ML20127M796

Notice of Violation from Insp on 921121-1228.Violations Noted:Surveillance Requirements for APRM Gain & Channel Calibr for Operational Condition 1 Not Completed within 12 H of Exceeding 25% Thermal Power

ML20127M796
Person / Time
Site:	Perry
Issue date:	01/21/1993
From:	Greger L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20127M789	List: IR 05000440/1992024 ML20127M785 ML20127M796
References
50-440-92-24, NUDOCS 9301290016
Download: ML20127M796 (2)

Text

_- __ _ _ _. _ _ _ _ . _ - _ __ _ _ _ _ _

NOTICE OF VIOLATION

. Centerior Service _ Company Docket No, .50-440. I Perry Nuclear Power Plant License No. NPF-58 During an NRC inspection conducted cn November 21 through December 28, 1992,.

three 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 (1992), the violations are listed below:

1. Technical specification (TS) Table 4.3.1.1-1, footnote (d), requires that average power range monitors-(APRMs) be calibrated during; operational condition I when thermal power is greater than or equal to 25 percent thermal power. Table 4.3.1.1-1, ' footnote (d), further states that the provisions of TS 4.0.4 are not applicable if the surveillance is performed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after reaching 25 percent thermal power.

Technical specification 4.0.4 requires, in part, that entry into an operational condition shall not be made unless the surveillance requirements associated with the limiting condition for operation have been performed within the applicable surveillance interval.

Contrary to the above, at 1:00 p.m. on November 1, 1992, after. reaching 25 percent thermal power, the surveillance requirements for average power range monitor gain and channel calibration .for operational condition 1, as described in technical specification Table 4.3.1.1 footiote (d), were not completed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> of exceeding 25 percent then.al power. ,

This is a Severity Level IV violation (Supplemant I). (50-440/92024-01).

L 2. Technical specification Table 3.3.7.5-1, Action 80-a, requires that with the number of operable accident monitoring . instrumentation channels less than the required number of channels shown in Table 3.3.7.5-1, restore the inoperable channel to operable status within 7 days or be in at i least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within L the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. 4 l?

l Contrary to the above,.from June 9, 1992, until November 10, 1992 with ,

the exception of some short periods in which the plant.was. shut down for maintenance, the number of operable accident monitoring instrumentation channels was less than the required number of- channels shown in Table 3.3.7.5-1, and the inoperable channel was not restored to ' operable status within 7 days and the plant;was not in at least HOT SHU100WN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

This is a Severity Level IV violation (Supplement I). (50-440/92024-02)

3. Appendix B of~10 CFR Part 50, Criterion II, requires in part, that activities affecting quality shall be accomplished under suitably controlled conditions. Controlled conditions include the use of appropriate equipment, suitable environmental conditions for 9301290016 930121

l. PDR ADOCK 05000440 PDR L..: G ,

a. . - - - .. - - =

accomplishing the activity, such as adeauate cleanliness, and-assurance-that all prerequisites for the given activity have been satisfied. -

Contrary to the above, between November 21 through December 11, 1992-based on inspectors observations of debris in plant areas, including the reactor core isolation cooling pump room and the . reactor feed. pump turbine rooms, adequate cleanliness was not maintained.

This is a Severity Level IV violation (Supplement I). (50-440/92024-03):

Pursuant to the provisions of 10 CFR 2.201, Centerior Service Company is hereby- required to submit a written statement or explanation to the U.S. --

Nuclear Regulatory Commission, ATIN: Document Control Desk, Washington,-D.C.

20555 with a copy to the U.S. Nuclear Regulatory Commission, Region III, 799 Roosevelt Road, Glen Ellyn, Illinois, 60137, and a copy to-the NRC Resident Inspector at the Perry Nuclear Power Plant within 30 days of the date of the=

letter transmitting this Notice of Violation (Notice). This' reply should be clearly marked as a " Reply to a Notice of Violation" and should include for -

each violation: (1) the reason for the violation, or if contested, the basis for. disputing the violation, (2) the corrective steps that have been taken and the results achieved, (3) the corrective steps that will be taken to tvoid further violations, and (4) the date when full compliance will be achieved.

If an adequate reply is not received within the time specified in this Notice, an order or a demand may be issued as to why the license should not be modified, suspended, or revoked, or why such other action as may be proper shoula not be taken. Where good cause is shown, consideration will be given to extending the response time.

(4fA Dated at Glen Ellyn, Illinois L. Robert Greger, Chief this J/k day of January 1993 Reactor Projects Branch 3 2

?

I a

, -., - - , n --v-..- -, . , . . , . , - - , . , ,- . - - , -, . , - - - . , , w s .