IR 05000298/1982005
| ML20052C258 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 03/31/1982 |
| From: | Dubois D, Westerman T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20052C245 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-1.C.6, TASK-2.B.2, TASK-2.F.1, TASK-TM 50-298-82-05, 50-298-82-5, NUDOCS 8205040541 | |
| Download: ML20052C258 (8) | |
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APPENDIX U.S. NUCLEAR REGULATORY COMMISSION
REGION IV
Report No. 50-298/82-05 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 3" 3 N or:
D. L. DuBois, Resident Reactor Inspector Date Reactor Project Section A 11 A Approved by:
D 7/ ~ 9 E-T. F. Westerman, Chief Date Reactor Project Section A Inspection Summary Inspection on February 1-28, 1982 (Report No. 50-298/82-05)
Areas Inspected: Routine, announced inspection of operational safety. verification; monthly equipment surveillance and maintenance observations; follow up of licensee events; previously identified items;- and TMI action plan requirements. This
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inspection involved 63 inspector-hours on site by one NRC inspector.
Results: Within the areas-inspected, no violations or deviations were identified.
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DETAILS 1.
Persons Contacted
"*L. Lessor, Plant Superintendent P. Thomason, Acting Operations Supervisor J. Sayer, C & HP Supervisor C. Goebel, Administrative Supervisor V. Wolstenholm, QA Supervisor A. Brungardt, Surveillance Planner D. Majeres, Maintenance Planner R. Peterson, Reactor Engineer L. Bednar, Electrical Engineer J. Scheer, Electronics 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 roora operators.
The inspector verified operability of:
'A' Core Spray System
'B'
RHR System
- 1 Diesel Generator Standby Liquid Control System 4160 VAC Vital Switchgear The 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 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.
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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 Speci-fications, 10 CFR and Administrative Procedures.
No violations or deviations were identified in these areas.
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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 revi~ewed by personnel other 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 Specification, 10 CFR and Administrative Procedures.
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'No violations or deviations wre identified in these areas.
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4.
Maintenance Observations The-inspector observed portions of the following maintenance activities:
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MWR 81-2698, 'D'. Service Water Pump MWR 82-0334, 'C' Fire Pump
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- MWR - Maintenance Work Request The following Clearance Orders were independently verified for proper placement / restoration of affected components:
82-49, 'D' RHR Service Water Booster Pump 82-68, 'D' Service Water Pump 82-84, 'A' Fire Pump 82-86, 'C' Fire Pump Included with the above were checks for avalability of redundant equipment, adequate safety isolation and clearance, accomplishment of work in accordance with approved procedures and Technical Specificati.on requirements, verification that QC checks were performed as required, cleanliness controls and health physics coverages were adequate.
No violations or deviations were identified in the above area.
5.
Licensee Event Follow Up The following LERs are closed on the basis of the inspector's in-office review, review of licensee documentation, and discussions with licensee personnel:
LER 81-07 Loss of Control Air to #1 Diesel Gen. Combustion Air Inlet Dampers LER 81-17 Failure of RCIC System Steam Supply Valve (M0V-016).to Open LER 81-20 Loss of Control Air to #1 Diesel Gen.
LER 81-22 Electrical Ground in RCIC System Steam Supply Valve (M0V-131).
Motor Operator
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6.
Follow Up of Previously Identified Items a.
Open-Item 8017-02 (Closed) Documentation of Op'erations Testing Following Maintenance of Safety-Related Equipment The NRC inspector reviewed the following Administrative Procedures applicable to this item:
AP 1.7.1, Rev. 2, 09/26/81, Work Item Tracking - Corrective Maintenance AP 1.7.2, Rev. 0, 09/26/81, Work Item Tracking Preventative Maintenance AP 1.7.4, Rev. O, 09/25/81, Special Maintenance Procedures AP 1.7.6, Rev. O, 02/19/82, Maintenance Quality Control Program AP 1.7.7, Rev. 0, 12/28/81, Work Item Tracking - Equipment History
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AP 1.9, Rev. 6, 12/20/78, Surveillance Program The above listed procedures identify and assign responsibility to Maintenance Work Request (MWR) reviewers and approvers relative to listing post-maintenance testing. An MWR is issued for each item or component requiring maintenance.
The procedures also address and require the usage of a Q/C Testing Checklist.
The checklist is used to identify quality control checks prior to, during, and upon completion of essential component repair.
Included with the checks are post-maintenance tests required to prove operability of the affected component. The Q/C Testing Checklist is attached to and becomes an integral part of the MWR package and undergoes the same completion and review process as the MWR.
Prior to declaring a system operable, all MWR packages applicable to that system are reviewed for adequacy and completeness, paying particular attention to individual component operability tests. The Shift Supervisor is responsible for identifying, performing, and documenting any integrated system surveillance tests that might be required as a result of individual component maintenance requirements. To assist the Shift Supervisor in this review, copies of all MWRs are retained in his office until all work items applicable to a specific system are completed. Also, after an extended outage, the maintenance planner provides the Shift Supervisor with a consolidated component work item printout that lists all MWRs performed for each specific system.
The NRC inspector has determined that these measures appear adequate.
b.
Open Item 8017-03 (Closed) Guidance Not Given in Procedures for Use of Vendors Manuals in Place of Written Procedures The NRC inspector has verified by his review of the procedures listed in 6.a above, that adequate guidance is provided to reviewers of Maintenance Work Requests for use in deciding which supporting documents should be required for the performance of a specific maintenance job.
In order to determine whether a maintenance procedure, special test procedure, QC instruction, design change, drawing, and/or vendor's manual is applicable and necessary to ensure quality work, the MWR reviewers are directed to consider factors such as the complexity of the job, the importance of performing the job in specified sequential steps, and the qualifications of the maintenance personnel assigned to the tas.
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7.
NUREG - 0737 Clarification of TMI Action Plan Reouirements a.
Item I.C.6 (Closed) Verify Correct Performance of Operating Activities The NP.C inspector has verified licensee actions with regard to independent verification of operating, maintenance, and surveillance procedures and activities.
The licensee has imposed independent verification requirements within the Safety Clearance Order Program.
Specifically, CNS Administrative Procedure 1.6, Rev. 21, dated October 2, 1981, " Personnel and Equipment Safety,"
requires independent verification of manual valves located in the main flow path of safety-related equipment. Also, any valves, switches, circuit breakers, and other devices whose mispositioning could render any safety-related system inoperable and which are required to be repositioned to facilitate maintenance, are identified on the Safety Clearance Order as a part of the total component or system tagout.
Verification of component or system operability following maintenance is assured through correct use of clearance orders, proper implementation of Maintenance Work Requests and QC/ Testing Checklists identified in 6.a above, and through individual component or integrated system surveillance tests.
Surveillance tests have been reviewed and revised as necessary to include independent verification requirements.
To ensure proper system alignment and operability following an extended outage, complete systems lineup check-lists are performed which include devices that perform actuoting functions for components located within the applicable system.
b.
Item II.B.2.2.B (Closed) Plant Shielding - Modify The NRC inspector has verified licensee actions with regard to this item based upon the following letters:
(1) Pilant to Denton dated January 11, 1980, describes the licensee's review (2)
Ippolito to Pilant dated April 10, 1980, states NRR acceptability of the licensee's review (3) Pilant to Eisenhut dated December 30, 1980, updates the status of this item The licensee stated in their letter that shielding modifications, for the purpose of personnel protection, are not necessary.
Further review of safety systems degradation caused by intense radiation fields is continuing in IE Bulletin 79-01.
c.
Item II.B.3.2.P, (0 pen)
Post Accident Sampling - Modify The NRC inspector has verified that the Reactor Coolant and Containment Atmosphere Post-Accident Sampling System has been installed and is operationa i l
6 The licensee reported completion in a letter from Pilant to Eisenhut, dated December 28, 1981.
The system installation was accomplished under CNS Minor Design Changes80-086 and 81-002.
The NRC Region IV staff has had further discussion with the licensee regarding the operability of the Reactor Coolant Post Accident Sampling System in the event of the loss of offsite power.
This item will remain open pending resolution of this issue.
d.
Item II.F.1.3 (Closed) Accident Monitoring - Containment High Range Radiation Monitor The NRC inspector has verified that the Containment High-Range Radiation Monitoring System is installed and operational.
The licensee reported completion in a letter from Pilant to Eisenhut, dated December 28, 1981.
The system installation was accomplished under CNS Minor Design Change 80-055.
e.
Item II.F.1.4 (Closed) Accident Monitoring - Containment Pressure The NRC inspector has verified installation and operation of the Containment Pressure Monitoring System.
The licensee reported completion per letter from Pilant to Eisenhut, dated December 28, 1981.
The system was installed under CNS Minor Design Change 80-116.
f.
Item II.F.1.5 (Closed) Accident Monitoring - Containment Water Level The NRC inspector has verified installation and operation of the Containment Water Level System.
The licensee reported completion in a letter from Pilant to Eisenhut, dated December 28, 1982.
The system was installed under CNS Minor Design Change 80-116.
8.
Exit Meetings Exit meetings were conducted at the conclusion of each portion of the inspection. The plant superintendent was informed of the above finding _.
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