IR 05000803/2009013

Notice of Violation from Insp on 850803-0913

ML20133D125
Person / Time
Site:	Perry, 05000803
Issue date:	10/03/1985
From:	Paperiello C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20133D124	List: IR 05000440/1985053 IR 05000803/2009013 ML20133D118
References
50-440-85-53, NUDOCS 8510080135
Download: ML20133D125 (2)

Text

{{#Wiki_filter:. . Appendix NOTICE OF VIOLATION The Cleveland Electric Illuminating Docket No. 50-440 Company (CEI) As a result of the inspection conducted on August 3 through September 13, 1985, and in accordance with the General Policy and Procedures for NRC Enforcement Actions, (10 CFR Part 2, Appendix C), the following violations were identified: CFR 50, Appendix B, Criterion V, as implemented by CEI's Corporate Nuclear Quality Assurance Program (CNQAP), Section 0500, Revision 6, states that, " Activities affecting quality shall be prescribed by documented instructions, procedures, or drawings, of a type appropriate to the circumstances."

Contrary to the above, preoperational test procedure TP 1P57-P001,

" Safety-Related Instrument Air," is not appropriate in that this procedure does not adequately control the sequence of testin Although Section 6.0, Note 2, Indicates that any independent section can be done in any order, there are two identified instances where performing the sections out of order will result in failed or inadequate testing. Contrary to test requirements, failing to perform step 6.1.1 prior to Section 6.5 will prevent depressurization of the compressor discharge pipin In addition, failing to perform steps 6.3.6 and 6.3.8 prior to Section 6.5 will result in a nonconservative partial test instead of a system wide pressure drop tes This is a Severity Level IV violation (Supplement II). CFR 50, Appendix 0, Criterion V, as implemented by CEI's CNQAP, Section 0500, Revision 6, states that, " Activities affecting quality shall be prescribed by documented instructions, procedures, or drawings of a type appropriate to the circumstances, and shall be accomplished in accordance with these instructions, procedures, or drawings."

Contrary to the abave, testing conducted in conjunction with preoperational test procedures TP 1R76-P001, "ECCS Initiation / Loss of Offsite Power," TP IC71-P001, " Reactor Protection System," and TP IM51-P001, " Combustible Gas Control System," was not acccmplished in accordance with appilcable procedure requirement In procedure TP 1R76-P001, step 6.4.9.a(4) consists of racking-in breaker D11210 and verifying that its associated system is in readiness for auto-start and operation. A failure to properly perform this procedure step by not turning on the charging spring 05100001350[[PDH33 PDH ADOCK 0 Q 4o _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ .

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Appendix 2 motor resulted in a failure of Residual Heat Removal Pump C to start during the simultaneous Loss of Offsite Power and Loss of Coolant Accident test. In addition, Reperformance #1 of procecure TP 1M51-P001 was not conducted in accordance with administrative requirements of Test Program Instruction (TPI)-26,

" Conduct of Preoperational, Special, and Acceptance Tests." The System Test Engineer (STE) did not specify to the Lead Test Engineer (LTE) the particular steps to be reperformed and did not have the LTE sign the chronological log entry depicting these steps to show his approval prior to the reperformance. Furthermore, in procedure TP IC71-P001, prerequisite step 5.2 was improperly verified and signed off as completed. This step indicated installation of the Main Steam Isolation Valve (MSIV) open limit switches was complete, even though the limit switch for MSIV 1821-F0228 was disassembled and incapable of supporting the test. Finally, a change was made to Attachment 5 of procedure TP 1C71-P001 to modify the method of simulating an open MSIV without processing a Test Change Form in accordance with the requirements of TPI-2 This is a Severity Level IV violation (Supplement II).

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 violation; and (3) the date when full compliance will be achieve Consideration may be given to extending your response time for good cause show _ anae W Dated W ^~ C.(/. Pagfriello, Director Division of Reactor Safety _ }}