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)

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.

Sincerely, Attachment 900A1~00?~ 90060S fDR- ~66t( 05000272 W PDC

Document Control Desk 2 6-8-90 NLR-N90114 c Mr. J. c. stone 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

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.