ML17325B602
| ML17325B602 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 05/24/1999 |
| From: | Grobe J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | Powers R AMERICAN ELECTRIC POWER CO., INC. |
| References | |
| NUDOCS 9905280216 | |
| Download: ML17325B602 (56) | |
Text
CATEGQRY REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:9905280216 DOC.DATE: 99/05/24 NOTARIZED: NO FACIL:50-315 Donald C.
Cook Nuclear Power Plant, Unit 1, Indiana M
50-316 Donald C.
Cook Nuclear Power Plant, Unit 2, Indiana M
AUTH.NAME AUTHOR AFFILIATION GROBE,J.A.
Region 3 (Post 820201)
RECIP.NAME RECIPIENT AFFILIATION POWERS, R. P.
American Electric 'Power Co., Inc.
DOCKET 05000315 05000316
SUBJECT:
Submits summary of 990520 meeting between NRC
& licensee in Lisle,IL re status of resolution of specific technical issues. List of meeting attendees 6 handout provided by "licensee, encl.
DISTRIBUTION CODE:
IE45D COPIES RECEIVED:LTR ENCL SIZE:
TITLE: Summary of Significant Meeting with Licensee (Part 50)
NOTES:
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NOTE TO ALL "RZDS" RECZPZENTS:
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ON EXTENSION 415-2083 TOTAL NUMBER OF COPIES REQUIRED:
LTTR 10 ENCL 10
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>1 00 UNITED STATES NUCLEAR REGULATORY COMMISSION REGION III 801 WARRENVILLEROAD LISLE, ILLINOIS60532.4351 stay 24, 1999 Mr. R. P. Powers Senior Vice President Nuclear Generation Group American Electric Power Company 500 Circle Drive Buchanan, Ml 49107-1395
SUBJECT:
SUMMARY
OF THE MAY20, 1999, PLIBLIC MEETING TO DISCUSS DONALDC. COOK NUCLEAR PLANTTECHNICALISSUES
Dear Mr. Powers:
This letter summarizes the meeting held on May, 20, 1999, between staff members of the NRC and the Donald C. Cook Nuclear Plant to discuss the status of the resolution of specific technical issues.
This meeting was held at the NRC Region IIIoffice in Lisle, Illinois, and was conducted from 9:00 - 11:30 a.m. This meeting was open for public observation.
Enclosure 1
provides a list of meeting attendees and Enclosure 2 provides the licensee handout for this meeting.
The licensee presented information regarding the actions taken or planned to resolve several NRC Manual Chapter 0350 Restart Oversight panel case specific checklist technical issues.
The technical issues discussed included the status of the ice condenser project, and resolution of instrument uncertainty issues.
The licensee presented a summary of each issue, including background, causes, extent of condition, actions completed, and actions underway.
In addition, the licensee presented a brief update of other engineering issues including containment liner pitting resolution, hot feg nozzle gaps, containment sump inventory, and control room habitability. The licensee committed to presenting to the NRC at future meetings further updates on the status of the resolution of the technical issues as corrective action plans were being implemented.
9'P052802i6
'790524 PDR ADQCK 050003f5 P
R. Powers In accordance with 10 CFR 2.790 of the NRC's "Rules of Practice," a copy of this letter and its enclosures willbe placed in NRC's Public Document Room.
Sincerely, Original signed by Docket Nos. 50-315; 50-316 License Nos. DPR-58; DPR-74 John A. Grobe, Director Division of Reactor Safety
Enclosures:
- 1. List of Meeting Attendees
A. C. Bakken III, Site Vice President M. Rencheck, Vice President, Nuclear Engineering R. Whale, Michigan Public Service Commission Michigan Department of Environmental Quality Emergency Management Division Ml Department of State Police D. Lochbaum, Union of Concerned Scientists Distribution:
RRB1 (E-Mail)
RPC (E-Mail)
Project Mgr., NRR w/encls J. Caldwell, Rill w/encis B. Clayton, Rillw/encls SRI D. C. Cook w/encls DRP w/encls DRS w/encls Rill PRR w/e Is
,PUBLI
'encls~
Docket Ft e w/encls GREENS DOCUMENT NAME: G:FCOON520MTG.WPD To receive a co of thIs document, Indicate In the box: "C" = Co w/o attach/end "E = Co w/attach/end N = No co OFFICE NAME DATE RIII:DRP Ve el/kc 05/
/99 RIII:DRS Hoimber 05/~
/99 RIII:D Grob 05/
/ 9 OFFICIAL RECORD COPY
C
Enclosure 1
Ma 20 1999 Meetin Attendance List NRC J. Grobe, Director, Division of Reactor Safety (DRS), Region III A. Vegel, Chief, Reactor Projects Branch 6, Division of Reactor Projects, Region III J. Jacobson, Chief, Mechanical Engineering Branch, DRS, Region III B. Bartlett, Senior Resident Inspector, D. C. Cook E. Duncan, Reactor Engineer, DRS, Region III G. Hausman, Reactor Engineer, DRS, Region III M. Holmberg, Reactor Engineer, DRS, Region III C. Thomas, Director, Project Directorate III, Office of Nuclear Reactor Regulation (NRR),
NRC Headquarters J. Stang, Senior Project Manager, NRR, NRC Headquarters AEP M. Rencheck, Vice President,'Nuclear Engineering D. Kunsemiller, Director, Regulatory Affairs P. Schoepf, Ice Condenser Project Manager S. Greenlee, Director, Design Engineering J. Kovarik, Acting Manager, l&C Engineering D. Crumpacker, l8 C Design Engineering Manager (Partner)
going ifzighf...
Everv step oftas vray.
"cmnr~zz ruNr 1
~6'resentations Introduction Overview Ice Condenser Project Expanded Instrument Uncertainty Other Issue Updates Conclusion S eaker M. Rencheck S. Greenlee P. Schoep f D. Crumpacker S. Greenlee M. Rencheck P~ae 1
19 37
'MERICAN KLEClRlC powm
Paul Schoep f Ice Condenser Project Manager
'hlER1CAN" ELEClRIC POWER
l)oingifzighf...
Every step ag (he wuy.
ccmmmwz vuNr L
Ice Condenser Project Update
+
~ MC 0350 Checklist Issue No. 6 Discovery Technical Issue Resolution Project Summary h,
'MER/CAN"
~
~
KLECIIC POWER
Dcung itrigh(,.
Every step aft'e way.
~~ ~~/jg FMNT t
~ Expanded System Readiness Re>,ew ~ESRR~
Westinghouse assessment
'rawing reconciliation
~
ANLama+
KLKClRIC PWER 4
Dain@ ifrighf...
Every step af Se way, COG'lUQFAR RAID Discovery: ESRR
'oal - Capable ofmeeting its safety and accident mitigation functions Initiated April 15
'cheduled completion June 28
'requent interface between ESRg team and project team
'MER)CAN" ELKcrasc POwm 5
I I
ggjng lfZ7g&f...
Ewrv step af$8 way, c~ m~wz mNT Discovery: Nfestinghouse
-.='ssessment Goal - Ensure quality of support
~ Actions:
Perform assessment complete Assessment report - complete Status offindings resolved
'NERlCAN" ELKCTRIC POWER
Doingit'ighf...
CCKKN'OCEF/iR RANT
+
a r a
Goal - Identify and resolve inconsistencies
'ctions:
Determine scope ofreview - complete Define attributes for verification - scheduled May 30 Complete walkdowns/identify scope scheduled June 30
'MERICAN'LKClRlC POWER 7
'~ Technical Issue Resolution: Open Technical Issues Blowdown Loads Lower Inlet Door Seals
~ Ice Basket Coupling Screws
~ Lattice Frame Gusset Plates Hold Down Bar Welds
'asket Bottom Brackets
~'AlERlCAN" ELECTRlC POWER 8
~ Technical Issue Resolution:
-...-"'lowdown Loads
~ Issue Ice condenser component loads not formally updated followingprevious containment re-analysis
~ Actions:
Resolve licensing and design inconsistencies in accordance with restart schedule
'NERlCAN" ELECTREC PO%VKR
Every step a/the way.
inlet Door Seals r
'ssue New seals failed post installation tests
'ctions:
Refine manufacturing methods - complete Revise seal material complete Prototype and pilot production runs complete Design control activities scheduled July 31 Seal installation in accordance with restart schedule
~ 'NERlCAN
~
~
KLECYRlC POWER 10
'~ Technical issue Resolution: lce Basket Coupling Screws
~ Issue - Missing coupling screws
'ctions:
Root cause evaluation - complete Implement preventive actions - complete Inspect basketslreplace missing screws ongoing in accordance with restart schedule e
'AIERICAN'LEClRlC POWER 1l
0
Doing ifrighf...
Every step of'(he way.
CC2QK N'(.~/iR PLhNr
'echnical Issue Resolution: Ice Basket Coupling Screws Issue Fangled couphng scpe~s
~ Actions:
Torx head screw failure analysis complete Implement actions to minimize future failu~~s scheduled June 11 Assess new inspection results/disposition current]y installed screws scheduled June 15 Operating experience summary scheduled June 29
'MERICAN
~
~
ELECrRtc POWER l2
0
~ Technical Issue Resolution: Lattice Frame Gusset Plates
~ Issue Torch cut gusset plates at crane wall Actions:
Exposed gusset plate inspections - complete Finite element analysis modeling complete Remaining gusset plate inspections in accordance with restart schedule Final analysis review and approval in accordance with restart schedule
'AIERICAN ELECTRIC POWER 13
s Technical Issue Resolution: Hold Down Bar Welds Issue - Hold down bar weld non-conformance Actions:
Independent review/reconciliation - complete Welder qualifications review Testing Review other ice condenser scope complete Weld manual changes complete Enhance planning process - complete
'MERICAN'LKCmlC POWER
]4
Doing it right...
Everv step of(he may.
rem Nicene mNr
'echnical Issue Resolution: Basket Bottom Brackets Issue - Bracket weld non-conformance Actions:
Sample for extent of condition complete Re-analysis ofbracket weld design complete Analysis review and approval - in accordance with restart schedule Final verification inspections in accordance with restart schedule
'NERlCAN'
~
ELECVREC POWER l5
Doingifrighf...
EVPCV Bt8p Ofth8 1YClj
C~ HOClEAR FVIN7 r
'iscovery Scheduled to be complete June Technical issue resolution progressing Mainta>n ice condenser within design and licensing basis
'ntegrat>on of issue resolution ~1th resta~
schedule
'NERlCAM'
~
ELKClRlC POWER 16
Dean Crumpacker I&CDesign Engineering Manager (Partner)
~
'hIKRICAN'LECTRIC POMfER
';. Expanded instrument Uncertainty:
Presentation Overview
~ MC 0350 Checklist Issue No. 3C
Background
Causes Extent of Condition
~ Actions Completed
'ctions Underway Summary
~
'MERlCAN KLEC1RIC POWER
'~ Expanded Instrument Uncertainty:
--'" Background Issues identified in Fall 1997 Uncertainty calculations
~ Bias and correction factors Uncertainties in procedures
'MER/CAN'fECmlC POWER 19
Doingifrighf...
Every step of$6 way.
rem Numen ~Mr Expanded Instrument uncertainty;
Background
Examples:
Refueling Water Storage Tank jssues
'ontainment Water and Sump Leve] issues and Control Room temperature 1ssues
'NERICAIII" ELKCTRIC POWER
Oaingif righf...
Evvry step og $ 6 way, cam~~z mNr 4
Causes ofthe RWST Level problems Understanding of design basis Non-standard level tap location E<pa<<ed instrument Uncertainty:
- --*'auses Causes ofthe Containment Level and Temperature Indication problems Communication of design info~ation Identification ofDesign Basis requirements
'AlERICAN'LKClRIC POWER 21
Doingifright...
Ewe step og the way.
coox nruaenz mNr Expanded instrument Uncertainty:
Extent of Condition Process measurement error application potential concern for sensors
~ Need for uncertainties to be consistently applied in procedures, calculations, and analyses
'MERICAN"
~
ELECfRIC POWER 22
E""".~.,'5"'.;>
> ExpBnded lnstfUment Unceggjnty:
Actions Completed The specific items have been resolved through revisions to the affected calculations and procedures, and design changes Refueling Water Storage Tank Containment Water and Sump Level
~ CCW, ESW, and Control Room Temperature
~
'AIERICAN" KLKClRlC POWER 23
..",:'.",';...,.. ) Expanded Instrument Uncertainty:
Actions Completed
'xisting calculations were reviewed for process measurement error application
~ A process was developed to consistently apply uncertainties considering "critical parameters"
'NERICAM'LECTRIC POWER 24
II
~ Expanded Instrument Uncerta>nty; Actions Completed The plant-specific methodology mzn<al no~
specifies improved methods Branch Technical position HICB-BTp]2 and SBICI procedure 93807 attributes incorporated for process measurements Design and license basis verified by third party Cook lessons learned incorporated
~
'MERICAN'LKC1RlC POWER 25
goxng ifrighf...
Every step of$ 8 way, COGÃt<L~/iRKhhV'xpanded Instrument unce~alnty
- - 'ctions Completed Controls developed to ensure uncertainties are considered for calculations and analyses O.
'NEHICANI ELKCNIC
, POWER 26
> Expanded Instrument Uncertainty;
-.-."'ctions Completed
~ Instrument uncertainties have already been incorporated into:
Reactor Trip and Engineered Safety Feature Actuation System Setpoints Operations Daily and Shiftly Technical Specification Compliance Procedures
'MER(CAN'LECYRlC POWER
0
Doingifrighf...
Ewry stsp ofthe way.
COOK ACKET/IRFMN3 Expanded Instrument Uncertainty; Actions Underway Establish controls for procedure revisions ad development Review plant instrument data used in safety analyses Review procedures Emergency Operating Procedures Normal, Abnormal, and Surveillance procedures Annunciator Response Procedures
'hlERICAN" ELKCTRIC POWER 28
Oaing ifrighf...
Emrv step af the way.
COG@ RLKTFllRAANJ
'xpanded Instrument UncertaInty:
Actions Underway Emergency Operating Proced<<es are nder revision 45 calculations need review/revision 23 new calculations being prepared
'MERICAN'LKCTRlC POWER
'79
Every step ofles very.
Actions Underway Normal, Abnormal, and Surveillance procedures are under review 75 calculations need review/revision 75 new calculations being prepared
'NERICAIII
~
~
ELECTRIC POWER
l Expanded Instrument Uncertainty Actions Underway
~ Annunciator Response Procedures are under review 10 new calculations to be prepared
'MERICAN KLECmlC POWER 31
Daing ifrighf...
Every step af fhe >vay.
CQKN"iCE/IR AANl Expanded Instrument Uncertainty:
Summary Procedure reviews willbe completed prior to restart Calculation revisions willbe complete prior to restart
'rocedure changes willbe evaluated against restart criteria and revised as needed
'MERICAN'
~
KLKCTRlC POWER 32
Doing ifzighf...
Eimn step of'the @ray.
5 C~ ROCZfAR PLhNT
'ontainment Liner
'ot Leg Nozzle Gaps Containment Sump Inventory
'ontrol Room Habitability ANERlCAN'
~
EIEClRIC POMfER 33