ML20210R523

Notice of Violation from Insp on 970707-25.Violation Noted: Final Safety Analysis Rept Updated File in May of 1996 Did Not Include Latest Matl Developed 6 Months Prior to Date of Filing

ML20210R523
Person / Time
Site:	Waterford
Issue date:	08/27/1997
From:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20210R504	List: IR 05000382/1997014 ML20210R500 ML20210R523
References
50-382-97-14, NUDOCS 9709030145
Download: ML20210R523 (2)

Text

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I l s 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 July 7-25,1997, one violation of NRC requirements was identified, in accordance.with the " General Statement of Policy anci Procedure for NRC Enforcement Actions," NUREG 1600, the violation is listed below:

10 CFR 50.71(e) requires that the licensee update the Final Safety Analysis Report to include the latest material developed. 10 CFR 50.71(e) further requires the licensee to update their safety analysis report 6 months aftur each refueling outage. The revision must reflect all changes up to a maximum of 6 months prior to the date of filing. -

Contrary to the above, the Updated Final Safety Analysis Report update filed in May of 1996 did not include the latest matarial developed 6 months prior to the date of filing. l Specifically:

1) Since the original submittal, Final Safety Analysis Report Table 9.21, " Design Data For The Component Cooling Water System and Auxiliary Component Cooling Water System Component," Sheet 1 of 5 incorrectly showed component cooling water system pump motor capacity as 3000 horsepower instead of 300 horsepower.

2) Since the original submittal, Final Safety Analysis Report page 8.12 had incorrect numbers for circuit breakers connecting the swing AB bus to the A or B bus.

3) Since the original submittal, Technical Specification Bases Section 3/4.7.1.2 incorrectly stated that each electric driven emergency feedwater pump was capable of delivering a total feedwater flow of 350 gpra at a pressure of 1163 psig to the entrance of the steam generators. On August 4,1995, the licensee determined that the bases section should have read that each electric-driven emergency feedwater  !

pump was capable of delivering a total flow of 350 gpm at a pressure of 1163 psig at the discharge of the pump.

This is a Severity Level IV violation (Supplement 1)(50 382/9714 01). '

The NRC has concluded, that information regarding the reason for the violation, the corrective actions taken and planned to correct the violation and prevent recurrence, and the date when full compliance will be achieved, is already adequately addressed in the enclosed report. However, you are required to submit a written statement or explanation pursuant to 10 CFR 2.201, if the description therein does not accurately reflect your corrective actions or your position. In that case, or if you choose to respond, clearly mark

-your response as a " Reply to a Notice of Violation," and send it to the U.S. Nuclear Regulatory Commission,' ATTN: Document Control Desk. Washington, D.C. 20555 with a 9709030145 970827 PDR ADOCK 05000382 _-

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2-l copy to :Se Regional Administrator, Region IV,611 Rycn Plaza Drive, Suite 400, Arlington, Texas 76011, and a copy to the NRC Resident inspector at the facility that is the subject l of this Notice, within 30 days of the date of the letter transmitting this Notice of Violation l (Notice).

Dated at Arlington, Texas this# day of August 1997 l

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