ML20054H069

Notice of Violation from Insp on 820115-0215

ML20054H069
Person / Time
Site:	Brunswick
Issue date:	03/31/1982
From:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20054H031	List: IR 05000324/1982005 ML20054H030 ML20054H047 ML20054H055 ML20054H063 ML20054H069
References
50-324-82-05, 50-324-82-5, 50-325-82-05, 50-325-82-5, NUDOCS 8206220542
Download: ML20054H069 (2)

Text

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MAR 311982 l

APPENDIX A NOTICE OF VIOLATION Carolina Power & Light Company Docket Nos.- 50-324 & 50-325 Brunswick 1 and 2 License Nos. DPR-62 & DPR-71 l As a result of the inspection conducted on January 15 - February 2 - 11, 1982 and .

in accordance with the Interim Enforcement Policy, 45 FR 66754 (October 7,1980), )

the following violations were identified. '

A. Technical Specification 6.8.1.a requires that written procedures shall be implemented covering the activities specified in Appendix A of Regulatory Guide 1.33, November,1972. Item A.2 of Appendix A requires procedures for responsibilities for safe operation. Procedure 01-4, LC0 Evaluation and Followup, step 4.1 requires that when any system with a Technical Specifi-cation LC0 is found inoperable, the Shift Foreman shall complete appropriate portions of an Event Evaluation Check Sheet and note the malfunction in the.

Shift Foreman's log.

Contrary to the above, on January 8,1982 the Shift Foreman did not complete an Event Evaluation Check Sheet nor make an entry in the Shift Foreman's log when informed that the Standby Liquid Control heat tracing circuits were inoperable. Verification of heat tracing operability is a daily surveil-lance requirement for Standby Liquid Control operability.

This is a Severity Level IV Violation (Supplement D.2.) applicable to Unit 1 only.

B. Technical Specification 6.8.1.a and c. require written procedures to be established and implemented for items recommended in Appendix A of NRC l Regulatory Guide 1.33, and for surveillance activities of safety-related equipment. Item E of Appendix A requires appropriate written procedures for each safety-related annunciator. Appendix A items D.1, F.18, D.6 and D.7 require appropriate written procedures for normal operation and expected transient shutdown of the recirculation system, operation of the reactor core isolation cooling (RCIC) system and energizing emergency core cooling systems.

Contrary to the above:

1. A written procedure had not been established as of February 9,1982, for the Unit 2 safety-related annunciator alara 1-10 on panel 2A3,

" Safety / Relief Valve Open", following installation of a plant modifi-cation making that annunciator operable.

2. As of February 9,1982, the Unit 1 and 2 Operating Instruction 3 Daily Surveillance Report sheets were not properly revised to document the recently installed containment pressure instrument (CAC-PI-4176) l l

8206220542 820609

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Carolina Power & Light Company 2 Docket Nos. 50-324 & 50-325 Notice of Violation License Nos. DPR-62 & DPR-71 surveillance checks required by Technical Specification Table 4.3.5.3-1.

3. Procedure EI-10 and OP-2 were not adequately established on January 18, 1982 in that compliance with them resulted in restart of an idle recirculation pump loop without meeting the requirement of Technical Specification 3.4.1.3 that the operating loop flow rate is less than or equal to 50% of rated loop flow.

4. Procedure PT 10.1.1 for the RCIC system was not adequately established on January 16, 1982 in that it.did not contain an instruction to verify after testing that the flow controller is set in " auto" with a flow demand of 400 gpm.

5. Procedure OP-17 was not adequately este.blished on January 12, 1982 in that it required the 1-E11-F010 valve breaker to be ON whereas Technical Specification 3.5.3.2.a.3 requires the valve to be deenergized. (valve 1-E11-F010 was f.eenergized)

This is a Severity Level V Violation (Supplement I.E.)

C. Technical Specification 6.10.1.b and d. require maintenance and surveillance activity records be retained for at least five years.

Contrary to the above, records identifying what maintenance activities were performed on flain Steam Isolation Valves (IISIV) 1-B21-F022D and 280 to allow demonstration of leakage within Technical Specification 3.6.1.2.c limit on September 9,1981 were unavailable on January 11, 1982.

Also contrary to the above, records documenting leak tests on ilSIVs 1-B21-F0220, 28D, 228 and 288 between August 29 and 31,1981 were unavail-able on January 11, 1982.

This is a Severity Level VI Violation (Supplement I.F.) applicable to Unit 1 only.

Pursuant to the provisions of 10 CFR 2.201, you are hereby required to submit to this office within thirty days of the date of this Notice, a written statement or explanation in reply, including: (1) admission or denial of the alleged viola-tions; (2) the reasons for the violations 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. Consideration may be given to extending your response time for good cause shown. Under the authority of Section 182 of the Atomic Energy Act of 1954, as amended, this response shall be submitted under oath or affirmation.

Date: MAR 3 7 7992