IR 05000206/1986044
| ML20207P920 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 01/02/1987 |
| From: | Johnson P, Qualls P NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML20207P909 | List: |
| References | |
| 50-206-86-44, 50-361-86-33, 50-362-86-32, NUDOCS 8701200406 | |
| Download: ML20207P920 (4) | |
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U. S. NUCLEAR REGULATORY COMMISSION-
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REGION V
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Report Nos.
50-206/86-44, 50-361/86-33, 50-362/86-32
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Docket Nos.
'50-206, 50-361, and 50-362-License Nos.
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Licensee:
Southern California Edison Company P. O. Box 800, 2244 Walnut Grove Avenue'
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Rosemead, California 91770~
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Facility Name:
San Onofre Nuclear Generating Station Units li 2, and 3
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' Inspection ats-
' San Clemente, California
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Inspection conducted-November 17 - December 16, 1986
Inspector:.
r. Mg alls, Project Inspector Date Signed Approved by:
[87 IF..H.
hnson, Chief, Date Signed Reac Projects Section 3 Inspection Summary
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Inspectionor$ November 17-December 16, 1986I(Report Nos. 50-206/86-44,-
' 50-361/86-33, 50-362/86-32)-
Areas Inspectied: Routine project inspection in the areas of design control s
i and independent inspection.
In'pection trocedures 30703 and 37700 were covered.y
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Results: In the areas inspected, no violetions 'or deviatifons were identified.
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8701200406 870102 PDR ADOCK 05000206 O
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S.' NUCLEAR ~ REGULATORY COMMISSION
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REGIONV[
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Report Nos.
50-206/86-44,50-361/86-33,l50-362/86-32
Docket \\Nos.
50-206, 50-361, and 50-362
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License Nos.
Licensee:.
Southern California Edison Company
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- . A P..~0. Box 800, 2244 Walnut Grove Avenue
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~Rosemead, California 91770
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Facility Name:-
' San ~0nofre Nuclear. Generating Station Units 1,_2, and 3 Inspectickat:
San Clemente, California
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Inspection conducted *
November 17 - December 16, 1986
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_ Inspec to'c :
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F..Mg alls, Project Inspector Date Signed
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Approved
IF..H.
hnson, Chief, Date Signed
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-Reac Projects Section 3
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Inspes:t' ion;' Summary
Inspection on. November 17 - December 16, 19861(Report Nos. 50-206/86-44,
'50-361/86-33, 50-362/86-32).
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Areas Inspect!adt Routine project inspection'in the areas of design control a-and independent inspection. Inspection procedure's 30703 and 37700 were covered.y
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s Results:- Inthhareasinspocted,noviolationsordeviatiionswereidentified.
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8701200406 870102
PDR ADOCK 05000206 G
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DETAILS 1.
' Persons Contacte'd
- H. Zenker, Compliance Engineer
- W Zinti,-Manager, Compliance
- D. Peacor,. Manager, Emergency Preparedness
- M. Rodia.. Supervisor. Reliability Engineering / Configuration Control
- R. Plappert, Compliance Engineer
- D.l Herbst, Supervisor, Independent Safety Engineering Group
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- D. Barreres, Supervising Engineer, Fire Protection
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- G. Robinson, Supervisor, Secondary Operations i
- W. Lazear, Supervisor, Quality Assurance a'
. *J; Winter, SDG&E Engineer;
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G. Whettion, Quality Assurance
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D. Brocknorst, E & C Protection
D. Smith, Station Technical
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- C. Couser, Compliance Engineer
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lIn' addition, the inspector contacted other members of the.-. licensee's
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- Denotes persons attending Exit Meeting on November 21, 1986.-
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Design,' Design Changes and Modifications (IE Chapter 37700)
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The inspector reviewed a number of Design Change Packages'(DCPs)
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involving instrumentation, electrical,-containment and reactivity control'
systems. The inspector verified that, for the DCI's reviewed:
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The changes were reviewed by the licens'ee in accordance with i
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'The DCP's were reviewed and approved in accordance with Technical Specifications.
- The DCP's were controlled by established procedures.
- Post-modification tests were conducted satisfactorily.
- Where required, procedure changes were made and approved.
The plant "as-built" drawings were controlled and updated.
- Design changes were accomplished in accordance with appropriate requirements.
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Acceptance testing.was conducted in accordance with approved procedure _
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'The. inspector reviewed the backlog of outstanding DCP's and determined
'that a-very small backlog exists.- The planning to accomplish. outstanding-
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'DCP's appeared adequate. No DCP's'which. involved immediate safety'
. concerns were,outstandieg.
The inspector reviewed the licensee's procedures to control temporary
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modifications, -lif ted leads and jumpers. The procedures required that:
Personnel use detailed, approved procedures
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Responsibility for procedural approval is assigned
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A formal: record of jumpers and modifications is required l
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Independent verification of lifted leads is required.
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No violations or deviations were identified.
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-, 3. ;. Independent Inspection
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~ '. < - Cold Les Accumulator Technical Specifications
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In TIA 85-50, NRR-Reactor Systems Branch (RSB) reviewed a' question r
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to' isolate cold leg accumulators at pressures greater than~
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,1000 psig. RSB recommended that Region II review older
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,,c Westinghouse, non-standard. tech spec plants to ensure that the s
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procedures prevent isolating these accumulators at pressures' greater i
4-than 1000 psig. Licensee personnel informed the inspectors that San
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.Onofre Unit-1 does not have these accumulators.
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Testing of PSV-9349
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.3 To provide low temperature overpressure protection, while on
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shutdown cooling, the licensee uses the shutdown cooling system (SDCS) safety / relief valve PSV-9349. To ensure operability the
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licensee coa' mitted to bench test this valve at intervals not to exceed 30 months. The inspector verified that the'11censee was ccaducting these tests. The licensee conducts a bench test of this valve at each refueling outage.
No violations or deviacfins were identified.
4.
~ Facility Tour
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The inspector toured the facilities with the Resident Inspectors, with the following observations.
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. No deficiencies were observed in health physics activities during the tours.
- The material condition of plant components appeared to be well i
maintained.
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Fire watch personnel, when questioned by the inspectors, were.
knowledgeable about duties.
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Housekeeping _ appeared satisfactory; however, the licensee allows bulk otorage of combustible materials inside of plant safety-related arecs. This item is addressed by the Resident Inspector in Inspection Report 50-361/86-34
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-In the Unit 1 area the inspector observed a number of steel-access plates, in the ground, labeled " Contact security prior to opening."'
~A number of these plates were not locked or welded... Licensee personnel informed the inspector that if these plates weigh 500 lbs then no lock is necessary. Based on the dimensions and weights per foot given in the structural steel manual for plate steel, it appeared to the inspector that some of these may weigh less than 500 lbs. iThis item is open pending further NRC review.
(50-206/86-44-01)
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' Exit Meeting
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An exit meeting was held with members of the licensee's staff on
. November 21, 1986.. The items listed in this report were discussed at that time.
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