ML19350B559
| ML19350B559 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 02/13/1981 |
| From: | Seyfrit K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | Pilant J NEBRASKA PUBLIC POWER DISTRICT |
| References | |
| NUDOCS 8103200895 | |
| Download: ML19350B559 (1) | |
Text
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UNITED STATES PDR:HQ i
NUCLEAR REGULATORY COMMISSION LPDR y.,,,
E REGION IV
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611 RYAN PLAZA DRIVE. SUITE 1000 8
ARLINGTON. TEXAS 76011
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STATE February 13, 1981 Docket No. 50-298 k
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d[g Q[f Nebraska Public Power District ATTN:
J. M. Pilant, Director g
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Post Office Box 499 Columbus, Nebraska 68601 9- %s. g
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Gentlemen:
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The enclosed lE Bulletin No. 80-17, Supplement 5, is forwarded hf 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, P
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'Karl V. Seyfri Director
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Enclosures:
1.
IE Bulletin No. 80-17, Supplement 5 2.
List of Recently Issued IE Bulletins l
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SSINS No.:
6820 Accession No.:
801104259 UNITED STATES NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20555 IE Bulletin No. 80-17, Supplement 5 February 13, 1981 Page 1 of 1 FAILURE OF CONTROL RODS TO INSERT DURING A SCRAM AT A BWR Description of Circumstances:
On July 3, 1980, 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.
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IE Bulletin No. 81-17, Supp. 5 February 13, 1981 RECENTLY ISSUED IE BULLETINS Bulletin Subject Date Issued Issued To No.
Sup. 3 Environmental Qualifica-10/24/80 All power reactor to 79-01B tion of Class IE facilities with an Equipment Operating License (0L) or Construction Permit (CP) 80-21 Valve Yokes Supplied by 11/6/80 All light water Malcolm Foundry Company,-Inc.
reactor facilities holding Operating Licenses (0Ls) or Construction Permits (cps) 80-22 Automation Industries, 9/11/80 All radiography licensees Model 200-520-008 Sealed-Source Connectors 80-23 Failures of Solenoid 11/14/80 All power reactor facilities Valves Manufactured by with Operating License (OL)
Valcor Engineering or Construction Permit (CP)
Corporation 80-24 Prevention of Damage 11/21/80 All power reactor facilities Due to Water Leakage with Operating License (0L)
Inside Containment or Construction Permit (CP)
(October 17, 1980 Indian Point 2 Event)
Sup. 4 Failure of Control Rods 12/18/80 To specified BWRs with Bulletin to Insert During A Scram an Operating License (OL) 80-17 at a BWR and All BWRs with a Construction Permit (CP) 80-25 Operating Problems with 12/19/80 All BWR facilities with Target Rock Safety-Relief Operating License (0L)
Valves at BWRs and specified near term Operating License (0L) l BWR facilities and all BWRs with a Construction Permit (CP) l 81-01 Surveillance of 1/27/81 All power reactor Mechanical Snubbers
. facilities with an l
Operating License (OL)
.and to specified facilities with Construction Permit (CP)
Enclosure l
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