IR 05000298/1981012
| ML20010A426 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 07/21/1981 |
| From: | Dubois D, Westerman T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20010A422 | List: |
| References | |
| 50-298-81-12, NUDOCS 8108110422 | |
| Download: ML20010A426 (6) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION IV
Report No. 50-298/81-12 Docket No. 50-298 License No. DPR-46 Licensee:
Nebraska Public Power Distri:t P. O. Box 499 Columbus, Nebraska 68601 Facility Name:
Cooper Nuclear Station Inspection At:
Cooper Nuclear Station, Nemaha County, Nebraska Inspection conducted:
May 31 - June 30, 1981 7,//13 h./.,__
7-2/- F/
n c or:
D. L.~DuBois, Resident Reactor Inspector Date Prcjects Section No. 1 Accompanying 7- [ /Ad/b_
Personnel:
7-2 /- f /
T. F. Westerman, Chief Date Projects Section No. 1 Inspection Summary Inspection on May 31 - June 30, 1981 (Report No. 50-298/81-12)
Areas Inspected:
Routine, announced inspection of operational safety verifi-cation; monthly equipment surveillance and maintenance observations; plant design changes; reactor scram review; administrative and startup procedures
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review; radioactive solid waste storage, handling and shipping; follow-up to bulletins, orders of modification and TMI action plan requirements.
This inspection involved 105 inspector hours on site by two NRC inspectors.
.Results: Within the areas inspected no violations or deviations were identified.
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8108110422 810723 PDR ADOCK 050002984 G
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DETAILS 1.
Persons Contacted
- L. Lessor, Plant Superintendent P. Borer, Engineer Supervisor R. Brungardt, Surveillance Planner R. Creason, Operations Supervisor D. Majeres, Maintenance Planner L. Bednar, Electrical Engineer J. Weaver, Licensing Manager J. Sayer, Chemistry and Health Physics Supervisor
- Indicates presence at exit meetings.
2.
Operational Safety Verification The NRC inspectors observed control room operations, instrumentation, controls, end reviewed applicable logs and conducted discussions with control room operators.
The inspectors verified operability of the Standby Liquid Control System, 'A' Core Spray System (M), 'B' Core Spray System (W), Nuclear Instrumentation /Incore Monitoring Systems and reviewed tagout records and verified proper return to service of affected components.
They also verified that maintenance requests had been initiated for equipment discovered to be in need of maintenance, that the appropriate priority was assigned and that maintenance was performed in a timely manner commensurate with the priority assigned.
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 cr deviations were identified in these areas.
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3.
Inspection of Solid Radioactive Waste Handling and Shipping Activities The NRC inspector witnessed activities concerning preparation for and
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subsequent handling and shipping of solid radioactive waste material.
Specifically, he observed that the waste material was properly classified, described, packaged, stored, handled, labeled, surveyed, documented and transported.
The transport vehicle and cask were also inspected and surveyed prior to and subsequent to loading.
The above shipment, No. 81-34, consisted of exclusive use, open transport, LSA material that was batched, mixed and solidified in seven 55 gallon D0T-174 barrels.
This shipment left the site June 25, 1981.
This inspection was conducted to verify conformance with 10 CFR, Technical Specifications and Administrative Procedures.
No violations or deviations were identified.
4.
Surveillance Observations The inspectors observed portions of Technical Specification required surveillance testing to verify that testing was performed in accordance with adequate procedures, that test instrumentation was in calibration, that Limiting Conditions for Operations were met, that removal and restora-tion of the affected components was accomplished, that test results conformed with Technical Specifications and procedure requirements and were reviewed by personnel other than the person directing the test, and that any deficiencies identified during testing were properly reviewed and resolved by appropriate management personnel.
The following tests were selected and observed in part:
S.P. 6.3.3.1 HPCI Test Mode Surveillance Operation S.P. 6.3.10.13 SDV Vent and Drain Valves Cycling and Open Verification Test S.P. 6.3.18.1 Service Water Pump Operability Test 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 areas.
5.
Maintenance Observations The inspectors observed portions of the following maintenance activities:
MWR #81-1180 'D' SW Pump Discharge Check Valve Replacement
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MWR #81-0422 Reactor Building Fire Protection System G5 Sprinkler Head MDC #81-097 Torus Saddle Modification The following Clearance Orders were reviewed:
C.0. #81-357 Fire Protection System #35 C.0. #81-364 Rod 42-27 HCU C.0. #81-372 Rod Equalizing Valve C.0. #81-373 'O'
SW Pump Included with the above were checks for availability of redundant equip-ment, adequate safety isolation and clearance, accomplishment of work in accordance with approved procedures and Technical Specification require-ments, verification that QC checks were performed as required, clean-liness controls and health physics coverage was adequate.
No violations or deviations were identified in the above areas.
6.
Plant Scram - Safety System Challenge The inspector reviewed records and interviewed plant personnel concerning an unscheduled reactor scram which occurred from power on June 12, 1981, at 11:09 a.m. (Scram Report #81-2).
The cause of scram was operator error, i.e., instrument technician failure to follow procedure.
All systems functioned as designed.
Appropriate corrective action was taken prior to restarting the facility.
No unreviewed safety questions w re discovered.
7.
Review of Plant Operations The inspector reviewed the following administrative and startup procedures:
1.4 Station Rules of Practice 1.6 Personnel and Equipment Safety
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1.7 Station Maintenance 1.7.1 Work Item Tracking 1.16 Hydrostatic / Leak Test 2.1.1 Cold Startup Procedure 2.1.1.2 Technical Specifications Pre-Startup Checks 2.1. 3 Approach To Critical 2.1.19 Nuclear Fuel Preconditioning 9.1.1.4 Special Work Permit 10.9 Control Rod Scram Time Evaluation The inspection was performed to review changes to the licensee's administrative controls, startup procedures and system checklists used for returning safety-related systems 9. w vice following refueling outage maintenance of system disturbance W4 review included
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verification that startup and power operat.~on procedures prerequisites met Technical Specification requirements.
No violations or deviations were identified.
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IE Bulletin 79-26 Rev. 1, Boron Loss From BWR Control Blades A representative from the licensee's licensing group stated that a reply to Revision 1 would be submitted.
$rder of Modification of BWR Scram Discharge System (Lu Air Pressure
9 cram) dated January 9, 1981
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The inspector has verified that:
(1) Surveillance Procedure #6.1.34, Rev. O, Low Air Pressure Scram Functional Test dated June 10, 1981, has been written, approved and distributed; (2) NPPD Special Order #81-6 NRC Order of Modification dated June 25, 1981 has been written, approved, and distributed.
This review closes NRC Open Item 8110-05.
10.
TMI Action Plan Item II.E.4.2 Attachment 1, October 23, 1979, Interim Position for Containment Purge and Vent Valve Operation Pending Resolution of Isolation Valve Operability.
Status In the licensee's December 18, 1979 letter (Pilant, NPPD to Ippolito, NRR) commitments were made as folicws:
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Limit Purges to a Minimum:
During inspection 50-298/80-01, the licensee's
commitment to limit purges was reviewed.
Exception was taken by the NRC inspector to venting the containment to preclude an isolation.
This issue was resolved prior to the inspector leaving the site.
Limit Opening of Purge and Vent Motorized Valves to 60 Open:
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The NRC inspector reviewed Maintenance Work Request (MWR) 80-1-21.
In accordance with Speciai Procedure 80-1, the notorized valves associated wi containment purge and vent were set for a maximum opening of 45 Diverse Containment Isolation:
During inspection 50-298/80-16
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the inspector determined that Minor Design Change 79-51 for modification of the PCIs had been completed.
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Installation of SGTS By-Pass Valves:
In the December 30, 1980 letter
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(Pilant, NPPD to Eisenhut, NRR), the licensee committed to install by pass valves in the SGTS for venting. The NRC inspector verified that MDC 80-003 has been completed, although the completion report was still in preparation.
The inspector verified that:
Design change was properly reviewed and approved.
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MDC 80-003 was reviewed and approved by the SORC on April 25, 1981, in accordance with Administrative Procedure 1.13.
Accomplished in accordance with approval procedures
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Work performed in accordance with MDC 80-003.
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Test results reviewed and evaluated.
Testing included NDT and pneumatic was satisfactorily completed.
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Operating procedure revised.
Procedure revision still pending completion report.
As-built drawings revised.
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Issuance of Drawing Charge Notices still pending completion report Training provided to operations personnel.
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Training is pending issuance of completion report.
The procedure and drawing revision, and training associated with MDC 80-003 will be carried as an open item (8112-01).
11.
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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