IR 05000275/1986005
| ML17083B716 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon |
| Issue date: | 03/07/1986 |
| From: | Burdoin J, Dodds R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML17083B715 | List: |
| References | |
| 50-275-86-05, 50-275-86-5, 50-323-86-06, 50-323-86-6, NUDOCS 8603240303 | |
| Download: ML17083B716 (6) | |
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NUCLEAR REGULATORY COMMISSION
REGION V
Report Nos.
Docket No.
License Nos.
Licensee:',
'acility Name:
Inspection at:
Inspection conducted:
50-"275/86-05, 50"323/86-06 50-275, 50-323 DPR-80",
Pacific Gas and Electric Company 77 Beale Street, Room 1451 San Francisco, California 94106 Diablo Canyon Units 1 and
't Diablo Canyon Site, San tuis Obispo County, CA February 10-'14, 1986 F
'nspector:
Approved By:
J. F. Burdoin, Reactor Inspector R. T. Dodds, Chief, Reactor Project Section
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Date Signed
Dat Signed Summary:
Ins ection durin eriod of Februar 10-14 1986 (Re ort, Nos. 50-275/86-05 and 50-323/86-06)
Areas Ins ected:
Unannounced inspection by one regional inspector of inservice inspection program for Unit 1, open item consisting IE Bulletin(s)/
Notice(s)
and Part 21 report(s),
and independent inspection of the plant.
Inspection procedure numbers 30703, 36100, 73755, 90712, 92703, and 71707 were used as guidance for the inspection.
The inspection involved 50 inspection hours by one inspector.
Results:
No items of noncompliance or deviations were identified.
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DETAILS Individuals Contacted Pacific Gas and Electric Com an (PG&E)
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C. Thornberry, Plant Manager R. Patterson, Assistant Plant Manager, Plant Superintendent R. D. Etzler, Construction Superintendent D. R. Bell, QC Supervisor
>'<D. A. Taggart, Acting Director, Quality Support QA
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Womack, Manager, Engineering Department D. B. Miklush, Manager, Maintenance Department W. J. Kelly, Licensing Representative
- T. L. Grebel, Regulatory Compliance Supervisor-R. L. Watson, Supervisor, Quality Support R.
W. Cook, Rate Case Group Coordinator M. I. Horseman; Quality Support Engineer 0. K. Pranks, ISI/NDE Supervisor J. E. Hill,, Lead lSI/NDE,Specialist Various other engin'eering'and QC personnel.
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"'Denotes, attendee's at exits management meeting on February 14, 1986.
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In addition, NRC Resident Inspectors attended the exit. management meeting.
I Area Ins ection An 'ind'ependent in'spection was conducted in Units 1 and 2 Turbine Building and Auxiliary Buildings.
The equipment spaces inspected for both units included:
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Five Emergency Diesel Generator Rooms.
Six 4160 Volt Switchgear Rooms.
Six Battery Rooms.
Six 480 Volt Vital Bus Rooms.
Two Cable Spreading Rooms.
Combination Two-Units Control Room Two Hot Shutdown Panel Areas.
Turbine Building, Elevations 85', 104'nd 140'.
Housekeeping and equipment status appeared to be satisfactory.
No violations of NRC requirement were identified.
Inservice Ins ection Pro ram The inspection of the inservice inspection program for Unit 1 was first addressed in Inspection Report 50-275/85-11 conducted during March 1985.
Inspection Report 85-11 indicated that the Unit 1 "Inservice Inspection and Testing Program Plan: First Ten-year Interval" had not been issued as a controlled document.
The licensee's administrative procedure NPAP E-4 requires that, inservice inspection program be subject to administrative
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procedures.
Upon discovery of this discrepancy, the licensee issued problem report DC1-85-ISP008 to monitor this item through to its final resolution.
Since the Unit 1 inservice inspection program was in the process of being revised, the resolution was to issue the revised (Rev. 3) edition as a controlled document.
Revision 3 of the inservice inspection program has been completed and approved by the Plant Safety Review Committee (PSRC)
and will be issued as a controlled document.
The revised issue of Unit 1 inservice inspection program will be forwarded in the very near future to the NRR staff for their review and acceptance.
The status of this review will be followed and reported in a future inspection report (50-275/86-05-01).
A second concern, which was identified in Inspection Report 85-11 involved whether there was adequate transfer of information to the preservice records for modifications made to primary piping systems and associated pipe support for the period between completion of construction and the time that Section KI repair and replacement requirements came into effect.
The inspector reviewed correspondence files and construction records of modifications to the primary piping systems and associated supports following the completion of construction.
March 1982 has been accepted as the date that Section XI repair and replacement requirement program came into effect at Diablo Unit 1.
The licensee's review of the construction records of modifications following the completion of construction pertaining to the inservice test program had not been completed.
This item will be examined during a future inspection (50-275/86-05-02).
4.
Miscellaneous Follow-u Items The status of three open items from Inspection Report 50-275/323/86-01 was reviewed.
However, none of these items had progressed to completion; and therefore will be examined during a future inspection.
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The inspector conducted an exit meeting on February 14, 1986, with the Plant Manager and other members of the plant staff.
During this meeting, the inspector summarized the scope of the, inspection activities and reviewed the inspection findings as described in this repor K a4
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