IR 05000272/1987010
| ML18092B568 | |
| Person / Time | |
|---|---|
| Site: | Salem, Hope Creek, 05000000 |
| Issue date: | 05/01/1987 |
| From: | Eapen P, Oliveira W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML18092B567 | List: |
| References | |
| 50-272-87-10, 50-311-87-13, 50-354-87-09, 50-354-87-9, NUDOCS 8705130046 | |
| Download: ML18092B568 (7) | |
Text
U.S. NUCLEAR REGULATORY COMMISSION
REGION I
Report No /87-10 50-311/87-13 50-354/87-09 Docket No License Nos. DPR-70 DPR-75 NPF-57 Licensee:
Public Service Electric and Gas Company 80 Park Plaza Newark, New Jersey 07101 Facility Name:
Salem and Hope Creek Generat1ng Stations Inspection At:
Hancocks Bridge, New Jersey Inspection Dates:
April 6-16,1987 Inspector:
Approved by:
date
'
s"-'/ /81 date~'
Inspection Summary: Routine unannounced inspection on April 6-16, 1987 (Report Nos. 50-271/87-10, 50-311/87-13, and 50-354/87-09).
Areas Inspected: Non Licensed Staff Training and Licensee Action on Previous Inspection Finding Results: No violations or deviations were identified.
8705130046 870505 PDR ADOCK 05000272 G
DETAILS 1. Persons Contacted Salem Generating Station L. Fry, Planning Manager M. Gray, Licensing Enginee~
J. Gueller, Operations Manager
- L. Miller, Assistant GM Operations
- J. Morrison, Maintenance Engineer
- D. Perkins, QA Manager
- L. Piotti, QA Auditor J. Ronafalvy, Technical Manager J. Trejo, Radiation Protection/Chemistry Manager J. Zupko, General Manager Operations Hope Creek Generating Station
- R. Beckwith, Licensing Engineer J. Cicconi, Planning Manager
- G. Connor, Operations Manager P. Eldreth, Site Protection Supervisor E. Galbraith, Chemistry Manager A. Giardino, Quality Assurance (QA) Manager
- R. Griffith Sr., Principal QA Engineer
- J. Hagan, Maintenance Manager
~
- J. Nichols, Technical Manager
- M. Shedlock, Maintenance Engineer Nuclear Training Department
- R. Edmonds, Assistant Manager
- H. Hanson, Manager S. Ketcham, System ~nd Reactor Engineering Supervisor
- P. Walzer, Principal Training Staff Administrator United States Nuclear Regulatory Commission
- W. Borchardt, Senior Resident Inspector, Hope Creek K. Gibson, Resident Inspector, Salem
- Denotes those who attended the exit meeting on April 10. 198 ** Denotes those who attended the exit meeting on April 16, 1987.
3 Non Licensed Trainin.1 Requirement lOCFR 50, Appendix B Criterion II, requires in part that a
. licensee 1 s Quality Assurance (QA) program shall provide for indoctrination and training of personnel performing activities affecting quality as necessary to assure that suitable proficiency is achieved and maintaine.2 Scope The effectiveness of the implementation of the licensee's non licensed staff training programs at Salem Generation Stations 1 &
2 (Salem), and Hope Creek Generating Station (HC) was assessed by reviewing the following activities in operations, maintenance (mechanical i electrical, and instrument and control), engineering, and quality assurance (QA) area.3 Details of the Review For each of the job functions selected, the inspector reviewed the implementing procedures, qualification, and experience of personnel, qualification and training of instructors, quality of the on the job training (OJT), and the effectiveness of training as evidenced in daily activities. The comme~ts and evaluations from the trainees, line supervisors, and instructors were also reviewed to established how this feedba~k was factored into future training; Management and QA involvem~nt in the training area was assessed for effectivenes At Salem and HC, the inspector reviewed shift turnovers, routine tours by non licensed operators (NLOs), and routine activities by engineer electricians, mechanics, and instrument and control (I&C)
technicians. The activities were conducted in accordance with the procedures by personnel knowledgeable in the requirements of the procedures and technical specifications. The i~spector witnessed additional work activities as detailed belo.4 Observation of Work Activities at Salem Units 1 and 2 The inspector observed an engineer verifying the positive tracking of change in the Safety Parameter Display System (SPDS) in accordance with procedure M13-STP-006-1366. He was using the inputs of a monthly surveillance of the pressure transmitter 2PT-514/21 SG being performed concurrently by an I&C technician in accordance with procedure 21C-2.6.030. The engineer and the I&C technician knew the requirements and both coordinated their efforts effectively. *
Three mechanics were involved in the replacement of the no.. 21 charging pump speed increaser gear. Two mechanics worked on the increaser gear and one placed outside the radiated area supported them. To minimize radiation exposure (ALARA), the mechanics rotated positions. They also knew the procedure requirements as well as the ALARA requirement An ED was observed training a utility operator (UO) in the requisition of lubricating oil and filling of the speed increaser gear discussed above to the proper leve A senior staff engineer reviewed a OCR no. ISM-00185/A for the installa-tion a new spent fuel demineralizer check valve with the inspector. The OCR was processed in accordance with Technical Department procedure TI 1-8 and the OCR included a 10CFR50.59 review. The engineer was knowledgeable of the procedural, 10CFR50.59, and technical specification (TS) require-ment.5 Observation of Work Activities at Hope Creek An electrician was observed revising paragraph 5.5.5.1 to procedure MD-GP.22-031(Q). He was using MOVAT Series 2100 scope to perform the steps described in paragraph 5.5.5.1 regarding the load cell TMD
Calibration Curve on a Limitorque SMB-000 used in the shop for trainin During the observation, another electrician came to the shop to check out a problem he was having on a similar Limitorque component. Both electricians discussed the problem and solution to make sure that the procedures they were using did not need to be revised. A third electrician was also observed revising paragraph 5.3.2 of procedure MD-ST.SB-002(0)
regarding Over Voltage Trip Adjustment. The electrician was using an electrical protection assembly (EPA) unit that will be used in the shop for training electrician ED verified that a breaker was properly tagged out for removal. As a result he had to use a third phone to notify the control room. The two
- phones closest to the breaker were not working. The ED notified the control room and told the inspector *that he would tag out the two phones for repairs. Later the inspector observed the ED tagging out the phone Two OEs were observed performing activities for the first time on the1r own. One ED was racking in the Reactor Core Spray Pump C breaker, and the other ED filled and vented the A and C Core Spray Loo.6 Training Policy and Progress The Manager of the Nuclear Training Department is responsible for non licensed training at the Salem and Hope Creek (HC) Generating Station The Manager reports to the General Manager of Nuclear Service The training program for the Salem Generating Stations received full INPO accreditation in November 198 The licensee has submitted it's two year self-analysis report on five training areas to INPO in March 198 The five training areas are: Nuclear Control Operator; Senior Reactor Operator; Shift Technical Advisor; Non Licensed Operator; and Instrument and Control Technician. The two year self-analysis report for the other five training areas is due in late 198 *
The Self Evaluation Reports (SERs) for all ten programs at the Hope Creek Generating Station are scheduled to be approved by INPO by the end of April 1988 with INPO Accreditation Board visits to follo The key procedures for the Non Licensed Training Program include:
Nuclear Training Department Training Procedures Manuals for Salem and H Salem Station Administrative Procedure (SAP) No. 9, Revision *6, Maintenance Progra SAP No. 14, Revision 5, Station Training Progra HC Station Administrative Procedure (SA-AP.ZZ) No. 014(Q),
Revision 1, Station Personnel Qualification an Trainin In the summer of 1985, management approved for Salem a system engineer concept based on the station e~gineering organization. The system engineers are required to. have a broad general knowledge and experience in plant oper~tions, maintenance, and engineering, as well as communication and project management abilities. A six month training program was developed and twenty engineers successfully completed the training in December 1986. Another class is in progress which includes Quality Assurance (QA) personnel and personnel from the Engineering Betterment Department. HC also has adopted the System Engineer concept and has all of it's system engineering candidates including QA personnel in school. In the interim the system engineering effort is being performed by contract personnel at H The inspector toured the Nuclear Training Department laboratories and discussed the improvements since his last inspection in June 1986. These improvements include the addition of: cyberex inverter; load centers and breaker cubicles for training purposes. For Salem the improvements include the addition of nuclear instrumentation, and rod control unit The laboratories hav~ been also used to develop or revise plant'
procedure The non licensed training staff of approximately fifty instructors, supervisors and management administer the training program and instruct a student body of 720 NLOs, craft, technical and supervisory personne The training records of the instructors and the personnel involved in this in~pection were reviewe These records are in compliance with the FSAR, ANSI N45.2.6 and INPO guidelines. The records are automated (computerized), current, complete and readily accessibl The non licensed training and qualification effectiveness is measured primarily through Project Tracking System, and secondarily through QA audits and surveillance.7 QA/QC Interface With Non Licensed Training Program QA audit reports NN 87-05 and NM 86-06 addressing training were reviewed and discussed with a corporate QA representative. The audits.are conducted annually for the Offsite Safety Review organization in accordance the Technical Specification paragraph 6.5.2.4. The audits were thorough and comprehensive, and all the findings were corrected in a timely manner. Auditing classroom activity was conducted for the first time in audit NN 87-0 Thirty QA surveillance reports were selected and reviewed with the respective Salem and HC QA personnel. Almost all of the reports addressed qualifications and training.of the pe_rsonnel observed performing an activity. The HC QA surveillance checklists attached to each surveillance report contain an attribute for reviewing the qualifications of the personnel observed. The Salem surveillance reports had notations by the auditor regarding the qualifications of the personnel observe The inspector observed a QC inspector following the maintenance and repair of an emergency diesel generator jacket for the cooling water system. The QC inspector was knowledgeable in the requirements of the tas QC personnel are assigned to the Nuclear Training Department as QC/NDE/ISI instructors and Site QA have personnel are attending the System Engineering trainin.8 Conclusion No violations were identified. The licensee's non licensed training program is implemented in accordance with NRC requirements and licensee commitments
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3.0 Licensee's Action on Previous NRC Concerns (Closed) Unresolved Item (50-272/86-20-01 and 50-311/86-20-01): Lack of control of contaminated M&T The inspector verified that the 11 Hot Shop 11 where the storage and calibration of contaminated M&TE is maintained is now a cleaned and controlled area. The M&TE is not only accounted for but the M&TE is also in the the calibration recall system. QA audits and surveillances have been conducted and confirmed that corrective actions have been fully implemente Based on the review of the licensee 1s action, this item is close.0 Unresolved Items Unresolved Items are matters about which more information is required to ascertain whether they are acceptable items or violations. An unresolved is discussed in paragraph.0 Management Meetings Licensee ma~agement was informed of.the scope and purpose of the inspection at the entrance interviews on April 6, 1987 with Salem personnel, and on April 13, 1987 with HC personnel. The findings of the inspection were discussed with the licensee representatives during the course of the inspection and presented to licensee management at the April 10, 1987 exit interview with Salem personnel, and at the April 16, 1987 exit interview with HC personnel (see paragraph 1 for attendees).
At no time during the inspection was written material provided to the licensee by the* inspector. The licensee indicated that no proprietary information was involved within the scope of this inspection.