IR 05000298/1990031

Sys Entry & Retest Insp Rept 50-298/90-31 on 900910-14 & 17. No Violations Noted.Major Areas Inspected:Sys Entry Retest in Areas of Design Changes,Temporary Design Changes & Maint Activities

ML20059M742
Person / Time
Site:	Cooper
Issue date:	09/26/1990
From:	Kelley D, Murphy M, Seidle W, Singh A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML20059M741	List: IR 05000298/1990031 ML20059M739
References
50-298-90-31, NUDOCS 9010050233
Download: ML20059M742 (9)

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APPENDIX

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U.S. NUCLEAR REGULATORY COMMISSION

REGION IV

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t NRC Inspection Report: 50-298/90-31 Operating License:' DPR-46 Docket: 50-298 .l Licensee: NebraskaPublicPowerDistrict(NPPD)  !

P.O. Box 499 .

Jolu ^us, Nebraska 68602-0499 '!

Facility Nane: CooperNuclearStation(CNS) f Inspection At: CNS, Brownville, Nebraska inspection Conducted: September 10-14, 1990, Onsite -

September 17, 1990, Inoffice

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Inspectors: 4 # "/ # O

'M.' E . Murp ,43eac)6r rector, Test Programs Date / ;

Section Division of eactor Safety Alth .

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D.1. Kelley, RWactor Tqspector, Jfst Programs Y 98 DKte /

Section,DivisionoffeactorSyety ,

b b 7, j 9/M /9e A. Singh, Reactbt Inspector rTest Programs Date /

Section Division of Reactor Safety

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h Accompanying Personnel: W. C. Seidle, Chief, Test Programs Section, Division of Reactor Safety (September 13-14, 1990)

ArDroved: / [ = ~, C M2 4 /90 -

W. C. Seidle, Chyf, Test Programs Section Date Division of Reactor Safety 9010050233 900929 PDR ADOCK 05000298 PDC t

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f In_spection Summary inspection Conducted September 10-14, and September 17. 1990 (Report 50-298/90-31) ;

Areas Inspected: Routine, announced inspection for system entry retest (SERT) !

in the areas of design changes, temporary design changes, and maintenance !

activitier, i Results: The licensee had a good program for determining the need for retest [

and the identification of the appropriate retest type. Retest requirements -l were. satisfactorily addressed in the areas of design changes, temporary design changes and maintenance work. Responsibilities were defined and personnel ;

training and experience were good at all levels of involvenen l No violations or deviations were identified, f i

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DETAILS

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s i- PERSONS CONTACTED 'I

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NPPD f i

R. Alexander, Maintenance Planner / Scheduler ,

• L. Bray, Pegulatory Compliance Specialist >

• R. Brungardt, Operations Manager  !

• J. Flaherty, Engineering Manager .

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• S. Freborg, Acting Plant Engineering Supervisor

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• R. Gardner, Senior Manager of Operations ,

• R. Gibson, Audit and Procurement Quality Assurance Supervisor '!

• H. Hitch, Plant Services Manager i

• G. Horn, huclear Power Group Manager l

'J. Hotovy, Nuclear Engineering Division, Project Engineer '

• R. Jansky, Outage and Modification Manager

• R. Krause,' Maintenance Engineer -

• J. Meacham, Division Manager of Nuclear Operations ,

• C. Moeller, Acting Senior Manager, Staff Support  ;

• 5. Peterson, Senior Manager Technical Support '

• M. Siedlik, Acting Nuclear Engineering Division Site Manager

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• M. Unruh, Acting Maintenance Manager ,

. NRC' I

.R. Bennett, Senior Resident inspector

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• G. Pick, Resident InQs ctor .

-* Denotes those attending the exit meeting on September 14, 1990. j

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, INSPECTION OBJECTIVES AND METHOD

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The overall objective of this inspection was to determine the licensee's performance in the area of system entry retest identification, documentation,-

and performanc To. accomplish this objective, the inspectors determined that retest "

requirements were evaluated during design change and maintenance planning and m . that the retest procedures met regulatory requirements, commitments, and i industry guides and s',vndards. It was also determined that retest requirements were considered for ali system boundary violations. -The inspectors further i verified that the retests proved operability and assured that the design basis

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was satisfied for structures, systems, and components that were modified or l l

subjected to maintenanc ] l

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The inspectors reviewed the licensee's administrative procedures for design changes, temporary design changes, plant tr.mporary nodifications, and maintenance. These procedures are listed in Attachment j Design changes and maint. nance work items accomplished during the last refueling outage were assessed, and the inspectors selected 12 design changes and 15 maintenance work requests for detailed review. Six temporary design  ;

changes (TDC) were selected from the list of outstanding TDCs for detailed review. The selected items are l'sted in Attachment . INSPECT 10fl FINDINGS SUMMARY t The licensee was found to have a good program for identifying retest requirements and for the planning, developing and performance of retest  :

procedures. Retest requirements were satisfactorily addressed in the areas of design changes, temporary design changes, and maintenance wor ;

pesponsibilities are defined and personnel training and experience were found

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to be good at all levels of involvemen *

No violations or deviations were identified during the inspectio . MODIFICATIONS (72701)

The purpose of this part of the inspection was to determine the process by which a design change is developed, reviewed, installed, and testeo prior to final close out of the modification packages. The inspector reviewed 12 plant design change packages and the associated retest packages. These design change  ;

packages are listed in Attachment )

The most extensive modification reviewed, DC8G-053B, involved the installation and modification of essential ventilation systems which provided cooling to the critical AC switchgear roons and the 903'-0" elevation of the control building under normal and accident conditions. This control building essential ventila- .

tion system utilized a network of supply and exhaust fans to remove heat generated by both the essential and normal electrical eqt gment. This design  :

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change provided additional cooling to the critical AC swicchgear roons. During the review of the package, the inspectors requested additional information, which was provided just prior to the exit meeting on September 14, 1990.

l Therefora, the review was completed in the NRC Region IV office on September 17, 1990. The inspectors found that appropriate tests had been specified and performed to assure the operability of the system. Appropriate tests had also .

been identified and performed on the fire dampers associated with the design change modification, i

l The inspectors found that all of the design change packages listed in Attachment B were prepared in accordance with the Cooper Nuclear Station's procedures. In each instance, operability of the component and/or system had L been verified upon completion of the required testing. The boundaries .

L established for the testing were appropriate. Test exceptions were identified l

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and dispositioned. The tests reviewed contained appropriate system restoration instructions as well as turnover to operation.; procedures for the modified system. The tests reviewed included mechanical, electrical, and instrumentation I and control testing. The inspectors noted that provisions had been made to revise instructions, procedures, and drawings prior to operation of the modified !

systems or components. The inspectors did not identify any discrepant es Juring the test. The test results met the acceptance criteria of the ces ;

No violations or deviations were ifentified in the review of this program are . MAINTENANCE (62700,6?702)  !

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The inspectors evaluate examined the methods the to in place lictosee's maintenance program control post-maintenance to (PMT tes+1ng identify)and

. Addi- i tional examinations were conducted of 15 completed nintenance work requests (MWR) !

to evaluate the implementation of post-maintenance test requirement The documents examined by the inspectors are included in Attechment.D to this -

report.- Maintenance Procedure 7.0.1.2, "Maintehance Work Requests - MWR Generation and Review," identified the personnel responsible for and the steps to ensure that post-maintenance testing requirements were evaluated for the scope of work performed. The MWR cover sheet cont 31ned a check off for FVT in i the planning and post-work review stag Specific guidance for post-maintenance testing was contained in >

Procedure 7.0.5, " Post Maintenance Testing." The procedure contained detailed instructions concerning responsibilities, delayed testing, resolution of failed tests and completed work package review as it pertains to PMT. Requirements for PMT were listed on the post-maintenance testing check sheet which was an attachment to the procedure. The procedure also contained a post-maintenance test guide, which lists maintenance activities with appropriate tests, and a test ,

matrix-for in-service and non-in-service testing of pumps and valve .

To determin; the effectiv- ass of the PMT implementation, the inspectors selected 15 completed work packages performed during the last refueling outag The review consicted of verifying that PMT was considered during the planning stage, the PMT's were listed on the check sheet, the check sheet was attached to the work package, and the testing specified was appropriate to the work *

performed. Six of the work packages had no PMT specified. The inspectors -

concluded af ter reviewing the scope of the work performed that PMT was not require The conclusion reached by the inspectors was that post-maintenance testing-control was suffleiently detailed to ensure that thorough reviews were l performed and appropriate PMT was included on the MWRs. Also, the tests

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specified were perforted, well documented, and reviewed in detai No violations or deviations were identified in the review of this program are e T

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6- TEMPORARY DESIGN CHANGE TESTING (72701)

The inspectors reviewed the licensee's temporary nodification program, which is comprised of two classifications of terporary changes. The first is called a plant torporary nodification (PTM) and the second a temporary design change (TDC).

This program is described and administrative 1y controlled by the plant procedores listed in Attachment The licensee defines PTMs as temporary minor alterations made to the plant that do not confern with approved drawings, procedures, or. other design document Examples are lif ted 1 cads, electricallumpers, and fuse renoval. ' Temporary design changes are changes to the plant needed to add temporary utilities, temporarily rectify a deficient situation, or add equipment on a trial basis after performing a special test procedure, pTMs are norra11y initiated by operations personnel and TDCs are initiated-by an approved engineering work reques The licensee maintains good control over the use of pTMs and TDCs. At the time of this inspection there were only 2 open PTMs and 23 open TDCs. Of these open items, the inspectors selected six TDCs for indepth review. The packages were found to be complete and met the requirements set forth in the licensee's administratise procedures. Testing requirements had been specified and were found to be appropriate to the work performe No violations or deviations were identified ia the review ~of this program are . EXIT MEETING An exit meeting was held September 14, 1990, with the individuals denoted in paragraph 1 of this report. At this meeting, the scope of the inspection and the findings were summarized. The licensee did not identify as proprietary any of'the information provided to, or reviewed by, the inspector !

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ATTACHMENT A r

! Procedures Reviewed No.- Title >

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2. Plant Temporary Hodific: tion Control, Re 'sion 12 ,

t 3.25 Replacement Component Evaluation, Re.ision 1 Station Modifications, Revision 12  ;

3. Design Change, Revision 1  :

l-- 3. Implementation and Acceptance Testing Activities  :

3. Temporary Design Change, Revision 3 i

3. Equipment Specification Change, Revision 0 s 3.4.10 Revisions, Amendments, and On-The-Spot Changes, i

Revision 1 3.4.11 Status Reports, Revision 1 ,

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7. Post Maintenance Testing, Revision 2 ,

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7.0. Maintenance Work Request - MWR Generation and Review

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s ATTACHMENT B i l

Docurents Reviewed

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, Design Change N Title ,

ESC 90-172 Drywell Personnel Airlock Upgrade

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ESC 90-139 RCIC Rack Starter Replacement DC 89-156 Torque Switch Bypass Jumper DC 90 001 Alternate Means of Boron Injection '

DC 88-053B Essential Control Building Ventilation System DC 88-053A Control Building Essential HVAC System t DC 89-285 CRD Testable Check Valve Assembly DC 89-252A Trim Modifications to RHR Valves 34A, B and 27A & B

DC 88-029 Redundant Power to Emergency Supply Fan HV-MDT-(BF-C-M)

DC 88-302A Pipe support Modifications

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DC-87-015M CNS Annunciator Upgrade DC 87-015D CNS' Annunciator Upgrade Project Panel 9-3 ,

MWR Packages N Title

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MWR 90-0064 Core Spray Pump B Test Line Isol an MWR 90-0172 Hi Drywell Press & Reactor Low Level Relay I

MWR 90-0123 Suppression Chamber Spray Loop A Inboard l' Throttle ,

MWR 90-0101 Limitorque SBM-000 Actuctor for Drywell Dilution Supply ISO MOV MWR 90-0309 Core Spray Pump Motor

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MWR 90-0361 HPCI & RCIC Exhaust Vacuum Bkr MWR 90-0351 RCIC Barometric Condenser and Vacuum Relief NWR 90-0871 Diesel Generator Diesel Engine l

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MWR 90-1200 DGI Starting Air Compressor and Diesel ,

MWR 90-1212 Core Sprav Pumps A & B Test Line-

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MWR 90-1494 Scram Inlet .

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MWR 90-1650 Splices on Drywell Side Terminal Box of .!

Penetration X100E  !

t MWR 90-1804 Rose Mount Transmitters

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MWR 90-1881 Torus to'Drywell Yacuum Breaker r

MWR 90-1897 Core Spray Pump B Discharge Relief ;

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Temporary Design Changes ,

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TDC 90-300 MCCX Transfer Switch kodification TDC 90-119 Control Room HV Supply Fan Damper Blocking

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'o TDC 90-144 DW System 11" Valve Installation

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TDC 89-096 Valve. Shaft Clamp For CW-MOV-102MV

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a TDC 89-110 Low Flow Alarm in HV-C-1A Unit-

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TDC 90-106 RRMG-TS-4B With Short Sensor

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