IR 05000361/1981013
| ML20009E112 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 07/07/1981 |
| From: | Thomas Young NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20009E111 | List: |
| References | |
| 50-361-81-13, NUDOCS 8107270120 | |
| Download: ML20009E112 (4) | |
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U. S. NUCLEAR REGULATORY C0!PISSION OFFICE OF INSPECTION AND ENFORCEMENT REGION Y Report flo.
5G-361/81-13 Docket flo.
50-361 License No.
CPPR-97 Safeguards Group Licensee:
Southern California Edison Company 2244 Walnut Grave Avenue Rosomead. California 91770 Facility Name:
San Gnofre Unit 2 Inspection at:
San Dieao County. California Inspection conducted:
June 8-11. 1981
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Inspectors:
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T. Young, Jr., Ele ~ actor
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T. Young, Jd., 3 ting Ch f,
actor Projects Section 7 Gate Signed
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Reactor Operati ns Proj
.t anch Summary:
Inspection on June 8-11, 1981 (Report No. 50-361/81-13)
l Areas Inspected:
Routine, unannounced inspection of licensee's preoperational l
test program, emergency procedures, operating procedures, maintenance procedures, l
power ascension test procedures, preoperational test procedure review and independent inspection effort.
The inspection involved 24 inspector-hours on-site and 52 inspector-hours off-site by one NRC inspector.
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Results: No items of noncompliance or deviations were identified.
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8107270120 810708 RV Form 219 (2)
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PDR ADOCK 05000361 l
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DETAILS 1.
Persons Contacted
- H. E. Morgan, Assistant Station Manager, Operations
- D. E. Nunn, QA Manager
- G. A. Chavez, Project Startup Supervisor
- P. A. Croy, Site Project QA Supervisor
- D. Stonecipher, Operations QA Supervisor
- C. R. Horton, Startup QA Supervisor R. M. Rosenblum, Startup Engineering Supervisor
- M. Z. Merlo, Startup Engineering Supervisor
- V. B. Fisher, Supervisor of Plant Coordination In addition, construction and maintenance craftsmon, engineers, and foremen were contacted durir.g the inspection.
- Denotes attendees at management meeting on June 11, 1981.
2.
Licensee Action on Previous Inspection Findings a.
Forced Evacuation of Control Room (81-10-01)
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(Closed) The licensee has committed to revising his procedures to address this issue.
The QA department has picked this item up in its tracking system and will track to completion.
b.
Waste Gas System Failure Procedure (81-10-02)_
(Closed) The licensee has determined that this procedure is needed and has committed to writing it.
The QA department will also track this item to completioc.
No items of noncompliance or deviations were identified.
3.
Operating Procedures The index of the plant operating procedures were reviewed for completeness and compared to R.G. 1.33.
A sample size of approximately 10 percent of the administrative, general plant operating, startup, operation and shutdown of safety-related systems, and surveillance test procedures were examined.
Following is a list of procedures reviewed:
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S023-1-1.0
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Instrument and Service Air System S023-2-2.13
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Diesel Generator Operation S023-3-2.6
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Shutdown Cooling System Operation S023-3-2.18
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Steam Bypass System Operation S023-5-1.4
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Plant Shutdown from Minimum Load to Hot 3tandby S023-5-1.5
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Plant Shutdown from Hot Standby to Cold S023-3-3.16
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Reactor Regulating System Failure S023-5-1.2
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Main Steam Safety Valve Testing S023-I-5.16
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Jockey Fire Pumps S023-3-1.1
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Reactor Startup S023-3-2.9
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Containment Spray System Operation S023-3-2.12
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Reactor Protection System Operation S023-0-5
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Unit ACO's Responsibilities & Duties S023-0-12
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Station Logs S023-0-16
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Abnormal Equipment S023-A-108
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Admittance to 3tation S023-G-3
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Technical Specification Surveillance Program During the review, the inspector verified that each procedure was in the appropriate format and appeared technically adequate to accomplish its stated purpose.
No items of noncomplian e or deviations were identified.
4.
Maintenance Procedures The index of the plant maintenance procedures was reviewed for completeness.
Following is a list of the maintenance procedures examined by the inspector:
S023-I-2.1
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Surveillance Testing of Pressurizer Safety Valves S023-I-3.6
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Receiving, Unloading, Inspection and Storage of New Fuel Assemblies 5023-I-6.7
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Mechanical Snubber Maintenance 5023-IC-12
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Requirements for Calib and Control of Measuring and 'est Equipment S023-0-5
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Equipment Testing The inspector verified that each procedure was in the required format and that each appeared technically adequate to accomplish its stated purpose.
5.
Power Ascension Test Procedures The following list of power ascension test procedures were examined by the inspector:
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Initial Core Loading
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Control Element Drive Module Tests 2HB-213-04
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Reactor Coolant System Leak Rate 2IC-301-01
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Initial Criticality
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-3-f 2LP-333-01
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Low Power Physics Testing 80% Total Loss of Flow Trip with Natural Circulation 2PA-215-01
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Verification Core Performance Reco
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100% Generator Trip / Load Rejection 2PA-382-01 Shutdown from Outside Control Room
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Loss of Offsite Power at 20% Generator Load 2PA-457-01
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Pseudo CEA Ejection Test The inspector verif.3d that the licensee's comnitments and requirements were included in all procedurcs examined.
Also that each procedure was in the proper format with acceptance criteria and technically adequate to perform its stated objective.
All procedures contained a section on returning the plant to normal configurallon after the test is completed.
No items of noncompliance or deviations were identified.
6.
Emergency Procedures Following is a list of emergency operating procedures examined by the inspector:
5023-3-5.21
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Malfunction of Reactor Coolant Letdown / Purification System S023-3-5.1
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Emergency Plant Shutdown Shutdown from Outsidc Control Room S023-3-5.18
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Loss of Instrument Air S023-3-5.31
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LOCA 3-5.6
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3-5.4
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Complete Loss of 05 Power with Turbine Trip 3-5.25
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Loss of Offsite Power 3-5.5
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Loss of RC Flow 3-5.2
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Loss of Condenser Vacuum Loss of Containment Integrity 3-5.11
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Loss of Saltwater Cooling 3-5.32
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3-5.12
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Loss of Shutdown C)oling 3-5.26
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RC Pump Seal Failure 3-5.33 Loss of CCW
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3-5-30
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Loss of Protective System Cnannel 3-5.8
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Slip ed or Dropped CEA Emergency Boration of RCS 3-5.10
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High Activity in RCS 3-5.14
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3-5.16
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Reactor Regulating System Failure 3-5.17
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Pressurizer Press Control System Malfunction 3-5.35
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Plant Fixes 3-5.27
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Earthquake 3-5.23
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Damage of Spent Fuel 3-5.36
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Abnormal Releases of Radioactive Liquids
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-4-In addition the inspector examined a 10% sample size of abnornal, offnorwel and alarm condition procedures (annunciator alarm procedures).
It was ascertained that each procedure was in the appropriate format and that each appeared technically adequate.to accomplish its stated purpose.
It was noted that the " Emergency Plant Shutdown Procedure" has been revised to address Anticipated Transient Without Scram (ATWS) conditions and that all emergency procedures with reactor trips would direct the operator back to the emergency plant shutdown procedure. This would cover all situations where an ATWS may occur.
No items of noncompliance or deviations were identified.
7.
Quality Assurance (QA) Procram for Operations The QA program for operations manual was reviewed along with the 18 station orders which covers quality assurance. The licensee was informed that when IE inspects the implementation of the QA program, within 90 days of OL issuance, the inspectors would be looking for the detailed
"how to" procedures along with.the actual performance of the activities.
- No items of noncompliance or deviations were identified. -
8.
Management Interview The inspector met with licensee representatives (denoted in paragraph 1)
at the conclusion of the inspection on June 11, 1981. -The inspector
sunnarized the purpose and the scope of the inspection and the findings.
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