IR 05000272/1980033
| ML18085B088 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 01/30/1981 |
| From: | Chung J, Greenman E, Shaub E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML18085B087 | List: |
| References | |
| 50-272-80-33, NUDOCS 8103270788 | |
| Download: ML18085B088 (14) | |
Text
U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Report No. 50-272/80-33 Docket No. 50-272
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Region I Licen.se No. DPR-70
Pri.ority -------
Category ____ c _____ _
Licensee:
Public Service Electric and Gas Company 80 Park Plaza - 15A Newark, New* Jersey 07101 Facility Name:
Salem Nuclear Generating Stati Inspe~tion at:
Hancocks Bridge, Inspection condu, ted:
Inspectors:
. Approved by:
i E. G. Greenman, Chief, Support Section No. 2, RO&NS Branch Inspection Summary:
Inspection *on *December*. 8-12: 1980 : (Report* No~ * so.:.272;ao.;. 33)
- /~~r-1/
date signed..
1-vY-f'/,
.date signed date signed.
/-30 -.Ji/
date signed Areas.Inspected: Routine, unannounced inspection by two. region-based inspectors of administrative controls for ~urveillance procedures; surveillance testing; inservice inspection program; performance of surveillance and inservice inspection tests; administrative controls for safety-related maintenance; safety-related maintenance activities; surveillance/inservice inspection and maintenance personnel qualifications; control room observations and facility tou The inspection involved 60 inspector-hours on _site by two region-based inspectors *.
Results:
Items of non comp 1 i ance:
Non Region I Form 12 (Rev. April 77).
8 1 0 3 2 7 0 1.<0'6
- Persons Contacted Principal Licensee Employees V. Gadzinski, Lead Engineer P. Kordziel, MIET Coordinator DETAILS
- H. Lave, Q.A. Engineer, PSG&E Resident Group B. Leap, Station Q.A. Supervisor
- H. Midura, Plant Superintendent T. Robbins, Instrument Supervisor
- J. Stillman, Station Q.A. Engineer W. Treston, MIET* Coordinator D. Vest, Associate Engineer USN RC
- W. Hill, Resident Inspector The inspectors also intervi~wed other lic~nsee employees during the inspection including Reactor Operators, Technical Support, Maintenance,.
Performance and Quality Assurance personne *Denotes those present at the exit int~rvie.
Administrative Controls for Surveillance Procedures and In-service Inspection Program The inspector performed an audit of the licensee 1s administrative controls by conducting a sampling review of the below listed administrative proce-dures with respect to the requirements of the Technical Specifications, Section 6, 11Administrative Controls 11, ANSI Nl Administrative Controls for Nuclear Power Plants 11 and Regulatory Guide 1.33 11Quality Assurance Program Requirements 11 *
AP-3, Station Documents, Revision 9, April 10, 197 AP-4, SORC, Revision 7, October 8, 1980.
. AP-5, Operating Practices Program; Revision 10, May 22, 1980 AP-10, Inspection Order System, Revision 3, September 7, 1979 AP-11, Station Records, Revision 4, February 5, 1979
AP-14, Station Training, Revision 3, May 11, 1977 AP-17, Quality Assurance Program, Revision 5, April 17, 1979 AP-23, Qualifications of Inspection, Examination and Test Personnel, Revision 3, January 23, 1979 AP-27, Inservice Inspection Program, Revision 2, February 26, 1980 SPM-Book 7, Suryeillance Procedure Index No unacceptable conditions were identifie.
Surveillance Testing *The inspector reviewed surveillance tests on a random basis to verify the fo 11 owin Tests required by Technical Specifications are available and covered by properly approved procedures; Test frequency is in conformance with Technical Specification requirements; Test format and technical content are adequate and provide satisfactory testing of related systems or components; Test results of selected tests are in conformance with Technical Specifications and procedure requirements have been reviewed by someone other than the tester or individual directing the tes Documentation of the following surveillance activities were reviewed to verify the abov SP(O) 4.1.3.1.2, Rod Control Assemblies, Revision 1, September 197 Data reviewed for eight tests performed January 17, 1980 through September 17, 198 SP(O) 4.3.2.1.1.(a), Engineered Safety Feature - Steam Line Isolation, Revision 1, August 197 Data reviewed for test performed December 25, 197 SP(O) 4.3.2.1.3, Engineered Safety Feature - Response Time Testing, Revision 3, January 18, 197 Data reviewed for test performed October 14, 1979.
- 1PD14.3.002, Instrument Response Time Test - Master, Revision 1, August 12, 197 Data reviewed for tests performed December 20, 1978 and September 24, 197 SP(O) 4.4.6.2(d), Reactor Coolant System - Water Inventory Balance, Revision 3, August 23, 197 Data reviewed for ten tests performed January 1, 1980 through November 27, 198 SP(O) 4.4.. 6.2(c), Reactor Coolant System - Controlled Leakage Measurement, Revision 1, January 21, 197 Data reviewed for five tests performed January 21, 1980 through May 20, 198 SP(O) 4.4.1.1.a, Reactor Coolant System - Coolant Loops, Revision 3, January 18, 197 No data was reviewed, three loop operation is not permitte SP(O) 4.S.4.2(a), Emergency Core Cooling - Vital Heat Tracing, Revisio~ 3, March 7, 197 Data reviewed for eight tests per-formed February 27, 1980 through July 20, 198 SP(O) 4.5.2.d.(l), Emergency Core Cooling - RHR Pressure Inter-lock Test, Revision 3, January 3, 197 Data reviewed for
. test performed November 13, 197 SP(O) 4.5.2.d(2), Emergency Core Cooling - Containment Sump, Revision 1, Febryary 16, 197 Data reviewed for test performed November 8, 197 SP(O) 4.6.2.2.(b), Containment Spray - Spray Additive, Revision 1, January 21, 197 Data reviewed for tests performed March 20, 1978, September 1, 1978, March 2, 1979, and September 8, 198 SP(O) 4.6.3.1.2.(d), Containment Ventilation Isolation; Revi-sion 3, January 18, 197 Data reviewed for test performed October 14, 197 SP(O) 4.7.1.3.2, Plant System - Auxiliary Feedwater, Revision 2, May 16, 197 Data reviewed for six tests performed January 29, 1980 through February 1, 198 SP(O) 4.8.1.1.1.(b), Electrical Power Sources - Bus Transfer, Revision 1, January 28, 197 Data reviewed for tests performed May 22, 1978 and September 22, 198 SP(FF) 4.7.10.2(a), Fire Suppression - Deluge Values, Appendix P of Fire Fighting and Organizational Manual, Revision 2, March 8, 197 Data reviewed for tests performed March 20, 1978, June 1, 1979 and August 14, 197 *
- SP(FF) 4.7.10.2.(b), Fire Suppression - Deluge Valve, Appendix Q of Fire Fighting and Organizational Manual, Revision 2, March 8, 197 Data reviewed for tests performed March 20, 1978 and June 1, 197 SP(FF) 4.7.10.4(a), Fire Suppression - Fire Hose Station Inspec-tion, Appendix E of Fire Fighting and Organizational Manual, Revision 2, March 8, 197 Data reviewed for five tests per-formed February 23, 1979 through May 30, 197 SP(O) 4.9.4, Refueling OPS - Containment Building Inventory, Revision 2, January 26, 1978, Temporary Change 1, November 11, 198 Data reviewed for nine tests perfonned May 3, 1979 through November 5, 198 lPD-2.2.066, Channel Calibration Check, PT-948A Containment Pressure Protection - Channel IV, Revision 2, October 9~ 197 Data rev.i ewed for test performed April 21, 198 *
lPD-2.5066, Channel Sensor Calibration, PT-948A Containment Pressure Protection - Channel IV, Revision 1, September 19, 1977~
Data reviewed for test performed May 22, 1979.
Findings (1) The Containment Isolation Valve 1(2)FP147 was identified as 1(2)FP47 in the Fire Fighting and Organizational Manual, Appen-dix E (SPCFF) 4.7.10.4a) and P(SP(FF)4.7.10.2B).
This item will be reviewed during subsequent inspection pending correction of the valve identification in the procedures (272/80-33-01).
(2) Several Surveillance Procedures were overdue for review, contrary to the requirements specified in Administrative Control Pro-cedure, AP-3, Revision This item had been identified during the previ-0us inspection, 272/80-31-01, and the licensee committed to comply with the two-year review requirements by June 1, 198 The inspector had no further questions in this are.
Inservice Inspection Program The inspector reviewed the in-service inspection plan and procedures on a sampling basis to verify the following:
Tests are in conformance with the in-service inspection program requirements.
- Test frequency is in conformance with Technical Specifications and the In-Service Inspection Progra Test format and technical content are adequate and provide satis-factory testing of related systems or component Test results have been reviewed as required by facility admi ni s-trative requirements and appropriate action was taken for results failing acceptance criteri Tests are performed by qualified personne The following in-service inspection plans, procedures and test results were reviewed to verify the above as applicabl Ml4A, General Instructions for Disassembly, Inspection, and Reassembly of Valves, Revision 10, September 11, 1980. * Procedure reviewe SP(0)4.0.5-V,.Inservice Testing - Valves, Revision 4, February 15,.
197 (1) Sheet 4.1, Category 11A" Valve Stroke Tim Test performed September 5, 198 (2) Sheet 4.2, Category 118 11 Valve Stroke Tim Test performed July 6, 198 (3) Sheet 4.3, Category "B", Position and Locking Device Veri-ficatio Test performed July 2~ 198 M17D, Pump Surveillance Test Results Analysis, Revision 5, June 4, 198 (1) #11 Boric Acid Transfer Pum Ten tests performed April 15, 1980 through November 17, 198 (2) #11 and #12 Service Water Pump Four tests performed May 27, 1980 through August 26, 198 (3) #11 Charging Pum Four tests performed July 17, 1980 through December 6, 198 Ml6E, Containment Isolation Type B and C Tests,.*:Revision l3,,
June 29, 197 *
-(1) Mechanical Penetratio Five tests performed October 14-21, 198 (2) Valve Three tests performed September 30, 1980, October 14, 1980, and Nove~ber 25t 198 (3)
Ai~ Lock Inner Door, EL 130 1 *
Test performed September 24, 198 (4) Electrical Penetration. Three tests performed September 20, 198 No unacceptable conditions were identifie.
Inspector 1s Witnessing of Surveillance and Inservice Inspection Tests The inspector witnessed the performance of surveillance and inservice inspection testings of selected.components to verify the following:
Test procedure was available and in use; '
Special test equipment required by procedure was calibrated and in use; Test prerequisites were met; The procedure was adequately detailed to assure performance of a satisfactory surveillance; Test was performed in accordance with procedural requirements; System restoration was correc The inspector witnessed the performance of the following surveillance tests:
lPD-2.6.019, Channel Functional Test, lPT-457 Pressurizer Pres-sure Protection - Channel III, Revision 6, November 28, 197 Test performed December 9, 198 M17D, Pump Surveillance Test Results Analysis, Revision 5, June 4, 1980; SP(0)4.0.5-P, Inservice Testing-Pum Test per-formed December 12, 1980 for #12 Charging Pum No unacceptable conditions were identifie *
8 Administrative Controls for Safety-Related Maintenance Administrative controls were reviewed to determine the licensee's program for implementing requirements associated with the conduct of safety-related maintenance was as specified in Technical Specifications Section 6 Regula-tory Guide 1.33; Quality Assurance Program Requirements; and ANSI 18.7, Administrative Controls for Nuclear Power Plant The following procedures wer-e reviewed: Station Administrative Procedures AP-8, Station Design Change, Test and Experiments, Revision 4, June 20, 197 AP-9, Work Order System, Revision 4, November 13, 197 AP-15, Work Order Procedures, Revision 1, November 17, 198 AP-21, Cleanliness and Housekeeping, Revision 1, March 2, 197 AP-25, Control of Station Maintenance and Repair, Revision 1, February 26, 197 Maintenance Department Administrative Procedures A-3, Maintenance Department Training Program, Revision 7, August 28, 197 A-4, Special Reports, Revisio~ 2, December 2, 197 A-6, Equipment History, Revision 5*, May 1, 198 A-8, Document Control, Revision 6, April 16, 197 A-10, Technical Sp~cification Surveillance Program, Revisi-0n 5, October 27, 198 A-11, Maintenance Department Procedure Writing/Revision Guide-lines, Revision 19, July 9, 198 SI-1 through 7, Standard Procedure - Qualification Cards, Revision 2, September 24, 198 SI-1-7, Standard Qualifications, Revision 0, April 17, 197 No unacceptable conditions were identifie..
7. * Review of Safety-Related Maintenance Activitie The inspector reviewed safety-related maintenance conducted by the licensee on a sampling basis to verify that:
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Technical Specification requirements were met while equipment was out of service, and a Licensee Event Report was submitted for maintenance associated with a reportable occurrenc Required administrative approvals were obtained to perform the wor An approved procedure was used where appropriat Required inspections were performe Records to substantiate the quality of work and parts used were available (this includes documentation associated with procurement, inspections,and test results). Documentation of the following maintenance activities were reviewed:
Work Order MD 910196, 2A Diesel Alarm; Recalibrate LTD No. 6441 and 6442, performed September 10, 1980; Procedure M3I, Auxiliary Control Calibration, Revision 5, March 1, 197 Work Order MD 910226, 2A*Diesel, Recalibrate Instrument 2PD 8314, performed September 16, 1980; Procedure M3I, Auxiliary Control Calibration, Revision 5, March 1, 197 Work Order OD 903570, 2B460V Vital Bus 4KV/4602 Transformer Feeder Breaker Tripped, performed March 12, 1979; Procedure M3Z, Electrical Equipment Troubleshooting and Repair, Revision 4, October 13, 197 Work Order 905641, 12 Boric Acid Transfer Pump, Leaking Pump Seals and Oil Seals, performed May 14, 1979; Procedure MllE, Mechanical Equipment Troubleshooting and Repair, Revision 6, January 20, 197 Work Order MD 910181, Station Batteries, performed September 10, 1980; Procedure M-3M, Weekly Battery Check Work Order OD 914050, Diesel Generator and Ventilation, performed April 24, 1980; OCR No. !EC 0478, Prg. 1, Revision Work Order OD 932203, Heat Trace - Panel 097B2, performed July 30, 198..
Work Order MD 919787, Valve 14-M5-8 Leaking-Repack, performed December 6, 197 Wor~--Order* MD 917659, Va 1 ve 2SJ-13 wi 11 not open e 1 ectri ca lly, performed April 4, 1980; Procedure M3Z, Electrical Equipment Troubleshoot and Repair, Revision 4, October 13, 197 Work Order MD 936438, Service Pressure Leak Examination, per-formed August 28~ 1980; Procedure M17F-l, Revision 0, August 2, 197 Work Order* MD 902929, Valve 1-SJ-119 Repack, performed May 17, 197 Work Order MD 903451, Va 1 ve 12-RC-17 Repack, performed April 14, 1979; Catalytic Repair Packing Leak 12-RC-17, Revision 0, March 14,.197 Work Order OD 937032, Valve 11-SJ-23 Repack, performed September 20, 198 Work Order OD 904592, #14 Service Water Pump - Replace Broken Shear Pin on Strainer Backwash, completed March 7, 1979; Procedure MllE, Mechanical Equipment Troubleshooting and Repair, Revision 6, January_20, 197 Work Order OD 904629, #11 Waste Gas Compressor Breaker lEGX wi 11 not close, performed March 19, 1979; Procedure M3Z, Electrical Equipment Troubleshooting and Repair, Revision 4, October 13, 197 Work Order OD 903565, 21 Auxiliary Building Supply Fan-Circuit Ground, performed February 12, 1979; Procedure M3Z, Electrical Equipment Troubleshooting and Repair, Revision 4, October 13, 197 Work Order MD 905905, No. 12 Steam Generator, performed September 10, 1979; Procedure OCR 130 Work Order RC 906987, No. 11 Iodine Removal Filter System, performed February 14, 198 Work Order OP 903052, No. 13, Fan Cooler Unit, performed April 20, 1979; Procedure MSA Technical Manual, M1 Work Order OD 911664, Auxilary Feed Pumps, performed December 1, 1980.
- Work Order OP 901596, No. 13 Component Cooling Pump, performed May 29, 1979; Procedures M6C, M6D, and OCR ISL-0148-13, Replace Stainless Steel Impelle Work Order MD 93305, Support Valve Dissambly - Following Correc-tive Maintenance, performed December 6, 198 Work Orders PD 928523 through PD 928527, Rep 1 ace so:1 enoid Valves, performed December 1980; Procedure DCR-1-EC-071 *oocumentation of the following Preventive Maintenance activities were reviewed:
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PM ID No. 200266, No. 1 Turbine Crane/Inspection, completed September 23, 197 PM ID No. 200234, No. 1 Station Power Transformeri completed August 11, 197 PM ID No.. 200303, Update Instructions, Test, and Surveillarice, completed June 17, 197 *
PM ID No. 200208, Fire Pumps Nos. 1 and 2, completed August 23, 197 PM ID No. 200393, Service Water Bays Nos. 11 through 16, com-pleted November 16, 197 PM ID No. 200425, Simpson 260 OM-118/Calibration, completed December 27, 197 PM ID No. 200646, Fuel Handling Cranes and Walkway, completed October 1, 197 PM ID No. 200441, Fluke 8600A M-127/Calibration, completed September 30, 197 PM ID No. 200102, 4KV Vital Buses, completed November 20, 198 PM ID No. 200102, Functional Test, Under Voltage-Vital Bus, completed November 3, 197 PM ID No. 200139, 125V D.C. Batteries lA, lB' and lC; completed November 22, 197 PM ID No. 200040, Cask Handling Crane-Bridge Drive, ~ompleted August 30, 197 *
PM ID No. 200174 125 V D.C. Batteries, completed March 28, 197 Findings (1) According to the Station Administrative Control Procedure AP-9, the post-maintenance retesting requirements should be specified in the appropriate column of the Work Order sheet, and the com-pletion of the retesting be recorded by entering a signature of the departmental reviewer in that colum Further, the completed retest package should be attached to the Work Order shee During the review of a completed maintenance work package, OP 901596, in which a new Stainless Steel Impeller was installed for #13 Component Cooling pump on May 29, 1979 in accordance with Design Change Request OCR ISC-0148-13, the inspector noted that
/ neither the post-maintenance retesting was specified nor the retest results were attached to the completed Work Order package, *
even though the post-maintenance surveillance test had been con-ducte A licensee representative stated that the post-maintenance test requirements for the safety-related components would be strictly enforced by instructing the importance of the proper doctimenta*
tion and record keeping to the appropriate personnel. This item is unresolved pending review of the post-maintenance test docu-.
mentation (272/80-33-02).
(2) Prior to the release of a Work Order for safety-related mainten-ance activities, the QA notification of the activities is require Also, Administrative Procedure AP-9, Paragraph 4.2.3 requires that work packages designated 11Safety Related" or 11QA Required" are subject to Station QA review in accordance with the Station QA Surveillance Progra Upon notification of the activities, the QA department may choose to participate in the activities by sending an independent QA sur-veillance team, and some of the completed work package will be sub-jected to the final QA review. Several licensee representatives acknowledged that this raised a confusion and misinterpretation of the QA review requirements of the completed work packages for the safety-related Work Orde A licensee representative clarified the QA review requirements by stating that starting January 1, 1981, all of the completed safety-related work order packages would be reviewed by the QA grou This area will be re-inspected during subsequent NRC:RI inspection (272/80-33-03).
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8 *. Maintenance/Surveillance Personnel Qualifications The inspector reviewed the qualification records of selected* technicians and craft personnel who were involved in pl ant operations,. sur.vei 11 ance, and inservice inspection maintenance activities on safety-related systems and components to certify that the individual's experience level and *
training were in accordance with guidelines of ANSI Nl8.l-l971, Selection and Training of Nuclear Power Plant Personnel, Section The qualification records of twelve personnel were selected from the depart-ments; two Inservice Inspection technicians, three instrument and control technicians, five maintenance technicians, and two Quality Control inspec-tors (contractor, Catalytic Inc.).
No unacceptable conditions were identifie.
Control Room.Observations and Facility Tours The inspector observed Control Room operations for control room manning, shift turnover and log sheets, and facility operation in accordance with the administrative procedures and Technical Specification requirement Inspection tours of turbine/generator building and selected protected areas were conducte No items of noncompliance were identifie. Unresolved Items Unresolved items are matters about which more information is required to clarify whether they are acceptable, or items of noncompliance, or devia-tion An unresolved item was identified and detailed in Paragraph 7.d(l).
11. Entrance and Exit Interviews Licensee management was informed of the purpose and scope of the inspection at the entrance interview, and the findings of the inspection were periodically discussed with the licensee representatives as summarized in the following:
Date Re~ortable Details Covered December 8, 1980 Entrance December 9, 1980 3.c(l), 3.c(2)
December 10, 1980 7.d(l)
December 11, 1980 7.d(l), 7.d(2), December 12, 1980 7.d(l), 7.d(2), Exit
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The.inspector conducted an exit interview with licensee representatives
- (denoted in Paragraph 1) at the conclusion of the inspection. The licensee acknowledged the inspection findings.