ML20207G462

Notice of Violation from Insp on 880605-0706.Violation Noted:Silicon Controlled Rectifier Temp Controllers for Standby Gas Treatment Trains a & B Not Included in List of Qualified Equipment & HPCI Operability Test Not Conducted

ML20207G462
Person / Time
Site:	Brunswick
Issue date:	08/08/1988
From:	Verrelli D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20207G447	List: IR 05000324/1988021 ML20207G444 ML20207G462
References
50-324-88-21, 50-325-88-21, NUDOCS 8808240125
Download: ML20207G462 (2)

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l ENCLOSURE 1 NOTICE OF VIOLATION l

Carolina Power and Light Company Doc.ket Nos. 50-325 and 50-324

, Brunswick 1 and 2 License Nos. DPR-71 and DPR-62 During the Nuclear Regulatory Commission (NRC) inspection conducted on June 5 -

July 6,1988, 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 (1987), the violations are listed below:

A. 10 CFR 50.49(d) requires that each licensee prepare a list of electrical equipment requiring environmental qualification and that information be provided which demonstrates that the equipment will perfonn its design function during and following design basis accidents.

10 CFR 50.49(b)(2) requires that electric equipment importint to safety include non-safety related electric equipment whose failure under postulated enviromental conditions would prevent the satisfactory accomplishme.nt of ifety functions.

Contrary to the above, on and before May 13, 1988, the silicon controlled rectifier temperature controllers for the Unit 1 and Unit 2 "A" and "B l Standby Gas Treatment (SBGT) trains (electrical devices whose failure would render the SBGT trains inoperable) were not included in the licensee's list of qualified equipment, nor was information available which demonstrated that the devices were cualified.

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

B. Technical Specification 6.8.1.a requires that written procedures shall be

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implemented for the applicable procedur~e s recomended in Appendix. A of Regulatory Guide 1.33, November 1972. Procedures *r performing 1 maintenance which can affer.t the performance of safety related aquipment are identified in Item I.1 of Appendix A. 1 Cont'ary to the above, procedure OP10-FIC001-R2 was not cirrectly l implemented in that, Step 6.2.1.1 of littachment 1, to OPIC-rIC001-R2, l which required the performance of PT-9.2 to verify High Pressure Coolarit l Injection (HPCI) operability, was not performed prior to declaring HPCI  !

operable on June 16, 1988.

This is a Severity Level IV violation (Supplement I), applicable to Unit 1 only, i i

l 8808240125 080B00 PDR ADOCK 05000324 0 PNU 4

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Carolina Power and Light Company 2 Docket Nos. 50-325 and 50-324 Brunswick 1 and 2 License Nos. DPR-71 and JPR-62 C. Technical Specification 3.7.8, requires that all fire barrier penetra-tions, including fire doors, in fire zone boundaries protecting safety-related areas shall be functional. Action statement "a" for that specification requires, if the nonfunctional fire barrier penetration is not restored within 7 days, tubmission of a Special Report to the Comission within 30 days outlining the plans and schedule for restoring the fire barrier penetration (s) to functional status. Special Report 1-SR-86-003, dated April 7,1986, was submitted pursuant to the above specification for diesel generator building fire doors.

Contrary to the above, a special report was not submitted outlining a schedule for restoring fire barrier penetrations to operable status, in that Special Report 1-SR-86-003 did not contain a schedule for restoring the diesel generator building fire doors to operable status.

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

Pursuant to the provisions of 10 CFR 2.201, Carolina Power and Light Company is hereby required to submit to this office within thirty days of the date of the letter transmitting this Notice, a written statement or explanation in reply, including (for each violation): (1) admission or denial of the violation,(2) the reasons for t'ne 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, considet ation will be given to extending the response time.

FOR THE NUCLEAR REGULATORY COMMISSION Da id M. V relli, Chief l Reactor P*ojects Branch I l Division

• Reactor Projects {

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1 Dated at Atlanta, Georgia i this 8th day of August 1988 l

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