ML17138B819
| ML17138B819 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 02/13/1981 |
| From: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Curtis N PENNSYLVANIA POWER & LIGHT CO. |
| References | |
| NUDOCS 8103030386 | |
| Download: ML17138B819 (5) | |
Text
~R AE0Ij, (4
fp
+4 0
Cy I
n0
~
~4~
Yg4~
~O
++*++
Docket Nos.
50-387 50-388 UNITED STATES NUCLEAR REGULATORY COMMISSION REGION I 631 PARK AVENUE KING OF PRUSSIA, PENNSYLVANIA19406 FEB 13 198l re&'ennsylvania Power and Light Company ATTN:
Nr. Norman W. Curtis
'ice President Engineering and Construction - Nuclear 2 North Ninth Street All entown, Penn syl vani a 18101 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 you information.
No written response is required.
If you desire additional information regarding this matter, please, contact this office.
Sincerely, oyce 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:
A.
R. Sabol,
- Nanager, Nuclear guality Assurance W.
E. Barberich,.Licensing Engineer H.
W. Keiser, Superintendent. of Plant 810308038'@
Y
UNITED STATES NUCLEAR REGULATORY COMMISSION MASHINGTON, D.C.
20555 February 13, 1981 SSINS No.:
6820 Accession No.:
801104259 IEB 80-17, Supp.
5 IE BULLETIN NO. 80-17, SUPPLEMENT 5:
FAILURE OF CONTROL RODS TO INSERT DURING A SCRAM AT A BWR Descri tion 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 BMRs.
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,
- 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 (ATMS) event.
These reports are no longer necessary since improvements have been accomplished to increase the reliability of control rod scram.
Actions No Lon er Necessar b
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'RC Regional Office.
Attachment:
Recently issued IE Bulletins
RECENTLY ISSUED IE BULLETINS Attachment IE Bulletin No. 80-17, Supp.
5
, February 13, 1981 Bul 1 etin No.
81-01 80-25 Supplement 4
to 80-17 80-24 80-23 80-22 80-21 Revision 1
to 79-26 Revision 1
to 80-19 80-20 Subject Surveillance of Mechanical Snubbers Operating Problems with Target Rock Safety-Relief Valves at BWRs
'ailure of Control Rods to Insert During a Scram at a
BWR Prevention of Damage Due to Water Leakage Inside Containment (October 'l7, 1980 Indian Point 2
Event)
Failures 'of Solenoid Val ves Manufactured by Valcor Engineering Corporation Automation Industries, Model 200-520-008 Sealed-Source Connectors Valve Yokes Supplied by Malcolm Foundry Company, Inc.
Boron Loss from BWR Control Blades Failures of Mercury-Wetted Matrix Relays in Reactor Protective Systems of Operating Nuclear Power Plants Designed by Combustion Engineering Failures of Westinghouse Type W-2 Spring Return to Neutral Control Switches Date Issued 1/27/81 12/19/80 12/18/80 11/21/80 11/14/80 9/12/80 11/6/80 8/29/80 8/15/80 7/31/80 Issued To All holders of a power reactor OL or CP All holders of a BWR power reactor OL or CP All holders of a BWR power reactor OL or CP All holders of a power reactor OL or CP All holders of a power reactor OL or CP All holders of a radiography license All holders of a power reactor OL or CP All holders of a BWR power reactor OL All holders of a power reactor OL or CP All holders of a power reactor OL or CP