ML20207T395

Notice of Violation from Insp on 870108-0205

ML20207T395
Person / Time
Site:	Crystal River
Issue date:	02/27/1987
From:	Reyes L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20207T391	List: IR 05000302/1987001 ML20207T390 ML20207T395 ML20207T397
References
50-302-87-01, 50-302-87-1, NUDOCS 8703230521
Download: ML20207T395 (2)

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~ ,M FEB 2 ? Igg 7 ENCLOSURE 1 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 January 8 - February 5,1987, a violation of NRC requirements was identified.

The violation involved the failure to adhere to plant procedures. 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:

Technical Specification 6.8.1 requires that written procedures covering the following activities be implemented and maintained:

- Procedures recommended in Appendix A of Regulatory Guide 1.33, November 1972; and,

- Procedures for Surveillance and test activities of safety related equipment.

Regulatory Guide 1.33, Appendix A, recommends procedures and or written instructions for the control of radioactivity. Operating procedure OP-412, Waste Gas Disposal System, provides the instructions for releasing a Waste Gas Disposal Tank (WGDT) to the environment and requires in steps 9.1.1 through 9.1.18 that the release flow monitor to be checked prior to beginning the release.

Surveillance procedure SP-181, Containment Air Lock Test (Semiannual),

requires in step 6.2 that warning signs be posted on both sides of the air lock stating that a test is in progress and in step 3.2 of enclosure 1 that the " Fast Charge" hose be disconnected from the pressure source prior to measurement of the air lock's leakage rate.

Surveillance procedure SP-422, Reactor Coolant System Heatup and Cooldown Surveillance, requires in step 4.3 that when the Decay Heat Removal (DHR) system is operating with no reactor coolant pumps operating, the indicated DHR system cooler outlet temperature shall be used for heatup calcolations.

Contrary to the above:

a. On Jar.uary 25, 1987, procedure OP-412, was not implemented in that the release flow monitor was not checked prior to initiating a WGDT release.

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

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b. On January 13, 1987, procedure SP-181 was not implemented in that I no warning signs were posted on both sides of the air lock during performance of this test. Furthermore, on January 14, 1987, the fast charge hose was not disconnected from the pressure source prior to measuring the leakage rate of the air lock,

c. On January 13, 1987, procedure SP-422 was not implemented in that the plant heatup calculation was performed using the cooler outlet temperature averaged with the cooler inlet temperature instead of the indicated cooler outlet temperature while the DHR system was in operation with reactor coolant pumps secured.

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 explanatien 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 Original Signed by Luis A. Reyes Luis A. Reyes, Director Division of Reactor Projects Dated at Atlanta, Georgia this day of 19