ML20134D343

Requests Additional Info Re Proposed TS Change Incorporating Performance Based Testing IAW 10CFR50,App J

ML20134D343
Person / Time
Site:	Limerick
Issue date:	10/10/1996
From:	Rinaldi F NRC (Affiliation Not Assigned)
To:	Hunger G PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC
References
TAC-M96117, TAC-M96118, NUDOCS 9610220004
Download: ML20134D343 (4)

Text

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Cctober 10, 1996 j i

Mr. George A. Hunger, Jr.

Manager-Licensing, MC 62A-1 i PECO Energy Company  :

Nuclear Group Headquarters Correspondence Control Desk l'

P.O. Box 195 Wayne, PA 19087-0195

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION (RAI), LIMERICK GENERATING STATION, UNITS 1 AND 2 (TAC NOS. M96117 AND M96118)

Dear Mr. Hunger:

On June 26, 1996, PFC0 Energy Company submitted for review and approval a proposed Technical Specifications change that would incorporate performance i based testing in accordance with 10 CFR Part 50, Appendix J, " Primary Reactor Containment Leakage Testing for Water Cooled Power Reactors," Option B. The NRC staff has reviewed your submittal and has determined that additional information, as stated in the enclosure, is needed by the staff to complete our review.

We request that the licensee provide its response within 30 days, to support our review schedule. If you have any questions on the enclosed RAI, please contact me at (301) 415-1447.

Sincerely,

/S/ 1 Frank Rinaldi, Project Manager Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Docket Nos. 50-352/353

Enclosure:

RAI See next page cc w/ encl:

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'% October 10, 1996 Mr. George A. Hunger, Jr.

Manager-Licensing, MC 62A-1 PECO Energy Company Nuclear Group Headquarters Correspondence Control Desk

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P.O. Box 195 Wayne, PA 19087-0195

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION (RAI), LIMERICK GENERATING STATION, UNITS 1 AND 2 (TAC NOS. M96117 AND M96118)

Dear Mr. Hunger:

On June 26, 1996, PECO Energy Company suomitted for review and approval a proposed Technical Specifications change that would incorporate performance based testing in accordance with 10 CFR Part 50, Appendix J, " Primary Reactor Containment Leakage Testing for Water Cooled Power Reactors," Option B. The NRC staff has reviewed your submittal and has determined that additional information, as stated in the enclosure, is needed by the staff to complete our review.

We request that the licensee provide its response within 30 days, to support our review schedule. If you have any questions on the enclosed RAI, please contact me at (301) 415-1447.

Sincerely,

,q,.1 A/ft-wQ-Frank Rinaldi, Project Manager Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Docket Nos. 50-352/353

Enclosure:

RAI cc w/ encl: See next page

t Mr. George A. Hunger, Jr.

i Limerick Generating Station,

PECO Energy Company Units 1 & 2 i

cc

J

. J. W. Durham, Sr., Esquire Mr. Rich R. Janati, Chief 3

Sr. V.P. & General Counsel Division of Nuclear Safety PECO Energy Company PA Dept. of Environmental Resources 2301 Market Street P. O. Box 8469 Philadelphia, Pennsylvania 19101 Harrisburg, Pennsylvania 17105-8469

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Mr. David P. Helker, MC 62A-1 Mr. Michael P. Gallagher Manager-Limerick Licensing Director - Site Engineering PECO Energy Company Limerick Generating Station 965 Chesterbrook Boulevard P. O. Box A Wayne, Pennsylvania 19087-5691 Sanatoga, Pennsylvania 19464 Mr. Walter G. MacFarland, Vice President Limerick Generating Station Mr. James L. Kantner Post Office Box A Manager-Experience Assessment Sanatoga, Pennsylvania 19464 Limerick Generating Station P. O. Box A Mr. Robert Boyce Sanatoga, Pennsylvania 19464 Plant Manager Limerick Generating Station Library P.O. Box A US Nuclear Regulatory Commission Sanatoga, Pennsylvania 19464 Region I 475 Allendale Road j Regional Administrator King of Prussia, PA 19406 l U.S. Nuclear Regulatory Commission  ?

Region I Mr. Ludwig E. Thibault  !

475 Allendale Road Senior Manager - Operations j King of Prussia, PA 19406 Limerick Generating Station i P. O. Box A Mr. Neil S. Perry Sanatoga, Pennsylvania 19464 Senior Resident Inspector US Nuclear Regulatory Commission Dr. Judith Johnsrud P. O. Box 596 National Energy Committee Pottstown, Pennsylvania 19464 Sierra Club 433 Orlando Avenue i Mr. Darryl P. Lequia State College, PA 16803 l Director - Site Support Services  !

Limerick Generating Station P.O. Box A Sanatoga, Pennsylvania 19464 Chairman Board of Supervisors ,

of Limerick Township j 646 West Ridge Pike l Linfield, PA 19468 J l

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RE0 VEST FOR ADDITIONA'. INFORMATION APPENDIX J. OPTION 8 LIMERICK GENERATING STATION. UNITS 1 AND 2

1. Provide a discussion of the potential increase in risk due to extending the drywell bypass leakage test interval to 10 years. Address such issues as: (1) increase in risk of overpressurizing containment due to bypass leakage following a severe accident, (2) increase in source terms for various events due to bypass of the suppression pool followed by contaitnent failure, and (3) the possibility of bypass leakage of large amcunts of hydrogen to the suppression pool.

2. Are there areas which could affect the drywell bypass leakage which will be inaccessib!e and therefore not readily inspected visually or not inspected at all?

3. What controls are there over modifications to the drywell/ suppression pool interface that could affect leakage?

4. Is there a backup to containment spray? 'f there are procedures governing the use of spray backup, describe them.

5. List all lines or penetrations between the drywell and the suppression pool which are not subject to Aprsndix J 1eak testing requirements. What assurance is there that these are not potential leak paths?

6. The Final Safety Analysis Report demonstrates that the suppression chamber sprays will maintain the pressure below the containment design pressure for the design basis bypass leakage. H9w much larger could the leakage be before containment spray becomes ineffective?

7. Describe the frequency and type of any non-destructive testing of the liner plate over the diaphragm slab at penetrations and at th-circumference where the diaphragm slab intersects the containment wall.

ENCLOSURE t