ML20211Q364

Notice of Violation from Insp on 970810-0920.Violation Noted:As of 970731,Condition Rept 97-0989 Identified 3 Addl Valves That Had Non Qualified Thermal Overload Relays Installed in TS Required Equipment

ML20211Q364
Person / Time
Site:	Waterford
Issue date:	10/17/1997
From:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20211Q353	List: IR 05000382/1997016 ML20211Q349 ML20211Q364
References
50-382-97-16, NUDOCS 9710220273
Download: ML20211Q364 (2)

Text

- ___-____ _ _ _ _ _ _ _ _

ENCLOSURE 1 NOTICE OF VIOLATION Entergy Operations, Inc. Docket No.: 50 382 Waterford Steam Electric Station, Unit 3 License No.: NPF-38 During an NRC inspection conducted on August 10 through September 20,1997,a violation of NRC requirements was identified, in accordance with the " General Statement of Policy and Procedure for NRC Enforcement Actions," NUREG 1600, the siolation is listed below:

A. 10 CFR 50, Appendix B, Criterion V, states, in part, that activities affecting quality shall be accomplished in accordance with documented instructions appropriate to the circumstances.

Procedure W2.501, " Corrective Action," Step 6.1.2.3, states that the shif t technical advisor or a senior reactor operator will perform an operability assessment for a condition report in accordance with the instructions given in Attachment II,

" Operability Assessment and immediate Reportability Determination." Attachment 11 provides an example of the OPERABILITY ASSESSMENT portion of the condition report form including instructions. Attachment II, Instruction 1.A requires persennel to identify whether the component affects Technical Specification or Technical Requirements Manual applicable equipment or systems. Attachment instruction 1.D.2 directs that if the equipment or system remains operable, dor ument an evaluation in the BASIS section of the form.

Contrary to the above, operability assessments, an activity affecting quality, were not processed in accordance with the administrative requirements discussed above, in that:

(1) As of July 31,1997, Condition Report 97-0989 identified three additional valves that had nonqualified thermal overload relays installed in Technical Specification required equipment without personnel assessing the impact on operability of the nonqualified relays in the basis section of the form.

2) On April 23,1997, Condition Report 97-0989 related to the overload relays for Valve EFW 2208, Emergency Feedwater Header A isolation valve, did not correctly identify this as Technical Specification / Technical Requirements Manual related equipment and, as a result, no operability evaluation was documented in the basis section of the form.

(3) On February 3,1997, Condition Report 97-0258, related to a missing spent fuel handling machine seismic restraint, did not have documented an appropriate evaluation of operability in the basis section of the form.

This is a Severity Level IV violation. (Supplement 11(50-382/9716-01) 9710220273 971017 PDR ADOCK 05000302 G PDR

_ . _ _ ~ ._ _ _ . _ _ _ m 4

i.

l 2-i.

Pursuant to the provisions of 10 CFR 2.201, Entery Operations, Inc. is hereby required to i submit a written statement or explanation to the U.S. Nuclear Regulatory Commission.

l

! ATTN: Document Control Desk, Washington, D.C. 20555 with a copy to the Regional l

Administrator, Region IV,611 Ryan Plaza Drive, Suite 400, Arlington, Texas 76011, and a

. copy to the NRC Resident inspector at the facility that is the subject of this Notice, within 30 days of the cate of the letter transmitting this Notice of Violation (Notice). This reply should be clearly marked as a " Reply to a Notico 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 l l compliance will be achieved. Your response may reference or include previous docketed j'

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, j- suspended, or revoked, or why such other action as may be proper should not be taken, j 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, proprietary, or safeguards  ;

l 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 j request for whhholding the information from the public.

! Dated at Arlington, Texas ,

l this 17th day of October.1997 i

i i

4 i

1 l

i l-

--w c, e.y,-,-m-- r h ."', ~,-,,-,n,--,.y,,, -% ,e m ,m..w,, vg-,.~,v,- -,,.%-r.,,.-4, ,-, , me- , ,.-- ..w%,,,,,,,,_w,,,.,yy,wn,-, , e,w,. ,-