ML17286A965
| ML17286A965 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 07/18/1991 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML17286A959 | List: |
| References | |
| 50-397-91-18, NUDOCS 9108050062 | |
| Download: ML17286A965 (4) | |
Text
APPENDIX A NOTICE OF VIOLATION Washington Public Power Supply System Post Office Box 968
- Richland, WA 99352 Docket No. 50-397
=
License No. NPF-21
'During an NRC inspection conducted on May 13 - June 23, 1991, violations of NRC requirements were identified.
In accordance with the "General Statement of Policy and Procedure for NRC Enforcement Actions," 10 CFR Part 2, Appendix C (1991),
the violations are listed below:
A.-
Technical Specification 6.8.1 states in part, "Written procedures shall be established, implemented, and maintained covering the activities
'eferenced below:
"a.
The applicable procedures recommended in Appendix A of Regulatory Guide 1.33, Revision 2, February 1978."
Appendix A of Regulatory Guide 1.33, Section 1.c, lists a procedure for "Equipment Control (e.g. locking and tagging)."
PPM 1.3.8C, Dan er Ta Clearance Order Manual
, Revision 0, Section 4.2.18,
- states, "Independent Verification is required when the component is SAFETY,RELATED (gC 1)...".
PPM 1.3.8A, Caution Ta
- Order, Revision 0, Section 6.B.2.c.(6),
states in part, "If work is associated with-Safety-Related...
- Systems, an independent verification of component position is required by a second qualified 'individu'al."
Contrary to the above, on May 24, 1991 the following clearance orders on safety related systems had not received independent (second) verification:
Clearance Order No.
91-6-C005 (Caution) 91-5-C094 (Caution) 91-5-C004 (Caution) 90-9-C021 (Caution) 90-12-C084 (Danger)
~Sstem Containment Atmospher ic Control Reactor Core Isolation Cooling Inverter No.
3 t
High Pressure Core Spray Leak Detection System This is a Severity. Level IV violation.
(Supplement I).
B.
Technical Specification 6.8.1 states in part: "Written procedures shall be established, implemented and maintained covering the activities referenced below:
PDR gZ)
~ 910748 910BOg Q
OCR 05000g9y PDP
l l
0 "g.
Fire Protection Program implementation."
PPM 1.3.10, Revision ll, Fire Protection Pr'o ram, states in part:
"10.0 FIRE PROTECTION SYSTEM IMPAIRMENT CHECKLIST "10.f
~Ri d
h "10. 1.6 Leaving a normal closed fire door or damper in open position."
Contrary to the above, on May 13, 1991, normally closed fire door R402 at the northeast corner of the 522'level of the reactor building.was propped in the open position and a Fire Protection System Impairment Checklist had not been provided.
This is a Severity Level IV violation (Supplement I).
Pursuant to the provisions of 10 CFR 2.201, Washington Public Power Supply System is hereby required to submit a written statement or explanation to the U. S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, DC 20555, with a copy to the Regional Administrator, Region V, and a copy to the NRC Resident Inspector, within 30 days of the date of the letter transmitting this Notice'of Violation (Notice).
This reply should be clearly marked as a "Reply to a Notice of Violation" and should include for each violation: (1) the reason for the violation, or, if contested, the basis for disputing the violation, (2) the corrective steps that have been taken and the results
- achieved, (3) the corr'ective steps that will be taken to avoid further violations, and (4) the date when full compliance will be achieved.
If an adequate reply is not received within the time specified in this
- Notice, an order may be issued to show cause why the license should not be
- modified, suspended, or revoked or why. such other action as may be proper should not be taken.
Where good cause is shown, consideration will be given to extending the response time.
Dated at Walnut Creek, California this g8i. day ot'1991