IR 05000206/1981010
| ML19347F692 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 04/14/1981 |
| From: | Miller L, Zwetzig G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML19347F691 | List: |
| References | |
| 50-206-81-10, NUDOCS 8105260052 | |
| Download: ML19347F692 (5) | |
Text
U.S. NUCLEAR REGULATORY COMMISSION
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0FFICE OF'INSFLCTION AND ENFORCEMENT
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REGION V
Report No. 50-206/81-10 Docket No. 50-206 License No. DPP.-13 Safeguards Group Licensee:
Southern California Edison Company 2244 Walnut Grove Avenue Rosemead, California 91770 Facility Name:
San Onofre Nuclear Generating Station Unit 1 Inspection at:
San Onofre, California Inspr; tion con ted: March 4-13 and 19-21,1981
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Inspectors:
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L. Mifler, Resident q ec
/ 'Date'9igned Date Signed Da e Signed Approved By:
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'Vate Signed G. B. Zwetzig, Acting fAief, Section 2, Reactor Operations P(roject Branch
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Summary:
Inspection on March 4-13 and 19-27,1981 (Report No. 50-206/81-10)
Areas Inspected: Routine, resident inspection of plant operations during long term outage and monthly maintenance and surveillance observations.
This inspection involved 40 inspector-hours on site by the Resident Inspector.
Results: No items of noncompliance or deviations were identified.
8105 2 60 0$:2-RV Form 219 (2)
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DETAILS 1.
Persons Contacted
- J. Haynes, Manager, Nuclear Operations
- D. Nunn, Manager, Quality Assurance
- J. Curran, Plant Manager W. J. Matter, Supervisor of Administration, Unit 2
- R. Brunet, Superintendent, Unit 1
- D. R. Nelson, Project Manager, Unit 1
- D. Dunn,. Project Quality Assurance Supervisor
- R. N. Santosuosso, Supervisor of_ Plant Instrumentation
- G. Mcdonald, Unit 1 Quality Assurance Supervisor
- S. McMahan, Supervisor of Plant Maintenance, Unit 1
- R. Warnock, Supervisor of Health Physics, San Onofre
- F. Briggs, Compliance Engineer
- N. R. Dirkinson, Construction Project Supervisor The inspector also interviewed other licensee employees and contractor employees during this inspection.
- Denotes those attending the Exit Interview on March 27, 1981.
2.
Inspection of Plant Operations During Long-Tern Outage The inspector observed Control Room operations frequently for proper shift manning, for adherence to procedures and limiting conditions for operation, and appropriate recorder and instrument indications.
The inspector discussed the status of annunciators with Control Room operators to deter--
mine the reasons for abnormal indications, and to determine the operators'
awareness of plant status.
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The Control Operator's log was reviewed to obtain information on plant conditions, and to determine whether regulatory requirements had been met.
Other logs, including the Watch Engineer's Log and Plant Chemistry Logs, were also reviewed several times. The licensee's lifted lead and jumper records were audited, and several lifted leads were physically verified to have been lifted in accordance with the records. The equipment clearance records were reviewed regularly, and clearance tags for the pressurizer heaters, south charging pump, and the auxiliary feedwater system were veri-fied to have been hung as recorded. The piping for the modified auxiliary feedwater system was walked down, and several pipe support anchor bolts wro e checked for adequate thread engagement.
The inspector frequently toured the accessible areas of the facility to assess equipment conditions, radiological controls, security and safety. The Physical Security Plan appeared to be properly implemented. Hanning of security posts, integrity of protected area barriers and isolation zones, conduct of search procedures, and personnel identification measures were all observed at intervals by the inspector. Several hydraulic shock suppressors were checked for proper oil level and integrity. Plant housekeeping was observed to have improved in this period, and was generally good. No fire hazards due to stored combus-tibles were apparent, but it was noted that the southwest door of the 4160
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Volt Switchgear Room, (a fire door), was often open, and fire doors did not generally carry any instructions that they should remain closed.
The inspector reminded the licensee that to provide assurance that fire doors remained closed, the Fire Protection Safety Evaluation Report had assumed that signs were used on doors to indicate that doors form a fire barrier and were to remain closed. A licensee representative agreed, and stated that the dcors would be properly marked prior to the facility's return to power.
(OI 50-206/81-10-01).
The inspector observed that radiation controlled area access points were usually under continuous surveillance by a Health Physics aide, and that these personnel observed the exit of all workers from the controlled areas of the facility. Access points were generally safe and cican. On some tours, however, the inspector found control point survey meters in use which exhibited defective audio count rate or alarm output. When the malfunction was brought to the attention of licensee personnel, they replaced the malfunctioning meter with an operable one. At the Exit.
Interview, the inspector expressed his general concern that because of these malfunctions some workers had monitored themselves at some control points with defective survey meters. A licensee representative acknow-ledged the inspector's concern and stated that more effort would be made to reduce 'he frequency of this problem. This item is closed.
c Finally, a transfer of low specific activity material was observed.
Pack-aging, surveys, labeling and shipping documentation appeared to be acceptable.
No items of noncompliance or deviations were identified.
3.
Monthly Maintenance Operations a.
Routine Activities The inspector observed portions of the following maintenance and modi-cation work:
Compensating voltage adjustment on Intennediate Range Nuclear Instru-ment Channel 1203, and Auxiliary Feedwater Control Panel cable termin-ations.
In addition, the records of the followf.ng completed maintenance were reviewed:
West Holdup Tank release and samplidg (flarch 11-13,1981),
Diesel Generator #2 post-maintenance testing, and Diesel Generator #2 Sequence or preoperational test (SPE-327).
The inspector determined that these activities did not appear to violate Limiting Conditions for Operation, that required administrative approvals and tagouts were obtained prior to initiating the work, and that approved procedures were being used by qualified personnel. However, in the case of the Diesel-Generator #2 Post-Maintenance testing, the records of the
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testing and discussions held by the Resident Inspector with licensee representatives indicated that the diesel generator control systems and annunciators were not completely operable prior to testing.
Specifically, the instrument air supply to the diesel turbocharger low oil pressure annunciator sensors on the east end of the diesel generator was not reconnected prior to the test. As a result, the air supply to many annunciators was lost, making the annunciators and the stop switches for the generator non-operable.
In addition, an equalizing valve for two other indicators (PI-806'and DPI-200) was left open following a refueling interval surveillance. This error was revealed by the test when the indicators did not funrtion. At the Exit Interview and in discussions with licensee representatives, the inspector stated that both errors appeared to have been the result of insufficient procedural guidance. The inspector observed that these errors had occurred in a non-safety related portion of the Diesel Generator System and were, therefore, not items of noncompliance.
He stated that they did indicate an area of weakness in the control of maintenance and surveillance activities which the licensee should remedy.
A licensee representative stated at the Exit Interview that the licensee appreciated the importance of having and using sound written procedures, and agreed to re-emphasize to all workers and supervisors the importance of properly completing work.
This item is closed.
b. Steam Generator Repair Program In this inspection period, the licensee continued the metallurgical
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sealing of sleeves previously inserted and began the installation of a sleeve of a different design, which will not be sealed. Tnis
sleeve is hard-rolled in place, top and bottom, and is referred to as a " leak-limiting" sleeve. Metallurgical seals were provided in approximately 1830 sleeves, of which approximately 410 have been ultra-sonically inspected. Approximately 130 of these were judged to be acceptable as installed, with the remainder requiring engineering evalu-ation to determine their suitability for service. Approximately 1710 leak-limiting sleeves were inserted and partially installed. A program to convert unacceptably sealed sleeves into a version of leak-limiting sleeves was started. At the end of this inspection period, this method j
appeared feasible - at least for 30" and 36" sleeves.
t After experiencing initial difficulty in keeping the plastic seals l
in place over the steam generator nozzle covers, (for cleanliness control), a more durable plastic material was substituted. This substitute material appeared to be effective. The inspector continued to review all changes to sleeving procedures and, in addition, reviewed the safety and environmental analysis for the Steam Generator Mechanical
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Sleeves (Design Change 81-09). At the Exit Interview, a licensee representative stated that the current schedule for completing all sleeving and tube plugging was to support a May 31, 1981 restart of the unit.
No items of noncompliance or deviations were identified.
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4.
Monthly Surveillance Observations
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The inspector reviewed the " Operator's Routine Check-Off List", for March,1981 and verified that all surveillances required to be _ completed by the Technical Specifications during this inspection period were recorded as having been completed. The inspector then selected four of these surveillances:
" Safety related systems valve alignment".
S-12.3-6,
" Auxiliary Feedwater System Operability Test".
S-12.2-5,
" Spent Fuel Pit Level Verification", and
" Fan A33 Damper Test and 1-Hour Run".
S-12.3-3.
The records fur each : surveillance were reviewed to verify that they wer i complete, that the procedure had been followed, that qualified personnel performed the work, that Limiting Conditions for Operation were met where applicable, and that the completed surveillance records had been properly reviewed where required.
No items of noncompliance or deviations were noted.
5.
Exit Interview The inspector met with licensee representatives (denoted in paragraph 1),
at the conclusion of the inspection on March 27, 1981 to summarize the scope and findings of the inspection.
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