ML20214M701

Notice of Violation from Insp on 860607-0703

ML20214M701
Person / Time
Site:	Crystal River
Issue date:	09/08/1986
From:	Walker R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20214M682	List: IR 05000302/1986020 ML20214M677 ML20214M701
References
50-302-86-20, NUDOCS 8609110232
Download: ML20214M701 (2)

Text

.- .

NOTICE OF VIOLATION Florida Power Corporation Docket No. 50-302 Crystal- River Unit 3 License No. DPR-72

- During the Nuclear Regulatory Commission (NRC) inspection conducted on June 7 -

July 3, 1986, a violation of NRC requirements .was . identified. The violation involved failures to properly implement procedures as required by the technical specifications. -In accordance with the " General _ Statement of Policy and Procedure for NRC Enforcement Action," 10 CFR Part 2, Appendix C (1986), the violation is listed below:

Technical Specification 6.8.1 requires the implementation of written procedures to cover those activities recommended in Appendix A of Regulatory Guide 1.33, November 1972 and the surveillance activities of safety related equipment.

Regulatory Guids 1,33, Appendix A, recommends procedures and/or written instructions for: the conduct of a plant startup, cold to hot; the operation of the emergency core cooling system; and performance of maintenance.

Procedure OP-202, Plant Heatup, step 6.4.7.15, requires the Decay Heat Removal system to ' be aligned for Engineered Safeguards (ES) operations in accordance - with procedure OP-404, Decay Heat Removal System. Procedure OP-404, Valve Checklist III, requires valve DHV-111 to be in the throttled position.

Administrative Instruction AI-600, Conduct of Maintenance, step 4.4.12, requires-that all nonemergency corrective maintenance on plant safety related equipment be authorized and documented by an approved Work Request (W/R),

Surveillance Procedure SP-201, Accessible / Inaccessible Hydraulic Snubbers Visual Inspection, revision 17, step 6.2.1, requires that if the reservoir sightglass fluid level is between 0-50 percent full, that the reservoir be refilled.

Contrary to the above:

a. On June 11, 1986, at approximately 1:30 p.m., procedures OP-202 and OP-404 were not implemented in that valve DHV-111 was found to be in the shut position;

b. On April 8, 1986, procedure AI-600 was not implemented in that corrective maintenance, in the form of a valve packing adjustment, was performed on valve IAV-90 prior to authorizing and documenting this maintenance with an approved W/R.

8609110232 860908 PDR ADOCK 05000302 G PDR

Florida Power Corporation 2 Docket No. 50-302 Crystal River Unit 3 License No. DPR-72

c. On February 27, 1986, procedure SP-201 was not implemented, in that snubber PdH-124 reservoir sightglass had a fluid level of 40 percent and the reserioir was not refilled.

This is a Severity Level IV Violation (Supplement I).

Pursuant to 10 CFR 2.201, Florida Power Corporation is hereby required to submit to this office within 30 days of the date of this letter transmitting this Notice a written statement or explanation in reply including for each violation:

(1) admission or dental of the violation, (2) the reason for the violation if admitted (3) the corrective steps which have been taken and the results achieved, (4) the corrective steps which will be taken to avoid further violations, and (5) the date when full compliance will be achieved. Where good cause is shown, consideration will be given to extending the response time.

FOR THE NUCLEAR REGULATORY COMMISSION

[

Roger D. Wal , Director Division o actor Projects Dated at Atlanta, Georgia this 8th day of September 1986