ML20041B772
| ML20041B772 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs |
| Issue date: | 02/05/1982 |
| From: | Lundvall A BALTIMORE GAS & ELECTRIC CO. |
| To: | Starostecki R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| Shared Package | |
| ML20041B767 | List: |
| References | |
| NUDOCS 8202250184 | |
| Download: ML20041B772 (3) | |
Text
,
B ALTIMORE G AS AND ELECTRIC COMPANY P.O. B O X 147 5 B ALTIMO R E. M A R YL A N D 21203 ARTHUR E. LUN DVALL,dR.
vice Parsieraa Sve>Lv February 5, 1982 U.S. Nuclear Regulatory Connission Docket Nos. 50-317 Region 1 50-318 631 Park Avenue King of Prussia, PA 19406 ATTENTION:
R. W. Starostecki, Director Division of Resident and Project Inspection Gentlenen:
This refers to your Inspection Report 50-317/81-24; 50-318/81-23, which transnitted two itens of apparent nonconpliance with NRC require-ments.
Enclosure (1) to this letter is a written statenent in reply to those items.
Should you have further questions regarding this reply, we will be pleased to discuss then with you.
Very truly yo,urs,
/
/
/
m s
[
[~
,[
g~vMt w d [
^
Vice Presiden - Supply AEL/DWL/gla Enclosure (1) cc:
J. A. Biddison, Esquire G. F. Trowbridge, Esquire D. 11. Ja f fe, NRC R. E. Architzel, NRC 8202250184 820217 PDR ADOCK 05000317 PDR G
R. W. Starostecki 2
February 5, 1982 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:
Cd.
Im Notary Pub'lic My Commission Expires:
(/ /,/
b
/
0
ENCLOSURE (1)
REPLY TO APPENDIX A 0F NRC INSPECTION REPORT 50-317/81-24; 50-318/81-23 ITEM A.1 Upon identification, the access plate was replaced using proper procedural controls. This action corrected the existing situation.
In order to mini-mize the possibility of similar events occuring, a memo has been issued by the Plant Superintendent to plant personnel regarding the use of procedural controls governing maintenance and modification activities. The memo stresses the importance of all maintenance and modification work on safety-related systems regardless of how insignificant the work may seem.
ITEM A.2 On November 9, 1981, at 0902, with Unit 2 in MODE 3, the Control Room Operator (CRO) commenced blended make-up to the Volume Control Tank (VCT) in response to a VCT low level alarm. Make-up was secured at 0907 after the low level alarm had cleared and a VCT hi-hi pressure alarm had sounded. At that time, VCT pressure indication had reached 60 psig. At 0914, the main vent and waste gas discharge header radiation monitors alarmed. The CR0 immediately vented the VCT to the waste gas system, observing VCT pressure at 63-64 psig. The VCT pressure decreased to the low alarm setpoint at 0917 at which point the CR0 secured the VCT vent to the waste gas system. At 0919, the radiation monitoring system alarm cleared terminating the event.
The path of the release was apparently from the VCT, past the VCT N /H, 2
supply check valve (2-CVC-195) and past the VCT relief valve (2-CVC 103-RV) to the main vent.
A walkdown of the systems and manipulation of the valving to the VCT was performed to determine the possibility of other release paths. None were found.
The immediate corrective action was to administrative 1y linit the VCT pressure to 50 psig. This was accomplished by the initiation of night orders by the General Supervisor-operations and by revision of Control Room logs to list 50 psig. as the upper limit for VCT pressure. This admin-istrative limit was imposed to account for uncertainities in the relief valve setpoint and uncertainities in VCT pressure indication since the VCT relief valve lifted at an indicated pressure approximately 4-9 psig below the VCT relief valve cetpoint.
Maintenance requests have been in.itiated for repair of the VCT N,/H, supply check valve and for the testingand resetting (as necessary) of the'VCT relief valve. As removal of these components requires cessation of letdown and depressurization of the VCT, these repairs will be performed during the next scheduled cold shutdown.
In addition, calibration of the VCT pressure ano level indication loops will be checked. Together, these corrective actions should prevent further such events.
_.