ML20215M768

Forwards Insp Rept 50-423/86-28 on 860812-1006.No Violation Noted.Prompt & Effective Actions Taken by Plant Operators in Response to Valve Failures on 860915 Noted.Receipt of 860619,20 & 0813 Ltrs Ack

ML20215M768
Person / Time
Site:	Millstone
Issue date:	10/28/1986
From:	Wenzinger E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:	Opeka J NORTHEAST NUCLEAR ENERGY CO.
Shared Package
ML20215M769	List: IR 05000423/1986028 ML20215M768
References
NUDOCS 8611030274
Download: ML20215M768 (3)

See also: IR 05000423/1986028

Text

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OCT 2 81986

Docket / License: 50-423/NPF-49

Northeast Nuclear Energy Company

ATTN: Mr. John F. Opeka

Senior Vice President-Nuclear

Engineering and Operations Group

P.O. Box 270

Hartford, Connecticut 06101-0270

,

Gentlemen:

Subject: Millstone 3 Routine Inspection 50-423/86-28 (8/12/86-10/6/86)

This transmits the report of the above subject inspection by Messrs. J. Shediosky

and F. Casella of this office. The inspection findings have been discussed with

Messrs. W. Romberg and J. Crockett of your staff.

While observing Control Room operations our inspectors witnessed the prompt and

effective actions taken by plant operators on September 15 in response to valve

failures in the feed and condensate system. Their timely response prevented a

challenge to the reactor trip system. Overall, however, despite excellent operator

performance and improvements in the steam generator (SG) level control equipment,

SG 1evel transients are still resulting in plant trips. {

Thank you for your June 19, 1986 letter in response to concerns stated in Inspec-

tion Report 50-423/86-12. These included the high number of illuminated control

room annunciators and also the deterioration of the rubber lining of service water

pump discharge valves. Your progress toward resolution of both of these items will

be. addressed in our routine resident inspections. Additionally, the Attachment

to the enclosed Inspection Report addresses the current status of control room an-

nunciators. A focus of our future inspections will be on whether, in light of your

commitment to the total " blackboard" concept, you have placed high enough priority

on annunciators to effect a significant reduction in the annunciators in an alarm

status.

Thank you, also, for your June 20, 1986 response to a Violation identified in In-

spection Report 50-423/85-74. This Violation concerned the failure to report a

deficiency in reactor coolant pump snubber support design to the NRC. Although

you decided not to contest this violation, we noted your comments upon it. Prompt

notification of deficiencies of this type provides information for evaluation of

potential safety consequences at facilities other than the one where the deficiency

is found. We consider this violation to be a valid safety consideration in prin-

ciple as well as a literal noncompliance with requirements. Therefore, the viola-

tion stands as cited. The ongoing effectiveness of your actions to assure timely

and valid reporting will be assessed incident to our routine inspection program.

Your August 13, 1986 letter addressed the impact on the plant's accident analysis

caused by a Reactor Coolant System (RCS) Loop No. 2 hot leg transit time in excess

of the previously established acceptance criteria for RCS resistance temperature

detector (RTD) response times. This issue was addressed in our Inspection Report

No. 50-423/86-21. You state in your letter that the increase in RTD response time

does not impact the acceptability of continued plant operation and that a follow-up

8611030274 861028

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Northeast Nuclear Energy Company 2 .00T 2 81986

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report will be submitted if any changes are necessary to the Technical Specifica-

tion or Final Safety Analyses reports. We wish to emphasize that the need for any

such changes should be promptly identified to us.

No violations were identified during this inspection and no reply to this letter

is required.

Thank you for your cooperation.

Sincerely, ,p ngm

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E ward C. Wenzinger, Chief

Projects Branch No. 3

Division of Reactor Projects

Enclosure: NRC Region I Inspectf n Report 50-423/86-28

cc w/ enc 1:

V. Papadopoli, Construction Quality Assurance Supervisor

E. R. Foster, Director of Generation Construction

W. J. Mroczka, Vice President, Nuclear Operations

D. O. Nordquist, Manager of Quality Assurance

R. T. Laudenat, Manager, Generation Facilities Licensing

W. D. Romberg, Station Superintendent

Public Document Room (PDR) '

Local Public Document Room (LPDR)

Nuclear Safety Information Center (NSIC)

NRC Senior Resident Inspector

State of Connecticut

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Northeast Nuclear Energy Company 3

MT 2 8150

bec w/ encl:

Region I Docket Room (with concurrences)

Management Assistant, DRMA (w/o encl)

DRP Section Chief

L. Prividy, RI, BV-2

T. Rebelowski, SRI, Millstone 1&2

B. Doolittle, LPM, NRR

Robert J. Bores, DRSS

J. Durr, DRS

M. Shanbaky, DRSS

W. Pasciak, DRSS

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0FFICIAL RECORD COPY