ML20058A449

Forwards Insp Rept 50-289/93-22 on 930910-1025.Violation Noted But Not Cited Re Failure to Perform Temp Surveys Prior to Performing Integrated Leak Rate Test,As Required by ANSI N45.4-1972,Section 7.4

ML20058A449
Person / Time
Site:	Crane
Issue date:	11/15/1993
From:	Blough A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:	Broughton T GENERAL PUBLIC UTILITIES CORP.
Shared Package
ML20058A452	List: IR 05000289/1993022 ML20058A449
References
NUDOCS 9312010089
Download: ML20058A449 (3)

See also: IR 05000289/1993022

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NOV 151993

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Docket / License:

50-289/DPR-50

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Mr. T. Gary Broughton

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Vice President and Director, TMI-l

GPU Nuclear Corporation

Three Mile Island Nuclear Station

Post Office Box 480

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Middletown, PA 17057-0191

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Dear Mr. Broughton:

SUBJECT: NRC INSPECTION REPORT NO. 50-289/93-22

This letter transmits the findings of the resident safety inspection conducted by Ms. M. Evans

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and Mr. D. Beaulieu from September 10, 1993 - October 25, 1993, at the Three Mile Island

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Nuclear Station Unit 1.

The inspectors based these findings on observations of activities,

interviews, and document reviews, and discussed them with Mr. T. G. Broughton and other

members of your staff. Inspector observations indicated safe and conservative operation.

Overall, your outage activities were well planned and coordinated. You had experienced some

nroblems with performance of infrequently performed evolutions during the last outage, and

clear improvement was noted this outage. However, there were numerous instances where a

problem with the understanding or control of plant conditions resulted in inadvertent losses of

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electrical equipment or inadvertent transfers of water. We understand you are in the process'of

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determining all the incidents that occurred during the outage and intend to evaluate these events.

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We view your corrective actions in this area to be important and intend to further review them.

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During the outage an inadvertent heatup of the reactor coolant system occurred while in mid-

loop operation. This incident revealed a number of weaknesses in the scheduling process and

implementation of the Outage Fuel Protection Criteria designed to enhance defense-in-depth

during shutdown activities. We view events of this type as significant and encourage ~you to

complete your corrective actions and incorporate lessons learned into future outage plans.

This report discusses an NRC identified violation which is not being cited because our review

found that this issue was promptly raised to management attention, was of low safety

significance, and was followed up with prompt and effective corrective actions. The issue

involved your failure to perform temperature surveys prior to performing the Integrated Leak

Rate Test, as required by ANSI N45.4-1972, section 7.4. Our decision to not cite this item is

based on the NRC enforcement policy goal of encouraging licensees to aggressively and

thoroughly pursue correction of problems.

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9312010089 931115

PDR

ADOCK 05000289

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NOV 110993

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Mr. T. Gary Broughton

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in accordance with 10 CFR 2.790 of the NRC's " Rules of Practice," a copy of this letter and'

its enclosure will be placed in the NRC Public Document Room. Your cooperation with us is

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appreciated.

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Sincerely,

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A. Randolph Blough, Chief

Projects Branch No. 4

Division of Reactor Projects

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Enclosure: NRC inspection Report No. 50-289/93-22

cc w/ encl:

A. Miller, Acting, TM1 Licensing Director

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M. J. Ross. Operations and Maintenance Director, TMl-1

J. Fornicola, Licensing and Regulatory Affairs Director

TMI-l Licensing Department

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E L. Blake, Jr., Esquire

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TMI-Alert (TMI A)

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K. Abraham,' PAO (2 copics)

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Public Document Room (PDR)

Local Public Document Room (LPDR)

Nuclear Safety Information Center (NSIC)

- NRC Resident inspector

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Commonwealth of Pennsylvania

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NOV 1 s 1993

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Mr. T. Gary Broughton

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bec w/ encl:

' Region 1 Docket Room (with concurrences)

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J. Rogge, DRP

bec w/enci (VIA IM1 AIL):

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V. McCree, OEDO

J. Stolz, PD I-4, NRR

. R. Hernan, PD I-4, NRR

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OFFICIAL RECORD COPY

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