ML20210E731
| ML20210E731 | |
| Person / Time | |
|---|---|
| Site: | Diablo Canyon  |
| Issue date: | 11/15/1983 |
| From: | Martin J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20209C222 | List: |
| References | |
| FOIA-86-151, RTR-NUREG-0737, RTR-NUREG-737, TASK-1.D.2, TASK-2.E.1.1, TASK-2.E.3.1, TASK-TM NUDOCS 8609250081 | |
| Download: ML20210E731 (3) | |
Text
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,o, UNITED STATES l *8' NUCLEAR REGULATORY COMMISSION o
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4 1450 MARIA LANE,SulTE 210
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WALNUT CREEK. CALIFORNIA 94596 November 15, 1983 Docket No. 50-275 MEMORANDUM FOR:
H. Denton, Director, Nuclear Reactor Regulation FROM:
J. B. Martin, Regional Administrator
SUBJECT:
FUEL LOADING - DIABLO CANYON UNIT 1 PACIFIC GAS AND ELECTRIC COMPANY Based on the results of our inspection efforto, we have determined that Construction and Preoperational Testing of the subject facility have been completed in substantial agreement with docketed commitments and regulatory requirements, with the exception of items indicated in the enclosures. With the exception of noted items, we have completed our inspections in accordance with the requirements contained in MC 2500. Region V is not aware of any additional items required to be completed before fuel loading. The remaining construction, testing, and inspection items identified in the enclosures have been categorized with recommended completion milestones.
As part of our inspection efforts, we have reviewed the licensee's implementation of the Quality Assurance Program for Operations, and have found that it meets the requirements of 10 CFR 50, Appendix B, as specified in the licensee's Quality i
Assurance Program (Chapter 17 of the FSAR), which was reviewed by the Office of Nuclear Reactor Regulation.
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Regional Administra l
Enclosures:
l A. Items to be Completed Before Initial Criticality B. Items to be Completed Before Exceeding 5 Percent Power cc w/ enclosure:
R. DeYoung, IE:HQ D. Eisenhut NRR 8609250081 860916 C. Knighton, NRR,
ME 131 PDR D. Kirsch, RV J. Crews, RV P. Morrill. RV M. Mendonca, RV
ENCLOSURE A ITEMS TO BE COMPLETED BEFORE INITIAL CRITICALITY CONSTRUCTION Essentially, all construction should be completed in Unit 1 before initial I
criticality. Exceptions include routine maintenance, adjustment of gaps on rupture restraints, and minor changes necessitated by the start-up testing program.
OPERATIONS The licensee must satisfactorily complete the relevant portions of the start-up test program. Specific tests or calibrations of concern are listed below.
1.
The Reactor Coolant System (RCS) saturation meter calibration, reactor vessel head vent test, and retetor vessel level indication calibrations must be completed prior to initial criticality.
2.
Westinghouse personnel must be on shift An the control room / plant prior to initial criticality.
3.
The selective examination of large and small bore piping thermal movements to validate the piping system thermal analyses must be completed. The licensee should report to the NRC the results of the walkdown and corrective actions taken or planned prior to initial criticality. Some examinations (feed-water system for example) will have to be done later since that piping will not reach full operating temperature until the plant is at 100 percent power.
ALLEGATIONS A number of allegations have been received by the NRC (RV, NRR, OI) regarding Diablo Canyon. A review of allegations within Region V has not identified any which could reasonably be expected to adversely effect the safety of fuel loading or precriticality testing. However, an allegation status review should be performed by the NRC staff prior to authorization of initial criticality.
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ENCLOSURE B ITEMS TO BE COMPLETED BEFORE EXCEEDING S PERCENT POWER OPERATIONS The licensee must satisfactorily complete the relevant portions of the start-up test program prior to exceeding 5 percent power.
1.
The pressurizer heater test, and 48-hour auxiliary feedvater pump endurance test must be completed prior to initial criticality (NUREG 0737 II.E.3.lt and II.E.1.1, respectively).
2.
The safety parameter display system must be operable and associated procedures for operations personnel must be implemented prior to exceeding 5 percent power (NUREG 0737, I.D.2).
3.
The Westinghouse review of the power ascension test program must be completed.
RADIATION PROTECTION The implementation of some NUREG 0737 items has not been completed, and there are concomitant inconsistencies or omissions in the Technical Specifications which require resolution (see memo, Bishop to Knighton, dated August 23, 1983, which describes these items and our recommendations regarding their resolution).
l The licensee's Core Damage Estimate Procedure is not consistent with the guidance being provided to operating reactors or other near term operating licensees.
Prior to exceeding 5 percent reactor power, the licensee should have an adequate Core Damage Estimate Procedure which has been reviewed by NRR and is based upon operable portions of the licensee's Post Accident Sampling System.
These matters have been discussed with Messrs. B. Buckley and J. Boebli of NRR by Mr. E. Garcia of the Region V staff.
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