ML20215A440

Notice of Violation from Insp on 870410-0511

ML20215A440
Person / Time
Site:	Crystal River
Issue date:	06/05/1987
From:	Reyes L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20215A432	List: ML20215A429 ML20215A440 ML20215A471
References
50-302-87-12, NUDOCS 8706160658
Download: ML20215A440 (2)

Text

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,.. a-ENCLOSURE 1 NOTICE OF VIOLATION Florida Power Corporation Docket No. 50-302 Crystal River Unit 3 License No. OPR-72 During the Nuclear Regulatory Commission (NRC) inspection conducted on April 10

- May 11, 1987, a violation of NRC requirements was identified. The violation involved . failure to properly implement procedures as required by the technical specifications. In accordance with tne " General Statement of Policy and Procedure for NRC Enforcement Actions," 10 CFR Part 2, Appendix C (1986), the violation is listed below:

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

Regulatory Guide 1.33, Appendix A,Section I.1, recommends procedures and/or written instructions for conducting maintenance activities.

Compliance Procedure CP-113, Handling and Controlling Work Requests and Work Packages, which was written to implement the requirements of Section I.1 of Regulatory Guide 1.33, requires in step 5.4.1.C that whenever the scope of work exceeds the instructions provided in part II of the work request, that the entire work package be returned to the Nuclear Planning Coordinator for further evaluation.

Surveillance Procedure SP-354A, Monthly Functional Test of the Emergency Diesel Generator 3A and Engineered Safeguards (ES) Bus A Undervoltage Relays, step 9.8.9 of section 9.8, ES Standby Mode for Auto Start, requires the control switch for diesel room fan AHF-228 to be placed in the normal-after-stop position.

Surveillance Procedure SP-216, Sample Line Leak Rate Test, specifies the sequence for test performance, the valve lineups, and the test equipment connection points to enable performance of the leak rate test.

Surveillance Procedure SP-335C, Radiation Monitoring Instrumentation Functional Test, (Tech Spec RMA's) step 7.7, requires that the procedure section in progress be completed before a new section in the procedure is started.

Surveillance Procedure SP-317, Reactor Coolant System (RCS) Water Inventory Balance, requires the calculation of the identified and unidentified RCS leakages from data collected over a time interval. This time interval is then used to obtain the RCS leakage rate.

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f :.0 Florida Power Corporation 2 . Docket No. 50-302 Crystal River Unit 3 License No. DPR-72 Contrary to the above:

a. On April 13, 1987, maintenance performed on control complex air compressor AHP-1C exceeded the work instructions provided in part II of the work request without the prior evaluation of the Nuclear Planning Coordinator.

b. On April 10, 1987, the control switch for AHF-228 was observed to be in the pull-to-lock position thus preventing automatic fan operation.

c. On April 10, 1987, procedure SP-216 was not adhered to in that steps were performed out of sequence, valve lineups were modified without making appropriate procedure changes, and test equipment was connected differently than that provided for in the procedure.

Additionally, procedure SP-216 was not properly established in that the procedure failed to restore systems to the normal configuration prior to . allowing procession to following procedure sections and failed to identify the proper sequence of operation for various system valves. As the result of these actions, plant radiation

' alarms were actuated, system pressures were exceeded, and personnel were contaminated.

d. On April 22, 1987, section 9.4 of procedure SP-335C was started prior to completing section 9.2 which was in progress. As a result of this action, the setpoint for radiation monitor RMA-11 was exceeded causing it to alarm and isolate the applicable ventilation ductwork.

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e. On May 1,1987, procedure SP-317 was performed incorrectly in that the actual data collection time of 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> was not used in calculating RCS leakage rates. This resulted in a nonconservative error being made in the calculation of the RCS unidentified leakage.

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

- Pursuant to the provisions of 10 CFR 2.201, Florida Power Corporation 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:

(1) admission or denial of the alleged violation; (2) the reasons for the violation if admitted; (3) the corrective steps which have been taken and the results achieved; (4) 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 jr ti V 7R-4 Luis A' Reyes, Director Division of Reactor Projects Dated at Atlanta, Georgia this 4th day of June 1987