IR 05000298/1982023
| ML20027E743 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 10/19/1982 |
| From: | Dubois D, Westerman T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20027E742 | List: |
| References | |
| 50-298-82-23, NUDOCS 8211150673 | |
| Download: ML20027E743 (6) | |
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APPENDIX U.S. NUCLEAR REGULATORY COMMISSION
REGION IV
Report: 50-298/82-23 Docket: 50-29'8 Licensee: Nebraska Public Power District P. O. Box 499 Columbus, Nebraska 68601 Facility Name: Cooper Nuclear Station Inspection At: Cooper Nuclear Station, Nemaha County, Nebraska Inspection Conducted: August 1-September 30, 1982 Inspector:
MM3NA D. L. DuBois, Senior Resident Reactor Date Inspector, Reactor Project Section A Approved:
N
/4/N/6'2-s T. F. Wes~ternran, Chief Date
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Reactor Project Section A Inspection Summary Inspection Conducted August 1-September 30, 1982 (Report 50-298/82-23)
Areas Inspected:
Routine, announced inspection of operational safety verifications, monthly surveillance and maintenance observations, inspector-identified problems, plant trips / safety system challenges, and the annual Systematic Assessment of Licensee Performance (SALP). This inspection involved 52 inspector-hours onsite by one NRC inspector.
Results: Within the areas inspected one violation was identified (violation -
failure to provide a detailed procedure to be used for maintenance of system components that could have an affect on nuclear safety - paragraph 4).
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DETAILS 1.
Persons Contacted
- L. Lessor, Plant Superintendent P. Thomason, Acting Operations Supervisor V. Wolstenholm, QA Supervisor L. Bednar, Electrical Engineer
- Indicates presence at exit meetings.
2.
Operational Safety Verification The NRC inspectar observed control room operations, instrumentation, controls, reviewed applicable logs, and conducted discussions with control room operators.
The NRC inspector verified operability of:
Automatic Depressurization System
'A & B' Core Spray Systems Standby Liquid Control System 480 V Emergency Power System Nuclear Instrumentation The NRC inspector reviewed safety clearance records, including verification that affected components were removed from and returned to service in a correct and approved manner, that redundant equipment was verified operable, and that limiting conditions for operation were adequately identified and maintained. The NRC inspector also verified that maintenance requests had been initiated for equipment discovered to require repair or routine preventive upkeep, appropriate priority was assigned, and maintenance commenced in a timely manner commensurate with assigned priorities.
Tours of accessible areas of the facility were conducted to observe normal security practices, plant and equipment conditions, including cleanliness radiological controls, fire suppression systems, emergency equipment, potential fire hazards, fluid leaks, excessive vibration, and instrumentation adequacy.
These reviews and observations were conducted to verify that facility operations were in conformance with the requirements established in the Technical Specification, 10 CFR, and Administrative Procedures.
No violations or deviations were identified in these areas.
3.
Monthly Surveillance Observations The NRC inspector observed portions of Technical Specification required surveillance tests to verify that testing was performed in accordance with adequate procedures, test instrumentation was in calibration, limiting conditions for operation were met, removal and subsequent restoration of affected components was accomplished, test results conformed with
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Technical Specification and procedure requirements, tests were reviewed by personnel other than the person directing the test, and deficiencies identi-fied during testing were properly reviewed and resolved by appropriate management personnel.
These reviews and observations were conducted to verify that facility operations were in conformance with the requirements established in the Technical Specification, 10 CFR, and Administrative Procedures.
No violations or deviations were identified in these areas.
4.
Monthly Maintenance Observations The NRC inspector observed portions of various maintenance-related activities to verify that work was accomplished in accordance with approved procedures and Technical Specification requirements, redundant equipment was available, equipment was adequately isolated and safety tagged, and that cleanliness controls and health physics coverages were adequate.
During a tour of the facility on August 13, 1982, the NRC inspector discovered the high pressure coolant injection (HPCI) pump turbine steam supply line isolation valves failed in the "open" position. The affected valves, motor operated valves (M0V's) HPCI-M0V-15 and HPCI-M0V-16, provide automatic primary containment isolation capability upon receipt of any one of three independent and diverse isolation closure signals. M0V's 15 and 16 power supply breakers were opened to prevent inadvertent HPCI turbine steam line isolation during the performance of maintenance on cables and conduits relating to the HPCI steam line high temperature-isolation system.
Further review indicated that an approved procedure did not exist which would have prescribed documented instructions to be used during the performance of the safety-related main-tenance activity. The duty shift supervisor was immediately informed of the error by the NRC inspector.
CNS Technical Specification, Section 6.3.1, states, " Station personnel shall be provided detailed written procedures to be used for operation and main-tenance of system components and systems that could have an affect on nuclear safety." The failure to follow the requirement of Technical Specification, Section 6.3.1 as described above, constitutes a violation.
(8223-01)
5.
Plant Trips - Safety System Challenges The NRC inspector reviewed records and interviewed plant personnel concerning two unscheduled reactor scrams which occurred during this inspection period.
The first unscheduled reactor scram occurred on August 17, 1982, at 4:23 p.m.,
(Scram Report #82-04). The plant was at full power, normal operating conditions prior to the scram.
Control room operators observed the main steam bypass valves cycling for no apparent reason and before corrective action could be initiated, the reactor scrammed on average power range monitor system (APRM)
high power level. The high power level resulted from sudden closure of the
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main steam bypass valves which caused a rapid increase in reactor pressure.
All systems responded to the scram as designed and appropriate scram recovery actions were taken by plant personnel. No unreviewed safety questions were discovered. The plant returned to power operation on August 19, 1982, following the replacement of electrical' components located within the turbine /
main steam bypass valves digital electro-hydraulic control system (DEH).
The second unscheduled reactor scram occurred on September 4,1982, at 11:06 a.m.,
(Scram Report #82-05). The plant was at full power, normal operating conditions prior to the scram. Control room operators noticed that reactor feedwater pump
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"A" (RFP "A") was decreasing to minimum speed for unknown reasons and RFP "B" was increasing speed to compensate for the sudden reduction in reactor feed-water flow. The reactor scrammed on low reactor water level before adequate corrective action could be completed by control room personnel. All systems responded to the scram as designed and appropriate scram recovery actions were performed by plant personnel.
No unreviewed safety questions were discovered. The plant returned to power operation on September 5,1982, after replacing the RFP "A" auto-manual controller.
The licensee initiated two manual reactor scrams from low reactor power levels to facilitate timely entry into scheduled outages. The scrams occurred on May 21, 1982, and July 14, 1982, (Scram Reports 82-02 and 82-03). The outages were for scheduled refueling and maintenance, respectively.
6.
Systematic Assessment of Licensee Performance (SALP)
The NRC SALP Board met on August 31, 1982, to evaluate the licensee's per-formance during the period of July 1,1981, through June 30, 1982.
The NRC Region IV Administrator and accompanying staff members met with Nebraska Public Power District's senior corporate management representatives on September 28, 1982, to discuss the SALP Board's tlalysis, evaluation, and recommendations.
The licensee has been requested to submit written comments concerning the evaluation of their performance to the NRC Region IV office by October 18, 1982.
Their coments, if any, and the SALP Board Report, will appear as enclosures to the Region IV Administrator's letter, which will issue the SALP Report as NRC Report 50-298/82-24.
7.
Exit Meetings Exit meetings were conducted at the conclusion of each portion of the inspection.
The plant superintendent was informed of the above findings.
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Contrary to CNS Technical Soecification. Section 6.3.1. the licensee failed to orovide
detailed written crocedures to be used for coeration and maintenance of system comoonents i
and systems that could have an affect on nuclear safety.
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