ML17158A823

Summary of 409th Meeting of Advisory Committee on Reactor Safeguards on 941208-10 Re Several Matters & Completion of Listed Repts,Including Loss of Spent Fuel Pool Cooling Following LOCA

ML17158A823
Person / Time
Site:	Susquehanna
Issue date:	12/29/1994
From:	Kress T Advisory Committee on Reactor Safeguards
To:	Selin I, The Chairman NRC COMMISSION (OCM)
References
ACRS-SL-0425, ACRS-SL-425, NUDOCS 9508160041
Download: ML17158A823 (12)

Text

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ACCESSION NBR:9508160041 DOC.DATE: 94/12/29 NOTARIZED: NO FACIL:50-387 Susquehanna Steam Electric Station, Unit 1, Pennsylva 50-388 Susquehanna Steam Electric Station, Unit 2, Pennsylva AUTH.NAME AUTHOR AFFILIATION KRESS,T.S.

ACRS Advisory Committee on Reactor Safeguards RECIP.NAME RECIPIENT AFFILIATION THE CHAIRMAN Commissioners (Post 750119)

SELIN,I.

Commissioners (Post.750119)

SUBJECT:

Summary of 409th meeting of Advisory Committee On Reactor Safeguards on 941208-10 re several matters E completion of listed repts,including loss of spent fuel pool cooling following LOCA.

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UNITEDSTATES NUCLEAR REGULATORY COMMISSION ADVISORYCOMMITTEEON REACTOR SAFEGUARDS WASHINGTON, D. C. 20555 December 29, 1994 SL-0425 P DR E//XJp~

The Honorable Ivan Selin Chairman U. S. Nuclear Regulatory Commission Washington, D.C.

20555

SUMMARY

REPORT -

FOUR HUNDRED SIXTEENTH MEETING OF THE ADVISORY COMMITTEE ON REACTOR SAFEGUARDSy DECEMBER 8 10y

1994, AND OTHER RELATED ACTIVITIES OF THE COMMITTEE During its 416th

meeting, December 8-10,

1994, the Advisory Committee on Reactor Safeguards (ACRS) discussed several matters and completed the following reports.

In addition, the Committee authorized Dr. Larkins, Executive Director, to transmit the letters noted below:

REPORTS Loss of S ent Fuel Pool Coolin Followin a Loss-of-Coolant Accident at the Sus uehanna Steam Electric Station (Report to Chairman Selin from T. S. Kress, ACRS Chairman, dated December 19, 1994)

Revisions to 10 CFR Part 71 Packa in and Trans ortation of Radioactive Material (Report to Chairman Selin from T.S.

Kress, ACRS Chairman, dated December 19, 1994)

Pro osed Final Draft Re ulator Guide DG-1023 "Evaluation of Reactor Pressure Vessels with Char U

er-Shelf Ener Less Than 50 ft-lb" (Report to Mr.

James M. Taylor, Executive Director for-Operations, from T.

ST

Kress, ACRS

Chairman, dated December 20, 1994)

NRC Technical Trainin Pro ram (Report to Mr. James M. Taylor, Executive Director for'perations, from T.

S.

Kress, ACRS

Chairman, dated December 15, 1994)

LETTERS Nuclear Re ulator Review Stud Final Re ort (Letter to Phillip Bayne, President and Chief Executive Officer, Nuclear Energy Institute, from John T. Larkins, Executive Director, dated December 13, 1994)

- Consistent with the Committee'

decision, Dr. Larkins informed Mr.

Bayne that a referenced letter in the Nuclear Regulatory Review Study Final Report by 9SOEIlSOOOI 9el22S DESIGNATED ORIGINAL PDR ACRS SL-0425 'P0R I

Geek,efiel By

I

',The Honorable Ivan Selin Towers Perrin represented the opinions of an individual ACRS member and not those of the whole, Committee.

Potential for BWR ECCS Strainer Blocka e

Caused b

LOCA-Generated Debris (Letter to.Gordon Pinsky, General

Manager, Performance Contracting, Inc., from John T. Larkins, Executive

Director, dated December 13, 1994)

Consistent with the Committee's decision, Dr. Larkins informed Mr. Pinsky that the Committee does not plan to issue another letter on this subject at this time and that the Committee intends to continue its review of the potential for strainer blockage and plans to consider the information provided by Mr.

Pinsky regarding the potential hazards of metallic foil insulation.

J HIGHLIGHTS OF KEY ISSUES CONSIDERED BY THE COMMITTEE Loss of S ent Fuel Pool Coolin Followin a Loss-of-Coolant Accident at the Sus uehanna Steam Electric Station The Committee heard presentations by and held discussions with representatives of the NRC staff, the Pennsylvania Power and Light Company, and also with one of the authors of a 10 CFR Part 21 notification, regarding the NRC staff Draft Safety Evaluation Report on issues associated with the loss of spent fuel pool cooling at the Susquehanna Steam Electric Station.

Conclusion The Committee issued a report to Chairman Selin dated December 19,

1994, on this matter.

2.

Status of Issues Related to the Use of Hi h-Burnu Fuel The Committee heard presentations by and held discussions with representatives of the NRC staff and the Nuclear Energy Institute regarding the issues related to the use of high-burnup fuel and the status of ongoing and proposed NRC staff and industry activities for resolving these issues.

Conclusion This briefing was for information only.

No Committee action was taken at this time.

The Committee plans to establish a

new Subcommittee to monitor NRC and industry activities relative to the resolution of this matter.

3.

Restart of Se uo ah Nuclear Power Plant Unit 1

The Committee heard presentations by and held discussions with representatives of the NRC staff and Tennessee Valley Authori-

1 P

I

'.The Honorable Ivan Selin ty regarding the resolution of issues associated-with the shutdown of the Sequoyah Nuclear Power Plant, Unit 1, includ-ing root causes of Sequoyah performance

problems, operations performance upgrade activities, technical program improve-

ments, and changes to the organizational structure.

Conclusion This briefing was for information only.

No Committee action ':

was taken.

4.

Revisions to 10 CFR Part 71 "Packa in and Trans ortation of Radioactive Material" The Committee heard presentations by and held discussions with representatives of the NRC staff and the Nuclear Energy Institute regarding revisions to 10 CFR Part 71.

Conclusion The Committee issued a report to Chairman Selin dated December 19,

1994, on this matter.

5.

U dates on the BWR Core Shroud Ins ections and Reactor Vessel Inte rit The Committee heard presentations by and held discussions with representatives of the NRC staff regarding the results of recent core shroud inspections',

the plans for future shroud inspections, and an update of European experience.

Also, the Committee heard presentations regarding the Palisades reactor pressure

vessel, which is expected to reach the screening limit for reactor vessel reference temperature in 1999 based on test results of retired steam generator welds.

Conclusion This briefing was for information only.

No Committee action was taken.

6.

Crackin in Nuclear Com onents The Committee heard presentations by and held discussions with representatives of the NRC staff regarding the different types of cracking found in nuclear components, the associated cracking mechanisms, and ongoing and proposed research efforts in this area.

~ The 'Honorable Ivan Selin Conclusion This briefing was for information only.

No Committee action was taken.

7.

Pro osed Final Draft Re ulator Guide DG-1023 "Evaluation of Reactor Pressure Vessels With Char U

er-Shelf Ener Less Than 50 ft-lb" The Committee heard presentations by and held discussions with representatives of the NRC staff regarding the subject draft Regulatory Guide.

Conclusion The Committee issued a report to James M. Taylor, EDO, dated December 20,

1994, on this matter.

8.

NRC Technical Trainin Center Curricula The Committee discussed the results of the December 7,

1994 meeting of the Ad Hoc Subcommittee on NRC Technical Training Center (TTC) Curricula regarding existing and planned curricu-la.

The Committee plans to establish a permanent Subcommittee for the review of NRC technical training programs.

Conclusion The Committee issued a report to James M. Taylor, EDO, dated December 15,

1994, on this matter.

9

~

Election of Officers for Calendar Year 1995 Dr. Kress was reelected as Chairman and Dr. Robert L. Scale was elected as Vice-Chairman of the ACRS.

Mr.

James C.

Carroll was elected as Member-at-Large to the Planning and Procedures Subcommittee.

10.

Reconciliation of ACRS Comments and Recommendations The Committee discussed the response 'from the NRC Executive Director for Operations to ACRS comments and recommendations included in a recent ACRS report.

~

EDO letter dated November 22,

1994, responding to the ACRS report dated September 19, 1'994, concerning Proposed Revisions to Appendix J to 10 CFR Part 50, "Primary Reactor Containment Leakage Testing for Water-Cooled Power Reactors"

.The Honorable Ivan Selin In its report, the Committee provided some recommenda-tions on two issues regarding shutdown risk benefit due to increasing test intervals and aging effects on valve leakage rate.

The NRC staff indicated that they would continue to address these issues during the public comment period and include the resolution of these two issues in the final rule package.

The Committee plans to consider the staff's resolution of these issues during its discussion of the proposed final version of Appendix to 10 CFR Part 50.

The Committee also discussed the concept of performance-based regulationq and expressed interest in further discussing this matter during a future meeting.

11.

Pro osed ACRS Meetin Dates for CY 1995

- The proposed ACRS meeting dates for CY 1995 are provided below.

ACRS MEETING NO.

418 419 420 421 422 423 424 425 426 427 428 1995 ACRS MEETING DATES February 9-11, 1995 March 9-11, 1995 April 6-8, 1995 May 4-6, 1995 June 8-10, 1995 July 13-15, 1995 August 10-12, 1995 September 7-9, 1995 October 5-7, 1995 November 2-4, 1995 December 7-9, 1995 OTHER RELATED ACTIVITIES OF THE COMMITTEE During the period from November 7,

1994 through December 7,

1994, the following Subcommittee meetings were held:

Plannin and Procedures

- December 7,

1994 The Planning and Procedures Subcommittee discussed proposed ACRS activities, practices and procedures for conducting the Committee business, and organizational and personnel matters relating to ACRS and its staff.

NRC Technical Trainin Center Curricula December 7,

1994 The Ad Hoc Subcommittee on NRC Technical Training Center (TTC)

Curricula discussed TTC curricula, including the probabilistic risk assessment curriculum and the status of a new digital instrumentation and control system curriculum.

.Th'e Honorable Ivan Selin LIST OF FOLLOW-UP MATTERS FOR THE EXECUTIVE DIRECTOR FOR OPERATIONS lt During the session on the status of issues related to the use of high-burnup fuel, the Committee noted that it plans to establish a

new Subcommittee to monitor NRC and industry activities relative to the resolution of this matter.

2.

During the discussion of a letter from the NRC Executive Director for Operations dated November 22, 1994, responding to

'he ACRS report dated September 19, 1994, concerning Proposed Revisions to Appendix J to 10 CFR Part 50, "Primary Reactor Containment Leakage Testing for Water-Cooled Power Reactors,"

the Committee expressed interest in scheduling further discussions on the concept of performance-based regulations during a future meeting.

During its discussion of the proposed final version of Appendix J to 10 CFR Part 50, the Committee plans to consider the NRC staff's resolution of two issues, identified in its September 19, 1994 report, regarding shutdown risk benefit due to increasing test intervals and aging effects on valve leakage rate.

PROPOSED SCHEDULE FOR THE 417TH ACRS MEETING The Committee agreed to consider the following during the 417th ACRS Meeting, January 12-14, 1995:

General Electric Nuclear Ener GENE Sim lified Boilin Water Reactor SBWR Test and Anal sis Pro rams - The Committee will hear presentations by and hold discussions with representatives of the NRC staff and GENE regarding the results of the NRC staff evalua-tion of the test and analysis programs being conducted by GENE in support of the certification of the SBWR passive plant design.

Status of AP600 Desi n Certification Review

- The Committee will hear presentations by and hold discussions with representatives of the NRC staff regarding the status of the AP600 design.certifica-tion review.

Representatives of Westinghouse will participate, as appropriate.

CANDU3 A lication Acce tance Review The Committee will hear presentations by and hold discussions with representatives of the NRC staff regarding staff findings resulting from its CANDU3 application acceptance review.

Representatives of the Atomic Energy of Canada Limited Technologies will participate, as appropriate.

0 Meetin with the Director of the NRC Office of Nuclear Re ulator Research The Committee will hear presentations by and hold

',,Thh Honorable Ivan Selin discussions with the Director of the NRC Office of Nuclear Regulatory Research regarding items of mutual interest.

Turbine Overs eed Stud The Committee will hear presentations by and hold discussions with representatives of the NRC staff regarding the results of the Turbine Overspeed Study performed by the NRC Office for Analysis and Evaluation of Operational Data.

Sincerely, T..S.

Kress Chairman

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