NRC Generic Letter 1981-26

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NRC Generic Letter 1981-026: Safety Concerns Associated with Pipe Breaks in BWR Scram System
ML031110014
Person / Time
Issue date: 07/07/1981
From: Eisenhut D
Office of Nuclear Reactor Regulation
To:
References
GL-81-026, NUDOCS 8108060123
Download: ML031110014 (4)


0 *UNITED STATES

NUCLEAR REGULATORY COMMISSION

WASHINGTON, D. C. 20555 July 7, 1981 TO ALL BWR LICENSEES

Gentlemen:

SUBJECT: SAFETY CONCERNS ASSOCIATED WITH PIPE BREAKS IN THE BWR SCRAM

SYSTEM (GENERIC LETTER NO. 81-26)

Our letter of April 10, 1981 forwarded draft NUREG-0785 (same subject) and requested a generic reply within 45 days of receipt. General Electric Company submitted a generic response on behalf of the BWR licensees by letter dated April 30, 1981.

The staff has completed its review of the generic evaluation prepared by GE. NUREG-0803 "GENERIC SAFETY EVALUATION REPORT REGARDING INTEGRITY OF

BWR SCRAM SYSTEM PIPING" dated June 1981 is in the final editing phase and is now planned for publishing in late July 1981. This report will provide guidance to individual licensees in answering the plant specific request contained in our April 10, 1981 letter.

Since the original time allowed for plant specific responses will expire on or about the time you receive the staff's guidance, we are hereby extending the time allowed to submit the plant specific information requested in our April 10, 1981 letter. This extension of time is warranted based on our finding that the analyzed sequence of events is not a dominant contributor to core melt. However, the assumptions made in the risk assessment supporting this conclusion must be confirmed with plant specific information.

Therefore, plant specific responses conforming to the guidance contained in NUREG-0803 should be provided within 120 days of your receipt of the NUREG

guidance.

Sincerely,

> Darrell G. Eisenhut, Director Division of Licensing Office of Nuclear Reactor Regulation cc: Service List

110806O123 610707 PDR ADOCK 05000010

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July 7, 1981 Distribution:

Docket File SEPB ACRS (10)

NRC PDR ORB LAs(6) D. Eisenhut Local PDR OELD (5)

TERA IE (7)

NSIC J. Wetmore TO ALL BWR LICENSEES DLADs C. Harwood ORBCs R. Diggs LB BCs P. Wooley Gentlemen: ORAB Gray Files SUBJECT: SAFETY CONCERNS ASSOCIATED WITH PIPE BREAKS IN THE BWR SCRAM

SYSTEM

Our letter of April 10, 1981 forwarded draft NUREG-0785 (same subject) and requested a generic reply within 45 days of receipt. General Electric Company submitted a generic response on behalf of the BWR licensees by letter dated April 30, 1981.

The staff has completed its review of the generic evaluation prepared by GE. NUREG-0803 'GENERIC SAFETY EVALUATION REPORT REGARDING INTEGRITY OF

BWR SCRAM SYSTEM PIPING" dated June 1981 is in the final editing phase and Is now planned for publishing in late July 1981. This report will provide guidance to individual licensees in answering the plant specific request contained in our April 10, 1981 letter.

Since the original time allowed for plant specific responses will expireo- on or about the time you receive the staff's guidance, we are hereby extending the time allowed to submit the plant specific Information requested in our April 10, 1981 letter. This extension of time Is warranted based on our finding that the analyzed sequence of events is not a dominant contributor to core melt. However, the assumptions made In the risk assessment supporting this conclusion must be confirmed with plant specific information.

Therefore, plant specific responses conforming to the guidance contained in NUREG-0803 should be provided within 120 days of your receipt of the NUREG

guidance.

Sincerely, Darrell G. Eisenhut, Director Division of Licensing Office of Nuclear Reactor Regulation cc: Service List DL:ORB#2 JHannon:ms

  • See attached concurrences 7 / /_8,1 r . I I

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USOPO: 1980-329-824 COPY

OFFICIAL RECORD

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  • USGPO: 1980-329-824

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318 (10/801 FORM 318 NRCNRC NRCM 0240

tlO/80J NRCM 0240 RECORD COPY

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NRC PDR LB BCs J. Wetmor L PDR 'URB PMs C=Harwood TERA ORAB R Diggs NSIC SEPB P Wooley DLADs ORB LAs (6) Gray File

_OELD (5) ACRS (10)

D Eisernhu TO ALL BWR LICENSEES AND APPLICANTS

Gentlemen:

SUBJECT: SAFETY CONCERNS ASSOCIATED WI / PIPE BREAKS IN THE BWR SCRAM SYSTEM

Our letter of April 10, 1981 forward draft NUREG - 0785 (same subject) and requested a generic reply within 45 ays of receipt. General Electric Company submitted a generic response on beh lf of the BWR licensees by letter dated April 30, 1981.

The staff has completed its revie of the generic evaluation prepared by GE.

NUREG - 0803 "GENERIC SAFETY EVA ATION REPORT REGARDING INTEGRITY OF BWR

SCRAM SYSTEM PIPING" dated June 981 is in the final editing phase and is now planned for publishing in late ly, 1981. This report will provide guidance to individual licensees in answ ring the plant specific request contained in our April 10, 1981 letter.

Since the original time allow for plant specific responses will expire on or about the time you receive the staff's guidance, we are hereby extending the time allowed to submit th plant specific information requested in our April 10, 1981 letter. Plane specific responses conforming to the guidance contained in NUREG - 0803 0-douldbe provided within 120 days of your receipt of the NUREG guidance. /

Sincerely, Darrell G. Eisenhut, Director Division of Licensing Office of Nuclear Reactor Regulation cc: Service List OFFICEl RPa .;;..

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USGPO: 1980-329-E

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BOILING WATER REACTOR LICENSEES

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Docket No. 50-293 Docket No. 50-245 Pilgrim Unit 1 Millstone Unit 1 Docket No. 50-325 Docket No. 50-263 Brunswick Unit 1 Monticello Docket No. 50-324 Docket No. 50-133 Brunswick Unit 2 Humboldt Bay Docket No. 50-10 Docket No. 50-277 Dresden 1 Peach Bottom Unit 2 Docket No. 50-237 Docket No. 50-278 Dresden 2 Peach Bottom Unit 3 Docket No. 50-249 Docket No. 50-333 Dresden 3 FitzPatrick Docket No. 50-254 Docket No. 50-259 Quad-Cities Unit 1 Browns Ferry Unit 1 Docket No. 50-265 Docket No. 50-260

Quad-Cities Unit 2 Browns Ferry Unit 2 Docket No. 50-155 Docket No. 50-296 Big Rock Point Browns Ferry Unit 3

1 Docket No. 50-409 Docket No. 50-271 Lacrosse A-' > Vermont Yankee Docket No. 50-321 Edwin I. Hatch Unit 1 Docket No. 50-366 Edwin I. Hatch Unit 2 Docket No. 50-331 Duane Arnold Docket No. 50-219 Oyster Creek Docket No. 50-220

Nine Mile Point Unit 1 Docket No. 50-298 Cooper Station

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