ML20148H107

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Notice of Violation from Insp on 871216-880211.Violation Noted:Procedure OP-703 Not Utilized During Operation of Vital Bus Transfer Switches & Inverter Manual Bypass Switches
ML20148H107
Person / Time
Site: Crystal River Duke Energy icon.png
Issue date: 03/11/1988
From: Wilson B
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20148H101 List:
References
50-302-88-01, 50-302-88-1, NUDOCS 8803290316
Download: ML20148H107 (2)


Text

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J ENCLOSURE 1 NOTICE OF VIOLATION Florida Power Corporation Docket No. 50-302 Crystal River Unit 3 License No. OPR-72 During the Nuclear Regulatory Comission (NRC) inspection conducted on December 16, 1987 - February 11, 1988, a violation of NRC requirements was identified. In accordance with the "General Statement of Policy and Procedure for NRC Enforcement Actions," 10 CFR Part 2, Appendix C (1987), the violation is listed below:

A. Technical Specification (TS) 6.8.1 requires the implementation of written -

procedures for those activities recomended in Appendix "A" of Regulatory Guide 1.33, Nover.ber 1972, for test activities of safety related equipment, and for implementation of the fire protection program.

Regulatory Guide 1.33, Appendix "A" Section C.19.(2) recomends procedures for operation of the onsite AC electrical system.

Operating Procedure OP-703, Plant Distribution System, Section 5.6, provides instructions for operating the vital bus transfer switches and inverter manual bypass switches.

Performance Testing Procedure PT-110 Controlling Procedure for Zero Power Physics Testing, Section 8.1.04, requires that the low load feedwater valve Integrated Control System (ICS) control stations be in the automatic mode.

Administrative Instruction AI-2205, Administration of CR-3 Fire Brigade

, Organization Sections 4.2 and 4.4, requires that the fire brigade team be i composed of qualified fire brigade team members.

Contrary to the above:

a. On December 5, 1987, procedure OP-703 we.s not utilized during

, operation of the vital bus transfer switches and inverter manual bypass switches which resulted in improper switch operation and r

- actuation of the Emergency Safeguards (ES) system.

b. At 7:45 p.m., on January 8, 1988, while approaching initial r criticality in accordance with procedure PT-110, the low load  !
feedwater valve ICS control stations were in the manual mode. l I

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I 8803290316 880311 PDR ADOCK 05000302 O_ . _ _ DCD _. _ _ _ _ _ _ . _ _ , ,

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

c. During the period of January 19 through January 22, 1988, two plant personnel assigned duty as fire brigade team members were not qualified.

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

B. TS 3.3.3.3 requires that the seismic monitoring instrumentation chanrels -

shown in Table 3.3-7 be operable. Table 3.3-7 requires the Triaxial Peak-Accelographs have a measurement range of 1 2.0 G.

Contrary to the above, since approximately June 1979, the Triaxial Peak Accelographs have had a measurement range of i 1.0 G.

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

Pursuant to the provisions of 10 CFR 2.201, Florida Power Corporation is hereby requirr.d to submit a written statement or explanation to.the Nuclear Regulatory

Commission, ATTN: Document Control Desk, Washington, DC 20555, with a copy to the Regional Administrator, Region II, [IF APPLICABLE: and a copy to the NRC ,

Resident Inspector, Crystal River 3,] 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 violation]: (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, 3 (4) the corrective steps which will be taken to avoid further violations, and (5) the date when full compliance will be achicved. Where good cause is shown,  ;

consideration will be given to extending tiie response time. If an adequate reply is not received within the tima 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

' rhilnel Signed %l O

BRUCE A. WILSON Bruce A. Wilson, Chief Reactor Projects Branch 2 Division of Reactor Projects 4

Dated at Atlanta, Georgia thisfifLday of March 1988 4

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