ML20244C127

Notice of Violation from Insp on 890324-0430.Violations Noted:Two Examples of Failing to Comply W/Tech Spec Requirements & Inadequate Control of Replacement Parts for safety-related Equipment

ML20244C127
Person / Time
Site:	Fort Saint Vrain
Issue date:	06/08/1989
From:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20244C124	List: ML20244C122 ML20244C127 ML20244C130
References
50-267-89-07, 50-267-89-7, NUDOCS 8906140133
Download: ML20244C127 (2)

Text

'

['

% y APPENDIX A NOTICE OF VIOLATION Public Service Company of Colorado Docket: S0-267 Fort St. Vrain Nuclear Generating Station License: DPR-34 During NRC inspections conducted on March 24 and 29 and April 30,1989,two violations of NRC requirements were identified. The violations involved a failure to comply with the requirements of Technical Specification (TS) LCOs and inadequate control of replacement parts for safety-related equipment. In accordance with the " General Statement of Policy and Procedure for NRC Enforcement Actions," 10 CFR Part 2. Appendix C (1988), the violations are listed below:

A. Failure to Comply with the Requirements of Technical Specifications Two examples of the failure to comply with the requirements of Technical Specifications prior to changing plant conditions are as follows:

1. LC0 4.2.7.c and d specify that the prestressed concrete reactor vessel (PCRV) shall not be pressurized to more than 100 psia unless the interspaces between the primary and secondary penetration closures are maintained at a pressure greater than primary system pressure with purified helium gas.

Contrary to the above, the PCRV was pressurized to greater than 100 psia from 10:18 p.m. on March 23, 1989, until 1:02 a.m. on March 24, 1989, with the purified helium supply to the Region 27 interspace isolated.

2. Surveillance Requirement (SR) 5.6.1d requires that diesel engine exhaust temperature " shutdown" and "declutching functions" be tested monthly when the standby diesel generators are required.

The diesel generators are required per LCO 4.6.1 when reactor power exceeds 2 percent.

Contrary to the above, reactor power was greater than 2 percent from 8:21 p.m. on March 27, 1989, until 1:20 a.m. on March 29, 1989, with monthly TS Surveillance Requirement (SR) 5.6.1d not completed within the required interval.

This is a Severity Level IV violation. (Supplements)(267/8907-01)

B. Inadeouate Control of Replacement Parts for Safety-Related Equipment Criterion VIII of Appendix B to 10 CFR Part 50 and the licensee's quality assurance program require that measures be established for the identification of materials, parts, and components to prevent the use of incorrect or defective materials, parts, and components.

690614013? 890608 PDR ADOCK 05000267 Q PDC

( - * ,

? '

Contrary to the above, on April 12, 1989, an incorrect part number was ,

specified and used to obtain a replacement part which was then installed I in the "D" emergency diesel generator engine.

This is a Severity Level IV violation. (Supplement I) (267/8907-02)

Pursuant to the provisions of 10 CFR 2.201, Public Service Company of Colorado is hereby required to submit to this office within 30 days of the date of the letter transmitting this Notice, a written statement or explanation in reply, including for each violation: (1) the reason for the violations if admitted, (2) the corrective steps which have been taken and the results achieved, (3) the corrective steps which will be taken to avoid further violations, and (4) the date when full compliance will be achieved. Where good cause is shown, consideration will be given to extending the response time.

Dated at Arlington, exas this g d day of / 1989.

_.- _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _