ML20237F144
| ML20237F144 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 12/10/1987 |
| From: | Forney W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20237F133 | List: |
| References | |
| 50-440-87-16, NUDOCS 8712290391 | |
| Download: ML20237F144 (2) | |
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l NOTICE OF VIOLATION The Cleveland Electric Illuminating License No. NPF-58 Company As a result of the inspection conducted on August 13, 1987 through October 19, 1987, and in accordance with the " General Policy and Procedures for NRC Enforcement Actions," 10 CFR Part 2, Appendix C, the following violations were identified:
1.
10 CFR 50, Appendix B, Criterion V, as implemented by the PNPP Quality Assurance Plan, Section 5.0, requires, in part, that activities affecting quality shall be prescribed by clear and complete documented procedures, instructions and/or drawings, of a type appropriate to the circumstances, and shall be accomplished in accordance with these documents.
Plant Administrative Procedure (PAP)-905, " Work Order Process", states, in part, that the Job Traveler (step-by-step instruction) associated with a Work Order shall specify those instances when interface with other CEI organizational elements or suppliers is necessary and how that interface is accomplished.
Contrary to the above, the Job Traveler associated with Work Order 87-733 which authorized and directed the rework of Main Steam Isolation Valve IB21-F028B in July and August,1987, did not specify that interface with Power Cutting Incorporated (PCI) was necessary during the valve rework nor did it specify how the interface was to be accomplished.
Valve seat lapping and verification of valve seating surface acceptability originally specified in the Job Traveler was not required to be performed following grinding of the valve seat by PCI.
Valve seating surface irregularities which remained following grinding by PCI therefore went undetected and contributed to subsequent valve inoperability due to excessive leakage.
This is a Severity Level IV violation (Supplement I).
2.
10 CFR 50, Appendix B, Criterion V, as implemented by the PNPP Quality Assurance Plan, Section 5, requires, in part, that activities affecting quality shall be prescribed by clear and complete documented instructions, procedures and/or drawings, of a type appropriate to the circumstances.
Contrary to the above, Periodic Test Instruction (PTI)-N27-P0001,
" Reactor Feedwater Pump Turbine Stop Valve Test" was inappropriate in that it did not require that the the feedwater pump controller be operating /placed in the manual mode prict to stroking the associated feedwater pump turbine low pressure stop valve.
Performance of the test,as written, on September 9,1987, resulted in a feedwater pump trip signal to the feedwater control circuitry, an unanticipated feedwater flow transient, and reactor scram due to high reactor water level.
8712290391 87i2iG PDR ADOCK 05000440 0
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This.is a Severity Level IV violation (Supplement I).
Pursuant to the provisions of 10 CFR 2.201, you are required to submit to this office within thirty days of the date of this Notice a written statement 'or explanation in reply, including for each violation:
(1) corrective action taken and the results achieved; (2) corrective action to be taken to avoid further violations; and (3) the date when full compliance will be achieved.
l Consideration may be given to extending your response time for good cause shown.
OEtt41987 w,[
Dated W. L. Forney, Chief /
Reactor Projects Branch 1
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