ML20206P101

Notice of Violation from Insp on 860626-0702.Violations Noted:Reactor Not Placed in Hot Standby & Then Cold Shutdown When Reactor Vessel Head Vent & Pressurizer Steam Space Vent Inoperable

ML20206P101
Person / Time
Site:	Yankee Rowe
Issue date:	08/19/1986
From:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML20206P094	List: ML20206P091 ML20206P101
References
50-029-86-09, 50-29-86-9, EA-86-130, NUDOCS 8608270096
Download: ML20206P101 (2)

Text

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NOTICE OF VIOLATION Yankee Atomic Electric Company Docket No. 50-29 Yankee Nucl' ear Power Station License No. DPR-3 EA 86-130 An NRC inspection was conducted on June 26 - July 2,1986, to review the circumstances associated with the installation of undersized trip coils in circuit breakers for motor operated valves located in the reactor head vent path, pressurizer steam space vent path, and an alternate emergency feedwater system flow path. The inst'allation of undersized trip coils resulted in two violations of Technical Specification req'uirements. In accordance with the " General Statement of Policy and Procedure for NRC Enforcement Actions," 10 CFR Part 2, Appendix C (1986) (Enforcement Policy),,the violations are set forth below:

A. Technical Specification Limiting Condition for Operation (LCO) 3.4.11 1

requires that in Modes 1, 2, 3, and 4, at least one main coolant system vent path must be operable at both the reactor vessel head and the pressurizer steam space. Technical Specification LCO Action Statement 3.4.11.b requires, in part, that whenever both main coolant system vent' i

paths are inoperable, at least one of the vent paths must be made operable within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, or the reactor must be placed in hot standby within six hours and in cold shutdown within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

l Contrary to the above, between December 2,1985 and June 20, 1986, while

! in Mode 4 (hot shutdown) or higher for the vast majority of this period, 1 both the reactor' vessel head vent and the pressurizer steam space vent were

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l inoperable, and the reactor was not placed in hot standby and then cold "

shutdown. The vant paths were inoperable in that undersized trip coils were placed in the respective circuit breakers for motor operated valve VD-MOV-559 in the reactor vessel head vent path, and motor operated valves PR-MOV-558 and PR-MOV-560 in the pressurizer steam space, which would result in loss of power to the valve motors during operation of the valves under design basis' conditions.

4 B. Technical Specification LCO 3.7.1.2 requires that in Modes 1, 2, and 3, at least two independent emergency feedwater pumps and associated flow paths shall be operable. Technical Specification LC0 Action Statement 3.7.1.2 requires that with one inoperable emergency feedwater pump, at least two i

feedwater pumps must be made operable within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or the plant must be placed in 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 />. .

Contrary to the above, between December 3,1985 and June 19, 1986, while in Mode 3 (hot standby) or higher for the vast majority of this period, a flow path (to the' steam generator blowdown lines) for emergency feedwater was inoperable, which would have resulted in the inability of the emergency

• feedwater pumps to perform their intended function under certain conditions,

! and the reactor was not placed in hot shutdown. The flow path was inoperable i in that an undersized trip coil was placed in the circuit breaker for motor operated valve EBF-M0V-557, which would result in loss of power to the

, valve motor during operation of the valve under design conditions. ~

, These violations have been categorized in the aggregate as a Severity Level III l preblem (Supplement I). '

0FFICIAL RECORD COPY CP PKG YR - 0004.0.0 08/18/86 R608270096 860019 9 PDR ADOCK 0500

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Notice of. Violation 2

, Pursuant to the provisions of 10 CFR 2.201, Yank'ee Atomic Electric Company is j hereby required to submit to this office within thirty days of the date of the i letter which transmitted this Notice, a written- statement or explanation in

. reply, including for eat h violation: (1) the rr tsons for the violation, if -

j admitted; (2) the corrective steps which hast be90 taken and the results .

achieved; (3) corrective steps which will be taken to avoid further violations; l and (4) the date when full compliance will be achieved. Where good cause is j shown, consideration will be given to extending this response time.

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i Dated at King of Prussia, Pennsylvania this day of August 1986 H

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