IR 05000269/1978034
| ML15223A385 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 12/18/1978 |
| From: | Kellogg P NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML15223A383 | List: |
| References | |
| 50-269-78-34, 50-270-78-32, 50-287-78-34, NUDOCS 7901110177 | |
| Download: ML15223A385 (7) | |
Text
t;,VkREGU4UNITED STATES
'NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTA STREET, ATLANTA, GEORGIA 30303 Report Nos.:
50-269/78-34, 50-270/78-32 and 50-287/78-34 Docket Nos.: 50-269, 50-270 and 50-287 License Nos.: DPR-38, DPR-47 and DPR-55 Licensee:
Duke Power Company 422 South Church Street Charlotte, North Carolina 28242 Facility Name:
Oconee Units 1, 2 and 3 Inspection at:
Oconee Site, Seneca, South Carolina Inspection conducted:
December 6-8, 1978 Inspector: J. E. Ouzt, Approved by:
P. J. Kief Date Nuclear pport Section No. 2 Reactor Operations and Nuclear Support Branch Inspection Summary Inspection on December 6-8, 1978 (Report Nos. 50-269/78-34, 50-270/78-32 and 50-287/78-34)
Areas Inspected:
Routine, unannounced inspection of plant procedures for Units 1, 2 and 3. The inspection involved 15 inspector hours on site by one NRC inspecto Result:
Of the area inspected, no items of noncompliance or deviations were identifie i7
RII Report Nos. 50-269/78-34, 50-270/78-32 and 50-287/78-34 I-1 DETAILS I Prepared by:
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Ouzts, ctor Inspector Da e Nuclear Support Section No. 2 Reactor Operations and Nuclear Support Branch Dates of Inspectio
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ember-8, 1978 Reviewed by:
D te NuleT Support Sction No. 2 Reactor Operations and Nuclear Support Branch Persons Contacted
- J. E. Smith, Station Manager
- R. T. Bond, Licensing Project Engineer
- R. M. Koehler, Superintendent Technical Services
- K. J. Brackett, Station Senior QA Engineer
- J. D. Norton, Corporate QA Engineer
- D. J. Vito, Assitant Engineer Four storage vault and file room clerks were also contacte *Denotes those attending exit intervie.
Licensee Action on Previous Inspection Findings No inspected Unresolved Items Unresolved items are matters about which more information is required in order to ascertain whether they are acceptable items, items of noncompliance or deviations. No unresolved items were identified during this inspectio.
Exit Interview The inspector met with licensee representatives (denoted in paragraph 1)
at the conclusion of the inspection on December 6-8, 1978. The inspector summarized the scope and findings of the inspection as discussed in paragraph 5. The licensee acknowledged the inspector's findings as discussed in these detail RII Report Nos. 50-269/78-34, 50-270/78-32 and 50-287/78-34 1-2 Plant Procedures Verification The inspector conducted a review of the following plant procedures:
Operating Procedures-OP-0-A-1205-01-Preparation for Refueling-OP-3-A-1102-02-Reactor Trip Recovery-OP-1-A-1106-01-Turbine Generator
-OP-0-A-1510-07-Control Rod Cluster Configuration Loading and Shipment-OP-1-A-1104-02-High Pressure Injection System Operational Procedure-OP-2-A-1103-05-Pressurizer Operation-OP-3-A-1103-06-Reactor Coolant Pump Operation-IP-0-A-0301-03T-Power Range Calibration at Power-IP-2-A-0305-03A-Reactor Protection System - Channel A - On Line
RII Report Nos. 50-269/78-34, 50-270/78-32 and 50-287/78-34 1-3 Abnormal (Alarm)
-2/1701/41-Control Rod Drive Sequence Fault-2/1702/01-High Pressure Loop "A" Emergency Flow Low-2/1704/16-Reactor Building Emergency Hatch Inner/Outer Door Open-2/1702/39-Reactor Coolant Pressure High/Low-2/1702/38-Letdown Tank Pressure High/Low-2/1702/20-Reactor Coolant Pressure Low-2/1701/08-N15 High Flux Trip-2/1701/07-Channel A - Reactor Projection System/Flux Trip Emergency Procedures-EP-0-A-1800-7-Steam Generator Tube Failure
RII Report Nos. 50-269/78-34, 50-270/78-32 and 50-287/78-34 1-4-EP-0-A-1800-29-Loss of Instrument Air-EP-0-A-1800-26-Loss of Component Cooling-EP-A-1800-23-Loss of Containment Integrity-EP-1-A-1500-02-Fire (PIE)
Maintenance Procedures-MP-0-A-1300-07-High Pressure Injection Pump Removal and Replacement-MP-0-A-1400-03-Removal and Installation of Type "A" Electrical Penetrations-MP-0-A-1800-17-Disassembly of Letdown Cooler and Test for Leaks-MP-0-A-3000-21-Pressurizer Safety Valve Setpoint Testing-1P-0-A-0305-05A-Reactor Protection System Channel "A" Reactor Building High Pressure Trip
RII Report Nos. 50-269/78-34, 50-270/78-32 and 50-287/78-34 1-5 Administrative Procedures-3.7.1-Containment Access Control During Refueling and Major Maintenance-3.1.1-Tagging and Safety-3.1.7-Access to Containment Temporary Procedures
-TO/0/A/1107/03-Temporary Drumming Procedure for Evaporator Bottoms-TO/0/A/3001/01-Disconnect DC Output Cables on Exide 600 Ampere Battery Charger The above procedures were reviewed to verify that:
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Reviews, approvals and changes covering the activities were in accordance with Technical Specification Temporary Procedures were not in conflict with Technical Specifications
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Where required procedure changes were made to reflect changes required by selected technical specification revisions
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Safety reviews were made and recorded in conformance with 10 CFR 50.59(a) and (b)
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Procedure contents were in accordance with Technical Specification requirements
I Report Nos. 50-269/78-34, 50-270/78-32 and 50-287/78-34 I-6
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Selected procedure contents were adequate to control required safety related operation Safety-related systems and components which may be exposed to a freezing environment were reviewed with the licensee. He reported no systems or components which were exposed to freezing that were not protected by heating. In addition prior to freezing weather a.checkoff procedure is put into use to check the operability of these systems and component The inspector usedone or more of the following acceptance criteria for evaluating the above items used in the procedure revie Regulatory Guide 1.33
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ANSI N 18.7 (1976)
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ANSI N 45.2.9(1) (1971)
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VEPCO Topical Report (17.0)
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Administrative Policy Manual -
(3.1.4) (3.1.5) (3.1.6) (4.1) and (4.3)
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Corporate Quality Assurance Program
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Inspector Judgement Within the areas inspected no items of noncompliance or deviations were identified.