ML20203K953
| ML20203K953 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 08/08/1986 |
| From: | Sieber J DUQUESNE LIGHT CO. |
| To: | Wenzinger E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| NUDOCS 8608220278 | |
| Download: ML20203K953 (3) | |
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Telephone (412) 393-s000 Nuclear Group August 8, 1986 P.O. Box 4 Shippingport, PA 15077-0004 U. S. Nuclear Regulatory Commission Office of Inspection and Enforcement Attn:
Mr. Edward C. Wenzinger, Chief Projects Branch No. 3 Division of Reactor Projects Region 1 631 Park Avenue Fing of Prussia, PA 19406
Reference:
Beaver Valley Power Station, Unit No. 1 Docket No. 50-334, License No. DPR-66 Inspection Report 86-11 Gentlemen:
In response to your letter of July 3, 1986, and in accordance with 10 CFR 2.201, the attached reply addresses the Notice of Violation which was included with the referenced report.
This response is being submitted late with the concurrence of the site NRC Sr. Resident Inspector.
If you have any questions concerning this
- response, please contact my office.
Very truly yours, A $v -
. D.
Sieber Senior Manager Beaver Valley Unit No. 1 Attachment cc: Mr. W. M. Troskoski, Resident Inspector U. S. Nuclear Regulatory Commission Beaver Valley Power Station Shippingport, PA 15077 U.
S. Nuclear Regulatory Commission c/o Document Management Branch Washington, DC 20555 Director, Safety Evaluation & Control Virginia Electric & Power Company P.O. Box 26666 One James River Plaza Richmond, VA 23261 8605230270 0.O r g
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DUQUESNE LIGHT COMPANY Beaver Valley Power Station Unit No. 1 Reply to Notice of Violation i
l Inspection 86-11 Letter Dated July 3, 1986 VIOLATION A (Severity Level IV:
Supplement 1) l Description of violation (86-11-02) 10 CFR 50, Appendix B,
Criteria XI, Test Control, requires the i
establishment of a
program to assure that all testing required to demonstrate that structures, systems and components will perform satisfactorily in service is performed in accordance with the requirements and acceptance limits contained in applicable design i
documents.
Contrary to the
- above, it was determined on May 22, 1986, that all i
features of the Backup Indicating Panel (installed prior to January 5,
- 1985, to meet the 10 CFR 50, Appendix R, Fire Protection safe shutdown requirements) were not tested to assure that they would perform satisfactorily in service by performing their intended design functions.
Specifically:
1.
A complete sensor to indicator functional test was not performed on the cold leg reactor coolant system temperature indicators.
As a
- result, functional testing did not identify that the instruments were incorrectly wired and inoperable.
2.
No' test was conducted to assure the keys provided for the BIP locking transfer
- switches, which are necessary to transfer indication from the control room to the panel, would work.
These keys did not fit the core of the lock, making actual transfer l
impossible.
Corrective Actions Taken i
i As noted in the Inspection Report the necessary wiring changes have i
been made and the BIP cold leg indication is operable.
In addition, i
the correct keys were permanently attached to the key rings and l
verified as fitting the BIP locking transfer switches.
Operations l
Surveillance Test 1.45.9 which tests the instrumentation channels at the BIP was completed satisfactory.
Action Taken to Prevent Recurrence I
The Nuclear Engineering Management Procedure 2.7
" Engineering i
specifications" will be revised to clearly establish minimum content requirements for design change test specifications.
The minimum i
i requirements will be consistent with the testing requirements for returning equipment to service as specified in Quality Assurance I
Procedure OP-ll, " Control of Maintenance and Modification".
- = -
e ply to Notica of Violation Inspection 86-11 Lstter dated July 3, 1986 Page 2 Date When Full Compliance will be Achieved Nuclear Engineering Management Procedure 2.7 will be revised by September 30, 1986.
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