ML20211C825

Notice of Violation from Insp on 861117-21 & 1201-05

ML20211C825
Person / Time
Site:	Crystal River
Issue date:	02/11/1987
From:	Reyes L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20211C810	List: IR 05000302/1986039 ML20211C805 ML20211C825 ML20211C852 ML20211C885
References
50-302-86-39, NUDOCS 8702200230
Download: ML20211C825 (2)

Text

_ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

i, .r

• i -

ENCLOSURE 1 NOTICE OF VIOLATION Florida Power Corporation Docket No. 50-302 Crystal River License No. OPR-72 During the Nuclear Regulatory Commission (NRC) inspection conducted on November 17-21 and December 1-5, 1986, a violation of NRC requirements was identified. The violation involved failure of the licensee to conduct an adequate safety ' evaluation and failure to perform required testing following completion of maintenance activities. In accordance with the " General Statement of Policy and Procedure for NRC Enforcement Actions," 10 CFR Part 2, Appendix C (1986), the violation is listed below:

10 CFR 50.59 states that the holder of a license may make changes in the (

~

facility, as described in the safety analysis report, without prior commission approval unless the change involves an unreviewed safety ques-tion. Also, the licensee's accepted quality assurance (QA) program (FSAR Section 1.7 Table 1.3) commits to Regulatory Guide 1.33, Quality Assurance Program Requirements (Operations) which endorses ANSI N18.7-1976, Administra-tive Controls and Quality Assurance for the Operational Phase of Nuclear Power Plants. Section 5.2.19.3 of this standard requires that testing shall be performed following plant modifications to confirm that the modification produces expected results.

a. Contrary to the above, the licensee modified the "C" temperature hot channel of the reactor protection system by removing a manufacturer's installed ground. The modification was performed under T-MAR T86-06-20-01 and work request 80209. The manufacturer's ground had to be reinstalled during system surveillance testing to determine the proper trip setting for the reactor trip temperature bistable. The removal of this ground was not adequately evaluated to insure this method of system operation does not involve an unreviewed safety question.

b. Contrary to the above, af ter the temporary modification, T86-06-20-01, was installed the "C" temperature hot channel was not tested in that surveillance procedure SP 110 was not completed after troubleshooting and then modifying the channel.

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

Pursuant to the provisions of 10 CFR 2.201, Crystal River is hereby required to submit to this Office within 30 days of the date of the letter transmitting this

{

1 - Notice a written statement or explanation in reply including: (1) admission or 8702200230 870211 PDR ADOCK 05000302 G PDR

') 't*

Florida Power Corporation - -2 Docket No. 50-302 Crystal River License No. DPR-72 denial 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, conside-ration will be given to extending the response time.

FOR THE NUCLEAR REGULATORY COMMISSION Original Signed by Luis A. Reyes Luis A. Reyes, Acting Director Division of Reactor Projects Dated at Atlanta, Georgia this lith day of February 1987 1

i e v ,-- , , - , , , , - - . - - - . . _ , , - - - ~ r -+~-e.