ML20209E281

Forwards Sser Input Re NUREG-0737,Item II.K.3.30 on Small Break LOCA Methods & Item II.K.3.31 on plant-specific Calculations,Per Request.No Need to Condition License on Issues

ML20209E281
Person / Time
Site:	05000000, Diablo Canyon
Issue date:	04/11/1985
From:	Houston R Office of Nuclear Reactor Regulation
To:	Novak T Office of Nuclear Reactor Regulation
Shared Package
ML082410749	List: ML20209A984 ML20209B531 ML20209B624 ML20209B724 ML20209B847 ML20209B894 ML20209C131 ML20209C225 ML20209C292 ML20209C320 ML20209C516 ML20209C643 ML20209C669 ML20209C675 ML20209C698 ML20209C705 ML20209C710 ML20209C715 ML20209C720 ML20209C836 ML20209C847 ML20209C848 ML20209C876 ML20209C881 ML20209C908 ML20209C921 ML20209C969 ML20209C975 ML20209C981 ML20209C993 ML20209D004 ML20209D012 ML20209D018 ML20209D030 ML20209D038 ML20209D044 ML20209D045 ML20209D071 ML20209D089 ML20209D114 ML20209D127 ML20209D130 ML20209D135 ML20209D139 ML20209D146 ML20209D154 ML20209D211 ML20209D218 ML20209D230 ML20209D235 ... further results
References
FOIA-86-197, RTR-NUREG-0737, RTR-NUREG-737, TASK-2.K.3.30, TASK-2.K.3.31, TASK-TM NUDOCS 8504180574
Download: ML20209E281 (2)

Text

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4 UNITED STATES 8'

NUCLEAR REGULATORY COMMISSION r,.

WASMINGTON, D. C. 20555 s,

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APR 11 1985 MEMORANDUM F0R:

Assistant Director for Licensing, DL FROM:

R. Wayne Houston, Assistant Director for Reactor Safety, DSI

SUBJECT:

DIABLO CANYON UNIT 2 LICENSE Plant Name:

Diablo Canyon Unit 2 Docket No.:

50-323 Responsible B anch:

LB-3 Project Manager:

H. Schierling Review Stage:

OL Review Status:

Continuing Per your request, we have reviewed the draft License for Diablo Canyon Unit 2.

The enclosure to this memorandum provides an SSER input on NUREG-0737 Item II.K.3.30, " Revised Small Break Loss-of-Coolant-Accident Methods to Show Compliance with 10 CFR Part 50, Appendix K," and Item II.K.3.31, " Plant Specific Calculations to Show Compliance with 10 CFR 50.46."

As explained in the enclosure, there is no need to condition the license on these issues.

R. We ne Houston, Assistant Director for Reacter Safety Division of Systems Integration cc:

R. Bernero H. Schierling B. Buckley RSB Section Leaders CONTACT:

N. Lauben, RSB x27579

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II.K.3.30 REVISED SMALL-BREAK LOSS-0F-COOLANT-ACCIDENT METHODS TO SHOW COMPLIANCE WITH 10 CFR PART 50, APPENDIX K II.K.3.31 PLANT-SPECIFIC CALCULATIONS TO SHOW COMPLIANCE WITH 10 CFR PART 50.46 THE NRC staff is currently reviewing the Westinghouse Owner's Group submittal (II.K.3.30) which describes the generic methodology for small-break LOCAs.

The staff requires that the Pacific Gas & Electric Company submit its plant specific analysis (II.K.3.31), within one year of staff approval of II.K.3.30, for staff evaluation and approval. By letter dated September 16, 1983, the Pacific Gas & Electric Company connitted to submit its plant specific analysis in accordance with the above schedule, thus removing the need to condition the license on this issue.

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