IR 05000272/1990027

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Insp Repts 50-272/90-27,50-311/90-27 & 50-354/90-23 on 901113-15.App R Issues Remain Open Pending NRC Review of Licensee Corrective Action.Major Areas Inspected:Status of Previously Identifed App R Issues & LER 90-021-00
ML18095A797
Person / Time
Site: Salem, Hope Creek  
Issue date: 02/11/1991
From: Anderson C, Paolino R
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
To:
Shared Package
ML18095A792 List:
References
50-272-90-27, 50-311-90-27, 50-354-90-23, GL-83-33, NUDOCS 9103200130
Download: ML18095A797 (36)
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Text

U. S. NUCLEAR REGULATORY COMMISSION

REGION I

50-272/90-27 50-311/90-27 Report No /90-23 50-272 50-311 Docket No License No DPR-70/DPR-75/NPF-57 Licensee:

Public Service Electric & Gas C P.O. Box 236 Hancocks Bridge, New Jersey 08038 Facility Name:

Sale~~its 1&2/Hope Creek Inspection At:

Lower Alloways Township, New Jersey Inspection Conducted:

November 13, 1990 to November 15, 1990, Discussions through December 31, 1990 and Meeting in Region I on November 16, 1990 Inspectors:

Approved by: Reactor Engineer-EB/PSS C. J. Anderson, Chief, Plant Systems Section DRS/EB

,-1 J- 'l I date date Inspection Summary

Inspection on November 13, 1990 to November 15, 1990, discussions through December 31, 1990, and meeting in Region I on November 16, 199 (Combined Inspection Report Nos. 50-272/90-27; 50-311/90-27 and 50-354/

90-23).

Areas Inspected:

Routine announced inspection to review and determine the status of previously identified Appendix R issues and followup of Hope Creek event No. LER 90-021-0 Results:

Appendix R issues remain open pending NRC review of licensee corrective action following NRC 1s Exemption Request approvals dated July 20, 198 One violation involving inadequate corrective actions resulting in the installation of non-EQ components.

00130 910305 91032 05000272 PDR ADOCK PDR Q

  • DETAILS 1.0 Persons Contacted 1.1 Public Service Electric & Gas Co. (PSE&G)
  • R. Bashall, Systems Analysis Supervisor R. Beckwith, Station Licensing Engineer (Hope Creek)

'*A. Blum, Progrm Analysis Supervisor

  • R. Braddick, Senior Staff Engineer (Fire Protection)
  • R. Brown, Principal Engineer (Nuclear Licensing & Regulatory)
  • J. Carey, I&C W. Daczkowski, Senior Staff Engineer (Hope Creek)
  • R. DeWeese, Engineer
  • G. Kapp, Project Manag~r
  • C. Lambert, Nuclear Engineering/Science-Manager
  • B. Preston, Licensing.& Regulation - Manager
  • A. Robinson, Project Manager
  • D. Smith, Station Licensing Engineer J. Thompson, Technici~n (Hope Creek)

M. Williams, PAG 1.2 U.S. Nuclear Regulatory Commission

  • T. Johnson, Sentor Resident Inspector The asterisk (*) denotes personnel attending exit meeting of November 15, 199.0 Background On November 19, 1980, the Commission published a revised section 10 CFR

~0.48 and Appendix R to 10 CFR Part 50 regarding fire protection features of nuclear power plants (45 FR 76602).

The revised 10 CFR 50.48 and Appendix R became effective on February 17,.1981; Section 50.48(c)

established the schedules for satisfying the provisions of Appendix R;Section III of Appendix R contains fifteen subsections; letter A through 0, each of which specifies requirements for particular aspects of fire protection features at a nuc.lear power plant *facilit By letter dated July 15, 1988, the licensee requested approval of exemptions from the technical requirements of Section III.G of Appendix R 10 CFR 50 in fourteen fire areas and a generic exemption relating to conditions in a riumber of plant location The submittal includes information contained in previous letters to the NRC staff dated January 31, 1985 and January 17, 198 Based on the review of licensee proposals, the staff concluded that the licensee's alternative fire protection configurations, including the proposed modifications provides an equivalent level of safety to that achieved by compliance with Appendix R to 10 CFR Part 5 *

On July 20, 1990 the Commission issued Exemptions for Salem Units 1&2 from the requirements of 10 CFR 50, Appendix R,Section III.G. It exempts Salem Units 1&2 from meeting the technical requirements of 10 CFR Part 50, Appendix R in th~rteen fire areas and allows use of non-3 hour fire rated features in 3 hour3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> fire barrier.0 Statu5 of Previously Identified Open Items (Closed) Violation No. 272/83-37-01 *pertaining to select shutdown areas in the containment which do not meet 10 CFR 50, Appendix R,Section II Thes.e non-conforming areas include:

1)

RHR Pump Room - Elevation 45 feet 2)

Charging Pump Area 3)

Intake Structure 4)

Containment 5)

460V Switchgear Room C02 An exemptton request (exemption 13) has been granted (July 20, 1989) for the RHR Pump.Room based on proposed modifications and evaluation of alternate fire protec~ion configuration:

Th~ modifications have been completed ~nd the RHR Pump Room is in complianc The Chargin~ Pump Area l~cked wide are~ suppressiori coverag The suppre~s ion system (not a dry system) has been expanded a*nd found to be acceptabl The exemption request for the Intake Structure has been withdrawn and the three-hour separation barrier and fire door has been installe The Containment lack of documented separation ~nalysis has been addressed in the January 1984 correspondence, and in the July 1988

  • 1ette To enhance fire safety, the licensee proposed to. install a localized fire suppression system to ptotect Panel 335 which contain~

redundant channels of pressurizer pressure-and level instrumentatio Engineering is complete for. this modificatio Installation of the suppression systems.is scheduled for the next outag Ite~~ 1, 2 and 3 of Violation No. 272/83-37-01 are close Item 5, 460V Switchgear Room, C02 is a duplicate of NRC Item No. 83-37-06 which is being closed and tracked on NRC Item No. 87-29-0 Item 4 (Containment) Panel 335 Modification will be tracked by NRC item Nos. 272/90-27-01; 311/90-27-0 (Closed) Unresolved Item No. 272/83-37-04 pertaining to the Auxiliary Feedwater Pump Area (Turbine Drive Pump and Cable trays) which do~s not meet 10 CFR 50, Appendix R,Section III.G.2.C requirement for one hour rated fire barriers for all equipmen Cable tray Nos. 1A033 and 1A046 in the vicinity of the motor driven feedwater pump No. 12 did not have the one hour fire wra The licensee has enclosed cable tray 1A033 with a one hour rated fire barrie However, cable tray 1A046, located in fire area lFA-AB-848 has not been fire wrapped pending completion of a fire wrap evaluation program

  • which is being done on a room by room basi This review is scheduled for completion by December 15, 199 The fire wrap evaluation program includes the:

1) Breaker Coordination (NRC item No. 87-29-08);

2) Administrative Controls required in the event of a fire to safely shutdown the plant; and, 3) cable ampacity including derating for fire wra Unresolved Item No. 272/83-37-04 is close Corrective action for the cable tray will be tracked on NRC Item No. 87-29-0 (Closed) Unresolved Item No. 272/83-37-05 pertaining to the Auxiliary Building, elevation 84 1, Component Cooling Water Room Two tomponent cooling water pumps (Nos. 12 and 13) are located in a common room with the No. 12 component cooling heat exchang Component cooling water pump No. 11 and component cooling heat exchanger No. 11 are in a separate adjoining roo There is no automatic suppression in this are The rooms are not completely separated from each other and other plant areas with a fire rated barrie Non-fire rated penetrations (electrical cable trays and HVAC ducts) exist in the wall between the room The doors are louvered and they are not fire-rate The licensee applied for and received an exemption (SER dated June 17, 1983) for the lack of an automatic suppression system in the are A three-hour fire barrier has been installed to separate the component cooling water pump The penetration seals have not been installe There is an on going program to evaluate the adequacy of existing penetration seals and to repair, replace or upgrade the seals as necessar Unresolved Item No. 272/83-37-05 is close The licensee seal program is being tracked by the NRC as item No. 87-29-0 The latest anticipated completion date for the penetration seal program is September 1991 for all installations and January 1992 for supporting documentatio (Closed) Unresolved Item No. 272/83-37-06 pertaining to the Auxiliary Building, elevation 84 1, 460V AC/230V AC Switchgear Room which contains a manual C02 system instead of the automatic suppression system required by 10 CFR 50, Appendix R,Section III G. Redundant switchgear for the 460V AC and 230V AC vital buses are separated by a one hour fire barrie However, th~ barrier p~rtitions terminate at the top of the switchgea The horizontal cable trays installed between redundant trains are considered as intervening combustibles as clarified in NRC Generic letter 83-3 The licensee submitted an exemption request (Item 6) from the requirements of 10 CFR 50, Appendix R,Section III.G.2 which requires that equipment be protected by a one-hour fire-rated barrier and an automatic suppression and detection syste The licensee justified the exemptions on the basis of existing protection and proposed modification Cables associated with the A and B division 125V DC Switchgear and the feeds to start diesel generators as well as the power feed from the 11 C11 Diesel will be enclosed in one-hour rated barriers throughout the are The existing manual carbon dioxide suppression system in this area will be

  • changed to an automatic suppression syste Based on the exemption ap-proval date of July 30, 1989, the automation of the C02 system in the subject areas is required to be completed during the Unit 1, 1991 refueling outag System modifications are in progress and are scheduled to be completed during the upcoming outage scheduled to end in April 199 Unit 2 will also be completed during that tim Since the one-hour rated fire barrier for this area is included in the licensee's evaluation program for fire wra Unresolved item No. 272/83-37-06 is close This item is being tracked by the NRC as item No. 87-29-0 (Closed) Unresolved Item No. 311/83-37-18 pertaining to wrapped cable trays with open ends to dissipate the heat generated in the cable due to current resistance (I 2 R) losse A licensee evaluation summarizing the required fire protection wrap needed for safe shutdown of the Salem Generating Station is in progress along with the Breaker Coordination Study resulting from an NRC inspection in September 14-18, 1987 (Inspec-tion Report 311/87-29-08).

The methodology for performing the evaluation of cables which are wrapped with the one-hour fire barrier is delineated in licensee procedure N AEI-PSEG-90080DC~Ol, dated June 14, 199 Calculations for determining cable ampacity, including cable ampacity for derating for the fire wrap, are in progress and expected to be completed by December 199 Installation of the fire wrap barrier is tentatively scheduled for October 1991 (Unit 1) and July 1992 (Unit 2).

Since the cable wrap issue is included as part of the Breaker Coordination Study which is being tracked by the NRC open item No. 311/87-29-08, Unresolved item No. 311/83-37-18 is close (Closed) Unresolved Items No. 272/88-03-02 regarding auditability of EQ Binder The licensee has revised the EQ binders to include a sign-off sheet, EQ check list, Equipment Identification Index, title page and other supporting documentation for environmental qualification of 10 CFR 50.49 electrical equipment installed in a harsh environmen The binders also contain applicable NRC documents such as.generic letters, Information Notices, Bulletins and Licensee Event Report Based on a review of six randomly selected EQ binders, the inspector concluded that the revised EQ files are auditable and that the paper trail was easily followe This item is close (Closed) Unresolved Item No. 272/89-03-02 pertaining to the installed configuration of the Victoreen Radiation Monito This item is a duplicate of unresolved Item No. 272/89-06-01 and 311/89-05-01 which was reviewed and closed in NRC Report Nos. 272/90-08 and 311/90-08.

This item is thereby close (Closed) Unresolved Item No. 272/89-13-06 regarding licensee exception to Regulatory Guide 1. 75 separation requirements for Regulatory Guide 1.97 component Regulatory Guide 1.97, section 1.3.1.b, states in part, that redundant or diverse channels should be electrically separated from each other and from equipment not classified important to safety in accordance with RG 1.75,

"Physical Independence of Electrical Systems" up to and including the isolation devic *

The licensee did not take exception to this requirement when requested by the NRC to identify their compliance with RG 1.9 However, the licensee provided documentation which indicates that RG 1.75 was not an original design criteria for the Salem facilit The Salem Final Safety Analysis Report (FSAR), section 7.8 of the original and Supplement 1 of the Safety Eva.luation Report provides NRC approval of the existing licensee separation criteri This item is close (Open) Deviation No. 50-272/89-13-02 and 50-311/89-12-02 regarding th lack of redundant instrumentation for Effluent Radioactivity-Noble Gas Exhaust Monito The licensee originally classified this monitor as a type A variabl Based on this classification, redundant class lE instrumentation is recommended by Regulatory Guide 1.97. The licensee did'not provide redundant class 1E instrumentation for this type A variabl Regulatory Guide 1.97 classifies this 'variable as type C or E and a category 2 or 3 variable for which no redundancy i~ require *

The licensee plans to follow the guidelines of Regulatory Guide 1.97 rega~ding the classification of the mbnito At this point, they see no

- _

need to classify this monitor as a type A variabl The FSAR will be revised accordingl This item remains open pending a change to the FSAR to reflect this reclassificatio (Open) Deviation No. 50-272/89-13-04 and 50-311/89-13-04 regarding lack of redundancy for the Steam Generator Radiation Monito The licensee classifies this monitor as a type A variabl Based on this classification, redundant class lE instrumentation is recommended by Regulatory Guide 1.9 The licensee provided a recorder which uses a redundant power supply.* However, the same signals are used for primary indication of the variabl *

During this inspection, the NRC identified several signal failures which could impair both redundant channels and, thus prevent the post-accident availability of this variable to the operato *

The licensee proposed to use the non-safety related condenser air ejector exhaust radiation monitor and the safety related steam generator's narrow and wide range level instruments to provide indication for the subject variable. It was agreed that the steam generator level would respond to a tube rupture, however, detection of the level change would depend largely upon the size of the leak and the speed of response to the feedwater contro In addition, the NRC determined that no direct relationship exists between radiation activity levels in the main steam line and water level in the steam generato The licensee's proposed resolution to the redundancy issue was not acceptabl The licensee has provided a revised position on variable function for NRC revie A modification is scheduled for the 10th and 6th refuleing outage for Units 1 and 2 respectively, pending NRC approva This item remains open pending completion of NRC review of the revised position on variable functio (Open) Unresolved Item No. 272/89-13-05 and 311/89-12-05 regarding the use of resistors as isolator To properly address the NRC concern regarding inadvertent or accidental feedback signals from the computer to safety related circuits, the licensee is evaluating not only the potential feedback as a result of credible faults occurring in the termination areas but also the capability of applicable interfacing components (e.g., computer cards) of isolating faults affecting other areas of the plant computer (e.g., power supplies).

This work is still in progres Scheduled completion of the analysis is in January 199 This item remains ope.0 Technical Meeting A technical meeting, at the request of NRC Region I, was held with Public Service Electric & Gas Personnel (Attachment A - List of Meeting Atten.dees)

on November 16, 199 The purpose of the meeting was to discuss the status of open Appendix R, 10 CFR Part 50 issues and to establish completion dates for complying with 10 CFR 50, Appendix R requirement The licensee committed to providing an update on the status of the Appendix R Program and to provide revised completion dates for complying with Appendix R commitment This information was received in a letter from the licensee, dated December 28, 199 The licensee's presentation (Attachment 1) provided background information relating to specific fire protection criteria including systems required for safe shutdow Included in the licensee's presentation was a

discussion of licensee Exemption Requests and final NRC approvals received in a letter dated July 20, 1989 which impacted the scheduled completion dates for complying with Appendix R requirement The penetration seal review project (Attachment 2) was discussed with new installation closeout date The objective of th~s program is to determine the adequacy of existing penetration seals and to repair, replace or upgrade penetration seals as require.0 Licensee Event Report LER 90-021-00 issued by Hope Creek on October 3, 1990, determined that maintenance had replaced an unknown number of source range monitors and intermediate range monitors (SRM/IRM) cable connectors with connectors having teflon insulatio Confirmation with the vendor supplying the connector resulted in the licensee declaring the SRM/IRMs inoperabl On October 12, 1990, a Justification for Continued Operation was prepared and approved by the Station Operating Review Committee (SORC).

Subsequent to SORC approval, the licensee notified the NRC of the even On November 9, 1990, during a forced outage, the licensee inspected all of the SRM/IRMs and replaced the unqualified component The inspection concluded that out of 12 detectors, 2 SRM's and 4 IRM's were found to contain the unqualified component The apparent contributing factor for the event was traced to inadequate documentation in developing the bill of material for the SRM/IR The unqualified components were identified by the NRC during a construction period inspection conducted August 5-9, 1985 prior to licensing (Report No. 354/85-39).

Licensee review of equipment history indicates the unqualified components were installed at various times during 1986 and 198 This is an apparent violation of 10 CFR 50, Appendix B, Criterion XVI which states, in part, that 11measures shall be established to assure that conditions adverse to quality, such as... nonconformances.... are promptly identified and corrected.... and corrective actions taken to preclude recurrence.

(354/90-23-01)

6.0 Unresolved Items Unresolved items are matters about which more information is required in order to ascertain whether they are acceptable items or violation Unresolved item(s) are discussed in Details, paragraph *

7.0 Exit Meeting The inspectors met with licensee representatives (denoted in Details, paragraph 1) at the conclusion of the inspection on November 15, 1990 and a subsequent meeting on the Region I office on November 16, 199 The inspector summarized the scope of the inspection and the inspection finding At no time during this inspection was written material provided to the licensee.

  • Attachment A Technical Discussion:

List of Meeting Attendees Appendix R,Section III.G issues Region I Office November 16, 1990 Public Service Electric and Gas (PSE&G) Personnel R. Bashall, Systems Analysis Supervisor R. Braddick, Senior Staff Engineer (Fire Protection)

R. Brown, Principal Engineer - Nuclear Licensing & Regulations G. Knapp, Project Manager c: Lambert, Nuclear Engineer Science - Manager B. Preston, Licensing & Regulation - Manager A. Robinson, Project Manager D. Smith, Station Licensing Engineer U.S. Nuclear Regulatory Commission (NRC) Personnel C. Anderson, Chief, Plant Systems Section J. Durr, Chief, Engineering Branch T. Johnson, Senior Resident Inspector R. Paolino, Senior Reactor Engineer J. Stone, Project Manager - NRR/PDl-2 P. Swetland, Chief, Reactor Projects Seciton - 2A

ATTACHMENT 1

-

..

"FIRE PROTECTION" S.. -\\LEM GE.NERATING STATIO~

NOVEMBER 16, 1990

1979

  • NRC SET SPECIFIC FIRE PROTECTION CRITERIA WHICH INCLUDED ALL SYSTEMS REQUIRED TO ACHIEVE AND MAINTAIN SAFE SHUTDOWN
  • PSE&G COMMITTED TO CRITERIA WITH CERTAIN SPECIFIC ALTERNATE PROPOSALS 1980
  • NRC PUBLISHED APPENDIX R. SECTIONS III. G, III.J, III.L, III.O WERE APPLICABLE TO UNIT PSE&G LATER AGREED THAT MODIFICATIONS MADE FOR UNIT 1 WOULD BE MADE FOR UNIT *NRC ISSUED GENERIC LETTER 81~12 WHICH REQUIRED APPENDIX R COMPLIANCE
  • NRC STAFF CONDUCTED AN EIGHT DAY AUDIT OF THE SALEM FIRE PROTECTION PROGRAM. IT WAS CONCLUDED THAT A FULL POWER LICENSE SHOULD BE ISSUED FOR UNIT *FINAL SAFE SHUTDOWN AND INTERACTION ANALYSIS REPORT SUBMITTED TO STAF.SUBMITTAL OF EXEMPTION REQUESTS BASED ON STAFF REVIEW OF SEPTEMBER SUBMITTA *

1982

  • SUPPLEMENTAL REPORT ISSUED TO NRC RELATED TO ALTERNATE SHUTDOWN 1983 9-NRC DETERMINED SALEM IN COMPLIANCE WITH SECTIONS III.G.3 AND III.L.OF APPENDIX R REGARDING ALTERNATE SHUTDOW SAFETY EVALUATION REPORT ISSUED BY NRC
  • NRC ISSUED GENERIC LETTER 83-33, 1 NRC POSITIONS ON CERTAIN REQUIREMENTS OF APPENDIX R TO 10CFR50
  • PSE&G REQUESTED EXEMPTIONS DUE TO GENERIC LETTER 83-33 1984
  • PSE&G REQUESTED ADDITIONAL EXEMPTIONS DUE TO GENERIC LETTER 83--33
  • NRC REGION I INSPECTION FOR UNIT 1 (83-37).

EIGHTEEN ITEMS OF CONCERN IDENTIFIED BY INSPECTION TEAM 1985

  • FIRE PROTECTION/APPENDIX R HISTORY 1986

. * NRC ISSUED GENERIC LETTER 86-10 NOTING THAT IT TOOK PRECEDENCE OVER PRIOR CLARIFICATIONS OF APPENDIX R

  • NRC GAVE PSE&G VERBAL NOTIFICATION OF PLANS TO AUDIT SALEM IN 1987
  • PSE&G PROVIDED ADDITIONAL INFORMATION TO NRC REGARDING THE 1986 EXEMPTION REQUEST LETTER
  • PSE&G INITIATED A FIRE PROTECTION IMPROVEMENT PROGRAM
  • PSE&G SELF-IDENTtFIED VARIOUS REPORTABLE ITEMS

, TO REGION I

  • NRC REGION I INSPECTION OF UNIT EIGHT ITEMS

. OF CONCERN IDENTIFIED

'

MM&-12 l

  • FIRE PROTECTION/ APPENDIX R HISTORY 1988
  • PSE&G INITIATED HARDWARE MODIFICATIONS 1989
  • SCHEDULE ESTABLISHED FOR REMAINING PLANT MODIFICATIONS 1990
  • REGION I OPEN ITEM FOLLOW-UP INSPECTIO (90-01).

ELEVEN ITEMS CLOSE I l ---

11/90

PUBLIC SERVICE ELECTRIC & GAS COMPANY APPENDIX R UPGRADE PROGRAM MODIFICATION SUMMARY MODIFICATION DESCRIPTION Reroute UHF Conmuunication System Cables Panel 119 Separation Correct Spurious Actuation of C02 System DG FO Transfer Pump Cable Separation Cable Separation - FO Storage Tank Room Cable Separation - Upper Electrical Pe Cable Separation - C02 Equipment Room DG Control Cable Reroute Detection System - Control Room Complex Detection System - Aux. Bldg Corridor Detection System - Aux. Equipment Area Detection System - RHR HX Area Detection System - Pipe Tunnel Detection System - C02 Equipment Room Upgrade Fire Doors - 13 Fire Areas Expand Sprinklers - Aux. FW Pump Area Emergency Lights - RHR HX & Pump Areas EXEM N OPEN ITEM 311/87-29-07 311/87-29-04 311/87-29-01 311/87-29-04 311/87-29-04 311/87-29-04 311/87-29-04 311/87-29-02 311/87-29-02 311/87-29-02 311/87-29-02 311/87-29-02 311/87-29-02 292/83-37-03

Page 1 of 2 LER STATUS 87/009 Installed 7/88 87/009 Installed 7/88 87/009 Installed 9 /88 87/010 Installed 3/88 87/009 Installed.10/88 87/009 Installed 10/88 87/009 Installed 10/88 88/006 Installed 4/89 Installed 5/86 Installed 3/88 Installed 3/88 Installed 3/88 Installed 3/88 Installed 3/88 Installed 12/89 Installed 10/89 Installed 12/89

PUBLIC SERVICE EL C & GAS COMPANY APPENDIX R UPG DE PROGRAM MODIFICATION SUMMARY MODIFICATION DESCRIPTION EXEM N Automate C02 Suppression System - Elect. Pe Automate C02 Suppression System - 480V Swg Suppression System for 335 Panel - Containment

Cable Separation for 24 Fire Areas Various Evaluate Dampers

OPEN HEM LER 88/007

. Page STATUS Installation in progress Install at ion in progress Eng. complete Outage instal Engineering in progress Eng. assessment

  • in progress

PUBLIC SERVICE ELECTRIC & GAS SALEM STATION UNITS 1 & 2 APPENDIX R AND PEN SEALS EXPENDITURES EXPENDITURES IN MILLIONS$

50 ~~~~~~~~~~~~~~~~~~~

20

........ **********

-

1 **************9:0.7 YEARS YEARLY ACTUAL CUMMULATIVE YEARLY PROJECTED

-

'

NOTE: EXPENDITURES FOR 1990-1992 PROJECTED

  • MODIFICATION PRIORITIZATIOX

'

  • MODIFICATIONS ASSOCIATED WITH LICENSEE EVENT REPORTS (ENHANCEMENT TO PLANT SAFETY)
  • MODIFICATIONS TO THE FIRE DETECTION SYSTEM (GREATEST INCREASE IN FIRE PROTECTION SAFETY)
  • MODIFICATIONS TO VARIOUS FIRE PROTECTION FEATURES IN ADVANCE OF EXEMPTION REQUEST APPROVAL (LOW RISK, HIGH GAIN DUE TO NATURE OF EXEMPTION)
  • MODIFICATIONS TO FIRE SUPPRESSION SYSTEMS ASSOCIATED WITH APPROVED EXEMPTIONS (GREATEST INCREASE IN FIRE PROTECTION SAFETY)
  • OTHER MODIFICATIONS TO SUPPORT APPROVED EXEMPTIONS

--l

INSPECTION REPORT 50-272/83-37 SALEM UN IT NO. 1

83-37-01

  • AHA PUMP ROOMS EL. 45.

.

- INADEQUATE ENCLOSURE

.&ADDRESSED BY APPROVED EXEMPTION

.&DETECTION SYSTEM EXPANDED-NO PROCEDURES FOR REPAIR OF CSD EQUIPMENT

  • AHR EQUIPMENT PROVIDED WITH SAME LEVEL OF PROTECTION AS HSD EQUIPMENT

- COMPLETE

  • CHARGING PUMP AREA

- SUPPRESSION NOT AREA WIDE

.& SYSTEM EXPANDED-SUPPRESSION SYSTEM NOT A DAY TYPE SYSTEM

.&ACCEPTABLE VIA CORRESPONDENCE AND MEETINGS WITH NRC

- COMPLETE

  • INT AKE STRUCTURE

.&LACK OF 3-HA SEPARATION PROVIDED INCLUDING INSTALLATION OF FIRE DOOR

- COMPLETE

e 83-37-01 (Continued)

  • CONTAINMENT

'

-LACK OF DOCUMENTED SEPARATION ANALYSIS

  • ADDRESSED VIA JAN. 1984 CORRESPONDENCE

- COMPLETE

- PANEL 335 SEPARATION A ADDRESSED VIA EXEMPTION REQUESTS A DESIGN CHANGE FOR SUPPRESSION SYSTEM, ENGINEERING COMPLETE AWAITING NEXT OUTAGE FOR INSTALLATION

- OPEN

  • 460V SWITCHGEAR ROOM C02

. - DUPLICATE OF ITEM 83-37-06

- OPEN

--3

  • 83-37-04
  • AUXILIARY FEEDWATER PUMP ROOM SEPARATION (TRAYS 1A046 AND 1A033 CONSIDERED INTERVENING COMBUSTIBLES)

=TRAY iA033 WRAPPED-TRAY 1A046 NOT WRAPPED (NRA ACCEPTED INTERVENING COMBUSTIBLES IN EXEMPTION REQUEST APPROVAL)

-NECESSITY TO WRAP 1A046 TO BE DETERMINED VIA WRAP REQUIREMENT REVIEW. FOR FIRE AREA 1FA-AB-84B (CURRENTLY ONGOING)

I I

!

'

83-37-05 PENETRATION SEALS

~

'

83-37-06 e.460V SWITCHGEAR ROOM MANUAL C02 SYSTEM-EXEMPTION REQUEST COMMITS TO PROVIDING AN AUTOMATIC SUPPRESSION SYSTEM (APPROVED)

  • ENGINEERING COMPLETE
  • JOB CURRENTLY BEING INSTALLED
  • NEED OUT AGE TO COMPLETE
  • SCHEDULED FOR COMPLETION - APRIL 1991

- OPEN

  • 83-37-18
  • OPEN ENOS ON WRAPPED TRAYS

--7-AMPACITY BEING ADDRESSED AS PART OF WRAP EFFORT-TRAY AND CABLES TO BE WRAPPED PER EXEMPTION REQUEST COMMITMENTS

- ENGINEERING BEGUN

. INSPECTION

.*. REPORT.

50-311/87-29

  • sALEM UNIT NO. 2
  • 87-29-08
  • LACK OF ADEQUATE BREAKER COORDINATION-DETAILED ASSOCIATED CIRCUIT REVIEW INCLUDED AS PART OF WRAP EFFORT
  • 18 UNIT 2 FIRE AREAS REVIEWED (36 TOTAL)
  • B UNIT 2 FIRE AREAS REMAINING (16 TOTAL)

-PROBLEM CIRCUITS TO BE COORDINATED OR PROTECTED

87-29-03 PENETRATION SEALS

---

'

  • ATTACHMENT 2 SALEM GENERATING STATION PENETRATION SEAL REVIEW PROJECT PROJECT BASIS CONCERNS IDENTIFIED DURING PSE&G'S REVIEW OF THE SALEM PENETRATION SEAL PROGRAM INCLUDED:

INSTALLED SEAL CONFIGURATIONS APPEAR TO HAVE INADEQUATE

.MATERIAL DEPTH PLANTS WITH SIMILAR CONFIGURATIONS PREVIOUSLY UPGRADED THEIR PENETRATION SEAL DESIGNS (RANCHO SECO & TROJAN).

QUALIFICATION TESTING IS NOT AVAILABLE TO SUPPORT INSTALLED SEAL CONFIGURATION BASELINE CONFIGURATION DOCUMENTATION IS NOT AVAILABLE TO SUPPORT EXISTING SEAL CONFIGURATION PENETRATION SEALS HAVE BEEN IDENTIFIED WITH DESIGNS THAT DEVIATE FROM THOSE ESTABLISHED BY ORIGINAL INSTALLATION VENDOR PENETRATION SEALS HAVE BEEN IDENTIFIED WITH UNACCEPTABLE OR UNQUALIFIED MATERIAL PENETRATIONS HAVE BEEN IDENTIFIED IN FIRE BARRIERS WITHOUT SEAL PENETRATION SEALS HAVE BEEN IDENTIFIED WITH DAMAGE AND MATERIAL DEGRADATION *

SALEM GENERATING STATION PENETRATION SEAL REVIEW PROJECT PROJECT CRITERIA

IDENTIFY, EVALUATE, AND DOCUMENT PENETRATIONS IN BARRIERS IDENTIFIED BY THE UFSAR TO ASSURE COMPLIANCE WITH

lOCFRSO APPENDIX R&A

LICENSING COMMITMENTS

NRC INFORMATION NOTICE 88-04

SALEM GENERATING STATION PENETRATION SEAL REVIEW PROJECT OBJECTIVES

EVALUATE THE ADEQUACY OF EXISTING PENETRATION SEALS AND REPAIR, REPLACE OR UPGRADE AS REQUIRE ° CORRELATE SEAL DETAILS TO SUPPORTING DOCUMENTATION (FIRE TESTS AND EVALUATIONS) TO PROVIDE TRACEABILIT ESTABLISH BASELINE CONFIGURATION DOCUMENTATION WHICH PROVIDES SEAL LOCATION, SEAL DETAIL, AND OTHER DESIGN INFORMATIO ESTABLISH COMPONENT IDENTIFICATION NUMBERS AND PROVIDE LABELS (BAR CODED) FOR IDENTIFICATION AND TRACKIN i I

ESTABLISH DESIGN, INSTALLATION AND TRAINING PROCEDURES FOR USE BY PSE&G PERSONNE ESTABLISH A PROGRAM TO CONTROL FUTURE DESIGN CHANGES AND MAINTENANCE ACTMTIE PROVIDE A PROGRAM THAT IS FULLY DOCUMENTED AND AUDITABL SALEM GENERATING STATION PENETRATION SEAL REVIEW PROJECT OBJECTIVES

EVALUATE THE ADEQUACY OF EXISTING PENETRATION SEALS AND REPAIR, REPLACE OR UPGRADE AS REQUIRE ° CORRELATE SEAL DETAILS TO SUPPORTING DOCUMENTATION (FIRE

. TESTS AND EVALUATIONS) TO PROVIDE TRACEABILI1 ESTABLISH BASELINE CONFIGURATION DOCUMENTATION WHICH PROVIDES SEAL LOCATION, SEAL DETAIL, AND OTHER DESIGN INFORMATIO ESTABLISH COMPONENT IDENTIFICATION NUMBERS AND PROVIDE LABELS (BAR CODED) FOR IDENTIFICATION AND TRACKIN ESTABLISH DESIGN, INSTALLATION AND TRAINING PROCEDURES FOR USE BY PSE&G PERSONNE ESTABLISH A PROGRAM TO CONTROL FUTURE DESIGN CHANGES AND MAINTENANCE ACTIVITIE PROVIDE A PROGRAM THAT IS FULLY DOCUMENTED AND AUDITABL *

SCOPE JANUARY 1988 AUGUST 1990 INCREASE OVER ORIGINAL ESTIMATES PERCENT OF CHANGE FROM ORIGii~AL ESTIMATES SALEM GENERATING STATION PENETRATION SEAL REVIEW PROJECT PROJECT SCOPE ESTIMATED ESTIMATED TO REPAIR TO ACCEPT (STANDARD)

(AS-BUILT)

4,060 4,140 6,280 5,420 2,220 1,280 54%

30.9%

PROGRESS TO DATE

_11\\f.\\TED 1))1.ALSCOPE 8,200 1l,70(

3,50f'

PENETRATION ISSUED IN STANDARD DCPS................................................ 5,141/84%

PENETRATIONS ACCEP'fED "AS IS"............................................................. 4,042/67o/o TOT AL SEALS.............. o*************************eo*o**e*********9,183/7 5%

TOT AL SEALS INST AILED *...**...**....*.....*.*..*.**....*...*.....*....*............*.............. 4673/76%

COMMI'ITED END DATE * NRC INSTALLATION MARCH 1991 CLOSEOUT JULY 1991 NEW END DATES BASED ON IMPACTS SEPT 1991 JAN 1992

,,

SALEM GENERATING STATION PENETRATION SEAL REVIEW PROJECT PROJECT IMPACTS

PROJECT SCOPE INCREASE 3500 ADDITIONAL SEALS ( 42.6% INCREASE)

ADDITIONAL ENGINEERING

..

PIPE MOVEMENT CALCULATION LOAD EVALUATION SEISMIC EVALUATION 11/1 FIRE AND PRESSURE TESTING AMPACITY CALCULATION

° CHANGING FIELD CONDITION ASBESTOS DOUBLE DAMMING ADDITIONAL SCAFFOLDING INTERRUPTION OF WORK DUE TO NRC/INPO INSPECTION OUTAGE WINDOW TO ACCOMPLISH CRITICAL WORK ALARA CONCERNS

ITEM 88049 CCW PUMP AND HEAT EXCHANGER COMPARTMENT PSE&G has committed to enclose the No. 11 (21) CCW pump and the No. 11 (21) CCW heat exchanger in a 3-hour rated cubicle (1 and 2FA-AB-84C) with one exception. The ventilation duct penetrations will be sealed to the thickness of the barrie The room numbers assigned by the Salem Penetration Seal Review Group to the CCW pump and heat exchanger compartments are 15407, 25407 for Units 1 and 2 respectivel All of the penetrations entering the CCW cubicles have been addressed by the Salem Penetration Seal Review Group as shown on the attached list. Reflected on this list is the

  • seal ID, opposite room, log points (status) and CP number for each penetratio Support documentation is provided for each penetration according to its current statu CCW STATUS 11/06/90 UNIT 1 UNIT 2 TOTAL Number of Seals

91 177 Number of Seals Complete

48 105 Remaining Seals to Install

43 72

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