ML20199A414

Summary of 970925 Meeting W/Listed Attendees in Lajolla,Ca at 14th Annual Operational Reactor Safety Engineering & Review Groups Workshop.W/Workshop Attendees List & Presentation Slides

ML20199A414
Person / Time
Issue date:	11/10/1997
From:	Malloy M NRC (Affiliation Not Assigned)
To:	Essig T NRC (Affiliation Not Assigned)
References
PROJECT-669 NUDOCS 9711170163
Download: ML20199A414 (28)

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Novombor 10. 1997 MEMORANDUM TO: Thomas H. Essig, Acting Chief Generic issues and Environmental Projects Branch Division of Reactor Program Management O*fice of Nuclear Reactor Regulation FROM: Melinda Malloy, Senior Reactor Engineer Original Signed By:

Generic issues and Environmental Projects Branch Division of Reactor Program Management Office of Nuclear Reactor Regulation

SUMMARY

OF SEPTEMBER 25,1997, MEETING WITH ELECTRIC POWER RESEARCH INSTITUTE (EPRI) OPERATIONAL REACTOR SAFETY ENGINEERING AND REVIEW GROUPS (ORSERG)

On September 25,1997, David Matthews, Deputy Director of the Division of Reactor Program Management, U.S. Nuclear Regulatory Commission (NRC), met with attendees at the 14th Annual ORSERG Workshop at Hyatt Regency La Jolla in La Jolla, Califomia. A list of workshop attendees is provided in Attachment 1, Mr. Matthews spoke to and answered questions from workshop attendees at two sessions. At the first session, he provided an overview of the NRC staff's recent lessons learned reviews and resulting recommendations for program changes to address implementation and compliance issues in the areas of nuclear power plant design bases, plant Final Safety Analysis Reports, and 10 CFR 50.59 (Changes, tests and experiments). At the second session, Mr. Matthews covered the same topics in more detail. His presentation slides for these sessions are provided in Attachments 2 and 3, respectively, Project No. 669 cc: See attached list Attachments:

1. Workshop Attendees

2. Presentation Slides, " Regulatory Issues Related to Design Bases and 10 CFR 50.59"

3. Presentation Slides,"What's New With 10 CFR 50.59 and Safety Analysis Reports' p Distribution: Hard Cooy (w/att.) E-Mail (w/o att.)

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,,,, November 10, 1997 MEMORANDUM TC'. Ihomas H. Essig, Acting Chief Ger.oric lasues and Environmental Projects Branch Division of Reactor Program Management Off% of Nuclear Reactor Regulation FROM: Melinda Malloy, Genior Reactor Engine r .

Generic lssues and Environmental Projects Branch Division of Reactor Program Management Office of Nuclear Reactor Regulation

SUMMARY

OF SEPTEMBER 25,1997, MEETING WITH ELECTRIC POWER RESEARCH INSTITUTE (EPRI) OPERATIONAL REACTOR SAFETY ENGINEERING AND REVIEW GROUPS (ORSERG)

On September 25,1997, David Matthews, Deputy Director of the Division of Reactor Program Management, U.S. Nuclear Regulatory Commission (NRC), met with attendees at the 14th Annual ORSERG Workshop at Hyatt Regency La Jolla in La Jolla, California. A list of workshop attendees is provided in Attachment 1.

Mr. Matthews spoke to and answered questions from workshop attendees at two sessions. At the first session, he provided an overview of the NRC staffs recent lessons-learned reviews and resuhing recommendations for program changes to add,ess implementation and compliance issues in the areas of nuclear power plant design bases, plant Final Safety Analysis Reports, and 10 CFR 50.59 (Changes, tests and experiments). At the second session, Mr. Matthews covered the same topics in more detail. His presortation slides for these sessions are provided in Attachments 2 and 3, respectively.

Project No. 669 cc: See attached list Attachments:

1. Workshop Attendees

2. Presentation Slides," Regulatory lasues Related to Design Bases and 10 CFR 50.59"

3. Prusentation Slides, 'What's New With 10 CFR 50.59 and Safety Analysis Reports'

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ei Page 1 OPERATIONAL REACTOR SAFETY ENGINEER. & REVIEW GROUP (ORSERG) 09/25/97 - 09/26/97 ATTENDEE' LIST BY COMPANY ,

Company attendee Name American Electric Power Co., Inc. Allan R. Barker l Arizona Public Service Co. Edward C. Sterling Baltimore Gas & Electric Co. Louis Larragoite Battelle Memorial Institute Larry McClellan s

Commonwealth Edison'Co. Robert Branson i

, John Hoeller Kenneth J. Housh Frank Myers Jack Nalewajka Rodger Saeets Randolph Weidner Diablo Canyon Power Plant Charles Belmont Dave Gouveig Duke Energy Corp. Richard T. Bond Mary Ritenour Fred Siurua Duke Power Corp. Bill Pitosa Edison International Robert J. McWey Entergy operations, Inc. Rick Ingram EPRI John Giscion EPRI, Palo Alto Lori J. Adams Jack Haugh Frank Rahn CPU Nuclear, Inc. George W. Busch Houston. Lighting & Power Co. Drsw Richards Illinois Power Co. Kent Beecher David W. Hodel Robert T. Kerestes Simon R. Wilson Independent Safety Engineering Robert J. Salmon IES Utilities, Inc. Dave Jantosik Attachment 1

m Page 2 OPERATIONAL REACTOR SAFETY ENGINEER. & REVIEW CROUP (ORSERG) 09/25/97 09/26/97 ATTENDEE LIST BY COMPANY

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Company - Attendee Name Lockheed Martin Energy Systems, Inc. Bob Lantz Lockheed Martin Utilities, Inc. John J. Mize Hollerus Engineering ,

William B. Rauland New York Power Authority Richard Bystrak Northeast Utilities Salvatore Orefice Nuclear Energy Institute Anthony R. Pietrangelo NPPD . Looper Nuclear Station David Robinson 4

Omaha Public Power District. Delvin Trausch Pacific Cas & Electric Co. Robert P. Powers Pennsylvania Power & Light Co. Richard Henry Public Service Electric & Cas Co. ,

Stan Kobylarz PECO Energy Company Scott Auve Jerry B. McLaughlin Thomas J. Niessen Rochester Gas & Electric Corp. Frank Puddu Seabrock Station Michael O'Keefe South Carolina Electric & Cas Company Eric W. Rumfelt Southern California Edison Co. Michelle P. Carr Ransey Clark Southern Nuclear Operating Co. Don M. Crowe Dean Drinkard Msrk A. Slivka Steven B. Tipps Supply System, The Dale K. Atkinson John E. Wyrick TU Electric Ronald D. Carver -

U.S. Nuclear Regulatory Commission David B. Matthews Union Electric Co. Gary Hughes

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Page 3 OPERATIONAL RECTOR SAFETY DGINEER. & REVIEW GROUP (ORSERG) '

09/25/97 - 09/26/97 ATTENDEE LIST SY CCHPANY Company. Attendee Name USEC Barry Tilden Wolf Creek Nuclear Operating Corp. Larry W.~ Stevens

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l U.S. INDUSTRY AVERAGE SAFETY PERFORMANCE i

!i NRC focus on operational safety since 1985 has been effective:

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. Automatic scrams have been reduced

. Safety system actuations have been reduced 4

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. Significant events have decreased i 1

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. Collective radiation exposure has decreased i i f i

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NRC SAFETY FOCUS i

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With increased focus on operational safety, by 1990's, NRC reduced efforts evaluating adequacy, availability, and

control of design and licensing bases information i

j . In 1995, issues identified at several plants sparked concerns about the regulatory processes associated with design and licensing bases information

. Although few immediate safety concerns have been identified,  !

identification of process concems alters our confidence in  ;

overall industry performance i

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. c' l LESSONS-LEARNED REVIEW l

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- On November 30,1995, Commission requested review I

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• Review performed in two parts

- Considered other ongoing efforts:

l Survey of refueling practices at all plants 3

Review of Maine Yankee issues  ;

Inspections on FSAR compliance j -

Evaluation of implementation of 10 CFR 50.59  ;

l (safety evaluation of proposed changes, tests, and j experiments)

Re-emphasis on design-basis oversight activities l 3 L.

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l LESSONS-LEARNED REVIEW i

j - Report on Part 1 of review issued in September 1996 Recommendations provided on licensing, inspection, i

enforcement, licensee reporting, management oversight i -

Identified policy questions on design and licensing bases,

FSARs,10 CFR 50.59 i

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. What information does NRC need to fulfill its regulatory responsibilities?

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i l LESSONS-LEARNED REVIEW

- Report on Part 2 of the review issued in

, February 1997 (SECY-97-036) i i

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Staff actions developed from further examination of key policy questions Staff proposed regulatory guidance on implementation of 10 CFR 50.59 in February 1997 (SECY-97-035), published as-NUREG-1606 in May 1997 j

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Staff advised Commission of need to consider the I recommendations contained in the two SECY papers in an j mtegrated fashion l

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NEAR TERM NRC PROGRAM CHANGES

. Re-emphasis on design bases information in inspection l activities

- Improvements to FSAR t

. Improvements to regulatory processes to define licensing requirements l

i . Issue revised inspection guidance on 10 CFR 50.59 1

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i LONGER TERM NRC ACTIONS .

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SECY-97-035 and SECY-97-036 discuss a number of regulatory ,

issues and staff actions regarding knowledge of and control

, of changes to design bases and licensing basis information

. Staff has proposed a follow-on report to the Commission which .

! would integrate these issues, and actions to result in a effective strategy for regulatory process improvements l

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• Commission provided prehminary views on the issues and l actions and endorsed staff plans to submit integrated l recommendations l

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- Follow-on " integration" paper recently sent to Commission

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i WHAT'S NEW WITH 10 CFR 50.59 AND l SAFETY ANALYSIS REPORTS 4

Presentation to EPRI Operational Reactor Safety Engineering and Review Groups Workshop

September 25,1997 1

David B. Matthews, Deputy Director  !

Division of Reactor Program Management

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Office of Nuclear Reactor Regulation Attuet 3 i

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, BACKGROUND 1

j . SECY-97-036 proposed many staff actions from i Millstone lessons-learned reviews SECY-97-035 focused on implementation issues for 10 CFR 50.59

. . Integration activities focused in four areas

- Design bases

) - Commitment management Safety analysis report 10 CFR 50.59 t

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I SRM GUIDANCE ON SECY-97-035 I

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j Publish NUREG-1606 for comment

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Commission Paper evaluate public comments on NUREG-1606 i

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consider guidance on SECY 97-036 provide recommendations for regulatory process improvements i

develop a rulemaking plan for 50.59

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l Longer Term evaluation of 50.59 requirements considering

! ties to Appendices A and B

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SRM ON RULEMAKING PLAN FOR 50.59

• Risk-informed approaches for the review process or USQ l

! threshold 4

. Negligible increase in probability or consequences or l decreases in margin of safety I

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! . Keep accident scope same as current rules

. Legal implications for Commission

. Expedited schedule i

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• Resources discussions and budget i

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SRM GUIDANCE ON SECY 97-036

• Discuss experience with short-term actions l

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implement 50.71(e) to ensure SARs are updated to I

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l changes to design bases l

effects of new analyses 1

Enforce compliance, applying discretion (two years) update more risk-significant first Deletion of less meanir gful information

• Risk-informed guidance on SAR contents l- .

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STAFF ACTIONS RELATED TO 50.59 l 1 .

Revise Generic Letter 91-18 and IMC 9900  ?

i l Recommending rulemaking on 50.59

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Longer term revision to incorporate risk-informed strategies '

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DEGRADED AND NONCONFORMING CONDITIONS (cont'd.)

NUREG-1606 guidance on when a 50.59 evaluation is needed ,

i compensatory measures with underlying condition delay beyond first available opportunity l -

change to licensing basis

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NUREG-1606 guidance on effects on plant operation if USQ involved j:

shutdown not required if equipment is operable j -

resolve before startup i i

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PROPOSED GL 91-18 AND IMC 9900

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' Revises guidance to inspectors such that plants may restart with nonconforming condition involving an unreviewed safety question provided I USQ results from evaluation of discovered degraded / nonconforming condition i

j all necessary equipment is operable l -

all Technical Specifications are met i

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PROPOSED GL 91-18 AND IMC 9900 (cont'd) i j - Provides guidance for conditions under which a 50.59 evaluation is needed for nonconforming conditions i

evaluate compensatory measures

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when changing licensing basis

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i RULEMAKING ON 10 CFR 50.59 l

Rulemaking package scheduled for submittal to Commission in December 1997 that will:

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revise threshold criteria that establishes an USQ clarify definition of margin of safety '

clarify where margins are located j -

consider elimination of term "USQ" clarify terms " facility" and " procedures" j Focus remains the safety analysis report i

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l NEl 96-07 l

NEl prepared revised guidance NEl 96-07 in July 1997.

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Major changes are:

- Definition of change l - Treatment of nonconforming conditions l - Narrower guidance on basis for any TS j - Discussion of screening documentation

! - Deletion of " compensating effects"

- Clarification on cause/effect for malfunctions

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l Industry positions related to increases in consequences up to acceptance limits and on small increases in probability / consequences are unchanged i

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j GUIDANCE /RULEMAKING ON SAR CONTENT

! Staff developing guidance and implementation vehicle l to improve contents of SAR. Staff is identifying:

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implementation vehicle (GL or rule) 4 a process for determining what information must be j added to SAR to satisfy 10 CFR 50.71(e) information that could be eliminated from SAR and still meet 50.2, 50.34, 50.71(e) l approach to permit window of time to complete, with l

I more risk-significant information updated first I

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staff recommendations on enforcement policy and the l use of discretion l

i i . Approact ad f;"udance due to Commission in December!

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Electric Power Research Institute Project No. 669 cc: Mr. Raymond C. Torok . ..

- Project Manager, Nuclear Power Group Electric Power Research Institute Post Office Box 10412 Palo Alto, CA 94303  !

Mr. Gary L. Vine Senior Washington Representative '

Electric Power Research Institute .

2000 L Street, N.W., Suite 805 Washington, DC 20036

- Mr. Bindi Chexal Electric Power Research Institute Post Office Box 10412 .

Palo Alto, CA 94303 4

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