IR 05000206/1986030
| ML20211P097 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 07/01/1986 |
| From: | Clark C, Thomas Young NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML20211P094 | List: |
| References | |
| 50-206-86-30, 50-361-86-21, GL-85-22, IEB-80-06, IEB-80-6, NUDOCS 8607220726 | |
| Download: ML20211P097 (5) | |
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e U. S. NUCLEAR REGULATORY COMMISSION: l
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REGION V
Report Nos. 50-206/86-30, 50-361/86-21 Docket Nos. 50-206, 50-361 Licer.se Nos. DPR-13, NPF-10 Licensee:
Southern California Edison Company P. O. Box 800 2244 Walnut Crove Avenue Rosemead, California 91770 Facility Name: San Onofre Nuclear Generating Station Units 1 and 2 Inspection at: San Clemente, California Inspection conducted: June 16-27, 1986 Inspector:
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C. Clark, Reactor Enspect
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Date Signed Approved by:
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Date Signed T. Young, Jr., C Lef Engineering Sectian Inspection During the Period June 16-27, 1986 (Report Nos. 50-206/86-30
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and 50-361/86-21
. Areas Inspected: A routine unannounced inspection of Unit 2 Inservice Inspection (ISI) activities, Open Items, Part 21 Item and Bulletins. The inspection involved Module Nos. 73052, 73053, 73055 and 92701.
Results:
In the areas inspected, no violations of NRC requirements were identified.
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8607220726 860707 PDR ADOCK 05000206 G
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DETAILS
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1.
Persons Contacted
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- M. Wharton, Deputy Station Manager
- D. Schone, Site QA Manager
- S. McMahan, ME&S Manager
- C. Chiu, Assistant Technical Manager
- C. Couser, Lead Compliance Engineer
- W. Lazear, QA Supervisor
- J. Mundis, Nuclear Services Supervisor
- P. Croy, IST Coordinator
- J.
Boardman, ISI Engineer
- Denotes those personnel in attendance at the exit meeting on June 20, 1986.
The inspector also held discussions with other licensee personnel during this inspection.
2.
Inservice Inspection a.
Inservice Inspection Plan The licensee's inservice inspection (ISI) of Class 1, Class 2 and Class 3 nuclear components in Unit 2 was performed in accordance with the 1977 Edition of Section XI of the ASME Boiler and Pressure Vessel Code with Addenda through the Summer of 1979. Combustion Engineering (CE) was the contractor performing ISI activities during this outage. The ISI program examination area summary sheets (Document Number M38218, dated November, 1982) list the areas to be examined, the method and extent of the examination, and the calibration blocks used.
b.
Review of Procedures The following procedures were examined to assure that they adequately covered all areas specified in the licensee's commitment for ISI requirements:
(1) 5023-ISI-018/1 (CE No. 9976-ISI-018, Revision 3), " Ultrasonic Examination Procedures for Reactor Ccolant Pump Flywheels and Balancing Devices."
(2) 5023-XXVII-4.0.5/0 (CE No. 9976-ISI-005, Revision 1), " Ultrasonic Examination Procedures for Reactor Vessel Flange Ligament Areas."
(3) 5023-XXVII-4.0.8/0 (CE No. 9976-ISI-008, Revision 2),
" Ultrasonic Examination Procedures for Closure Head Peel Segment, Circumferential Dome and Flange Welds."
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(4) 5023-XXV11-4.0.9/0 (CE No. 9976-ISI-009, Revision 2), " Ultrasonic Examination Procedures for CEDM Motor Housing Upper and Lower Welds."
(5) 5023-XXVII-4.0.10/0 (CE No. 9976-ISI-010, Revision 2)
" Ultrasonic Examination Procedures for RPV Closure Head Studs."
(6) 5023-XXVII-4.0.19/0 (CE No. 9976-ISI-019 Revision 3),
" Ultrasonic Examination Procedure Class 1 and Class 2 Piping and CEDM Upper Pressure Housing Welds."
(7) 5023-XXVII-4.0.22/0 (CE No. 9976-ISI-022, Revision 4),
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" Ultrasonic Examinaticu Procedure for Main Coolant Piping Safe End Welds."
(8) 5023-XXVII-4.0.27/0 (CE No. 9976-ISI-027 Revision 4),
" Ultrasonic Examination Procedures for Primary Coolant Pipe Circumferential, Longitudinal and Branch Pipe Nozzle Welds."
(9) 5023-ESS-064/0 (CE No. 9976-ESS-064, Revision 4), " Liquid Penetrant Examination Procedure for Preservice and Inservice Inspection."
(10) 5023-ESS-066/0 (CF No. 00000-ESS-066, Revision 8), " Visual Examination Proceduie for Preservice and Inservice Inspection."
All the above procedures were approved by authorized licensee personnel and a Level III examiner.
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c.
Observation of NDE Activities The inspector observed ultrasonic examination'being' performed on selected reactor vessel head welds, during a previous inspection (Inspection Report No. 50-361/86-16). In regard to the'above -
examinations, the inspector reviewed the calibration block certifications, transducer RF pulse wave forms,'and the ultras'onic l
couplant certifications for those welds during this-inspection,
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there were some minor discrepancies noted during the certification l
review, but the licensee and CE resolved all questions.
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NDE Personnel Qualifications
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l The qualification and certification records of the NDE personnel performing ISI examinations were reviewed by the inspector. The records were compared with the guidelines of the American Society for Nondestructive Testing Recommended Practice No. SNT-TC-1A,
" Personnel Qualification and Certification in Nondestructive
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Testing." There were some minor discrepancies noted during
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this record review, but the licensee and CE resolved all questions.
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Data Review and Evaluation The completed ultrasonic' examination records were reviewed to ascertain whether the following applicable documents /information were provided: Examination results and data sheets, examination equipment and material data, extent of examination calibration data sheets, examination evaluation data and appropriate signatures, f.
Quality Assurance Involvement The licensee's quality assurance involvement with CE and ISI activities were documented in the following field inspection reports:
Report Number Areas Inspected T-157-86 CE's ISI Procedures T-230-86 CE's Procedures, Personnel Qualifications, Equipment, Inspection Results, etc.
T-247-86 Data Reports were reviewed.
NoviolationsofNRCrequirementsordeviationswerekdentified.
3.
Licensee Action on Previously Inspector Identified Items ~
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a.
(0 pen) Followup Item No. 50-206/85-31-01: ' Remaining' Action >for I.E. Bulletin 80-06; Engineered Safety Features (ESF) Reset Controls This action was originally scheduled to be completed this refueling outage. It was to imple'_ent modification of the'
control circuitry for valves MOV 1100 B, C and D, to incorporate a seal-in reset function of ESF actuation.
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~ letter from M. O. Medford (SCE) to G. E. Lear (NRR), dated March 26, 1986, identified a revision of the integrated living schedule (ILS) to defer this-capital backfit to cycle 10 - the next refueling outage.
This item will remain open until the licensee's action is completed, and reviewed by an inspector.
b.
(0 pen) Followup Item No. 50-206/86-11-01: Safety Analysis and ASME Section XI Operability Limits for Inservice Testing of Pumps During a previous inspection, inspectors question whether the operability limits of IST requirements for pumps were bounded by the safety analysis. A memorandum from P. A. Croy to J. Rainsberry, dated April 7, 1986, on the subject of "In service inspection acceptance criteria San Onofre Nuclear
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Generating-Station, Unit 1",
requested a new review to
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determine if any pumps are currently being tested.and accepted
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_. hich do not meet the minimum required performance criteria of w
the safety analysis. As of this inspection'a reply to the
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above memorandum was not available for an inspector review.-
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This item will remain open until*the. identified review-in the
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April 7, 1986 memorandum is completed',and. reviewed by an
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inspector..
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4.
Licensee Action on Generic Letters
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(Open for~ Units 1, 2 and 3) Generic Letter' No'J8.5-22:,
Potential for Loss of Post-LOCA Recirculation tapability
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Due to Insulation Debris Blockage t;
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This letter addresses the potential losslof recirculation capacity due to a LOCA, if LOCA generated debris blocked'the emergency sump.
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L The analysis of this item was based on Regulatory Guide 1.82, /
Revision 0.
During this inspection a licensee representative stated they have just received this letter on site, which was identified to them during a previous inspection (Inspection Report Nos.'50-206/86-11, 50-361/86-16 and 50-362/86-16), and are working on it now.
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This item will remain open until the licensee has completed-its review and the results of this review are reviewed by an inspector.
5.
Licensee Action on Part 21 Items (Closed) Part 21, No. 85-22-P: AAF Intake Silencer TDM or FTDM for Standby Diesel Generator may-have an Internal Part not Welded in Place.
The licensee received this letter which stated "it is remotely possible that the intake silencer, produced by American Air Filter Company, has an internal part not. welded in place. If the part is not welded in place as required by the design, it is possible for it to' be -ingested into the engine upon start up."
The licensee inspected both Unit 1 diesel engines per maintenance orders No. 85112751000 (SI-DG1, on 12/10/85) and No. 85112752000 (SI-DG2, on 4/12/86) and found the intake silencer internal parts welded.
This item is closed.
6.
Exit Meeting The inspector met with licensee management representatives denoted in paragraph 1 on June 20, 1986. The scope of the inspection and the inspector's findings as noted in this report were discussed.
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