IR 05000206/1988002
| ML13316B871 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 03/09/1988 |
| From: | Johnson P, Obrien J, Qualls P NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML13316B870 | List: |
| References | |
| 50-206-88-02, 50-206-88-2, 50-361-88-02, 50-361-88-2, 50-362-88-02, 50-362-88-2, IEIN-87-008, IEIN-87-034, IEIN-87-035, IEIN-87-34, IEIN-87-35, IEIN-87-8, NUDOCS 8803290007 | |
| Download: ML13316B871 (8) | |
Text
U. S.. NUCLEAR REGULATORY COMMISSION
REGION V
Report Nos. 50-206/88-02, 50-361/88-02, 50-362/88-02 Docket Nos. 50-206, 50-361, 50-362 License Nos. DPR-13, NPF-10, NPF-15 Licensee: Southern California Edison Company P. 0. Box 800 2244 Walnut Grove Avenue Rosemead, California 91770 Facility Name:
San Onofre Nuclear Generating Station Units 1, 2, 3 Inspection at:
San Clemente, California Inspection Conduct d:
January 4-8 and February 1-5, 1988 Inspectors:
I -P. M. alls, Project Inspector Date Signed
4 O'BrY n, Reactor Inspector Date Signed Approved by:
Dae gse P. Onson, Chief Date Signed Reacto Projects Section 3 Inspection Summary:
Inspection on January 4 - February 5, 1988 (Report Nos. 50-206/88-02, 50-361/88-02, 50-362/88-02)
Areas Inspected:
Routine project inspection in the areas of licensed and non-licensed operator training programs, Information Notices and Part 21 report foll6wyup, compliance with ATWS rule (10 CFR 50.62), design change and modificationprograms surveillance testing, and calibration control program Inspection procedures 30703, 37700, 36100, 41400, 41701, 61725, 92701, 71707 and TI 2500/20 were covere Results:
In the areas inspected, no violations or deviations were identifie The licensee's responses to six Information Notices and Part 21 reports were reviewed and closed (for all three units). One followup item was opened concerning the licensee's annual 10 CFR 50.59 repor S0309 PDR ADOCK 05000206 QDR DCDi
DETAILS 1. Persons Contacted
+ C. B. McCarthy, Vice President/Site Manager
+*H. E. Morgan, Station Manager
+*D. B. Schone, Site QA Manager
+*M. A. Wharton, Assistant Technical Manager
+ S. T. Brooks, Radiation Material Supervisor
+*C. A. Couser, Compliance Engineer
- J. P. Shipwash, Compliance Supervisor
- M. P. Short, Nuclear Training Manager
- K. Slagle, M. and A.S. Manager
- J. W. Scott, Unit 1 HP Supervisor
- K. O'Connor, Project Field Manager
- N. R. Dickinson, Project Engineer
- J K. Yann, Project Engineer
- N. Maringas, ISEG Engineer
+ J. Winter, SDG&E Engineer
+ S. McMahan, Maintenance Engineer
" 0. C. Stonecipher, QC Manager B
J. Hammon, QA Supervisor T
G. W. McDonald, QA Supervisor
- Denotes attendance at January 8, 1988 exit meetin + Denotes attendance at February 5, 1988 exit meetin In addition, other members of the licensee's staff were contacted during the course of the inspectio. Training (IE Manual Chapters 41400 and 41701)
a. August 31, 1987 Event in Unit 2 The inspector reviewed the August 31, 1987 unisolable leak event in Unit 2 to determine whether training had been a factor in the even The following conclusions were reached by the inspector:
CahnMasr inom training in the licensing process appeared adequate. A 4pr~pedura1 problem associated with NCR closure was a contributing Str to the event, and additional training of the operators on
- D'ents tdtail was performed as followup to the event. It appeared to the inspector that the level of detail of the NCR problem was more than normally addressed by the licensed operator/non-licensed operator training process, and that the training program did not contribute to causing the event. The operators appeared to be adequately trained when the event occurred as is evidenced by the subsequent corrective actions take The operators appeared to have properly controlled the event to mitigate its consequence b; Records Review The inspector reviewed the training records of the operators involved in the August event and a random sample of other licensed and non-licensed personne The records contained results of the most recent exams, lecture attendance records, records of required manipulations, records of additional training received, records of completed self-study, and records of duty resumption after exam failure and subsequent passing of a repeat examinatio The pass rate for the licensee's requal exams has been about 90%.
INPO accreditation for the licensed operator training programs was received.in December 198 c. Training Lecture The inspector attended a training lecture for the licensed operator qualification training. The instructor was well prepared, knowledgeable and presented the material wel There was good class interaction and the instructor made good use of training aid. Information Notices (IE Manual Chapter 92701)
In a previous inspection in November 1987 the inspector reviewed the licensee's program to review and followup on NRC Information Notices. To complete the inspection, the inspector followed up licensee actions on Information Notices IN 87-08, IN 87-34 and IN 87-3 a. IN 87-08 (Closed) The notice concerning limitorque motors was addressed by the licensee previously when received as a Part 21 report. The motors were reworked and returned to service. This item is close b. IN-87-34 (Closed) This notice concerned the independence of instrument lines. The licensee review concluded that they clearly had independence. This item is close c. IN-87-35 (Closed) This notice concerned DS-416 Reactor Trip Breakers. The licensee review concluded that they used no DS-416 breaker as reactor trip breakers. This item is close The 1thi tdontshowed that the INs had been reviewed for applicability anddIos ted to appropriate personnel, and that appropriate followup act-ion* were take No items of noncompliance or deviations were identifie. Followup of Part 21 Reports (IE Manual Chapter 36100)
The inspector followed up licensee action on the following part 21 report a. 87-06-P (Closed) Westinghouse Coils for IE Motor Starters
3, The licensee review determined that they had 8 affected AC coil These were all in the warehouse and were returned to the vendo This item is close b. 87-08-P (Closed) GE HFA Relay Binding Station technical personnel reviewed this Part 21 report, which related to possible relay binding due to a mispositioned stop tab, and concluded that the current inspection program would detect suspect relays and thereby prevent the binding problem. They concluded that previous operating experience substantiated this conclusion. This item is close c. 87-14-P (Closed) Air Pressure Regulator The licensee reviewed the parts inventory and determined that none of the parts were in stock. This item is close No items of noncompliance or deviations were identifie. Compliance with ATWS Rule, 10 CFR 50.62 (Temporary Instruction 2500/20)
The purpose of this inspection was to assess the licensee's efforts to comply with the Anticipated Transient Without Scram (ATWS) rule, 10 CFR 50.62. Specifically, the inspector intended to review the licensee's plan for design, procurement, installation and testing for ATWS equipment that is not safety related. The NRC issued Generic Letter GL-85-06 on April 16, 1985, which provided guidance for this effort. The licensee's response to date was to submit to NRR their design criteria and schedule for implementation. Future inspection effort will involve verifying that the approved design criteria are met and that equipment is properly received, installed and tested. The status of each plant was as follows:
a. SONGS Unit 1:
o 10/27/87 - SCE submitted planned schedule for installation of equipment and submittal of specific design criteria for Unit o 4/1/87 - SCE submitted specific design details identifying which systems need redesig o
.7/24/87 -NRR approved planned schedule for installation during Cycle XI refueling outag o -1/29/88 - SCE submitted Plant Specific ATWS Mitigation System Actuation Circuitry (AMSAC) Design to NRR for approva No further inspection activity is anticipated until this design has been approved and procurement is started. The time frame is unknown at this tim b. SONGS Units 2/3:
0 10/15/85 - SCE made a commitment to a Diversified Scram System (DSS), identified affected systems, and proposed Cycle 4 refueling for installatio o 8/4/86 - NRR provided design criteria necessary for diversit o 12/30/86 - SCE and owners' group submitted system design and safety evaluatio o 7/27/87 - SCE submitted delay in schedule to Cycle 5 refueling for each uni o 1/11/88 - NRR informed the licensee that the design for new CE plants did not satisfy diversity requirement At the conclusion of the inspection the licensee had not completed plans for their course of action. A meeting at NRR was anticipated in mid-February '88. No inspection activity is anticipated for the near futur No violations or deviations were identifie. Design, Design Changes and Modifications - (IE Manual Chapter 37700)
a. The inspector reviewed a listing of all of the major modification in each of the units since the start of the last refueling outage Four modifications for each unit were selected and reviewed in detai The plant systems selected for each were:
the reactor coolant system, emergency core cooling system, radioactive waste system and power conversion syste The detailed review of each modification involved a thorough review of the proposed facility change (PFC) package, design change packages (DCP) and turnover package The inspector verified that for each modification:
o The changes were reviewed by the licensee in accordance with 10 CFR 50.5 The DCP's were reviewed and approved in accordance with Technical Specification The DCP's were controlled by established procedure o Post-modification tests were conducted satisfactoril o Where required, procedure changes were made and approve o The plant "as-built" drawings were controlled and update o Design changes were accomplished in accordance with appropriate requirement I
o Acceptance testing was conducted in accordance with approved procedure o When required, these modifications were listed and the modification descriptions were briefly summarized in the annual 10 CFR 50.59(b) report to the NR Concerning the last item, it was noted during the inspection that the compliance engineering staff has been selecting modifications for the report based on completion of the proposed facility change package. At that time no modification has actually been completed; the design work and safety analysis have been completed and the work is funded for the next fiscal year. The inspector noted that most licensees report such changes to the NRC when the modification has been substantially or completely installed. This will be reviewed during a future inspectio (Followup Item 206/88-02-01).
b. The inspector reviewed the backlog of outstanding DCP's and determined that a very small backlog existed. The planning to accomplish outstanding DCP's appeared adequate. No DCP's which involved immediate safety concerns were outstandin c. The inspector reviewed the licensee's procedures to control temporary modifications of plant systems. The inspector verified that:
controls of modifications required review and approval in accordance with Section 6 of the Technical Specifications, 10 CFR 50.59 and the approved QA program a
personnel were using detailed, approved procedures a
responsibility for approval was assigned
a formal record of modifications was maintained in the control rooms and the status of modifications.was known o
controls required functional testing of equipment affected following removal of temporary modifications o
jumpers and lifted leads were controlled by temporary changes to operating, surveillance or maintenance procedures No violations or deviations were identifie. Surveillance Testing and Calibration Control Program (IE Manual Chapter 61725) (Unit 1 only)
a. Review of Implementing Procedures The inspectors reviewed the latest revisions of the following station procedures which defined and implemented the surveillance testing and calibration control program:
Procedure N Title 50123-G-3
"Technical Specification Surveillance Requirements" S0123-I- "Maintenance Order Preparation, Use and Scheduling" 501-12.0-2
"Operating Surveillance Implementation" S01-12.0-4
"Operations Surveillance Requirements for Mode Changes" S0123-I- "Maintenance Documentation" S0123-I-1.19
"Maintenance Department Technical Specification Surveillance Program Implementation" The review also included discussion with personnel and management responsible for program development and implementatio Based on this review, the inspectors verified that a program existed to control surveillance and calibrations required by Technical Specifications through the use of inter-departmental surveillance schedule memos and the computerized San Onofre Maintenance Management System. The inspector also verified that responsibilities had been delineated to ensure surveillance requirements have been satisfie b. Review of Surveillance Test and Instrument Calibration Records The inspectors reviewed documentation for approximately 25 randomly selected surveillance tests and instrument calibrations. Attributes examined included performance of surveillance or calibration within the proper time interval including allowable time extensions; completion of all applicable elements with acceptable results; review and signoff by appropriate supervisor and quality assurance engineers, where required; verification of restoration and post maintenance checks; and use of calibrated instruments. Surveillance records were selected at random from the Operations, Maintenance, and Instrument and Controls groups. Calibration records were selected from the Instrument and Controls grou s review showed that surveillances and calibrations had been performed within the frequency required by Technical Specifications, and that the results had been reviewed by the appropriate level of management and by required departments. Additionally, those items that had failed to meet the required acceptance criteria were resolved and documented in accordance with procedure requirement Calibrated instruments were used to perform the surveillances and calibrations where require c. Inservice Testing Program - Review of Implementing Procedures The inspector reviewed the following documents which define and implement the Inservice Testing Program for Pumps and Valve Attributes examined and verified included the establishment of a program for scheduling and tracking testing requirements; the assignment of responsibility for completion of testing; the establishment of detailed test procedures; and the establishment of methods and responsibilities for the review and evaluation of test results and the reporting of deficient condition Procedure N Title S01-V-2.14 Inservice Testing of Pumps Program (Unit 1)
SO1-V-2.15 Inservice Testing of Valves Program (Unit 1)
501-12.4-2 Operating Inservice Valve Testing N/A IST Program Weekly Status Report and Monthly Schedule No violations or deviations were identifie. Plant Tour The inspector toured the facilities during the backshift hours of 10:00 p.m. to 2:00 a.m. on two consecutive evenings (Unit 3 - 2/3/88, Unit 1 - 2/4/88).
Shift turnover was observed, control room logs were reviewed, surveillance testing and maintenance in progress were reviewed, control boards were walked down and accessible areas of plants were toure o The inspector found the operators alert and attentive to their dutie o No deficiencies were observed in the health physics activities during the tour o The material condition of plant components was well maintained and housekeeping activities appeared to be effectiv No violations or deviations were identifie. Exit Meeting An exit mieeting was held with members of the licensee's staff at the concluion of each week of inspection (as noted in paragraph 1).
The inspectors summarized the inspection activities and observations as discussed in this report.