ML20235U832

Notice of Violation from Insp on 870715-0814.Violations Noted:Health Physics Not Notified When Alarm Received on 870715,evaluations of Abnormal Conditions Not Performed & Dailu Channel & Monthly Source Checks Not Performed

ML20235U832
Person / Time
Site:	North Anna
Issue date:	10/05/1987
From:	Grace J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20235U802	List: ML20235U798 ML20235U832
References
50-338-87-24, EA-87-152, NUDOCS 8710140278
Download: ML20235U832 (2)

Text

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, NOTICE'0F VIOLATION t: ~

Virginia' Electric and Power Company Docket No. 50-338

!. North Anna Unit 1 License No..NPF-4 L EA 87-152 L

During the Nuclear Regulatory. Commission (NRC) inspection conducted on

'a July'15 _ August 14, 1987, violations of NRC requirements were identified.

.In accordance with th' " General Statement of Policy and Procedure for NRC Enforcement Actions,' 10 CFR Part 2, Appendix C'(1987),.the violations are listed below:

} :A. Technical lSpecif'ication 6.8.1 requires written procedures to be established,

. implemented, and maintained covering the applicable procedures recommended in Appendix:"A" of. Regulatory' Guide 1.33, Revision 2, February 1977.

Regulatory Guide 1.33 appendix "A",.Section 5, requires written procedures

< for' Abnormal 0ff. Normal, or Alarm Conditions.

The North Anna _ alarm response procedures " Main Steam Loops 1A-B-C Auxiliary

. Steam Loop High Radiation" and " Main Steam Loops 1A-B C Auxiliary Steam Loop Radiation Alert" require the control room- operator to notify Health Physics when alarms'are received.

Contrary to the above, the: written procedures were not implemented in that-

.the control room operator did not notify Health Physics when the above alarms were received on July 15, 1987 This is a Severity Level IV violation (Supplement I).

B. Technical: Specification 6.5.1.6.c requires that the Station Nuclear Safety and Operating Committee (SNSOC) shall be responsible for review of all proposed changes or modifications-to= plant systems or equipment that affect' nuclear safety. Technical Specification 6.5.1.7.b requires that the SNSOC shall render determinations in writing with regard to whether or not the above proposed changes or modification-constitute an unreviewed safety question.

Contrary' to .the above, as of July 18, 1987, the SNSOC had not conducted required evaluations of two conditions which were abnormal and constituted

' changes to the steam generators in Unit 1. These conditions requiring evaluation were steam generator secondary side foreign cbjects and plant operation with leaking explosive steam generator tube plugs.

, Thisois a Severity Level IV violation (Supplement I).

C. 10 CFR 50 Appendix B XVI, Corrective Action, requires that measures be-established to assure that conditions adverse to quality, such as failures, malfunctions, deficien::ies, deviations, defective material and equipment, and nonconformances are promptly identified and corrected. In  !

the case of significant conditions adverse to quality, the measures shall assure'that the cause of the condition is determined and corrective action  ;

taken to preclude repetition.

B710140278 B71 5 I PDR ADOCK O 338 1 Q LPDR- ,

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Q' O .f' tNotice of Violation -:2 -

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! Contrary.to 'the above, adequate measures were not.taken.'to determine the

.cause nor were corrective' actions adequate when steam jet-air. ejector

, radiation monitor 1-RM-SV-121 was restored,to service in that', no func-tional or calibration test was'run prior to returning.the monitor to

' service following-monitor failures on July 13 and 14,1987.

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

D. -Technical Specification 4.3.3.11 states that.each radioactive gaseous-effluent monitoring' instrumentation channel shall be' demonstrated . .

operable by performance of a daily channel check, a monthly-source check, channel calibration during refueling, and quarterly' channel . functional test.-

Technical Specification 1.17 states that a system, subsystem, train, component ~, or device shall be operable or'have operability when it is-capable _of performing its specified function.

Contrary to the above, daily channel checks and monthly source checks for.

radiation monitor 1-RM-SV-121 were inadequate in that during July 1987 the acceptance criterion used for a'ceptable c radiation monitor performance,'i.e., free needle movement, was inadequate to verify that

-the radiation monitor;was capable of performing its specified function or was operable.

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

pursuant to the provisions of 10 CFR 2.201, Virginia Electric and Power Company is hereby required to submit to this Office within 30 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 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, consideration will be given to i extending the response time. ,

FOR THE NUCLEAR REGULATORY COMMISSION ,

original signed by Mal Ernst/for l

J. Nelson Grace Regional Administrator Dated at Atlanta, Georgia this5fdayofOctober1987

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