ML20132E894

Notice of Violation from Insp on 961001-08.Violation Noted: Licensee Staff Performed Bench Tests & Determined AOV Actuators in RCIC & PCIS Did Not Exhibit Preloaded Spring Closing Forces Specified in Written Specifications

ML20132E894
Person / Time
Site:	LaSalle
Issue date:	12/09/1996
From:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20132E882	List: ML20132E879 ML20132E894 ML20132E900
References
50-373-96-16, 50-374-96-16, NUDOCS 9612240020
Download: ML20132E894 (2)

Text

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e NOTICE OF VIOLATION Commonwealth Edison Company Dockets No. 50-373; 50-374 LaSalle County Station Units 1 and 2 Licenses No. NPF-11, NPF-18 During an NRC inspection conducted on October 1 through October 8,1996, one violation of NRC requirements was identified. In accordance with the " General Statement of Policy and Procedure for NRC Enforcement Actions," NUREG-1600, the violation is listed below:

1. 10 CFR 50, Appendix B, Criterion V states, in part, that activities affecting quality shall be prescribed by documented instructions and shall be accomplished in accordance with these instructions.

a. LAP-1500-8A, " Initiating A Problem Identification Form," Revision 0, Attachment B, Paragraph 4 states, in part, that a material which fails to meet drawing or written specifications or a material with faulty manufacturing warrants the initiation of a PlF.

b. LAP-220-5, " Equipment Operability Determination," Revision 3, Paragraphs 2.a,2.b, 2.c, and 2.d state, in part: that if any on-site personnel know of a possible operability issue then they must notify the Shift Engineer (SE) and promptly forward any documentation; that the SE shall review the information and ensure that a PIF is initiated; and that the SE shall make a determination of the issue's effect on SSC operability and document such determination on the PIF.

Contrary to the above,

a. On March 17,1996, licensee staff performed bench tests and determined that air operated valve (AOV) actuators in the Reactor Core isolation Cooling System (RCIC) and Primary Containment Isolation System (PCIS) did not exhibit the preloaded spring closing forces specified in their written specifications when adjusted using the vender's procedures, but no PlF was generated.

b. On April 1 and 2,1996, instructions were issued to rebuild RCIC and PCIS AOV actuators to bring them into compliance with their written specifications. Other PCIS AOVs were known to be equipped with similar actuators. Despite the acknowledgement of a non-conformance, t documentation of the identified need for corrective actions was not forwarded to the SE: no PIF was generated; and no documented operability j determination was made for the effected SSCs. o This is a Severity Level IV Violation (Supplement 1).

Pursuant to the provisions of 10 CFR 2.201, Commonwealth Edison Company is hereby  ;

required to submit a written statement of explanation to the U.S. Nuclear Regulatory l Commission, ATTN: Document Control Desk, Washington, DC 20555 with a copy to the Regional Administrator, Region Ill, and a copy to the NRC Resident inspector at the LaSalle 9612240020 961209 l PDR ADOCK 05000373 G PDR l

9 2-facility, within 30 days of the date of Notice of Violation 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 corrective steps that will be taken to avoid further violations, and (4) the date when full compliance will be achieved. Your response may reference or include previous docketed correspondence, if the correspondence adequately addresses the required response. If an adequate reply is not received within the time specified in this Notice, an order or a Demand for information may be issued as to 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. Because your response will be placed in the NRC Public Document Room (PDR), to the extent possible, it should not include any personal privacy, pr)prietary, or safeguards information so that it can be placed in the PDR without redaction. However, if you find it necessary to include such information, you should clearly indicate the specific information that you desire not to be placed in the PDR, and provide the legal basis to support your request for withholding the information from the public.

Dated at Lisle, Illinois this JL day of December 1996

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