ML20246E436

Notice of Violation from Insp on 890429-0602.Violations Noted:Procedure EM-202 & Emergency Plan Not Properly Implemented in That on 890507,unidentified RCS Leak of Approx 25 Gpm Occurred & Not Classified as Unusual Event

ML20246E436
Person / Time
Site:	Crystal River
Issue date:	06/30/1989
From:	Sinkule M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20246E435	List: ML20246E430 ML20246E436 ML20246E449
References
50-302-89-11, NUDOCS 8907120242
Download: ML20246E436 (3)

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w l T-ENCLOSURE 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 April 29 - June.2,1989, 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. 10 CFR 50.54(q) requires that a licensee follow and maintain in effect emergency plans which meet the standards of 10 CFR 50.54(b) and 10 CFR Part 50, Appendix E.

10 CFR 50.47(b)(4) requires in part that the licensee use a standard emergency classification and action level scheme.

Technical . Specification 6.8.1.e requires that the licensee establish, implement'and maintain written procedures for Emergency Plan implementa-tion.

Florida . Power! Corporation (FPC) Emergency Plan Implementing Procedure (EPIP).EM-202, Duties'of the Emergency Coordinator, provides instructions and guidelines to be utilized by the Emergency Coordinator during initia-tion of the Radiological Emergency Response Plan.

Enclosure 1 of EM-202 and Table 8.1 of the FPC Radiological Emergency Plan indicate that an Unusual Event is the ap greater than one gallon per minute (GPM)unidentified propriate classification for reactor coolant system (RCS) leakage.

, Contrary- to the above, procedure EM-202 and the Emergency Plan were not

. properly implemented in that on May 7,1989 an unidentified RCS leak of approximately 25 GPM occurred and was not classified as an Unusual Event

.and therefore the notifications required were not made.

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

B. Technical Specification 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", recommends procedures for equipment control (tagging), operating procedures for the Reactor Coolant System (RCS), and procedures for the control and monitoring of radioactivity in gas systems.

8907120242 890705 PDR O ADOCK 05000302 PDC

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I Florida Power Corporation 2 Docket No. 50-302 Crystal. River Unit 3 License No. DPR-72 FPC Compliance procedure CP-115. In-Plant Equipment Clearance and Switching Orders, Section 6.4 requires that items listed on the clearance order be tagged in the position specified by the clearance. Clearance order

1. 89-05-206 required the handwheel for valve EFV-14 to be red tagged closed.

FPC Operating Procedure OP-301, Filling and Venting Reactor Coolant System, Valve. Checklist I. requires valves RCV-1 and RCV-2 to be closed during filling of the RCS..

FPC Chemistry Procedure CH-348, Sampling at the Reactor Building Purge Duct Gas Monitor RMA-1, Section 4 requires that the trip interlock for this radiation monitor be bypassed during filter changeout.

Contrary to the above:

1) On May 23,1989, procedure CP-115 was not properly implemented in -

that the handwheel for valve EFV-14 was found not red tagged closed as required by equipment clearance #89-05-206. The red tag associated with this item was incorrectly placed on valve EFV-33 instead.

2) On May 7,1989, procedure OP-301 was not properly implemented in that valves RCV-1 and RCV-2 were open instead of closed during the filling operation of the RCS. This situation resulted in an unidentified leak from the RCS in excess of one gallon per minute.

3) On May 24, 1989, procedure CH-348 was not properly implemented in that the trip interlock associated with radiation monitor RMA-1 was not bypassed as required during changeout of this monitor's filters which resulted in an inadvertent isolation of the reactor building ,

purge system.

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 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, 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, (4) the 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, consi-deration will be given to extending the response time. If an adequate reply

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in 'l 7;M L Florida Power: Corporation 3- Docket No. 50-302

? l Crystal . River Unit 3 - License No. DPR-72..

t l-is'= not received within the time specified' in this. Notice, an order may be Lissued 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 M. 6 Marvin V. Sinkule, Chief Reactor Projects Branch 2 .

Division of Reactor Projects o .' ..

Dated' at Atlanta, Georgia this ScNay of June 1989 -

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