ML17334B699
| ML17334B699 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 03/02/1998 |
| From: | Fitzpatrick E INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| AEP:NRC:1260G7, NUDOCS 9803060348 | |
| Download: ML17334B699 (31) | |
Text
CATEGORY 1 ~
REGULATE INFORMATXON DISTRIBUTIOll&YSTEM (RIDS)
ACCESSION NBR: 9803060348 DOC.DATE: 98/03/02 NOTARIZED: NO DOCKET I FACIL:50-315 Donald C.
Cook Nuclear Power Plant, Unit 1, Indiana M
05000315 50-316 Donald C.
Cook Nuclear Power Plant, Unit 2, Indiana M
05000316 AUTH.NAME AUTHOR AFFILIATION FXTZPATRXCK,E.
(formerly Indiana S Michigan Ele
'RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
Documents ri~nfo presented during 980227 meeting at Cook Nuclear Plant, Units 1
&. 2 in Bridgman,MI.
DISTRIBUTION CODE: A001D COPIES RECEIVED:LTR ENCL SIZE:
TITLE: OR Submittal: General Distribution NOTES:
RECIPIENT ID CODE/NAME PD3-3 LA STANG,J INTERNAL I3i~MENTE
- -/D~EM NRR/DSSA/SPLB NUDOCS-ABSTRACT EXTERNAL: NOAC COPIES LTTR ENCL 1
1 1
1 1
1 1
1 1
1 1
1 1
RECIPIENT ID CODE/NAME PD3-3 PD NRR/DE/ECGB/A NRR/DRCH/HICB NRR/DSSA/SRXB OGC/HDS2 NRC PDR COPIES LTTR ENCL 1
1 1
1 1
1 1
1 1
0 1
1 D
N NOTE TO ALL "RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE. TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD)
ON EXTENSION 415-2083 TOTAL NUMBER OF COPIES REQUIRED:
LTTR 13 ENCL 12
4 4I JX, I
P t,
I
Indiana Michigan~
Power Company 500 Circle Drive Buchanan, Ml 491071395
)
ENSMNA NlCHIGAM PMfM March 2, 1998 Docket Nos.:
50-315 50-316 U.S. Nuclear Regulatory Commission ATTN:
Document Control Desk Mail Stop 0-P1-17 Washington, DC 20555-0001 AEP:NRC:1260G7 Gentlemen:
Donald C.
Cook Nuclear Plant Units 1 and 2
DOCUMENT INFORMATION PRESENTED DURING FEBRUARY 27 g 1 998 g PUBLIC MEETING The purpose of this letter is to document the information we provided you with during the February 27, 1998, public meeting held at the Cook Nuclear Plant in Bridgman, Michigan.
Attachment 1 provides copies of the overhead slides that were used during the February 27, 1998, meeting.
Sincerely, p~
E.
E. Fitzpatrick Vice President
/vlb Attachments J'.
A. Abramson A. B. Beach
'MDEQ -
DW & RPD NRC Resident Inspector Z.
R.
Sampson
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~>> v'vv7 9803060348
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ATTACHMENT 1 TO AEP:NRC:1260G7 OVERHEAD SLIDES USED DURING FEBRUARY 27'998'UBLIC MEETING
AN KRICAN'LKCTRlC PONDER 50.59 BYPA EVALUATION Paul Barrett Performance Assurance Director
~
'MERICAN'LKCTRlC POTE R
Evaluation Process Process Vehicle Population Sample Review For Change Missing 50.59 Screens Impact of inadequacies
- Safety Evaluations
- Operability
- Unreviewed safety questions
- Program deficiencies
AN ERICAN'EECmfC POWER Change
~ A change is any activity, including modifications to plant hardware or procedures, or new tests or ~
experiments, that may affect the design, function, or method of performing the function of a structure, system, or component (SSC) as described in the updated final safety analysis report (UFSAR). An activity involving a SSC not explicitly described in the UFSAR that has the potential to impact the function of a SSC that is explicitly described in the UFSAR is also considered a change.
~
'MERlCAN'lECTREC PCNfER Process Vehicle Engineering Specifications AR's lJO's Drawing Changes Operability Determination Technical Direction Memo's NPM Evaluations Mech. Engineering Memo's Elec. Engineering Memo's Design Change Deter.
Condition reports ASP's Receipt inspection Population 1,429 Revisions, C.S., &
Addendum 1,124 &
Several 1,000 2,074 Drawings 29 (100'lo) 176 Memo's 3196 Evaluations 115 Memo's 168 Memo's 885 Determinations 799 CR's 20,171 Receipt Inspection Pkgs.
Years reviewed 1975-1998 1987-1997 1980-1995 1980-1995 1994-1998 1991-1998 1980-1995 1980-1995 1989-1997 1986-1997 1975-1997 Sample Size 60 120 121 dwg.
WI 305 rev's 29 (100%)
60 60 60 60 60 60 198 Changes that required a new 50.59 screening 12
¹ of Safety Evaluations Required 0
¹of Operability Concerns
¹of Unreviewed Safety Questions Identified Does the current.
process vehicle need a change No, Previously Revised Yes
- Yes, No, Previously.
Revised Yes Yes No Longer Exists No I onger Exists Yes Yes Yes
~
'MERICAN'l,KCfÃlC PC@VER Process Vehicle Population Design Standards 582 Revisions Years reviewed 1980-1998 Sample Size 115 Changes that required a new 50.59 screening 10
¹ of Safety
¹ of Evaluations Operability Required Concerns
¹of Unreviewed Safety Questions Identified Does the.
current process vehicle need a change Yes Design Change Addendum Elec.8 I &C Setpoints DCDIR's Tech. Data Book PMI 5023 Plant Fabrications, Repairs Dedication Plans Old Clearances I Caution tags Open items log Workaround I watch list PMI4016 Temp. operator aid Permanent operator aid TOTAL 1,667 Design Change Units, Rev., 8 Sub-tasks 814 6,584 153 Figures 55 (100%)
Travelers 1,346 Revisions 109 (100%)
150 (100%)
29 (100%)
58 (100%)
210 (100%)
N IA 1980-1995 1975-1997 1987-1998 1992-1997 1994-1998 1988-1998 1990-1998 1995-1998 1996-1998 1990-1998 1985-1998 NIA 62 pkgs.
(120 addendum) 60 60 60 55 (100%)
60 109 (100%)
150 (100%)
29 (100%)
58 (100%)
210 (100%)
1916 5
3 88 0
0 No, Previously Revised No, Previously Revised No Yes No Yes Yes Yes No Yes Yes N/A
ADDITIONAL10 FR 50.59 ELF-A E SMENT JEB KINGSEED MANAGER, NUCLEAR SAFETY
'NERECAN'LECfRK POMfER AEPAmcrfars Eneqp ihrtner" 50.59 Self-assessment A enda
~ Focus
~ Scope
~ Team composition
~ Observations
~ Results
'MERICAN'LECTRlC POWER
't 0 CFR 50.59 Self Assessment Focus
~ Operability issues
~ Unreviewed safety questions
~ Improperly dispositioned screenings
'NERlCAN'ECrRrC POWER 10 CFR 50.59 Self Assessment-co e
~ 60 random samples from 50.59 products produced by engineering between 1980-1995
~ 60 random samples from 50.59 products produced by plant maintenance, operations 8
technical support staff between 1980-1995
'AIERlCAN'CECfRIC POWER AEMmefnt's Enemy Kroner" Team Composition
~ Team Composed of personnel from:
Nuclear Safety Nuclear Licensing Nuclear Fuels Operations
~ Training:
Qualified to perform 50.59 products they reviewed Trained on recent design/licensing basis insights Review addressed consideration of ATWS and SBO as "previously analyzed accidents"
'NERfCAN'EECTRlC POWER Observations Engineering Products
~
17 of 60 products inadequately justified by today's standards:
Evaluations with correct conclusion that did not directly address all 7 USQD process questions Evaluations where answers were little more than negative repetition of the question Evaluations that addressed Tech Spec 8 Chapter 14 engineering issues wlo 7 questions
'MERICAN'IKClRIC POMfKR Observations Engineering Products (cont'd)
~ One evaluation did not direct a needed change to.UFSAR. Though it was verified that the. necessary change had been implemented, the source of UFSAR change initiation could not be verified due to historical age of document.
ANKRlCAN EEECfRlC POWER Observations Engineering ProdUcts (cont'd)
~ A safety evaluation documented the rejection of a minor modification due to its potential to "increase the malfunctions of equipment important to safety" and offered alternatives.
~ Quality of 50.59 products increased from 1980 to 1995. All inadequately justified products were prior to 1994.
~
ANERlCAN'MCTRfC-POWER AEhAmerka's Eaegy Ruiner" Observations Plant Products
~
13 of 60 products inadequately justified by today's standards:
No references to UFSAR and Tech Spec sections reviewed Change not adequately described References given, but answers on screening questions not justified
'MRlCAN'I EClRIC POWER AEPAmerica's Enny Rrtner Observations Plant Products (cont'd)
~ Quality of 50.59 products increased between 1980 and 1995. All inadequately documented screenings were prior to 1994.
Results
~ No operability issues due to 50.59 process
~ No unreviewed safety questions
~ No improperly dispositioned 50.59 screenings or safety evaluations.
~ Programs in place to address other identified long-term issues (UFSAR Update Program and 10 CFR 50.59 Training).
'NERlCAN'LECTRIC POWER AEP.Americu's Enemy fbrtner" PR I SUES AE INSPECTION GRAMMATI Tom Quaka Project Management 8 Installation Services Manager
'NERlCAN'LECTRlC POW'ER AEMmesku's Energy Kroner Mission and Purpose To:
~ Independently review AE inspection information with program perspective
~ Identify other weaknesses
~ Recommend and verify corrective actions
AMERICAN'MCTRIC POWER MiSSiOn and PurPOSe (cont'd)
So That:
~ Nature and extent of past programmatic issues characterized
~ Assurance reviews identified program or design bases concerns
~ Current programs will prevent future non-conformances or inoperability
'NERlCAN'EKCTRfC POMfER Team Composition
~ Nine member team assembled from Design Engineering Regulatory Affairs Performance Assurance
. Production Engineering
~ 'NERlCAN'
~
SLECTR1C PCNfER AEMmerica's Energy ibriner" TEAMAPPROACH Review AE related information Compile AE issues, weaknesses, 8 causes Establish "Programs" to be evaluated Correlate issues, weakness, causes to "Programs" Capture other review results 8 relate to "Programs"
~
'NERlCAN'LECTRIC POMfER Past samples or reviews sufficient for
" rograms" No Notify mgmt for added actions Complete actions Yes Critically evaluate "Program" status
~Individually
~Collectively Complete actions Evaluate current "Program" controls Current "Program" controls adequate?
No Notify mgmt for added actions Yes Document basis for assurance no future non-conformances
'NERICAN'LECTRIC POMfER AEPAmedw's Eneqp Rrlner" Team "Programs"
~ Preservation of Design and Licensing Bases
~ Design Change
~ 10 CFR 50.59 Imjlementation
~ Calculations
~ Instrument Uncertainty
Team "Programs" (cont'd)
~ Developing 8 Maintaining Procedures
~ Corrective Action
~ Quality Assurance Related to AE Issues
~ Review of NRC/Industry OE Information
~ 'NERfCAN'-
ELECFREC POWER Team Actioris
~ Independent re-review of 20 system functional calculations Using structured review process Uniform characterization of results Technical Oversight Committee (TOC)
~ Expanded to statistically significant sample
Y I