ML20126F188

Notice of Violation from Insp on 921018-1114.Violation Noted:Dg Inoperable for Two H During Performance of Surveillance procedure,SP-907B.Required Breaker Alignment & Power Availability Verifications Not Performed

ML20126F188
Person / Time
Site:	Crystal River
Issue date:	12/11/1992
From:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20126F164	List: ML20126F160 ML20126F188 ML20126F215
References
50-302-92-27, NUDOCS 9212300139
Download: ML20126F188 (3)

Text

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4, fE 1 E .R_E_1 NOTICE OF VIOLATION Florida Power Corporation Docket No. 50-302 Crystal River Unit 3 License No. DRP-72 During an NRC inspection conducted on October 18 - November 14, 1992, violations of NRC requirements were identified. In accordance with the

" General Statement of Policy and Procedure for NRC Enforcement Actions," 10 CFR Part 2, Appendix C, the violations are listed below:

A. Technical Specification (TS) section 6.8.1 requires that written procedures shall be established, implemented, and maintained covering Surveillance and test activities of safety related equipment. Step 4.7.1 of Surveillance Procedure SP-340B, "0HP-1A, BSP-1A, and Valve Surveillance," revision 23, stated " Establish flow at 1500 gpm (with allowable oscillation averaged value between 1470 gpm and 1530 gpm), by throttling BSV-28."

Contrary to the above, on October 12, 1992, a licensed operator failed to properly implement step 4.7.1 and throttled flow by opening valve BSV-3, the motor operated spray header isolation valve, which resulted in delivering spray flow to the Reactor Building.

This is a Severity Level IV violation (Supplement 1).

B. Technical Specification section 3.8.1.1 requires that two separate and independent diesel generators be operable. With one diesel generator inoperable, action b. requires that the operability of the remaining AC sources be demonstrated by verifying correct breaker alignment and indicated power availability within one hour.

Contrary to the above, on October 27, 1992, the "B" diesel generator was inoperable for approximately two hours during the perfonnance of Surveillance Procedure, SP-907B, " Monthly functional Test of 4160V ES f

Bus B Undervoltage Relays," but the required breaker alignment and indicated power availability verifications were not performed.

This is a Severity Level IV Violation (Supplement 1).

Pursuant to the provisions of 10 CFR 2.201, Florida Power Corporation.is hereby required to submit a written statement or explanation to the U.S.

Nuclear Regulatory Conmission, ATTH: Document Control Desk, Washington, DC 20555, with a copy to the Regional Administrator, Region II, and a copy to the NRC Resident Inspector, at the facility that is the subject of this Notice, within 30 days of the date of the letter transmitting this Notice of Violation.

(Notice). This reply should be clearly marked as a " Reply to a Notice of Violation" and should include for each violation: (1) the reason for the violation or, if contested, the basis for disputing the violation,- (2) the corrective steps that have been taken and the results achieved, (3) the-corrective steps that will be taken to avoid further violations, and (4) the date when full compliance will be achieved. If-an adequate reply is not 9212300139 921211 PDR ADOCK 03000302 O PDR

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Florida Power Corporation 2 Docket 50-302 Crystal River Unit 3 License No.JDRP-72 received within the time specified in this Notice, an order or demand for information may be issued as to why the license should not be~ modified, suspended, or revoked, or why such other action as may be proper should not be taken. Where good cause is shown, consideration will be given to extending the response time.

Dated at Atlanta, Georgia this M day of December 1992 l

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-2 In the area of Emergency Preparedness, the . licensee conducted an annual exercise on November 5=. - This was the first occasion in which the control room simulator was used to simulate accident conditions and provide. realistic time

- frames for emergency condition parameters (paragraph 3.b)

! In the area of maintenance / surveillance, licensee action to address sporadic

- erratic reactor coolant drain tank level indication impact on SP-317, Reactor-Coolant Water Inventory Balance, was approprihte (paragraph 4.b),

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