ML20052B320
| ML20052B320 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 04/14/1982 |
| From: | Starostecki R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20052B309 | List: |
| References | |
| 50-333-82-06, 50-333-82-6, NUDOCS 8204300285 | |
| Download: ML20052B320 (2) | |
Text
- __
l APPENDIX A NOTICE OF VIOLATION Power Authority of the State of New York Docket No. 50-333 James A. FitzPatrick Nuclear Power Plant License No. DPR-59 As a result of the inspection conducted March 1-31, 1982, and in accordance with the NRC Enforcement policy (10CFR2, Appendix C) 47 FR 9987 (March 9, 1982), the following violations were identified:
A.
Technical Specification 6.8(A) requires that written procedures and administrative policies be established, implemented and maintained that meet or exceed the requirements and recomendations of Section 5,
" Facility Ad::11nistrative Policies and Procedures," of ANSI 18.7-1972.
ANSI 18.7, Section 5.3.4.l(1), requires a determination that startup prerequisites have been met, including confirmation that valves are properly aligned.
Contrary to the above, the licensee failed to establish adequate controls to ensure all valves were properly aligned prior to startup in the following two examples.
On March 4, 1982, two manually operated Residual Heat Remeval System valves,RHR 250C and RHR 45C,were found in a position different from the position signed off on the prestartup valve checkoff list.
On March 15, 1982, a containment isolation valve in the Breathing Air System, BAS 4, which was signed off as locked closed on February 28, 1982 on the surveillance data sheet for F-ST-15H, Primary Containment Integrity, Manual Isolation Valves Position Verification, was found open. No prestartup valve lineup check was completed on this system and none is required by the Cold Startup Checkoff List in F-0P-65, Startup and Shutdown Procedure, Revision 10, dated January 22, 1982.
This is a Severity Level IV Violation (Supplement I).
B.
Technical Specification 3.6.A.1 requires that the average rate of reactor coolant temperature change during manual heatup not exceed 1000F/hr. when averaged over a one hour period.
Contrary to the above, the process computer alarm printer and the surveillance data sheet for F-ST-26J, Heatup and Cooldown Temperature Checks, indicate that the reactor coolant temperature change from 9:15 p.m. to 10:15 p.m. on March 6,1982 was 106.480F.
This is a Severity Level IV Violation (Supplement I).
8204S0G N i
Appendix A 2
C.
Technical Specification 3.7.A.9 requires that the primary containment atmosphere be continuously monitored for hydrogen and oxygen when containment integrity is required.
Contrary to the above, the primary containment was not continuously monitored for oxygen from 10:00 p.m. on March 12,1982 until 10:00 a.m.
on March 13, 1982 and from about 4:30 p.m. on March 13, 1982 until 10:45 a.m. on March 15, 1982.
This is a Severity Level IV Violation (Supplement I).
Pursuant to the provisions of 10 CFR 2.201, The Power Authority of the State of New York is hereby required to submit to this office within thirty days of the date of this Notice, a written statement or explanation in reply, including:
(1) the corrective steps which have been taken and the results achieved; (2) corrective steps which will be taken to avoid further violations, and (3) the date when full compliance will be achieved. Under the authority of Section 182 of the Atomic Energy Act of 1954, as amended, this response shall be submitted under oath or affinnation. Where good cause is shown, consideration will be given to extending your response time.
Dated Richard W. StarR tecki, Director, Division of Project and Resident Programs l
I i
l l