IR 05000298/1982003
| ML20041F301 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 02/12/1982 |
| From: | Dubois D, Westerman T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20041F290 | List: |
| References | |
| 50-298-82-03, 50-298-82-3, NUDOCS 8203160373 | |
| Download: ML20041F301 (6) | |
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APPENDIX U.S. NUCLEAR REGULATORY COMMISSION
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REGION IV
Report No. 50-298/,82-03 Docket No. 50-298 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: January 1-31, 1982 b
MNE or:
D. L. DuBois, Resident Reactor Inspector Date Projects Section 1
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Approved by:
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T. ~ F. Westerman, Chief, Projects Section 1
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Inspection Summary Inspection on January 1-31, 1982 (Report No. 50-298/82-03)
Areas Inspected: Routine, announced inspection of operational safety verification; monthly. equipment surveillance and maintenance observations; follow up of licensee TMI action plan requirements; and independent events; previously identified items;d 85 inspector-hours on site by one NRC inspection. This inspection involve inspector.
Results: Within the areas inspected no violations or deviations were identified.
8203160373 820216 PDR ADOCK 05000290
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DETAILS 1.
Persons Contacted
- L. Lessor, Plant Superintendent
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P. Thomason, Acting Operations Supervisor J. Sayer, C & HP Supervisor L. Lawrence, Maintenance _ Supervisor P. Borcr, Engineering Supervisor C. Goebel, Administrative Supervisor D. Majeres, Maintenance Planner A. Brungardt, Surveillance Planner L. Bednar, Electrical Engineer
- Indicates presence at exit meetings.
2.
Operational Safety Verification The NRC inspector observed control room operations, instrumentation, controls, reviewed applicable logs, and conducted discussions with control room operators.
The inspector verified operability of:
'A' Core Spray System
'B' Core Spray System
- 2 Diesel Generator-Standby Liquid Control System Diesel Fire Pump The inspector reviewed safety clearance records, including verification that affected components were removed from and returned to service in a correct and approved manner, redundant equipment was verified operable, and limiting conditions for operation were adequately identified and maintained. The inspector also verified that maintenance requests had been initiated for equipment discovered to require repair or routine preventative 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 Specifications, 10 CFR and Administrative Procedures.
No violations or deviations were identified in these area.
3.
Surveillance Observations The 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 Operations were met, removal and subsequent restoration of affected components was accomplished, test results conformed with Technical Specification and procedure requirements, tests were reviewed by personnel othr-than the person directing the. test, and deficiencies identified 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 Speci-fications, 10 CFR and Administrative Procedures.
No violations or deviations were identified in these areas.
4.
Maintenance Observations The inspector observed portions of the following maintenance activities:
'A' Circulating Water Pump - MWR 81-2428*
'B' Reactor Equipment Cooling Heat Exchanger - MWR 81-2696*
'D' RHR Service Water Booster Pump - MWR 81-2697*
'B' RHR Service Water Booster Pump - MWR 82-0011*
'B' Diesel Fire Pump - PM 33-28, 33-46
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- MWR - Maintenance Work Request PM - Preventative Maintenance The following Clearance Orders were independently verified for proper placement /
restoration of affected components:
82-10, 'B' RHR Service Water Booster Pump 82-16, 'C' Circulating Water Pump 82-19, 'B' RHR Service Water Booster Pump 82-40, 'A' Circulating Water Pump
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82-41, 'B' Reactor Equipment Cooling Heat Exchanger (
82-48, 'B' Diesel Fire Pump j
82-49, 'D' RHR Service Water Booster Pump i
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Included with the above were checks for availability of redundant equipment, adequate safety isolation and clearance, accomplishment of work in accordance
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with approved procedures and Technical Specification requirements, verification that QC checks were performed as required, cleanliness controls and health l
physics coverages were adequate.
No violations or deviations were identified in the above are m
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5.
Licensee Event Follow Up The following LERs are closed on the basis o'f the inspector's in-office review, review of licensee documentation, and discussions with licensee personnel:
LER 81-09 Inoperable Mechanical Snubber LER 81-12 Instrument Drift of HPCI-PS-68D LER 81-18 Instrument Drift of NBI-PS-52A LER 81-19 #1 Diesel Gen. Fuel Supply Hose Leak LER 81-21 #2 Diesel Gen. Fuel-Injector Line Break LER 81-25 Inadequate Sampling of Floor Drain Sample Tank 6.
IE Circulars a.
81-06(Closed)
Potential Deficiency Affecting Certain Foxboro 10 to 50 Milliampere Transmitters The Plant Superintendent determined that Foxboro 10 to 50 Milliampere Transmitters are not installed in the plant.
b.
81-07 (Closed) Control of Radioactive Contaminated Material From discussion with the Chemistry and Health Physics Supervisor, through review of CNS Health Physics Procedure 9.1.3, '" Radiation Safety Standards," and by NRC resident inspector observations of applicable licensee actions, it appears that adequate measures are being taken by the licensee which prevent the transfer of contaminated waste to the CNS site located land fill.
c.
81-08 (Closed) Foundation Materials The Plant Superintendent commented that soils work activities performed during initial plant construction were adequately controlled and monitored by quality assurance and quality control measures. Also, there has not been any structural settlement problems identified during the subsequent plant operating phase.
d.
81-09 (Closed) Containment Effluent Water that Bypasses Radioactivity Monitor.
The licensee determined that all containment effluent water that flows directly to the environment is monitored.
Service water effluent from the Reactor Equipment Cooling and Residual Heat Removal Heat Exchangers, though mcnitored, is not automatically isolated on a high contair. ment pressure signal due to safety-related functions. The affected heat exchanger (s) can be isolated locally / remotely within an acceptable time frame, should a Service Water Process Radiation Monitor indicate an alarm conditio.
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81-11(Closed)
Inadequate Decay Heat Removal:During Reactor Shutdown e.
The inspector' reviewed the following CNS General Operating Procedures and.
determined that they adequately address all the recommended items listed in Circular 81-11:
2.1.4 Normal Shutdown From Power 2.2.69 Residual Heat Removal System 2.4.2.4.1 RHR - Loss of Shutdown Cooling f.
81-13(Closed) Torque Switch Electrical Bypass Circuit for Safeguard Service The licensee inspected all Motor Operated Valves in the following systems and verified correct torque switch bypass circuit installation:
Core Spray System Residual Heat Removal System Reactor Core Isolation Cooling System High Pressure Coolant Injection System The inspection was performed and documented per Maintenance Work Request 81-1498.
g.
81-14(Closed) Main Steam Isolation Valve Failures to Close The Engineering Supervisor was not aware of any MSIVs failing to close at Cooper Nuclear Station.
7.
Follow Up of Previously Identified Items a.
Violation Item 8114-03 (Closed) Failure to Meet Radiation Area Posting Requirements The licensee performed the following corrective actions:
(1.) All radioactive material was removed from the affected area.
(2.) NRC Inspection Report #81-14, which described the posting violation, was routed to Health Physics personnel for review.
(3.) CNS Procedure 9.1.2.2, " Area Posting and Access Control," was routed to Health Physics personnel for review.
b.
Violation Item 8117-01 (Closed) Failure to Meet Posted Contaminated Area Clothing Requirements The licensee performed the following corrective actions:
(1.) The affected station operator was given subsequent retraining relevant to posting requirements.
(2.) The CNS Radiation Protection Training Program was modified to include end-of-course written exams.
Exam results will be used to determine subsequent re-training /re-testing need.
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(3.) Area posting and accegs control requirements'were discussed
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during the licensee's November CNS safety meeting.
c.
Open Item 8117-02 (Closed) Replacement.of Mechanical Snubbers Having Inadequate Load Bearing Capacity During the design review of mechanical. snubbers required per IEB 81-01, three Pacific Scientific mechanical snubbers were identified as having inadequate load bearing. capability per load definitions resulting from the Mark 1 program. Two were replaced per Minor Design Change (MDC)-
No.80-099, and the third per MDC No.81-064.
d.
Unresolved Item 8123-01 (Closed) Misinterpretation of Number of Operable Instrument Channels for APRM Rod Withdrawal Block The licensee has revised CNS Technical Specification as necessary to provide clear interpretation of the minimum channel operability requirement for APRM rod withdrawal block.
8.
Exit Meeting 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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