IR 05000206/1985021
| ML13323A991 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 07/02/1985 |
| From: | Ivey K, Thomas Young NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | |
| Shared Package | |
| ML13323A990 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-1.A.1.3, TASK-2.E.1.1, TASK-2.F.1, TASK-2.F.2, TASK-3.D.3.4, TASK-TM 50-206-85-21, 50-361-85-20, NUDOCS 8507220363 | |
| Download: ML13323A991 (6) | |
Text
U. S. NUCLEAR REGULATORY COMMISSION
REGION V
Report No /85-21 and 50-361/85-20 Docket No and 50-361 License No DPR-13 and NPF-10 Licensee:
Southern California Edison Company P. 0. Box 800, 2244 Walnut Grove Avenue Rosemead, California 91770 Facility Name:
San Onofre Units 1 and 2 Inspection at:
San Clemente, California Inspection conducted:
June 10-14, 1985 Inspector:
7/
I A9 Ivey, Jr., Reactor Inspect D te S gned Approved By:
(___/
____
T. Young, Jr.,
Ch f, Eng'n e g Section Date Signed Summary:
Inspection between June 10-14, 1985 (Report Nos. 50-206/85-21 and 50-361/85-20)
Areas Inspected: Routine inspection of the implementation of selected TMI Action Items. This inspection effort required 35.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> by one regional inspecto Results:
No violations or deviations were identifie PDR ADOCK 05000206 PDR'
DETAILS Persons Contacted
- G. T. Gibson, Compliance Supervisor J. Walderhaug, Computer Engineer
- P. R. King, Operations Quality Assurance Supervisor D. Barney, Unit 1 Shift Superintendent
- C. Kergis, Lead Compliance Engineer
- M. Freedman, Compliance Engineer W. McGhee, Unit 1 Coordination Supervisor
- J. Grosshart, Quality Assurance Engineer M. Kirby, Unit 1 Operator Training Manager D. Wilcockson, Unit 1 Operations Instructor The inspector also talked with other licensee personnel during the inspection. These included plant staff engineers and document control personne *Denotes personnel present during the exit interview on June 14, 198.
TMI Action Plan Items Unit 1 (1) (Closed) I.A.1.3 Shift Manning -
(Sub-item 2.A, Minimum Shift Crew)
Summary:
NUREG-0737 requires that licensees of operating plants include in their administrative procedures provisions governing required shift staffing and movement of key individuals about the plan Findings and Conclusion:, In a letter dated February 16,.1983 (Baskin, SCE to Crutchfield, NRC), the licensee stated that license testing was completed successfully and the current shift manpower is in accordance with commitment The licensee utilizes five full shift crews with a contingency to accomodate the loss of personnel. In NRC Inspection Report N /84-20, the inspectors found that procedures had been revised to reflect, minimum shift manning requirements and proposed Technical'Specification Change No. 130 was submitted for NRC approva Change No. 130 is presently undergoing review by the NRC. The licensee has taken appropriate action to comply with the requirements of the TMI Action Plan. This item is closed for Unit No violations or deviations were identifie (2) (Closed) II.E.1.1 Auxiliary Feedwater System Evaluation (Sub-item 1, Short Term System Modifications)
Summary:
Per NUREG-0737, the NRC Office of Nuclear Reactor Regulation requires that all operating plant licensees reevaluate their PWR plant auxiliary feedwater system and implement recommendations for improving system reliabilit Findings and Conclusion:
In a letter dated October 22,1982 (Crutchfield, NRC to Dietch, SCE), the NRC found the response to recommendations on this item to be acceptable. NRC Regional Inspectors, in IE Report No. 50-206/84-20, found that the licensee had taken the appropriate actions to comply with the TMI Action Plan Requirements. Therefore, this item is closed for Unit No violations or deviations were identifie (3) II.F.1 "Accident Monitoring" The inspector verified the licensee's actions taken in response to the following NUREG-0737 sub-items are as documented in correspondence between the licensee and the NR Areas of inspection included:
o Review of design changes.to ensure that modifications were reviewed, approved, inspected, and tested in accordance with established procedure o Review of as-built drawings and.procedures (including control room copies) to ensure that revisions were incorporated to reflect modifications made to the system o Visual verification of control room indication for the monitors located on panel C0 o Discussions with training personnel and review of individual training histories to ensure that applicable training was given for the modifications and has been incorporated into the training progra Sub-item 4 (Closed) - Containment Pressure Monitor Summary:
NUREG-0737 requires that a.continuous indication of containment pressure be provided in the control room of eac operating reacto Findings and Conclusion:
By letter dated August 3, 1984 (Paulson, NRC to Baskin, SCE),
the NRC accepted the licensee'sproposal for this item. The proposal was to modify the existing containment pressure monitor computer program to record the highest reading each
minute. This would give the'program the ability to trend containment pressure for short transient The modification :was performed in accordance with Software Modification No.FOX-3/84-0002 and completed October 21, 198 The inspector reviewed the modification package which included; the reviewed and -apprbved.-modification, 10 CFR 50.59 review, and post-modification test plan.and.results. The inspector visually verified operation of the system on the FOX-3 computer located in the Technical:Support Center (adjacent to the control'room).his modification'appears to' satisfy NUREG-0737 requirements and closes this item for Unit Sub-item 5(Closed) - Containment Water Level Monitor Summary: NUREG-0737 requires that a continuous indication of containment water level be provided'in the control room for all plant Findings and Conclusion By letter.dated April 6, 1984 (Crutchfield, NRC. to Baskin, SCE), the NRC accepted the licensee's proposal for satisfying this item. The proposal involved installing a new containment sump Water level indication system and a new containment water level indication system., Both systems are powered by Class 1E power supply and designed to meet Regulatory Guide 1.75 separation criteri These systems replaced the existing water level systems used in the plan The new installation was performed in accordance with Design Change (DC) No. 80-35 and completed May 8, 198 The change is presently being reviewed by configuration control to provide final verification of document changes. The inspector reviewed the DC package for completeness and.reviewed associated documentation including; turnover Packages, 10 CFR 50.59 reviews,.work permits, calibration records, drawings, and pre-operational test results. These installations appear to satisfy NUREG-0737.requirements.and closes this item for Unit Sub-item 6 (Closed) -
Containment Hydrogen'Monitor Summary:
NUREG-0737 requires that a continuous indication of hydrogen concentration in the containment atmosphere be provided in the control roo Findings and Conclusion:
By.letter dated April 6, 1984 (Crutchfield, NRC to Baskin,,SCE), the NRC accepted.the licensee's proposal for satisfying this item. The proposal included installation of a new containment hydrogen monitoring system to provide redundafit hydrogen sensing, analysis, and indication. All instrumentation and controls are separate and independen The installation was performed in accordance with Design Change (DC) No. 80-34 and completed March 18, 198 The DC is presently undergoing Configuration Review to provide the assurance that all affected design documents and procedures reflect the new installation. The inspector reviewed the DC package for completeness and reviewed associated documentation including; turnover packages, drawings, procedures, system test reports, pre-operational calibration test results,.and configuration control reports. This. DC appears to satisfy NUREG-0737 requirements and closes this item for Unit No violations or deviations were identifie (4) (Open) III.D.3.4 Control Room Habitability Summary: NUREG-0737 requires that licensees assure that control room operators will be adequately protected against the effects of accidental release of toxic and radioactive gases and that the nuclear power plant can be safely operated or shut down under design basis accident condition Findings and Conclusion:
The licensee has performed a.risk assessment for a loss of control room habitability resulting in the conclusion that no modifications to the current control room HVAC and habitability systems are appropriat Notwithstanding the risk assessment, the licensee has committed to perform a review of upgrades that can reasonably be implemented to enhance the reliability of the control room HVAC. The present scheduled completion date is July 19, 198 This item will be examined further during a future inspectio No violations or deviations were identifie Unit 2 (1) II.F.2 "Instrumentation for Detection of Inadequate Core Cooling" Sub-item 4. (Closed) -
Installation of Additional Instrumentation Summary:
NUREG-0737 -requires,the installation of additional instrumentation or controls (primary or backup) to supplement existing instrumentation in order to provide an unambiguous, easy-to-interpret indication ofdinadequate core cooling (ICC).
Findings and Conclusion:
The licensee has committed to implement a final ICC system which meets the requirements delineated in NUREG-0737. By a letter dated September 26, 19.84 (Medford, SCE to Knighton, NRC), the licensee stated that the miodifications to satisfy the requirements for this item would be installed at Unit. 2 prior to startup following the first Unit 2 refueling outage. This was also made a Unit 2 license condition (No. 2.C(19).5).
The modification included
installation of a Heated Junction Thermocouple (HJTC) system and upgrading the incore detector assemblies (core exit
- thermocouples, etc).
In a letter dated May 29, 1985 (Medford, SCE to Knighton, NRC),
the licensee stated that the Unit 2 HJTC system was installed with all associated instrumentation calibrated and operable on February 27, 1985. The licensee considers all outstanding commitments related to the HJTC system at San Onofre Unit 2 to be complete. The Unit 2 first refueling outage ended on April 17, 198 The modification was performed in accordance with Proposed Facility Changes.(PFC) No. 2/3-83-431 and No. 2/3-83-432. Work has been completed on PFC No. 2/3-83-431 and it is. presently undergoing Final Review by Station Engineering for turnover to Configuration Control. PFC No. 2/3-83-432 has been completed and is undergoing Configuration -Review for final closeout. The inspector reviewed the PFCs and their associated documentation including: turnover packages, configuration reports, safety evaluations, pre-operational test records, and document change lists. This item is closed for Unit No violations or deviations were identifie.
Exit Interview On June 14, 1985, an exit interview was held with the licensee representatives identified in paragraph 1. The inspector summarized the scope of the inspection and findings as described in this repor I"5