ML19341C397
| ML19341C397 | |
| Person / Time | |
|---|---|
| Site: | Clinton  |
| Issue date: | 02/13/1981 |
| From: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Gerstner W ILLINOIS POWER CO. |
| References | |
| NUDOCS 8103030318 | |
| Download: ML19341C397 (2) | |
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Docket No. 50-461 Docket No. 50-462 Illinois Power Company ATTN:
Mr. W. C. Gerstner Executive Vice President 500 South 27th Street Decatur, IL 62525 cc w/ enc 1:
Central files AD/ Licensing AD/ Operating Reactors PDR v
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Dean Hansell, Office of gl FEB 2 71937,17,)
Assistant Attorney General Gary N. Wright, Deputy
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Director V
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Randall L. Plant, Prairie Alliance (v
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GLEN ELLYN, ILLINOIS 60137 February 13, 1981 Gentlemen:
Enclosed is IE Bulletin No. 80-17, Supplement 5, which is transmitted for information with regard to your nuclear power facility.
Should you have any questions regarding this bulletin supplement, please contact this office.
Sincerely h
4 kJamesG.Keppler U
Director
Enclosure:
IE Bulletin No. 80-17, Supplement 5 i
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u SSINS No.: 6820.
Accession No.:
8011042b9 V
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, 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 Loncer 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 1
you have any questions regarding this matter, please contact the appropriate NRC Regional Office.
Attachment:
Recently issued IE Bulletins 6-.
.Lu, Attach 0Gnt IEB 80-17, Supp. 5 4
February 13, 1981 RECENTLY ISSUED IE BULLETINS Bulletin No.
Subject Date Issued Issued To 81-01 Surveillance of 1/27/81 All power reactor Mechanical Snubbers facilities with an OL
& to specified facilities with CP 80-25 Operating Problems with 12/19/80 All BWR facilities Target Rock Safety-Relief with an OL & specified Valves at BWRs near term OL BWR facilities & all BWRs with a CP Supplement 4 Failure of Control Rods 12/18/80' To specified BWRs to 80-17 to Insert During a Scram with an OL & All at a BWR BWRs with a CP 80-24 Prevention of Damage 11/21/80 All power reactor Due to Water Leakage facilities with an Inside Containment OL or CP (October 17, 1980 Indian Point 2 Event) 80-23 Failures of Solenoid 11/14/80 All power reactor Valves Manufactured by facilities with Valcor Engineering OL or CP Corporation 80-22 Automation Industries, 9/11/80 All radiography i
Model 200-520-008 Sealed-licensees Source Connectors 80-21 Valve yokes supplied by 11/6/80 All light water Malcolm Foundry Company, Inc.
reactor facilities with OLs or cps Supplement 3 Environmental Qualification 10/24/80 All power reactor to 79-018 of Class 1E Equipment facilities with an OL Supplement 2 Environmental Qualification 9/30/80 All power reactor to 79-01B of Class 1E Equipment facilities with an OL OL = Operating License CP = Construction Permit i
.