IR 05000298/1987026
| ML20236R711 | |
| Person / Time | |
|---|---|
| Site: | Cooper  |
| Issue date: | 11/09/1987 |
| From: | Bennett W, Madsen G, Plettner E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20236R697 | List: |
| References | |
| 50-298-87-26, NUDOCS 8711230441 | |
| Download: ML20236R711 (6) | |
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.i APPENDIX U. S. NUCLEAR REGULATORY COMiilSSION
REGION IV
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NRC Inspection Report:
50-298/87-26 License: DPR-46
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Docket: 50-298 Licensee: Nebraska Public Power District (NPPD)
P. O. Box 499 Columbus, NE 68601
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Facility Name: Cooper Nuclear Station (CNS)
Inspection At: Cooper Nuclear Station, Nemaha County, Nebraska
Inspection Conducted:
October 11-31, 1987 Inspectors:
. N. M
/0/30/17 E. A. Piettner, Resident Inspector, (RI)
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1I/a./yy i..~ k. Bennett, Senfor Resident Inspector, (SRI)
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G. L. $Idsen,'TiffRg~Cfiief, Project section c.
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Reactor Projects' Division
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8711230441 871118 gDR ADOCK 05000298
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-2-Inspection Summary l
Inspection Conducted October 11-31, 1987 (Report 50-298/87-26)
Areas Inspected:
Routine, unannounced inspection of licensee actions on
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previous inspection findings, monthly surveillance and maintenance J
observations, operational safety verification, radiological protection, and l
secu rity.
I Results: Within the areas inspected, no violations or deviations were identified.'
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-3-DETAILS
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Persons Contacted Principal Licensee Employees
- G. R. Horn, Division Manager of Nuclear Operations
- L. E. Bray, Regulatory Compliance Specialist
- R. Brungardt, Manager, Operations
- D. Norvell, Manager, Maintenance
'The NRC inspectors also interviewed additional licensee. personnel during the inspection period.
- Denotes those present during exit-interview on October 30,1987; 2.
Licensee Action on Previous Inspection Findings a.
-(Closed) Unresolved 298/8703-04:. Regulatory Conflicts in Regard to
Operability of Appendix "R" Systems.
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This item involved conflicting regulatory requirements concerning I
shutdown cooling primary containment isolation valve RHR-M0-17. The l
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review was conducted by the NRC office of Nuclear Reactor Regulation (NRR). Results of the review were documented in a letter
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from NRR to Resident Inspector, Cooper Nuclear Station (CNS), dated l
October 14, 1987. The NRC project manager for CNS stated that
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RHR-M0-17 while in its normal de-energized position, is capable of j
performing its required safety function and is therefore operable.
RHR-M0-17 being operable, the licensee is not required to log the position of RHR-M0-18 daily.
This item is closed.
b.
(Closed) Open Item 298/8704-01:
Shelf for Procedures and Prioritization of Valve Lineups.
This item involved the prioritization of valve lineups in Emergency.
Procedure (EP)5.4.3.2, " Post-Fire Shutdown to Cold Shutdown Outside Control Room," and the installation of a' shelf for procedures in the alternate shutdown room. Corrective actions included the following:
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A revision dated February 26, 1987, was made to EP 5.4.3'.2 which.
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established valve priority.
A movable podium to hold the required emergency procedures was
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located in the alternate shutdown room.
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The'RI reviewed the above licensee actions and determined that those actions were completed and adequate.
l This item is closed.
c.
(Closed)OpenItem 298/8704-02:
Implementation of Fuse Replacement Controls.
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This open item' involved.the implementation of fuse replacement controls' by the licensee.. Corrective actions 11ncluded the following:
i Revision 4 to Conduct of Operations Procedure 2.0.1, '!0perations
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Department Policy," was issued _on.May 7, 1987, establishing controls to assure blown fuses are replaced with a fuse of.the q
same type and size; and specifying'that an engineering i
evaluation should be performed'if a blown fuse results.in the
issuance of a Nonconformance Report.
d Revised CNS electrical drawings to include. fuse type and size
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information The RI reviewed the above licensee corrective actions and determined those actions to be completed and adequate.
i This item is closed, d.
(Closed)OpenItem 298/8621-02: kechnicalSpecification(TS)
l Discrepancies Concerning Reactor Coolant System (RCS) Unidentified Leak Rate.
This open item contained three separate items.
Items No. 1 and 2 involved Standard Technical Specification and CNS TS differences.
These differences have been resolved through the reissuance'of
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page 135 to CNS TS.
Item 3 involved containment inerting required in l
CNS TS 3.7.A.5.b and subsequent limiting conditions for operations.
This item was resolved in a letter from the NRC office of NRR to the Deputy Director, Division of Reactor Safety and Projects, Region IV, dated March 20, 1987.
The letter contained guidance for interpreting the TS requirement. No permanent or emergency TS change was required.
This item is closed.
3.
Monthly Surveillance Observation The NRC inspectors observed required Technical Specification: surveillance-testing and verified that testing was performed in accordance with
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adequate procedures, that test instrumentation was calibrated, that limiting conditions for operation were met, that removal and restoration of the affected components were accomplished, that test results conformed with technical specification and procedure requirements and were reviewed by personnel other than the individual directing the test, and that any
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-5-deficiencies identified during the testing were properly reviewed and resolved by appropriate management personnel.
The NRC inspectors observed the following surveillance activities on the
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indicated date:
J October 13, 1987:
Surveillance Procedure (SP) 6.4.8.10. " Main Turbine Orain Valves Functional Test," Revision 3, dated February 20, 1987 October 14, 1987:
SP 6.1.9, " Reactor Vessel Low-High Water Level Calibration and Functional / Functional Test," Revision 20, dated March 13, 1986 October 27, 1987:
SP 6.3.12.1, " Diesel Generator Operability Test,"
Revision 21, dated July 30, 1987 l
No violations or deviations were identified in this area.
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4.
Monthly Maintenance Observation
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Station maintenance activities of safety-related systems and components were observed and reviewed by the NRC inspectors to verify that they were l
conducted in accordance with approved procedures, regulatory guides and industry codes or standards and in conformance with Technical Specifications.
The following maintenance activities were observed and reviewed:
i October 20-23, 1987: WorkItem(WI) 872614 "RHR Service Water Booster Pump D," dated August 14, 1987 using Maintenance Procedure (MP) 7.2.14,
"RHR SWBP Overhaul and Replacement," Revision 11, dated October 8, 1987 No violations or deviations were identified in this area.
5.
Operational Safety Verification The NRC inspectors observed operational activities throughout the inspection period.
Control room activities and conduct were observed to be well controlled, Proper control room staffing was maintained.
Discussions with operators determined that they were cognizant of plant status and understood the importance of and reason for each lit annunciator. The NRC inspectors observed selected shift turnover meetings and noted that information concerning plant status was properly communicated to the oncoming operators.
Maintenance requests were reviewed to verify that appropriate priority was assigned and that the maintenance was performed in a timely manner.
Tours of accessible areas at the facility were conducted to confirm operability of. plant equipment including the fire suppression systems and other emergency equipment.
Controls were adequate to ensure a safe working environment.
Facility operations were performed in accordance
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-6-with the requirements established in the CNS Operating License and TS.
Overall plant cleanliness was good.'
No violations or deviations were identified in this area.
6.
Radiological Protection Observations o
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The NRC inspectors verified that selected activities of the licensee's radiological protection program were implemented in conformance with facility policies, procedures, and regulatory requirements.
The NRC inspectors verified that radiation work permits contained the appropriate information to ensure work was performed in a safe and controlled manner; personnel in radiation controlled areas (RCA) were wearing the. required personnel monitoring equipment and protective clothing; radiation and/or contaminated areas were properly posted and controlled based on the activity levels within the area; and radiation monitors were being properly utilized to check for contamination.
No violations or deviations were identified.
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Security The NRC inspectors observed security personnel perform their duties of and escorted or controlled within the protected area (properly authorizedPA). The vehicle, personnel and package search.
Vehicles were had adequate illumination and and the isolation zones were free of transient material.
Compensatory measures were implemented in a timely manner when equipment failed. These observations verified that the physical security plan was being implemented in accordance with the requirements established in the CNS Operating License.
No violations or deviations were identified in this area.
8.
Exit Interview An exit interview was conducted on October 30, 1987, with licensee representatives (identified in paragraph 1).
During this interview, the senior resident inspector and the resident inspector reviewed the scope and findings of the inspection.
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