IR 05000272/1987025
| ML18093A462 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 10/14/1987 |
| From: | Swetland P NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML18093A460 | List: |
| References | |
| 50-272-87-25, 50-311-87-27, IEIN-80-21, NUDOCS 8710260175 | |
| Download: ML18093A462 (16) | |
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Public Service Electric and Gas Company
Report No Docket No License No Licensee:
U. S. NUCLEAR REGULATORY COMMISSION
REGION I
50-272/87-25 50-311/87-27 50-272 50-311 DPR-70 DPR-75 050311-830413 050311-870806 050311-870806 Public Service Electric and Gas Company 80 Park Plaza Newark, New Jersey 07101 Facility Name:
Salem Nuclear Generating Station - Units 1 and 2 Inspection At:
Hancocks Bridge, New Jersey Inspection Conducted:
August 25, 1987 - September 28, 1987 Inspectors:
Approved by:
T. J. Kenny, Senior Resident Inspector K. ~ibson, ~n_;g.;ctor
~~
P. D. Swetland, Chief, Reactor Projects
- section No. 28, Projects Branch No. 2, DRP Inspection Summary:
Inspections on August 25, 1987 - September 28, 1987 (Combined Report Numbers 50-272/87-25 and 50-311/87-27)
Areas Inspected:
Routine inspections of plant operations including:
operational safety verification, maintenance, surveillance, review of special reports, licensee event followup, review committee followup, closeout of regional temporary instructions, and Appendix R followu The inspection involved 204 inspector hours by the resident NRC inspectors, including backshift inspections on August 26, 28, September 3, 8, 10, 13, and 17, and *weekend inspection on Sunday, September 1 ~~686~72 PDR ADOC~
PDR G
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Public Service Electric and Gas Company
Results:
Unit operations were consistent throughout this report period and no concerns in that area were identifie However, as a result of another NRC inspection, concerns were raised within the Appendix R revie The concerns mainly centered around breaker coordination and separation of circuits in safety related system These concerns have resulted in compensatory measures being taken and a more strict overview of the fire protection progra This report highlights the resident inspectors*
interface with the Appendix R audit and actions taken by the license The report also closes out two Region I temporary instructions relating to diesel generators and storage of transient equipment in safety related area No violations were identified.
- L Public Service Electric and Gas Company
DETAILS Persons Contacted Within this report period, interviews and discussions were conducted with members of licensee management and staff as necessary to support inspection activit.
Operational Safety Verification Documents Reviewed Selected Operators' Logs Senior Shift Supervisor's (SSS) Log Jumper Log Radioactive Waste Release Permits (liquid & gaseous)
Selected Radiation Work Permits (RWP)
Selected Chemistry Logs Selected Tagouts Health Physics Watch Log Security Post Orders 2. 2. The inspectors conducted routine entries into the protected areas of the plants, including the control rooms, Auxiliary Building, fuel buildings, and containments (when access is possible).
During the inspection activities, discussions were held with operators, technicians (HP & I&C), mechanics, security personnel, supervisors, and plant managemen The inspections were conducted in accordance with NRC Inspection Procedures 71707, 71709, 71710, and 71881 and affirmed the licensee's commitments and compliance with 10 CFR, Technical Specifications, License Conditions, and Administrative Procedure No violations were tdentifie.3 Engineered Safety Feature (ESF) System Walkdown:
The inspectors verified the operability of the selected ESF system by performing a walkdown of accessible portions of the system to confirm that system lineup procedures match plant drawings and the as-built configuratio This ESF system walkdown was also conducted to identify equipment conditions that might degrade performance, to determine that instrumentation is calibrated and functioning, and to verify that valves are properly positioned and locked as appropriat The Unit 2 Charging System (High Head Safety Injection) was inspecte No deficiencies were identified.
Public Service Electric and Gas Company 6.4 Plant Operation:
The inspector reviewed selected phases of the units* operation to determine compliance with the NRC 1 s regulation The inspector determined that the areas inspected and the licensee's actions did not constitute a health and safety hazard to the public or plant personne.4.1 Unit 1 began the inspection period operating at 80% reactor power and maintained steady state conditions throughout the inspection period with a slow power decrease to 75% resulting at the end of the period due to unit coastdow.4.2 Unit 2 was synchronized to the grid on August 27~ 1987, following a 19 day outa~e to replace the main power transformer and recover from a conoseal leak on the reactor vessel hea Unit 2 operated at 100% reactor power throughout the remainder of the inspection period with the exception of short duration power reductions for turbine valve testing or to establish electrical system stability during thunderstorm warnings.
No violations were identifie Maintenance Observations The inspector reviewed the following fire protection department maintenance activities to verify that repairs were made in accordance with approved procedures and in compliance with NRC regulations and recognized codes and standard The inspector also verified that the replacement parts and Quality Control utilized on the repairs were in compliance with the licensee's QA progra Work Order Number 870916106 870914161 Maintenance Procedure M3Y Repair of Fire Barrier and Flood Protection Seals MlO-SST-026 Fire Barrier Penetra-tion Surveillance -
M3Z Electrical Equipment Trouble-shooting and Repair Description Repair Penetration Seal N A10005F Troubleshoot and Replace 1FP4CC Manual Pull Station Switch
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Public Service Electric and Gas Company
4.
Work Order Number 870921163 870920066 870923169 Maintenance Procedure MlO-SSN-040-1 Fire Alarm Pull Box Functional Test Ml4A-l Bolted Bonnet Gate Valve Maintenance MP7.l Valve Packing MP7.l Valve Packing Ml4A-l M23A Torquing Guide-1 ines No violations were identifie Surveillance Observations Description Repack Valve N llFPlll Repack Valve N FP243 Repair Valve N FP246 During this inspection period, the inspector reviewed in-progress surveillance testing as well as completed surveillance package The inspector verified that the surveillances were performed in accordance with licensee approved procedures and NRC regulation The inspector also verified that the instruments used were within calibration tolerances and that qualified technicians performed the surveillance The following surveillances were reviewed:
lPD-2.2.030 lPD-2.2.035 Channel Calibration Check lPT-514 No. 11 Steam Generator Steam Pressure Channel I Channel Calibration Check lLT-519 No. 11 Steam Generator Level Protection Channel II Reactor Engineering Manual Part 2 - Calorimetric Calculation SP(0)4.0.5-V (Room Coolers)
!ST-Room Coolers Visual Inspection, Valve Cycling and Timing, Modulating Valves No violations were identified.
Public Service Electric and Gas Company 8 Review of Periodic and Special Reports Upon receipt, the inspector reviewed periodic and special report The review included the following:
inclusion of information required by the NRC; test results and/or supporting information consistent with design predictions and performance specifications; planned corrective action for resolution of problems, and reportability and validity of report informatio The following periodic reports were reviewed:
Unit 1 Monthly Operating Report - August 1987 Unit 2 Monthly Operating Report - August 1987 No violations were identifie.
Licensee Event Report Followup The inspector reviewed the following LER 1 s to determine that reportability requirements were fulfilled, immediate corrective action was taken, and corrective action to prevent recurrence had been accomplished in accordance with Technical Specification Unit 2 83-014/03L-1 87-011-00 87-011-01 Loss of No. 21 RHR Pump Due to Spurious Operation of the Safeguards Equipment Control System (SEC).
This supplemental LER details corrective actions taken with regard to upgrading the SE Actions taken involved implementation of design changes and additional relay testin No spurious operation of the SEC has occurred since completion of corrective action The inspector considers this LER close Reactor Trip - No. 24 Steam Generator (SG) High-High Level; Personnel Erro This event was discussed in combined Inspection Report 272/87-24; 311/87-2 This LER and Supplement detail a turbine/reactor trip from 100% power on No. 24 SG High-High Level due to the operator not correcting a feed-steam flow deviation during a functional tes The unit was immediately stabilized in Mode Corrective actions included a performance review of the operator involved, corrective discipline, inclusion of the event in the Operator Training Program, and distribution of the LER to all licensed operator The inspector considers the corrective actions adequate and therefore the LER is close No violations were identified.
Public Service Electric and Gas Company 7.0 Review Committees
Technical specifications require that the following review committees function to advise licensee management and provide an independent safety review for activities related to nuclear safet The review committees are the Station Operations Review Committee (SORC) and -the Nuclear Safety Review (NSR) group which consists of the onsite safety review group (SRG) and the offsite safety review group (OSR).
The resident inspectors performed an inspection of the above review groups to evaluate implementation of their functions in accordance with Technical Specifications, ANS 3.1 (1981) and ANSI N18.7 (1976).
The following paragraphs give an overview of the review groups'
functions and the inspectors finding.1 Station Operations Review Committee (SORC)
The SORC is responsible for advising the General Manager - Salem Operations by written approval or disapproval of matters concerning nuclear safet The inspectors routinely attend SORC meetings and are on distribution for and review all minutes of SORC meeting As a result of the above, the inspectors have verified that:
The composition of the SORC conforms to Sections 6.5.1.2 and 6.5.1.3 of the Technical Specifications (T.S.).
The SORC meets a minimum of once per week (T.S. require once/month frequency)
A minimum quorum of the Chairman and five members (including alternates) is present at the SORC meeting The SORC reviews required documents and changes thereto and recommends approval or disapproval in writing to the General Manager - Salem Operation The SORC maintains written minutes of each meeting and provides copies to the Vice President - Nuclear, General Manager - NSR, and Manager, OS The activities and responsibilities of SORC are implemented through Station Administrative Procedure (AP)- The committee reviews and concurs in all matters relating to the cause of a reactor trip and subsequent startup.
Public Service Electric and Gas Company 7.2 Nuclear Safety Review (NSR)
The NSR includes two review groups:
one that consists of a General Manager and at least four dedicated, full time engineers located onsite, and the other includes a Manager offsite that is supported by at least four dedicated, full time engineer These organizations perform continuous evaluations and serve to advise the Vice President on matters of nuclear safet.2.1 Onsite Safety Review Group The Onsite Safety Review Group (SRG) functions to provide a review of plant design and operating experience for potential opportunities to improve plant safety, to evaluate plant operations and maintenance activities, and to advise management on the overall quality and safety of pla~t operation The SRG makes recommendations for revised procedure equipment modifications, or other means of improving plant safety to appropriate station/corporate managemen The inspectors reviewed the activities performed by this group and noted that procedure changes and design changes have been instituted as a result of their finding.2.2 Offsite Safety Review Group (OSR)
The offsite review group performs reviews of the following:
Safety evaluations for changes to procedures, equipment, or systems and tests or experiments completed under the provisions of lOCFR 50.59, to verify that such actions did not constitute an unreviewed safety questio Proposed changes to procedures, equipment, or systems that involve an unreviewed s~fety question as defined in lOCFR 50.5.
Proposed tests or experiments that involve an unreviewed safety question as defined in lOCFR 50.5 Proposed changes to Technical Specifications or to the Operating Licens Public Service Electric and Gas Company
Violations of codes, regulations, orders, Technical Specifications, license requirements, or of internal procedures or instructions having nuclear safety significance..
- Significant operating abnormalities or deviations from normal and expected performance of plant equipment that affect nucle'ar safet All reportable event All recognized indications of an unanticipated deficiency in some aspect of design or operation of safety-related structures, systems or component Reports and me~ting minutes of the Station Operations Review Committe The offsite review group is also cognizant of the performance of plant audits conducted by the Nuclear Quality Assurance Department or an independent consultan Audit results and recommendations are reviewed by OS The inspectors reviewed the documentation related to OSR activities itemized in Attachment 1 to this repor.3 Conclusion As a result of the above reviews, the inspectors have determined that the licensee's review groups performance meet or exceed Technical Specification and applicable industry standards/require-ment Through their published meeting minutes, reports, open item tracking systems, and verbal communication, these groups keep the General Manager and Vice President apprised of matters pertaining to nuclear safet No violations were identifie.0 Closeout of Regional Temporary Instructions The Region issued temporary instructions _to review two matters that concern nuclear safet They are RI 87-03, "Storage of Transient Equipment in Safety-Related Areas 11 and RI 87-04, "Bypass of Non~Essential Diesel Generator Trip The following paragraphs address these concern Public Service Electric and Gas Company 12 RI 87-03, "Storage of Transient Equipment in Safety-Related Areas" The purpose of this inspection was to assess the status and implementation of licensee administrative controls for the storage of transient equipment having the potential to adversely affect safety-related equipmen The inspectors discussed the subject with licensee licensing, operations, maintenance, chemistry, technical, and management personnel; performed plant tours; and reviewed the following documents:
Trip Report for Seismic Criteria Implementation Review dated April 25, 1979 Licensee internal response to IN 80-21 dated November 6, 1980 Safety Evaluation S-C-A900-MSE-307, Revision 0, "Temporary Storage Areas for Outage Equipment" dated April 9, 1985 Safety Evaluation S-C-A900-SFD-278, Revision 3, "Use and Control of Scaffolding in Safety-Related Areas 11 dated February 10, 1986 Station Administrative Procedure (AP)-23, Revision 0,
"Scaffolding Program 11 dated October 9, 1985 AP-31, Revision 4, 11Housekeepi ng Program 11 dated July 10, 1986 Nuclear Department Safety Manual
- Section III Storage and Handlihg of Compressed Gases
- Section X Materials Handling and Rigging Equipment
- Section XI Ladders, Scaffolding, Floor, Wall Opening and Stairways
- Addendum II Portable Ladder Use and Care (MlO-ISD-006)
The inspectors made the following observations and conclusions:
The licensee addressed the seis~tc design concerns documented in NRC In.formation Notice 80-21, by reference to their resolution of inspection findings from an NRC Seismic Qualification Review Team (SORT) inspection performed at Salem in February 197 However, these findings did not address the issue of temporary storage of heavy equipment which may invalidate the seismic desig **
Public Service Electric and Gas Company
The licensee's general housekeeping policy requires that equipment be in use, properly stored, or removed from the statio The inspectors have not identified a generic weakness in station implementation of this polic The licensee has performed safety evaluations and has a detailed program relative to the use and control of scaffolding in safety related area The licensee has performed safety evaluations addressing when, where and how transient equipment may be stored in safety-related areas in the Auxiliary Buildin The licensee has not performed a safety evaluation or
- established procedural controls for storage of transient equipment in the relay, switchgear, or diesel generator room The inspectors rece~tly identified several discrepancies in the switchgear rooms with regard to unsecured ladders and tool boxe The items were being used to support Unit 1 pre-outage activities. The issue was brought to the attention of the Senior Shift Supervisor who directed operating personnel to make a tour of the plant and identify similar deficiencie As a result the licensee compiled a list of items not properly stored (also attributed to pre-outage activities). Although the above items were not stored in designated storage areas, inspector review of the items and locations concluded that the impact to safety -
related equipment was minimal due to either the type or size of the item or the distance from surrounding equipmen The inspectors identified the following concerns to station management: Storage of transient equipment in the switchgear, relay, and diesel generator rooms does not appear to have been addressed by the licensee through safety evaluation or procedure, policy, et.
With the exception of scaffolding for which policy is well d~fined and use is strictly controlled, the policy for control and storag~ of other transient equipment does not appear to be known and/or followed by station and/or contractor personnel at least during this pre-outage time perio Public Service Electric and Gas Company
The licensee has committed to upgrade their policy and program for storage of transient equipment in safety-related areas by November 30, 1987, including: Issue a letter in the near future to all site personnel addressing proper storage locations and method.
Perform a safety evaluation addressing storage locations in the switchgear, relay, and diesel generator room.
Upgrade the Station Administrative Procedures to define the licensee's policy and progra.
The licensee is considering physically labeling approved storage areas throughout the plan The inspectors will follow licensee's progress toward these commitments and will continue to monitor the presence and impact of transient equipment in safety related areas at Salem during routine resident inspection.2 RI 87-04, "Bypass of Non-Essential Diesel Generator Trips" During a loss of coolant accident (LOCA) or loss of offsite power (LOOP) certain diesel generator trips are bypassed because of the urgent need of diesel generators during these accident condition The bypassed trips are:
Diesel generator breaker failure Hi-lube oil temperature Emergency stop Hi-jacket water temperature Over crank relay Loss of excitation relay Voltage sensing relay However, diesel generator trips essential for the protection of the diesel remain in the circuit, they are:
Engine overspeed Low lube oil pressure Generator differential 4 KV bus differential The objective of this inspection was to access how the licensee addressed the testing of the above listed diesel generator trip **
Public Service Electric and Gas Company
By the review of completed licensee operating and surveillance procedures, the inspector determined that the trips are calibrated and tested by qualified technicians and operators in accordance with manufacturer 1 s instructions and technical specification.3 Conclusion The resident inspectors consider the above temporary instructions close No violations were identifie.
Appendix R Followup As a result of the NRC Appendix R inspection performed the week of September 14 (50-311/87-29) which identified fire protection (FP) program deficiencies, the licensee committed, via letter dated September 18, 1987, to establish the following compensatory measures which the resident inspectors verified:
That continuous and roving firewatches are established as appropriate to the areas of concer That containment temperatures are monitored hourly and plant operators are cognizant of actions to be taken if containment temperatures ris That high radiation areas where FP problems exist were identified and detection/surveillance methods are implemented as appropriat Two Chemical and Volume Control System (CVCS) Hold-Up Tank (HUT)
rooms per unit were without detection and are not accessible for routine surveillance due to changing radiological dose rates in the room Interim compensatory measures for these rooms consist of *television camera surveillance by roving firewatche The licensee has committed to install smoke detectors in the common ventilation exhaust ducting for each unit with the design change request (OCR) issued by September 30, 1987 and the detectors installed by October 15, 198 That the fire protection department 1 s work order tracking system is in effec The licensee has committed to provide the resident inspectors, on a monthly basis, a status report of fire protection work order The inspectors will meet with fire protection supervision to perform a detailed review of outstanding work orders to ascertain the magnitude and safety significance of the backlog and licensee plans to minimize that backlo Public Service Electric and Gas Company
The licensee 1 s immediate compensatory measures were found to be adequat Further licensee actions and NRC followup will be addressed during a meeting at the Region I office the week of October 5, 198.
Exit Interview At periodic intervals during the course of the inspection; meetings were held with senior facility management to discuss the inspection scope and finding An exit interview was held with licensee management at the end of the reporting perio The licensee did not identify 2.790 materia Public Service Electric and Gas Company
ATTACHMENT 1 Offsite Review Group Records Reviewed OSR Procedures
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M40-POP-Ol
Organization and Responsibility
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M40-LEP-Ol
Technical Qualifications and Resources
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M40-LEP-02
Independent Safety Review Program
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M40-LEP-03
Audits
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M40-MSP-Ol
Offsite Safety Review -
Manual Preparation and Control Experience and Competence Matrix, Revision 10, May 1, 1987 Staff Resumes OSR Biweekly Reports to the Vice President OSR Review of the following documents: Procedures Changes
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M6A Design Changes
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4-HMJ-86-1256
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2EC-1680 Deficiency Report
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HlC-87-0126 NRC Inspection Reports
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272/85-01, 311/85-04
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311/86-26
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272/87-02, 311/87-02
Public Service Electric and Gas Company Licensee Event Reports
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87-01
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87-02 Special Report - 86-11 SORC Meeting Minutes (Salem)- 86-021
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87-010 - 87-013 Audit Reports
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NM-86-026
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NM-87-02