05000423/LER-1996-046, Fowards LER 96-046-00.Licensee Commitments Listed,Including Containment Fuel Drop Radiation Monitor Design Reviewed & TS Change Request Will Be Submitted to NRC for Approval

Fowards LER 96-046-00.Licensee Commitments Listed,Including Containment Fuel Drop Radiation Monitor Design Reviewed & TS Change Request Will Be Submitted to NRC for Approval

ML20132B814
Person / Time
Site:	Millstone
Issue date:	12/06/1996
From:	Brothers M NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES SERVICE CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20132B817	List: 05000423/LER-1996-046, Fowards LER 96-046-00.Licensee Commitments Listed,Including Containment Fuel Drop Radiation Monitor Design Reviewed & TS Change Request Will Be Submitted to NRC for Approval 05000423/LER-1996-046-01, :on 961108,time Response of Containment Fuel Drop Radiation Monitor Less Conservative Then Value Assumed within Fsar.Caused by Inadequate Original Design & Failure of Surveillance Test Program.Design Reviewed
References
B16027, NUDOCS 9612170406
Download: ML20132B814 (4)

LER-1996-046, Fowards LER 96-046-00.Licensee Commitments Listed,Including Containment Fuel Drop Radiation Monitor Design Reviewed & TS Change Request Will Be Submitted to NRC for Approval

Event date:
Report date:
Reporting criterion:	10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)
4231996046R00 - NRC Website

text

'

"g$) Northeast wila=>, orrm. mye rerry mi., warrera cr Utilities System p.o. m,,128 Waterfore, CT 06360128 (203) 447-1791 December 6,1996 Docket No. 50-423 B16027 Re:10CFR 50.73(a)(2)(v)(C) 10CFR 50.73(a)(2)(v)(D)

U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Millstone Nuclear Power Station Unit 3 Licensee Event Report 96-046-00 Submitted Pursuant to i

10CFR 50.73(a)(2)M(C) and 10CFR 50.73(a)(2)(v)(d)

This letter forwards Licensee Event Report 96-046-00, documenting a condition that was determined at Millstone Unit No. 3 on November 8,1996. This LER is submitted pursuant to 10CFR 50.73(a)(2)(v)(C) and 10CFR 50.73(a)(2)(v)(D).

NNECO's commitments in response to this event are contained within i to this letter.

Should you have any questions regarding this tubmittal, please contact Mr.

James M. Peschel at (860) 437-5840.

I l

Very truly yours, b}

4 h

NORTHEAST NUCLEAR ENERGY COMPANY

/?f /

160103 M,n syt'ners M

.dnit Director, Milfst6ne Unit No. 3 9612170406 961206 PDR ADOCK 05000423 S

PDR

U.S. Nucinr Regul* tory Commission B16027\\Page 2 Attachment: 1)

NNECO's commitments in response to LER 96-046-00 2)

LER 96-046-00 cc:

H. J.

Miller, Region i Administrator A. C. Cerne, Senior Resident inspector, Millstone Unit No. 3 V.L.

Rooney, NRC Project Manager, Millstone Unit No. 3 W. D. Travers, Dr., Director, Special Projects i

i 1

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j Docket No. 50-423 i

B16027 i

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Millstone Nuclear Power Station, Unit No. 3 t

NNECO's Commitments j

in Response To 1

(LER 96-046-00) j J

a 1

December 6,1996

,s I

j-U.S. Nucl:cr Regulatory Commission i

i.

B16027\\ Attachment 1\\Page 2 i

i Enclosure l

List of Regulatory Commitments The following table identifies those actions committed to by NNECO in this document.

Any other actions discussed-in the submittal represent intended or planned actions by NNECO.

They are described to the NRC for the 'NRC's information and are not regulatory commitments. ~ Please notify the Manager -

i i

Nuclear Licensing at the Millstone Nuclear Power Station Unit No. 3 of any questions regarding this document or any associated regulatory commitments.

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i 3

Number

Commitment

Due B16027-01 The Containment Fuel Drop Radiation May 1,1997 j

7 Monitor design will be reviewed. Based on this review the design of the monitor j

will be modified or a Technical l

Specification change request will be submitted to the NRC for approval.

B16027-02 As part of the ongoing FSAR design Prior to entry into review, the response time data for safety mode 4 i

related non-Engineered Safety Features j

(ESF) actuations which support FSAR

{

chapter 15 analysis will be reviewed to i

verify that the data is supported by surveillance procedures. Applicable I

surveillance procedures will be updated as necessary.

816027-03 As part of the ongoing FSAR review, 1/31/97 applicable sections of the FSAR will be revised to accurately reflect the isolation time of the Containment Purge Isolation valves

((3HVU*CTV32A/B and 3HVU*CTV33A/B).

B16027-04 Coordinated with the ongoing FSAR 2/28/97 review, Section 3.2.2 of the Technical j

Requirements Manual (TRM) will be revised to accurately reflect the response time of the Containment Purge Exhaust and Supply Valves radiation monitors.

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