ML20063L119
| ML20063L119 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 08/12/1982 |
| From: | Lundvall A BALTIMORE GAS & ELECTRIC CO. |
| To: | Starostecki R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| Shared Package | |
| ML20063L084 | List: |
| References | |
| NUDOCS 8209080640 | |
| Download: ML20063L119 (3) | |
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BALTIMORE GAS AND ELECTRIC CHARLES CENTER P.O. BOX 1475 BALTIMORE, MARYLAND 21203 ARTHum E. LUNDVALL, JR.
WCC PRESIDENT August 12,1982 sumv U.S. Nuclear Regulatory Commission Docket Nos.
50-317 Region I l 50-318 631 Park Avenue License Nos.
DPR-53 King of Prussia, PA 19406 DPR-69 ATTENTION:
R. W. Starostecki, Director Division of Project and Resident Programs Gentlemen:
This refers to your Inspection Report 50-317/82-16; 50-318/82-14, which transmitted one item of apparent noncompliance with NRC requirements. Enclosure (1) to this letter is a written statement in reply to that item noted in your letter of July 16,1982.
Should you have further questions regarding this reply, we will be pleased to discuss them with you.
Very truly yours;
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Vice Presidedt - Supply AEL/DWL/gla Enclosure cc:
- 3. A. Biddison, Esquire G. F. Trowbridge, Esquire.
D. H. Jaffe, NRC R. E. Architzel, NRC
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B209080640 820902 PDR ADOCK 05000317 G
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Mr. R. W. Starostecki August 12,1982 Page 2 -
STATE OF MARYLAND TO WIT:
CITY OF BALTIMORE Arthur E. Lundvall, Jr., being duly sworn states that he is Vice President of the Baltimore Gas and Electric Company, a corporation of the State of Maryland; that he provides the foregoing response for the purposes therein set forth; that the statements made are true and correct to the best of his knowledge, information, and belief; and that he was authorized to provide the response on behalf of said Corporation.
WITNESS my Hand and Notarial Seal:
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Notary Public My Commission Expires:
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ENCLOSURE (1)
REPLY TO APPENDIX A OF NRC INSPECTION REPORT 50-317/82-16; 50-318/82-14 i
Item A Technical Specification 3/4.3.2, Engineered Safety Features Actuation System Instrumentation requires that the Auxiliary Feedwater Actuation System (AFAS) be operable in MODES 1,2, and 3. Contrary to this requirement, the AFAS was found to be inoperable-following entry into MODE 3 from MODE 4 on June 28, 1982, when the r
handswitches for the main steam supply isolation valves (MOV-4070 & 4071) were in pull-to-lock. Upon discovery, the handswitches were immediately returned to their normal positions. Initiation of auxiliary feedwater flow in the event of an AFAS would not have
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been delayed due to the procedural steps in the Alarm Manual which would have directed l
operators to manually initiate auxiliary feedwater flow upon receipt of an AFAS Time Delay initiated alarm.
Neither the plant start-up procedure checklist or the Surveillance Test Procedure 0-62, t
" Monthly Valve Position Verification," provided a check of the two handswitches prior to entry into MODE 3. Both documents have been revised to include a check of the valve position prior to entry into MODE 3.
Additionally, a verification of the sufficiency of administrative controls for MODE 1 & 2 Technical Specification Limits was conducted prior to completion of the start-up.
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