ML19341C386
| ML19341C386 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 02/13/1981 |
| From: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Pasternak R POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| References | |
| NUDOCS 8103030278 | |
| Download: ML19341C386 (1) | |
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION L {p,(
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631 PARK AVENUE
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FEB 131981 0
Docket No. 50-333 s
N{C fQ Power Authority of the State of New York I
62 James A. FitzPatrick Nuclear Power Plant J
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ATTN: Mr. R. J. Pasternak
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IlTT [' Y Gentlemen:
The enclosed IE Bulletin No. 80-17, Supplement 5, " Failure of Control Rods to Insert During a Scram at a BWR," is forwarded to inform you of actions that are no longer required. A written response to this supplement is not required.
If you desire additional information regarding this matter, please contact this office.
Sincerely, Boyce H. Grier Director
Enclosures:
1.
IE Bulletin No. 80-17, Supplement 5, with 1 Attachment CONTACT:
D. L. Caphton (215-337-5266) cc w/encls:
George T. Berry, President and Chief Operat.ing Officer J. P. Bayne, Senior Vice President-Nuclear Generation A. Klausmann, Director, Quality Assurance M. C. Cosgrove, Site Quality Assurance Engineer J. F. Davis, Chairman, Safety Review Committee C. M. Pratt, Assistant General Counsel G. M. Wilverding, Manager-Nuclear Licensing 9
8103030878
o SSINS No.:
6820 Accession No.:
801104259 IEB 80-17, Supp. 5 UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C.
20555 February 13, 1981 IE BULLETIN NO. 80-17, SUPPLEMENT 5:
FAILURE OF CONTROL RODS TO INSERT DURING A SCRAM AT A BWR Description of Circumstances:
On July 3, 198C, the NRC issued IE Bulletin No. 80-17, that required actions to be taken by licensees of all operating GE BWRs.
Among the actions required, Item 6(a) required a prompt notification report by telephone to the appropriate Regional Office followed by a telecopy or other written submittal.
These reports were required in the event that any of the systems (HPCI, RCIC, SLCS, RPT, RHR/ pool cooling, and main steam bypass) were found to be less than fully operable.
These reports have served the purpose of notifying NRC of cases of potential reduction in operability of systems important to the mitigation of consequences of an anticipated transient without scram (ATWS) event.
These reports are no longer necessary since improvements have been accomplished to increase the reliability of control rod scram.
Actions No Longer Necessary by Licensees:
Further reporting is not required in response to Item 6(a) of IE Bulletin No. 80-17.
This does not change the reporting requirements set forth in your license technical specifications.
No written response to IE Bulletin 80-17, Supplement 5, is required.
If you have any questions regarding this matter, please contact the appropriate NRC Regional Office.
Attachment:
Recently issued IE Bulletins l
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Attachment IE Bulletin No. 80-17, Supp. 5 February 13, 1981 RECENTLY ISSUED IE BULLETINS Bulletin Subject Date Issued Issued To No.
81-01 Surveillance of 1/27/81 All holders of a Mechanical Snubbers power reactor OL or CP 80-25 Operating Problems 12/19/80 All holders of a with Target Rock Safety-BWR power reactor Relief Valves at BWRs OL or CP Supplement 4 Failure of Control Rods 12/18/80 All holders of a to 80-17 to Insert During a BWR power reactor Scram at a BWR OL or CP 80-24 Prevention of Damage Due 11/21/80 All holders of a to Water Leakage Inside power reactor OL Containment (October 17, or CP 1980 Indian Point 2 Event) 80-23 Failures of Solenoid 11/14/80 All holders of a Valves Manufactured by power reactor OL Valcor Engineering or CP Corporation 80-22 Automation Industries, 9/12/80 All holders of a Model 200-520-008 Sealed-radiography license Source Connectors 80-21 Valve Yokes Supplied by 11/6/80 All holders of a Malcolm Foundry Company, Inc.
Revision 1 Boron Loss from 8/29/80 All holders to 79-26 BWR Control Blades of a BWR power reactor OL Revision 1 Failures of Mercury-8/15/80 All holders of a to 80-19 Wetted Matrix Relays in power reactor Reactor Protective OL or CP Systems of Operating Nuclear Power Plants l
Designed by Combustion Engineering 80-20 Failures of Westinghouse 7/31/80 All holders of a Type W-2 Spring Return to power reactor OL Neutral Control Switches or CP m
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