ML18096A757

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Forwards Safety Insp Repts 50-272/92-04,50-311/92-04 & 50-354/92-04 on 920322-0502.No Violations Noted.Unresolved Item Re Steam Line Break Event Identified
ML18096A757
Person / Time
Site: Salem, Hope Creek  PSEG icon.png
Issue date: 06/08/1992
From: Wenzinger E
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To: Miltenberger S
Public Service Enterprise Group
Shared Package
ML18096A758 List:
References
NUDOCS 9206150117
Download: ML18096A757 (3)


See also: IR 05000272/1992004

Text

Docket Nos. 50-272

50-311

50-354

Mr. S. E. Miltenberger

JUN 0 8 1992

Vice President and Chief Nuclear Officer

Public Service Electric and Gas Company

P.O. Box 236

Hancocks Bridge, NJ 08038

Dear Mr. Miltenberger:

SUBJECT:

SALEM AND HOPE CREEK RESIDENT SAFETY INSPECTION

50-272/92-04; 50-311/92-04; 50-354/92-04 (3/22/92 - 5/2/92)

This letter transmits the findings of an inspection conducted by Mr. Thomas P. Johnson-Senior

Resident Inspector, Mr. James C. Stone, Licensing Project Manager, and other members of the

NRC resident staff at the Salem and Hope Creek Generating Stations for the period between

March 22 and May 2, 1992. The findings of this inspection were previously discussed with

Messrs. C. Vondra and R. Hovey of your staff.

Within the scope of this inspection, our inspectors verified that the Salem and Hope Creek

facilities were operated in a safe manner. The inspectors reviewed Salem Unit 2 restart activities

and concluded that your staff was appropriately prepared for reactor and unit startup.

Our staff also reviewed your discovery of a nonconservatism affecting certain previous analyses

used for the Salem licensing basis relative to assessment of the impact of a steam line break event

as reported in Licensee Event Report (LER) No.91-036, dated January 9, 1992. According to

your re-analysis, using Salem plant-specific data, a postulated steam line break event could have

resulted in exceeding containment design pressure when a current plant-specific model of

auxiliary feedwater flow is used in lieu of the original Salem steam line break analyses,

previously performe<;l by Westinghouse and approved by the NRC. This issue was previously

identified as an Unresolved Item in NRC Inspection Reports 50-272/311-91-28 and 50-272/311-

92-01. The current details of this item are discussed in Section 10.6.A of this report .

~D~' I

2

This matter will be dispositioned by separate NRC correspondence upon receipt of the committed

supplement to LER 91-036.

No response to this letter is required.

Sincerely,

Edward C. Wenzinger, .Chief

Projects Branch No. 2

Division of Reactor Projects

Enclosure: NRC Inspection Report.Nos. 50-272/92-04; 50-311/92-04; 50-354/92-04

cc w/encl:

S. LaBruna, Vice.President - Nuclear Operations

C. Vondra, General Manager, Salem Operations

J. Hagan, General: Manag~r,_Hope Creek Operations

C. Schaefer, ExtemalOperations.-Nuclear, Delmarva Power & Light Co.

F. Thomson, .. Manager, Licensing and Regulation*

J; Robb, Drrector, Joint Owner Affairs

A. Tapert, Program' Administrator

L. Reiter, General- Manager, QA and: Nuclear Safety-Review

M. Wetterhahn, Esquire

R. Fryling, Jr., Esquire

J. Isabella, Director;* -Generation~-Proj_ects- DeQartmeilt; Atlantic Electric D. Wersan, Assistant

Consumer Advocate~ Office of Consumer Advocate*

J. Lipoti, State of New. Jersey

Lower Alloways.*. Creek-Township:-*

K. Abraham, PAO fjj.J

Public Document Room- (PDR)-

Local Public.Document Room (LPDR)

Nuclear Safety Information Center (NSIC)

NRC Resident Insnec;tor

State of-New. Jersey_

bee w/encl:

Region I Docket Room (with concurrences)

Management Assistant, DRMA (w/o encl)

J. Joyner, DRSS

E. Wenzinger, DRP

J. White, DRP

J. Stone, NRR

S. Dembek, NRR

B. Norris, DRP

L. Cheung, DRS

R. Cooper, DRSS

DRS SALP Coordinator

DRSS SALP Coordinator

R. Lobel, EDO

C. Miller, PDI-2, NRR

bee w/letter and Executive Summary Only:

W. Hehl, DRP

S. Shankman, DRP

W. Hodges, DRS

L. Bettenhausen, DRS

~ire

I

IJl 10192

3

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~nzinger

18192

OFFICIAL RECORD COPY