ML19344E407
| ML19344E407 | |
| Person / Time | |
|---|---|
| Site: | Limerick  |
| Issue date: | 08/19/1980 |
| From: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | Kemper J PECO ENERGY CO., (FORMERLY PHILADELPHIA ELECTRIC |
| References | |
| NUDOCS 8008280526 | |
| Download: ML19344E407 (1) | |
Text
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UNITED STATES 8'
NUCLEAR REGULATORY COMMISSION o
,E REGION I o,
631 PARK AVENUE l
,o',c KING OF PRUSSIA, PENNSYt.VANIA 19406 August 19, 1980 Docket Nos. 50-352 50-353 Philadelphia Electric Company ATTN:
Mr. John S. Kemper Vice President Engineering and Research 2301 Market Street Philadelphia, Pennsylvania 19101 Gentlemen:
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The enclosed IE Information Notice No. 80-30, " Potential for Unacceptable l
Interaction Between the Control Rod Drive Scram Function and Non-Essential Control Air at Certain GE BWR Facilities," is forwarded to you for information.
No written response is required.
If you desire additional information regarding this matter, please contact this office.
Sincerely,
'I4?tik Vt -
i Bo ce H. Grier rector
Enclosures:
1.
IE Information Notice No. 80-30 2.
List of Recently Issued IE Information Notices CONTACT:
D. L. Caphton (215-337-5266) cc w/encls:
V. S. Boyer, Senior Vice President, Nuclear Power
.80082807 %
SSINS No.:6870 Accession No.:
8006190057 IN 80-30 UNITED STATES NUCLEAR REGULATORY COMMISSION 0FFICE OF INSPECTION AND ENFORCEMENT WASHINGTON, D.C.
20555 August 19, 1980 IE Information Notice No. 80-30:
POTENTIAL FOR UNACCEPTABLE INTERACTION BETWEEN THE CONTROL R0D DRIVE SCRAM FUNCTION AND NON-ESSENTIAL CONTROL AIR AT CERTAIN GE BWR FACILITIES Continued NRC evaluation of possible failure modes of the control rod drive system related to the Browns Ferry event (IE Bulletin 80-17), has identified a potentially significant single failure mechanism which could degrade the scram function.
The slow loss of non-essential control air pressure could degrade the scram function at certain facilities which have relatively poor communica-tion between the scram discharge volume (SDV) and the scram discharge instru-mented volume (SDIV) such that the SDIV drains more rapidly than the SDV drain rate into the SDIV.
The significance of such a single failure warrants transmission of an interim assessment by the NRC Office for Analysis and Evaluation of Operational Data as an early notification of a possibly significant matter that is still under review by the NRC staff.
It is expected that recipients will review the information for possible applicability to their facility.
No specific action or response is requested at this time.
If you have any questions regarding this matter, please contact the Director of the appropriate NRC Regional Office.
Enclosure:
Memo from C. Michelson to H. Denton, dated August 18, l
1980 l
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