IR 05000298/1989023

Insp Rept 50-298/89-23 on 890626-30.No Violations or Deviations Noted.Major Areas Inspected:Plant Mods & Licensed Operator Training Program

ML20236E660
Person / Time
Site:	Cooper
Issue date:	07/20/1989
From:	Mckernon T, Seidle W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20236E659	List: IR 05000298/1989023 ML20236E656
References
50-298-89-23, NUDOCS 8907310492
Download: ML20236E660 (5)

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APPENDIX U.S. NUCLEAR REGULATORY COMMISSION

REGION IV

NRC Inspection Report: 50-298/89-23 Operating License: DPR-46 l Docket: 50-298 i Licensee: Nebraska Public Power District P.O. Box 499-Columbus Nebraska 68602-0499 Facility Name: Cooper Nuclear Station (CNS)

Inspection At: CNS, Brownville, Nehrcska Inspection Conducted: June 26-30, 1989 l

Inspector: d -- JL / 7 /Je /49 T. O. McKernopt Reactor Inspector, Test Date *

Programs Section Division of Reactor Safety Accompanied By: W. C. Seidle, Chief Test Programs Section (June 29-30)

Approved: 4 C Y!7 W. C. Seidle, Chief Test Programs Section Date Division of Reictor Safety Inspection Summary Inspectio_n Conducted June 26-30, 1989 (Report 50-298/89-23)

Areas Inspected: Routine, unannounced inspection of the licensee's plant modifications and licensed operators training program Results: Within the areas inspected, no violations or deviations were identified. The licensee's plant modification program appeared to be in conformance with NRC requirements and licensee commitments. To the extent examined and excluding the enclosed observations, the licensee's licensed operators training program appeared sufficien DR ADOCK0500p{8

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DETAILS .i Persons Contacted

• G. R. Horn, Operations Division Manager

• J. M. Meacham, Operations Senicr Manager

• D. C. Shrader, Assistant to Operations Superintendent

• J. R. Elaherty, Plant Engineering Supervisor

• R. J. Mcdonald, Chemistry Supervisor

• R. L. Gibson, Audit and Procurement Quality Assurance (QA) Supervisor

• S. J. Jobe, Acting Training Manager G. Hanson, Engineer D. Warner, Training Specialist NRC

• B. Bennett, Senior Resident Inspector

• G. A. Pick, Resident Inspector

• J. B. Nicholas, Reactor Inspector, RIV

• Denotes those attending the exit interview on June 30, 198 . Facility Modifications (37701)

This portion of the inspection involved the review of the licensee's fecility modificatic, program to ascertain conformance with regulatory requirements, Technical Specifications (TS), and applicable codes and standards. During the inspection, the NRC inspector reviewed the following design change packages:

DC 86-21, Part II, " Alternate Shutdown," completed January 13, 198 *

DC 88-156, "250 VDC Station Service Batteries IA and IB " completed June 15, 198 * DC 87-171, "EPCI Min. Flow Valve Modification," completed May 27, 198 DC 85-112. " Critical AC Bus Breaker and Fuse Coordination Modification," completed February 17, 198 During the review, the NRC inspector examined installation records,

epplicable design change calculations, acceptance . test results, and l appropriate es-built drawings. The NRC inspector verified that the i

licensee had revised control room blue-line drawings and trained control room operators on the design changes prior to resuming operation of the facility. The licensee's safety evaluations and fire protection analysis appeared sufficient and documentation was approved and authorized by the appropriate key manager _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ - - _

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-3-A review of Design Change 86-21, Part II, " Alternate Shutdown," initially identified potential areas of concern related to the licensee's fire protection strategy. The NRC inspector identified an internal memorandum which addressed fire disablement of high pressure coolant injection valve (HPCI)-MOV-M014 Power Cables MR54 and MR55. Furthermore, the memorandum stated that the fire protection strategy would be accommodated for Design Change 86-21 by manually closing HPCI-MOV-M014 (steam supply to HPCI turbine) in a post-fire conditio In discussions with the licensee and by review of Emergency Procedure 5.4.3.1, " Post-Fire Shutdown Outside

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Control Poom," the NRC inspector verified that a condition requiring l manual operation of components inside the reactor building had been i proceduralized. The NRC inspector had no further questions regarding the l alternate shutdown modificatio DLring review of Design Change Package DC-156, the NRC inspector noted that an Abnormal Procedure A.P.2.4.6.9, "250 VDC System Failure," was identified as a procedure requiring revisio Identification of documents requiring revision, which are needed following completion of the design change, is required by CNS Engineering Procedure 3.4.3, " Design Change,"

Revision 0, dated December 5, 1988. Furthermore, CNS TS 6.3.2 requires, in part, that written procedures shall be established, implemented, and maintoined for actions to be takcn to correct specific cnd foreseen pctential or actual malfunctions of safety-releted systems. As of the inspection exit interview, the above identified abnormal procedure had not been revised, issued, and control room operators trained. In response to the concern, the licensee stated at the exit interview that because the third battery charger was not credited as a safety-related component the abnormal procedure did not require revision and, as such, had not yet been issued under a new revision. The NRC inspector stated that the abnormal procedure was identified in the design change package es a procedure requiring revision. Furthermore, whereas the Design Change 88-156 addition of the third battery charger, singularly, may not be a safety-related component, the design change does affect the Division I and 11 station battery system In addition, if, in-fact, the abnormal procedure did not require revision, then the procedure should have been deleted from the design change package in accordance with an on-the-spot change (OSC).

The requirement for revision and operator training on the cited Abnormal Procedure A.P.2.4.6.9 and/or the requirement for deletion from the design change package shall remain an unresolved item pending further review by the NRC inspector. The licensee committed at the time of the exit interview to resolve the above concern with the NRC senior resident inspector as soon as possible. (298/8923-01)

3. Licensed Operator Training (41701)

This portion of the inspection involved a review of the licensee's licensed operator training program. During the inspection, the KRC inspector reviewed the following procedures and job performance measures (JPM):

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. General Observations During the inspection period June 29-30. 1989, the NRC Region IV Test Programs Section Chief conducted a walkdown inspection of major reactor plant areas. The NRC Section Chief noted that the licensee generally maintained good housekeeping and those individuals interviewed appeared knowledgeable of their responsible disciplines. No areas of concern were identifie . Exit Interview l The NRC inspector met with licensee representatives denoted in paragraph I on June 30, 1989, and summarized the scope and findings of this inspectio The licensee did not identify as proprietary any of the information provided to, or reviewed by, the inspecto !

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