hold discussions with representatives of the NRC staff and its contractor regarding results of the study on the PWR primary system leaks.

1 Proposed Commission Paoer on Ootions to Revise the Enforcement Policy (Open)

The Committee will hear presentations by and hold discussions with representatives of the NRC staff regarding the proposed Commission paper on options to revise the enforcement policy.

Proposed Final Safetv Evaluation Report (SER) on Westinahouse Owners Group (WOG)

Topical Report on Risk-Informed Inservice insoection of Pioina (Open)

The Committee will hear presentations by and hold discussions with representatives of the NRC staff and the Westinghouse Owners Group (WOG) regarding the staff's safety i evaluation report on the WOG topical report on risk-informed inservice inspection of piping at nuclear power plants, as well as the results of the associated pilot applications. )

1 ProDosed Inspection Procedure for Graded Quality Assurance (Open)

The Committee will hear presentations by and hold discussions with representatives of the l

NRC staff regarding the proposed NRC inspection procedure for evaluating the l effectiveness of the licensee's graded quality assurance programs, i

The Honorable Shirley Ann Jackson 7

s Salem Nuclear Plant Units 1 and 2 (Open)

The Committee will hear presentations by and hold discussions with representatives of the licensee of the Salem Nuclear Plant Units 1 and 2, and the NRC staff regarding the issues that led to the shutdown of Salem Units 1 and 2, resolution of issues prior to restart, regulatory requirements currently being implemented by the licensee, current status of the plant, and other related matters.

Sincerely,

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Robert L. Seale Chairman 4

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