NRC Generic Letter 1981-30: Difference between revisions
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| issue date = 07/31/1981 | | issue date = 07/31/1981 | ||
| title = NRC Generic Letter 1981-030: Safety Concerns Associated with Pipe Breaks in the BWR Scram System (Previously Issued July 7, 1981 as Generic Letter 82-26 Is Now Identified as 81-30) | | title = NRC Generic Letter 1981-030: Safety Concerns Associated with Pipe Breaks in the BWR Scram System (Previously Issued July 7, 1981 as Generic Letter 82-26 Is Now Identified as 81-30) | ||
| author name = Eisenhut D | | author name = Eisenhut D | ||
| author affiliation = NRC/NRR | | author affiliation = NRC/NRR | ||
| addressee name = | | addressee name = | ||
| Line 15: | Line 15: | ||
| page count = 1 | | page count = 1 | ||
}} | }} | ||
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BEQ UNITED STATES | |||
NUCLEAR REGULATORY COMMISSION | |||
5 iWASHINGTON, D. C. 20555 July 31, 1981 TO ALL BWR LICENSEES | |||
Gentlemen: | |||
SUBJECT: SAFETY CONCERNS ASSOCIATED WITH PIPE BREAKS IN THE BWR SCRAM | |||
SYSTEM (GENERIC LETTER NO. 81-30) | |||
(PREVIOUSLY ISSUED JULY 7, 1981 AS GENERIC LETTER 8r-26 IS NOW | |||
IDENTIFIED AS 81-30) | |||
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. | |||
Sincerely,> Darrell G. Eisenhut, | 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 | |||
8112170381 8107531 PDR NUREGQ qz | |||
0803 C Ono | |||
, M9n}} | |||
{{GL-Nav}} | {{GL-Nav}} | ||
Latest revision as of 03:06, 24 November 2019
| ML031110033 | |
| Person / Time | |
|---|---|
| Issue date: | 07/31/1981 |
| From: | Eisenhut D Office of Nuclear Reactor Regulation |
| To: | |
| References | |
| GL-82-026 GL-81-030, NUDOCS 8112170381 | |
| Download: ML031110033 (1) | |
v~ it ftrak :
BEQ UNITED STATES
NUCLEAR REGULATORY COMMISSION
5 iWASHINGTON, D. C. 20555 July 31, 1981 TO ALL BWR LICENSEES
Gentlemen:
SUBJECT: SAFETY CONCERNS ASSOCIATED WITH PIPE BREAKS IN THE BWR SCRAM
SYSTEM (GENERIC LETTER NO. 81-30)
(PREVIOUSLY ISSUED JULY 7, 1981 AS GENERIC LETTER 8r-26 IS NOW
IDENTIFIED AS 81-30)
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
8112170381 8107531 PDR NUREGQ qz
0803 C Ono
, M9n