ML18095A272

Responds to NRC 900329 Ltr Re Weaknesses Noted in Insp Repts 50-272/90-80 & 50-311/90-80.Corrective Actions:Fire Doors Placed on Blanket Preventive Maint Work Order & Damaged Fire Doors Will Be Repaired Immediately

ML18095A272
Person / Time
Site:	Salem
Issue date:	06/08/1990
From:	Labruna S Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NLR-N90114, NUDOCS 9006150023
Download: ML18095A272 (6)

See also: IR 05000272/1990080

Text

• Public Service Electric and Gas Company anley LaBruna Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-4800

Vice President

-Nuclear Operations

June 8, 1990 NLR-N90114

United States Nuclear Regulatory

Commission

Document Control Desk Washington, D.C. 20555 Gentlemen:

RESPONSE TO NRC INSPECTION

REPORT NO. 50-272/90-80

AND 50-311/90-80

SALEM GENERATING

STATION UNIT NOS. 1 AND 2 DOCKET NOS. 50-272 AND 50-311 Public Service Electric and.Gas Company (PSE&G) acknowledges

receipt of the subject report dated March 29, 1990. PSE&G hereby transmits

our response, including

expected completion

dates, to the identified

weaknesses.

• * Should you have any questions

regarding

this transmittal, do not hesitate to call. Attachment

90060S fDR-

05000272 W PDC Sincerely,

Document Control Desk NLR-N90114

c Mr. J. c. stone 2 Licensing

Project Manager -Salem Mr. T. Johnson Senior Resident Inspector

Mr. T. Martin, Administrator

Region I Mr. Kent Tosch, Chief New Jersey Department

of Environmental

Protection

Division of Environmental

Quality Bureau of Nuclear Engineering

CN 415 Trenton, NJ 08625 6-8-90

NLR-N90114

ATTACHMENT

RESPONSE TO NRC INSPECTION

REPORT 50-272/90-80

AND 50-311/90-80

SALEM GENERATING

STATION UNIT NOS. 1 AND 2 DOCKET NOS. 50-272 AND 50-311 Your letter of March 29, 1990, forwarded

combined NRC Inspection

Report 50-272/90-80

and 50-311/90-80

for Salem Units 1 and 2. This report included weaknesses

identified

during the inspection

and requested

a response to these weaknesses.

The specific weaknesses

and associated

responses

are provided below. Unresolved

Item 272 and 311/90-80-01

Resolve fire door automatic

closure problem and establish

interim *compensatory

measures.

Response Interim Compensatory

Measures In-Place -* PSE&G Nuclear Fire Department

performs a daily inspection

of fire doors in safety related areas. Each Technical

Specification

fire door closure/latch

mechanism

is examined for operability.

• Appendix R and Penetration

Seal Projects require compensatory

hourly f irewatches

in all safety related areas. Firewatches

are instructed

to observe fire doors during their hourly roves and ensure they are in the closed position.

• PSE&G anticipates

no reduction

in the present level of fire watch activity before May, 1991. Before an existing fire watch is removed from a safety related area, PSE&G Nuclear Fire Department

will assess the area for ventilation

related fire door problems.

A* decision to continue compensatory

f irewatches

will be made then based on the assessment

results. Planned Corrective

Actions -* Nuclear Fire Department

has compiled a list of recurring, ventilation

related, fire door problems.

These fire doors will be placed on a blanket preventive

maintenance

work order. When damaged fire doors are observed, Fire Department

personnel

will notify Maintenance

to take immediate

action to repair the door.

• Nuclear Fire Department

plans to disseminate

information

to site personnel

on the importance

of keeping fire doors closed. * A task force is reviewing

the ventilation

problems at Salem, and will be recommending

root cause corrective

actions. Since most fire door problems stem from ventilation

related causes, addressing

the ventilation

issues should resolve the long standing fire door problems.

Open Item 272 and 311/90-80-02

Correct deviation

document errors and more fully document deviation

justifications.

Review EOPs and correct logic statements

that have action and decision steps in the wrong sequence.

Response PSE&G will correct deviation

document errors and expand appropriate

deviation

justifications

in conjunction

with Salem EOP Revision 2. This revision is under development

and scheduled

for issuance September, 1990. Open Item 272 and 311/90-80-03

Identify and correct in-plant labeling deficiencies

during procedure

Validation

and Verification (V & V). In the control room, correctly

identify the containment

air particulate

detector isolation

valves, and remove Boron Injection

Tank and CV-139/140

indicating

lights that are no longer in-use. Response Inspection

identified

in-plant labeling deficiencies

will be corrected

by August 31, 1990. In-plant labeling deficiencies

noted during the EOP/AOP V&V effort will be corrected

as part of the V&V process. Control Room labeling deficiencies

will be incorporated

into the Control Room Design Review program scope. Open Item 272 and 311/90-80-04

Perform V & V walkdowns

of AOPs as they are revised, and correct any identified

deficiencies.

Response PSE&G will evaluate all audit deficiencies

indicated

on attachment

2 of the Inspection

Report, and revise the AOPs to correct any technical

deficiencies

by September

1990. All AOPs will undergo a Human Factors Upgrade as part of the Procedure

Upgrade Program, including a V & V walkdown.

The present schedule for completion

is December 1991.

Open Item 272 and 311/90-80-05

Organize EOP Table actions to minimize required operator movement in the control room. Provide P/A phone capability

for the Desk Operator in the simulator.

Response PSE&G contacted

L. Briggs (NRC Region 1) to determine

the specific EOP Table. Larry stated that he directed the comment to EOP-Trip-1, Table c. PSE&G will review this Table and make any appropriate

changes with EOP revision 2, presently

scheduled

for September, 1990. Installation

of a P/A for the simulator

desk operator, with the same capabilities

that exist in the Salem Unit 2 Control Room, will be completed

by December, 1990. Open Item 272 and 311/90-80-06

Correct differences

between EOP-Trip-4, 5, 6 and AD-44. Revise AOP writer's guide to require local versus Control Room action distinction

within the AOPs. Response AD-44 will be revised to correct the identified

discrepancy

by July 31, 1990. PSE&G reviewed the existing AOP dual column format and decided to eliminate

this format during the PUP effort. AOP steps will be listed in sequential

order, with question steps using the "Yes/No/Go

To" format. The Implementing

Procedure

Writer's Guide will be revised by August, 1990, requiring

local versus Control Room action distinction

in the AOPs. Open Item 272 and 311/90-80-07

Develop a formal and objective

means to determine

training required on EOP revisions.

Revise AD-44 to require immediate

EOP changes to be made within 2 weeks. Response PSE&G will revise AD-44 to address training requirements

by September, 1990. A revision to AD-44 requiring .immediate

EOP changes within 2 weeks is complete.

Open Item 272 and 311/90-80-08

Revise AD-44 and AD-2 to require in-plant walkdowns

for EOPs and AOPs.

Response Operations

Department

deleted AD-2. AD-44 was revised to include EOP in-plant walkdowns

as part of the validation

process. Additional

clarification

of the walkdown requirements

will be incorporated

by July, 1990. The governing

procedure

for AOP V & V, sc.TE-AP.PUP-OOOl(Z), will be revised to include in-plant walkdowns

by June, 1990.