ML20045G480

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Forwards Meeting Summary for Mgt Meeting Conducted on 930622 in Brownville,Ne Re Licensee Actions to Correct Plant Deficiencies Prior to Start Up from Current Refueling Outage.Meeting Beneficial
ML20045G480
Person / Time
Site: Cooper Entergy icon.png
Issue date: 07/08/1993
From: Beach A
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To: Horn G
NEBRASKA PUBLIC POWER DISTRICT
References
NUDOCS 9307140023
Download: ML20045G480 (76)
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Text

{{#Wiki_filter:- f UNITED ST ATES y e Rfc ?g NUCLEAR REGULATORY COMMISSION ) T' l REGION IV ~?\\. E d ,E 611 RYAN PLAZA DRIVE, SUITE t.00 J g AR LINGTCN. TEXAS 760114064 JUL - 8 1993 Docket: 50-298 License: DPR-46 Nebraska Public Power District ATTN: Guy R. Horn, Nuclear Power Group Manager P.O. Box 499 Columbus, Nebraska 68602-0499

SUBJECT:

MANAGEMENT MEETING This refers to the management meeting conducted on June 22, 1993, at the Cooper Nuclear Station, Brownville, Nebraska, concerning activities authorized by NRC License DPR-46 for the Cooper Nuclear Station. This meeting addressed the licensee's actions to correct plant deficiencies prior to start up from the current refueling outage. These ceficiencies are identified and discussed in Nebraska Public Power District letters dated April 29, June 7, and June 22, 1993. Meeting participants are listec in Attachment I to the Meeting Summary. This meeting was open for public observation. The subjects discussed at this meeting are described in the enclosed meeting summary. It is our opinion that this meeting was beneficial and has provided a better understanding of your corrective actions. As discussed, some actions were not fully completed. I understand that jou will notify us when these actions are completed so that we can make our final determination on plant start up. In accordance with Section 2.790 of ine NRC's " Rules of Practice," Part 2, Title 10. Code of Federal Regulations. a copy of this letter will be placed in the NRC's Public Document Room. Should you have any questions concerning this matter, we will be pleased to discuss then with you.

erely, I,g g

Bill Bcach, Ehrector n. Division of Reactor Projects

Enclosure:

Meeting Summary w/ attachments 9307140023 930708 PDR ADDCK 05000298 PDR p

,.) ~ 1 i Nebraska Public Power District cc w/ enclosure: Nebraska Public Power District ATTN: G. D. Watson, General Counsel P.O. Box 499 Columbus, Nebraska 68602-0499 Cooper Nuclear Station ATTN: John M. Meacham, Site Manager P.O. Box 98 Brownville, Nebraska 68321 l Nebraska Department of Environmental Control ATTN: Randolph Wood, Director P.O. Box 98922 Lincoln, Nebraska 68509-8922 Nemaha County Board of Commissioners ATTN: Richard Moody, Chairman Nemaha County Courthouse 1824 N Street Auburn, Nebraska 68305 Nebraska Department of Health ATTN: Harold Borchert, Director j Division of Radiological Health 301 Centennial Mall, South P.O. Box 95007 Lincoln, Nebraska 68509-5007 Kansas Radiation Control Program Director

s lcl / l JUL -8 503 Nebraska Public Power District bcc to DMB (IE01) \\ \\ bcc distrib. by RIV: J. L. Milboan Resident Inspector Section Chief (DRP'C) Lisa Shea, RM/ALF, MS: MNBB 4503 MIS System DRSS-FIPS Section Chief (DRP TSS) Project Engineer (DRP/C) RIV file Senior Resident Inspector - River Bend Senior Res cent Inspector - Fort Calhoun l 130005

h. / */ JUL -8 1993 Nebraska Public Power District bcc to DMB (IE01) bcc distrib. by RIV: J. L. Milhoan Resident Inspector Section Chief (DRP/C) Lisa Shea, RM/ALF, MS: MNBB 4503 MIS System DRSS-FIPS Section Chief (DRP/TSS) Project Engineer (DRP/C) RIV File Senior Resident Inspector - River Bend Senior Resident Inspector - Fort Calhoun D1TQ, A RIV:fI:13RP/C C:DRP/C /> / EEdfb;df JEGagh[rdo kB[kbb 7/T/93 7/f//3 3 h

II = MEETING

SUMMARY

Licensee: Nebraska Public Power District (NPPD) i Facility: Cooper Nuclear Station (CNS) License No: DPR-46 i Docket No: 50-298 i

Subject:

Managemen+ Meeting i On June 22, 1993, representatives of Nebraska Public Power District met with i Region IV personnel in Brownville, Nebraska. This meeting was open for public observation. The licensee presented the corrective actions taken or in progress to correct r 10 plant items. The licensee had committed to resolving these items prior to resuming plant operation from the current refueling outage. A copy of the licensee's presentation is enclosed in Attachrant 2. i Attachments: 1. Meeting Participants List 2. Licensee Presentation (NRC distribution only) i i s i k i

In]' 1 j LIST OF PARTICIPANTS j l. Participants in the management meeting between Nebraska Public Power District l and NRC on June 22, 1993. NPPD l H. Parris, Vice President, Production G. Horn, Nuclear Power Group Manager j J. Meacham, CNS Site Manager i V. Wolstenholm, Division Manager, Quality Assurance j D. Whitman, Division Manager of Nuclear Support R. Wilbur, Division Manager of Nuclear Engineering and Construction l R. Gardner, CNS Plant Manager l E. Mace, CNS Senior Manager of Site Support S. Peterson, CNS Senior Manager of Operations i M. Estes, Management Trainee G. Smith, Nuclear Licensing and Safety Manager i R. Sanchez, NPPD Contractor NRC l J. Montgomery, Deputy Regional Administrator, Region IV j A. Beach, Director, Division of Reactor-Projects (DRP) R. Kopriva, Senior Resident Inspector. DRP R. Schaaf, Project Engineer, Office of Nuclear Reactor Regulation l 'd. Walker, Resident Inspector, DRP E. Collins, Project Engineer, DRP J. Gilliland, Public Affairs Officer, Region IV j i t 5 P -i o i h i J' i-i e i i

7 T~ V U V U U U U U V y, ATTACHMENT 2 COOPER NUCLEAR STA TION 1993 REFUELING OUTAGE PRE-STARTUP MEETING JUNE 22,1993 H

COOPER NUCLEAR STA TION 1993 REFUELING OUTAGE PRE-STARTUP MEETING AGENDA NRC OPENING REMARKS J. M. MONTGOMERY INTRODUCTION AND OUTAGE OVERVIEW E. M. MA CE PRE-STARTUP ISSUES R. L. GARDNER G. S. MCCLURE J. M. MEACHAM NPPD CLOSING REMARKS G.R. HORN NRC CLOSING REMARKS J. M. MONTGOMERY H

4 ~ ~~ 4 9 U U U U U U U U, INTRODUCTION AND OUTAGE OVERVIEW E. M. MA CE SENIOR MANAGER OF SITE SUPPORT H l l

COOPER NUCLEAR STA TION 1993 REFUELING OUTAGE PRE-STARTUP MEETING OUTAGE OVERVIEW E MAJOR ACTIVITIES E ORIGINAL OUTAGE SCHEDULE E SCHEDULE IMPACTS l E CURRENT STA TUS/ SCHEDULE H l l

_ _ _ T.... U U UT-1) T7 ,5 6, COOPER NUCLEAR STA TION 1993 REFUELING OUTAGE MAJOR ACTIVITIES E MODIFICA TIONS E PROJECTS E INSPECTIONS E REPLACEMENTS BG

COOPER NUCLEAR STA TION 1993 REFUELING OUTAGE ORIGINAL WORKSCOPE E MODIFICA TIONS E PROJECTS Emergency Transformer Replacement Motor Operated Valves Alternate Shutdown " Hot Short" Eddy Current Testing - FW Hardened Torus Vent Pipe Installation Heat Exchangers RSCS Removal & RWM Auto Bypass ISI/IVVI Setpoint Reduction Erosion Corrosion MSL Radiation Monitor Scram & Group I Torus Surfaces Isolation Removal E INSPECTIONS E REPLACEMENTS Both Diese! Generators 1 Switchyard Output Breaker Both LP Turbines 66 DC HFA Relays B RFP Turbine 12 SRM/lRM Dry Tubes 2 Condensate Pumps 14 CRD Mechanisms 3 Condensate Pump Motors 3 LPRM's 5 Control Rod Blades 184 Fuel Bundles 280 CRD Capscrews

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u u u v v v v e ,o., COOPER NUCLEAR STA TION 1993 REFUELING OUTAG.E PRE-STARTUP MEETING SCHEDULE IMPACTS E SECONDARY CONTAINMENT LEAK TEST + 312 HOURS E LPRM/ CONTROL BLADE 40 HOURS E SW/ REC MODIFICA TIONS + 125 HOURS E RHR-MOV-MO17/MO18 REPAIR + 594 HOURS E FUEL LOAD DELAYS + 44 HOURS E RHR-MOV-MO27A UPGRADE + 100 HOURS E DG #2 ha ' AIR + 269 HOURS E RHR-MO V-MO25A/MO27A + 75 HOURS 1479 HOURS /62 DA YS BG

3 PAGE 1 OF 2 SCHEDULE EVALUATION LISTED BELOW ARE THE ACTIVITIES AND THE AMOUNT OF TIME THAT HAS BEEN ADDED TO THE OUTAGE DURATION. 1. SECONDARY CONTAINMENT LEAK TEST (6.3.10.8) + 312 HOURS ORIGINALLY SCHEDULED TO COMPLETE 4/4, 1000. 3 ACTUAL COMPLETION 4/17, 1000. RF 13CV AND 15CV MAINTENANCE. REASON MWR93-1204 - FPC RUPTURE SEAL DRAIN LINE - INSTALL LOOP SEAL. COMPLETING SECONDARY CONTAINMENT CORRECTIVE D ACTION PLAN. PLANT REQUIREMENTS WERE COMPLETED 4/12, 0800, HOWEVER, WIND CONDITIONS PREVENTED RUNNING UNTIL 4/16, 1900. 3 2. 3 LPRM STRING REPLACEMENT AND CONTROL ROD BLADE SWAPS - 40 HOURS WAS PERFORMED PRIOR TO SECONDARY CONTAINMENT BEING ESTABLISHED SAVING APPROXIMATELY 40 HOURS CRITICAL PATH TIME. 3 3. DC93-057, SW AND REC SYSTEM MODIFICATION + 125 HOURS WAS INCORPORATED INTO THE REFUELING SCHEDULE. ORIGINALLY SCHEDULE TO ADD 72 HOURS TO THE CRITICAL PATH, ACTUALLY ADDED 125 HOURS, DUE TO REC-V-21 FITUP PROBLEMS. 4. MWR 93-1180, RHR-M0V-M018 REPAIR AND MWR 93-1421, RHR-MOV-M017 REPAIR + 594 HOURS REPAIR WORK AND TESTING IS REQUIRED TO BE COMPLETED PRIOR TO FUEL RELOAD. SCHEDULED TO BE COMPLETED 5/14, 1800. 5. ACTIVITIES REQUIRED TO LOAD FUEL, ONCE SECONDARY CONTAINMENT WAS ESTABLISHED ON 5/12, 0100. + 44 HOURS WIND CONDITIONS. STROKE ALL CRDS, 11 CRDS WERE STUCK. 8 REPAIRED RPIS INDICATION AND ROD DRIFT. PERFORM SP 14.2.27. O

3 PAGE 2 OF 2 SCHEDULE EVALUATION 6. DC89-252E, RHR-M0-27A TRIM UPGRADE + 100 HOURS ACTUAL COMPLETION 5/21, 1900. THE ADDITIONAL TESTING REQUIRED ON RHR-A VALVES. 3 7. DG #2 REPAIR AND TESTING + 269 HOURS REPAIR 2 CYLINDERS LOW COMPRESSION (ORIGINAL SCOPE). RINGED ALL PISTONS AND REFURBISHED ALL 3 THE HEADS (ACTUAL SCOPE). ACTUAL START 6/14, 1200 AND SCHEDULED COMPLETION 6/19, 0100. 8. RHR-MOV-25A AND 27A REPAIR AND TESTING + 75 HOURS 3 SCHEDULED 6/20, 2000 TO 6/29, 0800. THE TOTAL TIME ADDED TO THE OUTAGE SCHEDULE: = 1479 HOURS /62 DAYS J 9 D e 9 9

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RFt/ ting nCIVITIES 5744 ES '304PR1310 00 E F 30wrR93 15 54 l 7 00 6 TF 0 5 t ar t RF P-4 Pr i or to 500: R750 ES 304PR93 16 00 EF 30@ R93 21 59 l 7 GD 6 TF 0 Heatup to Rated Preesur e i 201 iPV ) R760 FS 304PP'43 22.00 EF 304PR93 23 59 i. v! OD 2 TF 0 6 3 3 3 HPCI Simulated auto Actuateen Tes' R770 E5 lOGP93 22:00 EF 30@993 23.59 l l v OD 2 TF 0 6 3 6 3 RCIC Simulated n to Actuation les o R7UU E5 IM4Y93 0.00 EF 1McV9J 1 54 l vi 00 2 TF 0 S y rithernere Tu bire Gnrmra t or, 21 1. r WsIGN CHANGES 92029 ES 17 MAR 93 /:00 EF 30MnR93 18.59 m OD 124 keplace lvM/SPM Drytutes & Detr.ctors (0!!00 E3 7MnR43 19 00 EF 40PP43 IH r 4 m] 7 OD 672 IF 204 nUu bystem uv agei C06700 E3 7M0093 19 Go EF 11 & P43 IB 54 m m :] v rg p49 TF 216

1. W bystem Maintenance 107400 ES 7 MAR'O 1 % 00 E! %PR13 0 $4 mm]

'? OD '*7 4 IF 226 IM l $ysted Dufago f_ C8i.4)O ES 7 MAP 93 19 00 EF 14MsRM 19 59 M -T 03 108 HV tIUPBINE BLDUi Srstem Maintenave 008i'00 ES 7MsR93 19 00 if N 'F8] 19 59 -] v CD 672 TF 23 ju aystem Maintenance COB 400 ES 7MoR9319 00 tr 4 APRU I U 59 Y OD 672 LU dystem Vutage (0V30 ES 7M4P9319 00 EF 11oPR73 18 59 J ? R_8_4 0 TF 228 PL b y s t eil Ma i ntenanc e C09400 ES 7M4P93 19 00 EF 21MLR43 18 b9 m] ~v CD 3M TF 2;'6 k:,, i t. nystem Outagg (10000 ES 7McP4319 00 El 21MafN3 Id M m) v DD 3% TF 276 kW byste<a Uutage 83009 ES EMAR93 23 00 E F NM*9 3 17 59

v CD 30 i, 'u aysu i imta r (05500 ES 9MR4] 19 v0 EF AMnHJ 18 '/s

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PRE-STARTUP ISSUES R. L. GARDNER PLANT MANAGER 1 L BG l

v-v v v v v v v-v v q COOPER NUCLEAR STA TION 1993 REFUELING OUTAGE PRE-STARTUP MEETING ISSUES Presentation Methodology 1. Surveillance Testing Of Secondary Containment 2. Diesel Generator Fuel Oil Particulate Levels 3. Local Leak Rate Testing Criteria For Containment Penetrations One Inch And Less in Diameter 4. Service Water System Integrity H m - m --- ----- m a a w e ---4r9 = v

COOPER NUCLEAR STA TION 1993 REFUELING OUTAGE PRE-STARTUP MEETING SURVEILLANCE TESTING OF THE SECONDARY CONTAINMENT Secondary Containment Integrity Testing As Performed is Of Concern Because The Performance Of Maintenance Activities Precluded The Opportunity To identify System Degradation During Operation BG

u u u u u u u v v u & v., COOPER NUCLEAR STA TION 1993 REFUELING OUTAGE PRE-STARTUP MEETING 1 SURVEILLANCE TESTING OF THE SECONDARY CONTAINMENT Actions Taken E Secondary Containment Action Plan Developed Evaluation Of Plant Design Requirements Identified and Reviewed All Building Boundary Interfaces And Design Requirements. Evaluated Sensor And Instrumentation Design Reviewed Design Change Procedures To Verify Adequate Controls Exist To Assure Future Penetration Interfaces Are Addressed Appropriately BG

g 7_ g .C COOPER NUCLEAR STA TION 1993 REFUELING OUTAGE l PRE-STARTUP MEETING l l SURVEILLANCE TESTING OF THE SECONDARY CONTAINMENT Actions Taken (Continued) Evaluation Of Existing Maintenance / Surveillance Requirements Secondary Containment Testing Penetration Evaluation Evaluated increased Frequency And Trending Program M

o o o o o o o o o o ,o., COOPER NUCLEAR STA TION 1993 REFUELING OUTAGE PRE-STARTUP MEETING SURVEILLANCE TESTING OF THE SECONDARY CONTAINMENT Actions Taken (Continued) Evaluation Of Testing Methodology Verified Wind Speed Effects Established An Administrative Limit For Operational Margin Tested Building Interfaces To Verify Leak Tightness Performance Of Design Change Acceptance Testing Performed Extensive Testing To Assure Adequacy Of Drain Line Loop Seal For A Variety Of Plant Conditions M

v. _

_v_. - y- -..y. VENT EXTENSION REMOVED WATERTIGHT COVER BOLTED IN PLACE for REFUELING RPV BELLOWS 8KIRT REFUELING BULKHEAD -.- -----~,- >(g 7 r" g g.v y npy 1 I k l- -a p v k 'g b MAIN REACTOR J-FUEL h s' WELL DRAIN STORAGE / gl 31n. DULKHEAD DR AIN g [ poot fg Rotated into View s / , f i e

  1. g g

SE AL RUPTURE DR AIN To Drywell Equip Drah Sump SEAL RUPTURE DR AIN 'I'* BELLOWS LOW POINT DRYWELL To Vaste Surge Tank \\,,hh g g, DRAIN DQ dMW YWELL to REACTOR BLDG i, Seal Drain \\;... / ) Containment Penetration b, -- S (Typical) Missing Loop Seal REFUELING BULKHEAD and ASSOCIATED BELLOWS FIGURE #3 (Row m

o o o o o o o o o o ,o., COOPER NUCLEAR STA TION 1993 REFUELING OUTAGE PRE-STARTUP MEETING SURVEILLANCE TESTING OF THE SECONDARY CONTAINMENT Status E Secondary Containment Action Plans Have Been Completed E All Startup Issues Associated With Secondary Containment Surveillance Testing Have Been Implemented Or Completed E Future Secondary Containment Testing Requirements Are Being l Evaluated f H

U U O O O O O O O O ,O., COOPER NUCLEAR STATION 1993 REFUELING OUTAGE PRE-STARTUP MEETING DIESEL GENERATOR FUEL OIL PARTICULATE LEVELS DIESEL GENERATOR FUEL OIL Particulate Levels Were Discovered To Be in Excess Of Administrative Limits H

e - u o u o u o u .u.. COOPER NUCLEAR STA TION 1993 REFUELING OUTAGE PRE-STARTUP MEETING D_I_E_SEL GENERATOR FUEL OIL PARTICULATE LEVELS Actions Taken R Filtered Storage And Day Tanks To Reduce Particulate Levels E Revised Surveillance Procedure To Establish Appropriate Administrative Limits And Controls BG

u u-u-- u-- u-v-v w u .u., Cooper Nuclear Station 1993 Refueling Outage Pre-Startup Meeting ) l t Diesel Fuel Oil Particulate Levels i l Actions Taken (Continued) E Processing A Technical Specification Submittal For Additional Surveillance Requirements Includes Sampling And Removal Specifications For Water in Storage And Day Tanks l Completed A Design Change On Day Tanks To Facilitate Sampling For Water E Working With An Industry Expert To Further Assure Continued Quality Of Stored Fuel Oil [ l l H l

--- m -- m - - m-_m__ COOPER NUCLEAR STA TION 1993 REFUELING OUTAGE PRE-STARTUP MEETING Diesel Generator Fuel Oil Particulate Levels f Status j E Actions And Programmatic Changes Required To Assure Diesel Generator Operability In Support Of Plant Startup Are Complete E Fuel Oil Expert Recommendations Will Be Completed Subsequent To Plant Startup H

___m________ COOPER NUCLEAR STA TION 1993 REFUELING OUTAGE PRE-STARTUP MEETING Local Leak Rate Test Program 1 Present Performance Of Local Leak Rate Testing For One Inch And Less Containment Penetrations May Not Comply With Code Requirements H

o o o o o o o o o o ~~, li., COOPER NUCLEAR STA TION 1993 REFUELING OUTAGE PRE-STARTUP MEETING Local Leak Rate Testing Criteria For One Inch And Less Containment Penetrations Actions Taken E Re-Evaluated Compliance With Appendix J Testing Of Primary Containment Penetrations One Inch And Less in Diameter - No Apparent Problems Noted Status E Review Completed And Compliance is Assured With Appendix J Type B and C Testing BE

COOPER NUCLEAR STA TION 1993 REFUELING OUTAGE PRE-STARTUP MEETING Service Water System Integrity Concems Existed Regarding The Ability Of The Service Water System To Perform its Safety Function During The Next Operating Cycle M l =

7_ COOPER NUCLEAR STA TION 1993 REFUELING OUTAGE PRE-STARTUP MEETING Service Water System Integrity Actions Taken E Evaluation Of Maintenance / Surveillance Requirements Reviewed Actions Taken To Reduce Silting And Biological Fouling Effects Design Features And Elimination Of Potentially Effected Locations Surveillances To Assure Adequate Flow Rates And Function Performance of Preventive Maintenance BG

COOPER NUCLEAR STA TION 1993 REFUELING OUTAGE PRE-STARTUP MEETING Service Water System Integrity Actions Taken (Continued) E Piping Pressure Boundary Integrity Inspection And Evaluation Included Within The Augmented Erosion / Corrosion Program Inclusion Of Buried Piping H --r ,..__.-__._s a w ,w e

v u - u u u v v v v v .v., COOPER NUCLEAR STA TION 1993 REFUELING OUTAGE PRE-STARTUP MEETING Service Water System Integrity Actions Taken (Continued) E Piping StructuralIntegrity Inspection Of Piping Supports Performed A Water Hammer Analysis H l l l

7 T-U U U U O~ W7 U-- ,e,,. COOPER NUCLEAR STA TION 1993 REFUELING OUTAGE PRE-STARTUP MEETING Service Water System Integrity Actions Taken (Continued) E Active Component Performance Inservice Testing (IST) Initiated in 1986 Per ASME Section XI ~ Includes 34 Valves And 8 Pumps E Heat Transfer Capability To The Ultimate Heat Sink Preventive Maintenance And Test Programs For 10 Heat Exchangers H

u v v u-u u u u u C ,s., COOPER NUCLEAR STATION 1993 REFUELING OUTAGE PRE-STARTUP MEETING Service Water System Integrity Status E Service Water System Integrity Demonstrated To Be Capable Of Performing its Safety Function For This And Subsequent Operating Cycles E The Remaining Issue Associated With The SW System is The System Classification And Will Be Addressed in Response To NRC Inspection Report 93-17 M -. 2. m. m- -m -m m ic-w -~e =

PRE-STARTUP ISSUES G. S. MCCLURE NUCLEAR ENGINEERING DEPARTMENT MANAGER l l H

o o . O. O o' o o o .o o- .o.,_ COOPER NUCLEAR STA TION 1993 REFUELING OUTAGE PRE-STARTUP MEETING HYDROGEN / OXYGEN ANAL YZER issues 1. Operability of Hydrogen / Oxygen Analyzers during plant operation. 2. Operability of heat tracing within the analyzer cabinet. 3.- Leak Rate Testing of the analyzers. H

r e T-e v v v v v v u .u., COOPER NUCLEAR STA TION 1993 REFUELING OUTAGE PRE-STARTUP MEETING HYDROGEN / OXYGEN ANAL YZER Actions Taken n identified and corrected known operational problems. Water Problems Line slope was verified and adjusted as necessary. Removed particulate filters. Pump Problems Installed enhanced design sample pumps. BG

u u o COOPER NUCLEAR STA TION 1993 REFUELING OUTAGE PRE-STARTUP MEETING HYDROGEN / OXYGEN ANALYZER Actions Taken (Continued) Installed heat trace failure detection. m Leak tested analyzer to 58 psi. a Reverified the capability of the system to perform its accident function. m LOCA Simulation Test performed by the manufacturer. Analysis performed on pump capabilities and system pressure requirements specific to CNS tubing configuration. N

[ u u u v v v v v COOPER NUCLEAR STATION 1993 REFUELING OUTAGE PRE-STARTUP MEETING HYDROGEN / OXYGEN ANALYZER Actions Taken (Continuedi Enhanced pump design. Sample line slope verified. Initiated review for instrument cabinets with a similar situation. m Post modification surveillance. m H

o ~U o u o o' u o o o .o., COOPER NUCLEAR STA TION 1993 REFUELING OUTAGE PRE-STARTUP MEETING HYDROGEN / OXYGEN ANAL YZER _ Status a Review forinstrument cabinets with a similar situation willbe completed before startup. m The other startup actions have been completed. a Post startup monitoring. M

u e u o o o u o u .u.. COOPER NUCLEAR STA TION 1993 REFUELING OUTAGE PRE-STARTUP MEETING RMV-RM-1 AND RMV-RM-4 REPLACEMENT issues 1. Large number of Nonconformance Reports. 2. Lack of sufficient root causes. 3. Less than adequate 10CFR50.59 evaluation. M

O o o O O o o g ,g, COOPER NUCLEAR STATION 1993 REFUELING OUTAGE PRE-STARTUP MEETING RMV-RM-1 AND RMV-RM-4 REPLACEMENT Actions Planned Enhance awareness of Nonconformance Reports. a OA Program is being enhanced to review frequent NCR occurrences. Identify Nonconformance and Deficiency Reports associated with Engineering Work Requests for evaluation by the Work Planning a Management Committee. Reevaluate the design for replacement of RMV-RM-4. m Management and QA independently identified primary containment concerns and requested engineering to justify the design. BS 1- - - - - - ~ ' - - - - - _ _ _ _ _ _ _,

COOPER NUCLEAR STA TION 1993 REFUELING OUTAGE PRE-STARTUP MEETING RMV-RM-1 AND RMV-RM-4 REPLACEMENT Actions Planned (Continued) Design was reevaluated for primary containment and Appendix J Testing concerns - double isolation valves were added to the supply and return lines. n Enhance the understanding by Design Engineers of the primary containment and Appendix J requirements. Adda primary containment / Appendix J checklist to the Design Change Procedure. M

g g COOPER NUCLEAR STA TION 1993 REFUELING OUTAGE l PRE-STARTUP MEETING l RMV-RM-1 AND RMV-RM-4 REPLACEMENT Actions Planned (Continued) Perform a review to ensure other similar programs are includedin the Design Change process. Provide enhanced training to Design Engineers on primary containment integrity and Appendix J requirements. m Initiated a review of past design changes for similar occurrences. N

u r ~T O' O VT o e a .e... COOPER NUCLEAR STA TION 1993 REFUELING OUTAGE PRE-STARTUP MEETING RMV-RM-1 AND RMV-RM-4 REPLACEMENT Status a Program to provide added awareness to the number of Nonconformance Reports written against individualitems is currently being developed by QA. a Design for replacement of RM-4 was modified to include automatic isolation valves and Appendix J testing. Procedure change to add the Appendix J checklist willbe developed and n implemented after startup. H

. __u__ - - - y_ -_ _- -_ _ _ -_ __ y__ _ _ y _ _ _ _ _ COOPER NUCLEAR STA TION 1993 REFUELING OUTAGE PRE-STARTUP MEETING RMV-RM-1 AND RMV-RM-4 REPLACEMENT Status (Continued) m Appendix J training for Design Engineers will be developed and implemented after plant startup. Review of past design changes for similar concerns is in progress and will a l be completed prior to startup. l l l I l i H l l

1 PRE-STARTUP ISSUES J. M. MEACHAM SITE MANAGER H

o u o-o ~ o ~ ' ' -- ' m ~ u~o-- w - ' ~w 101 l l COOPER NUCLEAR STA TION 1993 REFUELING OUTAGE PRE-STARTUP MEETING E PRESSURE ISOLATION VALVE AND LOCAL LEAK RATE TESTING E MANUAL VALVE TESTING E SAFETY RELIEF VAL VE SETPOINT DRIFT E CONDITIONS REQUIRING EVALUATION PRIOR TO STARTUP H

__g___ COOPER NUCLEAR STA TION 1993 REFUELING OUTAGE PRE-STARTUP MEETING l PRESSURE ISOLA TION VAL VE AND LOCAL LEAK RA TE TESTING l Issues E Pressure Isolation Valve (PlV) Testing was not being conducted, and E Reverse (non-accident) direction Local Leak Rate Testing did not always yield conservative results. H

U 0 0 0 0 0 0 0 0- ..O., 4 1 COOPER NUCLEAR STA TION 1993 REFUELING OUTAGE PRE-STARTUP MEETING PRESSURE ISOLATION VALVE AND LOCAL LEAK RATE TESTING Actions Taken E PlV Testing Program now being implemented as a safety enhancement. Scope per Standard Technical Specifications and Generic Letter 87-06. ASME Section XI, IWV-3420 used for test methodology guidance. l H

-__-g---__--___u-___-___--_-_ t COOPER NUCLEAR STATION 1993 REFUELING OUTAGE PRE-STARTUP MEETING PRESSURE IS_QLATION VALVE AND LOCAL LEAK RATE Actions Taken (Continundl Previous LLRT methodology has been re-evaluated. E 47 valves were being tested in the reverse direction. 8 of these valves have now been testedin the accident direct For 29 of these valves, reverse direction testing re-verified to yield conservative results. Schedular exemption submitted for remaining 10 valves. l M L

1 l l COOPER NUCLEAR STA TION 1 1993 REFUELING OUTAGE 1 PRE-STARTUP MEETING 1 l l PRESSURE ISOLATION VALVE AND LOCAL LEAK RATE TESTING l Status l E For PlV Testing, 9 of 14 valves have been tested satisfactorily. 3 more will be tested before startup. Remaining 2 willbe tested next refueling outage. E For LLRT, Awaiting approval of Schedular Exemption. Further actions to be taken prior to startup from the next refueling outage. BG

g g-D O O O O 'O ..O., COOPER NUCLEAR STA TION 1993 REFUELING OUTAGE PRE-STARTUP MEETING MANUAL VALVE TESTING lssue Certain manual valves which may be required to be operated to mitigate the consequences of an accident are not being periodically tested. BG

_g-g g g g COOPER NUCLEAR STA TION 1993 REFUELING OUTAGE PRE-STARTUP MEETING MANUAL VALVE TESTING Actions Taken E Re-evaluated compliance with Technical Specifications and ASME Section XI-no apparent problems noted. E Recognized the increased assurance of safety gained by periodically cycling manual valves. l N 1 l

v v v. v v v v v v v ,v., COOPER NUCLEAR STA TION 1993 REFUELING OUTAGE PRE-STARTUP MEETING MANUAL VALVE TESTING Status E Continuing to evaluate this issue. E Numerous manual valves are periodically cycled per PM Program and others will be included, as required. E Effort will be completed by end of 1993. H

u u u u u u u u u u .. c COOPER NUCLEAR STA TION 1993 REFUELING OUTAGE PRE-STARTUP MEETING l _ SAFETY RELIEF VAL VE SETPOINT DRIFT Issue Measures have not been established to initiaate or prevent recurrence of Safety Relief Valve (SRV) setpoint drift. l l 1

T-u m-u .u.. 1 l COOPER NUCLEAR STA TION 1993 REFUELING OUTAGE PRE-STARTUP MEETING SAFETY RELIEF VAL VE SETPOINT DRIFT Actions Taken E This generic industry issue has been closely followed. Significant effort has been expended by industry - problem not yet solved. New hardware is latest development - not yet available. NiiC has been kept informed ofindustry efforts through BWROG. N

g o o -o o o O O O O 0' ^ ^ COOPER NUCLEAR STA TION 1993 REFUELING OUTAGE PRE-STARTUP MEETING SAFETY RELIEF VAL VE SETPOINT DRIFT Actions Taken (Continued) E NPPD has proactively pursued the safety consequences and the new hardware. CNS trend is not conclusive. One of the first plants to evaluate safety impacts. Safety consequences well understood, no safety concerns for upcoming cycle for any plausible setpoint drifts. CNS attempted to obtain new hardware for this refueling outage, but it was not yet commercially available. N

U e O O O O O O O O .O.. Valva 1988 Outcgo (14 oa) 1989 Outcgu (10 mos) 1950 Outcg2 (9 mos) 1991 Outega (17 mos) 1903 Outcg2 (14 moa) 5: rial Rumber Test Refurbish Test Refurbish Test Refurbish Test Refurbish Test Refurbish Resl Activity Resi Activity Resi Activity Resl Activity Resi Activity 379 1090 1090 A0 rebuilt Spare 1090 A0 rebuilt 1079 1086 Pilot assy 1242 Pilot assy -1.0 -0.4 reworked (]C((3D reworked Sol rebuilt 380 1100 1100 A0 rebuilt 1100 A0 rebuilt 1100 Pilot assy 1220 1108 Pilot assy 1119 Pilot assy 1123 reworked IIIE[l) +0.7 reworked ( +1. 7 ) reworked ( +2.1 ) Sol rebuilt Sol rebuilt 181 1080 1080 Ao rebuilt 1080 to rebuilt spare l 1090 1065 Pilot assy 1110 New pilot disc & +0.9 ( - 1. 4 ) reworked ( +2.8 ) seat Sol rebuilt New Sol 382 1100 1100 A0 rebutit 1100 A0 rebuilt 1100 Body to base 1096 1152 Pilot assy 1246 New pilot disc 1125 leak -0.4 (D reworked (M Sol rebuilt ( +2,3 ) Bolting Sol rebuilt replaced 383 1090 1090 A0 rebuilt 1090 AO rebuilt 1090 Pilot assy 1117 1119 Pilot assy 1182 New pilot dise & 1145 reworked (Il 5') ( +2 7 ) reworked C +8.4 3 disc tab washer [ +5.0 ) 501 rebuilt New main spring Sol rebuilt 304 1100 1100 A0 rebuilt 1100 New pilot seat 1122 1185 New pilot disc 1167 ( +2.0 ) C +7 71 Sol rebuilt (;dL,1) 385 1090 1090 None 1090 None 1110 1119 1128 ( +1. 8 ) ( Q f +3.5] 386 1090 1090 A0 rebuilt 1080 Pilot assy 1071 1112 Pilot assy 1201 reworked ( - 1. 8 ) (@ reworked L + n.23 Sol rebuilt 387 1080 1080 A0 rebuilt 1080 A0 rebuilt 1080 None 1102 1096 Pilot assy 1095 Pilot assy 1078 ( +T T ) ( +1. 5 ) reworked (g reworked -0.2 Sol rebuilt Sol rebuilt

u u u u nu v v v e .e.,_ COOPER NUCLEAR STATION 1993 REFUELING OUTAGE PRE-STARTUP MEETING SAFETY RELIEF VALVE SETPOINT DRIFT Status E CNS experience comparable with other BWRs. E Operability Evaluation performed for upcoming cycle. E New hardware being pursued for spare SRVs - willinstall next outage. BG

u u u u o u .v., CNS DATA COMPARED TO OTHER PLANTS l CNS* ALL PLANTS *

  • DES _CRIPTION
2. 7%

2.8% Average Deviation From Setpoint 3.9% 4.4% Standard Deviation 7.3 % 6.6% Valves With Drift > 10% 27% 31% Valves with Drift > + 3% 73 % 68 % Valves With Drift Between -3% and + 3% 0 1% Valves With Drift <-3%

  • Includes data from 1981 to the present.

Note:*

  • Utilizes the BWROG data through July 1992.

N

g g g g COOPER NUCLEAR STATION 1993 REFUELING OUTAGE PRE-STARTUP MEETING TUR _ CONDITIONS REQUIRING EVALUATION PRIOR TO STA lssue Conduct reviews to identify any existing conditions that may not have been adequately resolved. BG

O O O 'O O O O O O O .O., l 1 COOPER NUCLEAR STA TION 1993 REFUELING OUTAGE PRE-STARTUP MEETING l CONDITIONS REQUIRING EVALUATION PRIOR TO STARTUP Actions Taken E Corrective Action Program Overview Group (CAPOG) established. 1 Consists of three senior levelpersonnel, reporting to the Site Manager. I Scope of overview to include past documentation, personnel l interviews, and on-going activities. Tracking system implemented for identified items. M

v v-v. v v _v v v v v v..- ^ Sample of CURRECTIVE ACil0N PROGRAM OVERVIEW GROUP ISSUES 06/15/93 DATE WAmER DESCRIPfl0N REeutRED ASSIGNED EVAluAil0N/ACil0N STATUS 1.2.01 NCR 92-090 - LOCA toss of 125 VDC taas. Committment to 05/30/93 Swent: The ECCS SFA Finst Report was received on 5/17/93. No closed complete e Single Feiltre Anotysis of NPCI, ADS, CS, single failure vulnerabilities were identified that LPCI by 930601 Verify that no restert f esues have would result in the inability of the ECCS to perfore been identified. Its regJired functions. 1.2.02 NCR 92 073 - temperature profiles took OK for revised complete suman Received ABB calc on 6/2/93. Cooperison of this Closed Ans E0 calculations, but the finst calculations are not erproved revision to enetysis performed for Olep. 82 dJe m tfl 5/17/93. Verify that there are no outtlers, reveats the existing enetysis bomda the new revielen to the Age cate. 1.2.03 DR 93-071. RHR-CV-26CV has crack in weld and bulge in 05/30/93 Swanson Open conopy seat ring. Can't do PIV test if not fized. 1.2.04 NCR 93 019

  • Remove the interconnections between Complete Gocek Pius 93 '1T and 93-08 disabled the intercomection via Resolved EE-CHG-125(1A/8/C) and between EE CHG 250(1A/8/C).

the load sharing circuit identified by NCR 93-019. DC Easy eED fin if paperwork is done. work Item reserved 93 058 (SORC approved May 29, 1993) will make the PIMs the intercorviections. DC93-058 is being prepared to a permanent change, document the PiM. Additionetty, the DC will remove temperature switches now that essentist cooling has been provided. 1.2.05 act 92 136 - PC NRVs not indicating closed. New Complete Smneberg The fort e exerted on the disc by the limit switch is Closed position indicating switches are better, but the accomte3 for dJring the calibration (adjusting of the plunger offers more resistence to disc closure. As e megnet). When the disc is futty closed, the timit reustt, the closing force requirenent was towered from switch exerts a continuous and constant force on the e minious of 0.2 psig to a minisue of 0.1 psig which disc of approximately four pounds. The magnet is will me&e then herder to close and may result in adjusted so that a force of 20.5 to 42.8 lbs of force operationet problems. is regJired to open the disc. Therefore, the timit switch regJirement of 4 lbs will not cause any operationets problems. 1.2.06 NCR 90 029, 90-069, 90-110, 90-130, 91-014, 91-048, Comtete Boesch These NCRs are tracked by NAITS and therefore this itse closed 91-123, 92-058, 92-118. AnV 1 & 4. should be closed. 1.2.07 NCE 90-153, 91-030, 92-024, 92 131 - SW effluent complete McClure corrective action to NCR's 90-153, 91 030 and 92-131 le closed radiation sonitor. complete as a result of instellation of DC 90-367 on 5/11/93. The DC instatled a tedder cepecity pump and new ttbing. Corrective action to NCR 92-024 was completed by otheitting PCN for Procedsre 2.3.2.1TA to inittete greb sempling when the SW flow through the REC WX's le throttled via SW-MO-650 and 651. PAGE 1 l l

COOPER NUCLEAR STA TION 1993 REFUELING OUTAGE PRE-STARTUP MEETING CONDITIONS REQUIRING EVALUATION PRIOR TO STARTUP Actions Taken (Continued) E Personnel mindset for identifying and documenting plant concerns was enhanced. Management expectations related through correspondence and discussions. E Stressed utilization of existing programmatic controls. E Providing feedback from CAPOG overview effort. M

o 'o 6 o o o o o o o .o., COOPER NUCLEAR STA TION 1993 REFUELING OUTAGE PRE-STARTUP MEETING CONDITIONS REQUIRING EVALUA TION PRIOR TO STARTUP Status E CAPOG review of past documentation is complete. E Personnelinterviews by CAPOG are complete. E Overview activities are on-going. E 265 issues identified, 95 which must be resolved prior to startup. BG

e B e u o u u -u u o .u,, i 1 CAPOG REVIEW OF PAST DOCUMENTA TION ~1,353 AH open MWRs, Essential, EO, and Nonessential ~ 2,870 AH Essential and EQ MWRs, both open and closed. ~ 5,841 AU Preventive Maintenance items worked. ~1,800 1993 MWRs for evidence of work scope expansion. ~ 786 AH MWRs since April 21,1993. ~ 700 Completed surveiHances which are current, including those from the 1991 Refueling Outage to the present. ~ 450 300 complete and 150 left to do, of the remaining surveiHances to be performed this outage. Effort is up to date with no major problems identified. ~ 832 AH the 6.XX,10.XX, and 14.XX series procedures (surveiHance, nuclear performance, andinstrument & control procedures, respectively). BG

......,...__7._.. CAPOG REVIEW OF PAST DOCUMENTA TION (Continued) ~ 169 All ODs and OEs to date. ~ 350 All NCRs, both open and closed. ~ 300 All DRs, both open and closed. ~ 350 All EWRs, both open and closed. ~ 10 All RSIRs. ~ 50 All License Event Reports. ~ 21 All Technical Specification change submittals. ~ 70 Allinspection Reports and responses. ~ 28 All NRC Generic Letter responses. ~6 All NRC Bulletin responses. M

O 'D' ^ 'O O O O O O O ,O, O COOPER NUCLEAR STA TION 1993 REFUELING OUTAGE PRE-STARTUP MEETING CONDITIONS REQUIRING EVALUATION PRIOR TO STARTUP Status (Continued) E Corrective Action Program effectiveness has increased. To date: 118 Outage related NCRs (compared to 59 last outage). 233 Outage related DRs (of 272 total for 1993). 22 Outage related LERs (compared to 11 last outage). l E Approximately 35 CAPOG issues and 160 other Corrective Action Program issues remain to be resolved prior to startup. BG .}}

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