ML20151D938

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Notice of Violation from Insp on 880512-0608.Violation Noted:Channel Calibr,Including Check of Channel Alarm Functions,Not Performed & Chemistry Procedure CH-101 for Sample Vol Not Implemented
ML20151D938
Person / Time
Site: Crystal River Duke Energy icon.png
Issue date: 07/08/1988
From: Wilson B
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20151D928 List:
References
50-302-88-16, NUDOCS 8807250298
Download: ML20151D938 (2)


Text

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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 May 12 -

June 8, 1988, 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 (1988), the violations are listed below:

A. Technical Specification (TS) 4.6.4.1 requires that a channel calibration, which includes a check of the channel alarm functions, be performed on the containment hydrogen analyzers.

Contrary to the above, as of June 8,1988, a channel calibration that included a check of the channel alarm functions has not been performed since this instrumentation was initially installed in August 1983.

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

B. TS 6.8.1.a requires the implementation of written procedures for those activities recommended in Appendix "A" of Regulatory Guide 1.33, November 1972.

Regulatory Guide 1.33, Appendix "A", Section J recommends written laboratory instructions to prescribe the nature of sampling and analysis.

Chemistry Procedure CH-101, Determination of Boron, Mannitol Complex Titration Method, step 9.2.1 and Table 1, requires that a 25 milliliter volume of sample be aliquoted for analysis.

Contrary to the above, on June 1, 1988, procedure CH-101 was not implemented in that a 10 milliliter volume of sample was aliquoted for analysis.

-This is a Severity Level V violation (Supplement 1).

C. 10 CFR Part 50 Appendix B, Criterion XVI requires corrective action measures that assure that nonconformances are p omptly identified and corrected and that such measures prevent repetition of these nonconformances.

Section 1.7.1.16 of Florida Power Corporation's (FPC) Quality Program requires nonconformances to be promptly identified and corrected, and that the corrective action taken be sufficient to prevent repetition of the nonconformances.

In a letter to the NRC from FPC, dated November 18, 1.987, in response to and providing corrective actions for the violation identified in NRC Inspection Report 50-302/87-30, the licensee stated that correct D 88070s fO((p05000302 Q

PDC ,

Florida Power Corporation 2 Docket tio. 50-302 Crystal River Unit 3 License No. DPR-72 chart paper associated with the liquid radioactive release flowrate recorder would be ordered and used.

Contrary to the above, as of May 14, 1988, FPC has failed to take prompt corrective action to obtain and use the correct chart paper. This failure contributed to the recurrence of the violation identified in Inspection Report 50-302/87-30.

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

Pursuant to the provisions of 1.0 CFR 2.201, Florida Power Corporation is hereby required to submit a written statement or explanation to the fiuclear Regulatory Conmission, ATTri: Document Control Desk, Washington, DC 20555, with a copy to the Regional Administrator, Region II, and a copy to the NRC Resident Inspector, Crystal River within 30 days of the date of the letter transmitting this Notice.

This reply should be clearly marked as a "Reply to a Notice of Violation" and should include for each vitlation: (1) admission or denial of the alleged 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 (S) the date when full compliance will be achieved. Where good cause is shown, consideration will be given to extending the response time. If an adequate reply is not received within the time specified in this Notice, an order may be issued to show cause why the license should not be modified, suspended, or revoked or why such other action as may be proper should not be taken.

FOR THE NUCLEAR REGULATORY COMMISSION

,%x Ym Br'uce A. Wilson, Chief Reactor Projects Branch 2 Division of Reactor Projects Dated at Atlanta, Georgia this 8th day of July 1988

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