IR 05000275/1980015
| ML16340B154 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 08/11/1980 |
| From: | Bagaglio M, Sternberg D, Thomas Young NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML16340B153 | List: |
| References | |
| 50-275-80-15, NUDOCS 8009230219 | |
| Download: ML16340B154 (8) | |
Text
50-275/80-15 U. S.
NUCLEAR REGULATORY CO~iKISS ION OFFICE OF INSPECTION AND ENFORCEtO.'NT
REGION V
Report No, License No.
Licensee:
50-275 Priority Pacific Gas and Electric Company 77 Beale Street CPPR<<39 Category Facility Name:
Inspection at:
San Francisco, California 94106 Diablo Canyon Unit 1 Diablo Canyon Site, San Luis Obispo County, California Inspection conducted
'.
July 1-31, 1980 Inspectors.. Tolbert Young Jr.
Senio Hr
~ggic Hario Bagag o Jr.,
e s
t Reactor nspector eactor Inspector D'e Signed D te Signed Approved by:
D. ti. Stern erg, C
~e, Reac rojects ection 1, Reactor Operations and Nuclear Support Branch Summary:
Inspection of Jul 1-31 1980 Re ort No. 50-275/80-15 Date Signed
'0 l)
e o ate Signed Areas Ins ected:
Routine inspection of preoperational testing, plant tour, fire protection/prevention, operator training and witnessing of testing in progress.
This inspection involved 140 inspector-hours onsite by two NRC resident inspectors.
Results:
No items od noncompliance or deviations vora identified.
IE:V Form 919(1)
8 oo92ao g)q
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DETAILS 1.
Persons Contacted J.
D. Shi.ffer, Manager, Nuclear Plant Operations
>>R.
D. Ramsay, Plant Manager R.
D. Etzler, Project Superintendent
>>R. Patterson, Plant Superintendent
>>H. N. Norem, Resident Startup Engineer
- C. H. Seward, QA Engineer
>>J.
S.
Diamonon, QC Supervisor
>>J. H. Gisclon, Power Plant Fngineer
>>D. A. Blackens, Supervisor of Maintenance
- W. B. Kaefer, Technical Assistant to Plant Superintendent
>>J. A. Sexton, Supervisor of Operations The inspector also talked with and interviewed a number of other licensee employees including members of general construction, the operations staff and QA personnel.
- Denotes those attending the exit interview.
2.
Fire Protection/Prevention The control room and the cable spreading rooms were inspected.
The fire alarm, extinguishing enuipment, actuating controls and fire fighting ecuipment were verified to be operable in the'able spreading rooms and 25%
of the balance of the plant.
The new cable penetration seal material was verified not to be flammable.
No items of noncompliance or deviations were identified.
'.
Plant Tour The inspector walked through various areas of the plant on a ~.eekly basis to observe activities in progress; to inspect the general state of clean-liness, housekeeping and adherence to fire protection rules; to check the proper approval of "man on the line, caution and clearance" tags on eouip-ment, and to review with operation personnel the status of various systems in the plant.
The inspector noted that the status of the systems and the housekeeping appeared consistent with construction activities.
The reactor cavity is still being maintained as a clean area and extra personnel are still assigned to cleanup crews.
Cleanliness and housekeeping of t'e plant is still improving.
No items of noncompliance or deviations were identifie.
0 erator Traininm The operations division is continuing their intensive retraining program for the operators and technical advisors to include two weeks at the Mestinghouse simulator.
The inspectors have monitored some of these classes and will monitor more classes throughout the training program.
No items of noncompliance or deviations
~ ere identified.
5.
Preooerational Tasting a.
Portions of the following tests vere witnessed by the inspector:
1.13 Preop.
Remote Manual Valve Operators 34.1 Fuel Transfer System Functional Test b.
Mhile ~'itnessing the above testing (in 'some tests only parts of the-tests were being performed or redone),
the inspector verified that the procedures were technically adequate; the latest revisions
~:ere available and approved; the overall crew performance was adenuate and, in the case of completed tests, the acceptance criteria were met.
Administrative controls for design change and documentation were followed.
No items of noncompliance or deviations were identified.
6.
0 eratin and Surveillance Test Procedures An inspector reviewed several new and revised operating and surveillance test procedures.
Procedures reviewed were:
OP-7 OP-10 OP-15 OP-17 OP<<20 OP-21 OP-32 OP>>34 OP-36 STP I-28 STP I-684 STP I-884 STP I-11A STP I-1182 Loss of Condenser Vacuum Loss of Auxiliary Salt Mater Loss of Feedwater Flow Ifalfunction of the Residual Heat Removal System Excessive Reactor Coolant System Leakage Loss of Coolant Loop RTD Rod Ejection Generator Trip - Full Load Rejection Turbine Trip Nuclear Power Range Channel Functional Test Response Time Testing of Pressurizer Pressure Transmitters.
Response Time Testing of Reactor Coolant Flov Transmitters Functional Test of Steam Generator Level Channels Calibration of Steam Generator Level Protection and Safeguards Channels
~I %)
i
+J
-3-STP I-1183 Calibration of Steam Generators Level Transmitters STP I-1184 Response Time Testing of Steam Generator Level Transmitters STP I-1185 Reinstatement of Steam Generator Level Channels to Service Based upon revie~
one item of concern is pertinent.
The minimum Lo-Lo Steam Generator Level Trip Setpoint in STP I-11A and STP I-1182 is established at 14% on the narrow range level channel.
Supplement 9 to the Diablo Canyon Safety Evaluation Report renuires that the minimum Lo-Lo steam Generator Level Trip Setpoint be established at 16% on the narrow range level channel.
Pending resolution of this difference between NRR and the licensee, this concern will remain an open item.
(80-15-01)
7.
Exit Interview The inspector met with a senior licensee representative on a weekly basis and
~ ith the representatives denoted in Paragraph 1 on August 1, 1980.
The scope and findings of the inspection were summarized by the inspecto i'I 4W LlII