NSD-NRC-98-5728, Responds to Request for Addl Status Re Issues Raised During Insp on 980615-17 Pertaining to Ice Condenser Basket Screws. Preliminary Schedule for Completion of Potential Issue Investigation Is Listed
| ML17334B810 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 06/26/1998 |
| From: | Liparulo N WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP. |
| To: | Robert Pettis NRC (Affiliation Not Assigned) |
| References | |
| NSD-NRC-98-5728, NUDOCS 9807130177 | |
| Download: ML17334B810 (11) | |
Text
CATEGORY 2 I REGULATORY INFORMATIONhDISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:9807130177 DOC.DATE: 98/06/26 NOTARIZED: NO DOCKET ¹ 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 AFFIL1ATION LIPARULO,N.J.
Westinghouse Electric Company, Div of CBS Corp.
RECIP. NAME RECIPXENT AFFILIATION PETTIS,R.L.
SUBJECT:
Responds to request for addi status re issues raised during insp on 980615-17 pertaining to ice condenser basket screws.
Preliminary schedule for completion of potential issue investigation is listed.
DISTRIBUTION CODE: IE19T COPIES RECEIVED:LTR ENCL SIZE:
TITLE: Part 21 Rept (50 DKT)
NOTES:
E RECIPIENT ID CODE/NAME PD3-3 PD INTERNA FILE CENT 01 NRR DRP /PECB/B RES/DET/EIB RGN2 RGN4 COPIES LTTR ENCL RECIPIENT ID CODE/NAME STANG, J NRR/DRPM/PECB PDR WARD, M.
RGN1 RGN3 COPIES LTTR ENCL EXTERNAL: INPO RECORD CTR 1
NRC PDR 1
NOAC SILVER,E 1
NUDOCS FULL TXT 1
QE,c.dA'3 QhQ
< R L'Sd i (0g e 'bs NOTE TO ALL "RZDS" 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 h
FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPTES REQUTRED:
LTTR 15 ENCL
Westinghouse Electric Company, a division ot CBS Corporation
~
Box 355 Pittsburgh Pennsylvania 152304355 June 26, 1998 NSD-NRC-98-5728 Mr. Robert L. Pettis Senior Reactor Engineer Of6ce ofNuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC
Subject:
Supplemental Information Regarding the NRC Inspection ofWestinghouse, June 15-17, 1998
Dear Mr. Pettis:
The following information is in response to your request for additional status regarding the issues raised during your inspection pertaining to ice condenser basket cracked screws.
I.
Ice Condenser Basket Sheet Metal Screws Westinghouse is investigating this situation as a Potential Issue (PI) within our 10 CFR Part 21 program as delineated in Westinghouse procedure ESBU-21. This investigation willinclude a review ofboth the TVACentral Laboratory Services report produced in June 1995 and the Gelles Laboratories report produced for American Electric Power in May 1998 and provided to Westinghouse in June 1998. Westinghouse has further committed to inform our utilitycustomers whose plants incorporate ice condensers ofthe interactions between Westinghouse and the NRC on this issue.
A preliminary schedule for completion ofthe Potential Issue (PI) Investigation is as follows:
Com letion Tar et l.
Perform metallurgical evaluation of~D. C. C tngheet Metal Screws (200 supplied by utility) 7/1/98
- Preliminary results:
100 screws evaluated.
Only two screws contained cracks: one was indication of a quench crack and one had cracks at the apex of the thread.
Approximately ten (10) screws with screw heads broken offindicated failure due to overtorquing. No service induced failures were apparent.
.)gLog 4
i41r. Robert L. Pettts 2.
Review screw design including coatings.
7/15/98 3.
Investigation and confirmation ofthe failure mechanism and root cause.
7/15/98 4.
Review ofavailable reports and draft W technical position.
Includes:
7/22/98
- Evaluation ofGelles Report supplied by D. C. Cook.
- Review 1995 Westinghouse Evaluation ofTVA Central Lab Services Report 95-1021 (Preliminary and Final).
- Interface with Duke Power Company and TVA regarding previous metallurgical work.
5.
Investigate consequences ofhaving cracked screws.
- CAR 98-1157, "Design Documentation to assure correct screws specified".
i)
Review Vendor Purchase Order Documentation.
ii) Revise Ice Basket Dwg./Spec to include screw required mechanical properties.
iii) Issue report.
7/22/98
- CAR 98-1170 'W Report MSE-REE-1371 i)
Address TVACentral Lab Services Report 95-1021 ii) Address consequences ofejected ice baskets hitting air handling units.
iii) Address potential presence ofadditional cracked sheet metal screws.
6.
Conduct Test Program to establish load carrying capacity of Screws (ifdetermined to be necessary).
8/14/98 (7/31 Preliminary) 2.
Additional Information on the Evaluation ofthe TVACentral Laboratory Services Report, Jun 1995 Westinghouse is continuing to assess the circumstances and decisions made in 1995 regarding the TVAreport and the potential impact on ice condenser equipment.
However, we do note that the issue ofice basket screw cracking was given a broad dissemination at the time ofits discovery in 1995 and at various times thereafter.
For example, the issue ofice basket sheet metal screw failures was discussed at length at the "International Ice Condenser UtilityGroup Symposium" held from June 26-28, 1995. This symposium, hosted by American Electric Power at their Cook Nuclear Plant facilityin Bridgman, Michigan was attended by all three domestic ice condenser utilities. We also note that the NRC may have reviewed sheet metal screws issues during the course ofits oversight activities prior to issuing the Watts Bar OL in 1995 and again as a part of an inspection at TVAin 1997 (NRC Inspection Report 97-04).
, -i, Mr. Robert L. Pettis 3.
D. C. Cook Gelles Report, June 1998 Finally, we would like to reiterate our position that, at the time ofthe NRC's recent inspection, the issue ofice basket screws cracked at D. C. Cook was being assessed by our cognizant engineering organization to reach the necessary engineering conclusions that are a prerequisite to determining whether to institute a Part 21 investigation.
In accordance with the Part 21 regulations and our Part 21 procedure, these conclusions, as well as any other information available to us, including the fact and extent ofthe NRC's prior knowledge ofthe issue, would have then been taken into account in any decision to commence a formal Part 21 investigation. As was noted to the inspection team, the engineer responsible for conducting our preliminary evaluation ofthe Gelles report was only a short time away from completing his assessment so that the appropriate determinations on this issue under Part 21 could be made.
Westinghouse is always willingto meet with the NRC to further discuss any facet ofthis issue.
Should you wish to discuss this further, please contact Mr. H. A. Sepp,
- Manager, Regulatory and Licensing Engineering at (412) 374-5282 at your convenience.
Very truly yours, N. J. Liparulo, Manager Equipment Design and Regulatory Engineering Enclosures Mr. Melvin S. Holmberg Reactor Inspection NRC Region III 801 Warrenville Road Lisle, Il 60532
l
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CATEGORY 1~
REGULATORY INFORMATION DISTRIBUTIOWSYSTEM (RIDS)
ACCESSION NBR:9807130177 DOC.DATE: 98/06/26 NOTARIZED: NO DOCKET 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 LIPARULO,N.J.
Westinghouse Electric Company, Div of CBS Corp.
RECIP.NAME RECIPIENT AFFILIATION PETTIS,R.L.
SUBJECT:
Responds to request for addi status re issues raised during insp on 980615-17 pertaining to ice condenser basket screws.
Preliminary schedule for completion of potential issue investigation is listed.
DISTRIBUTION CODE:
IE19T COPIES RECEIVED:LTR J ENCL 0 SIZE:
TITLE: Part 21 Rept (50 DKT)
NOTES:
E RECIPIENT ID CODE/NAME PD3-COPIES LTTR ENCL RECIPIENT ID CODE/NAME STANG, J COPIES LTTR ENCL INTERN
- FI E CENTER 01 R
DRPM P RES/DET/EIB RGN2 RGN4 NRR/DRPM/PECB PDR WARD, M.
RGN1 RGN3 EXTERNAL: INPO RECORD CTR NRC PDR NOAC SILVER,E NUDOCS FULL TXT D
U E
N YHIS DOCUMENT HAS BEEN SCANNED
-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 FULL TEXT CONVERSION REQUIRED TOTAL NUMBER OF COPIES REQUIRED:
LTTR 15 ENCL k5'
I p II 6'ti f*,
g" f',
a
Westinghouse Electric Company, a division ofCBS Corporation Box 355 Pittsburgh Pennsylvania 152304355 June 26, 1998 NSD-NRC-98-5728 Mr. Robert L. Pettis Senior Reactor Engineer Once ofNuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC
Subject:
Supplemental Information Regarding tbe NRC Inspection ofWestinghouse, June 15-17, 1998
Dear Mr. Pettis:
The following information is in response to your request for additional status regarding the issues raised during your inspection pertaining to icc condenser basket cracked screws.
I.
Ice Condenser Basket Sheet Metal Screws Westinghouse is investigating this situation as a Potential Issue (PI) within our 10 CFR Part 21 program as delineated in Westinghouse procedure ESBU-21. This investigation willinclude a review ofboth the TVACentral Laboratory Services report produced in June 1995 and the Gclles Laboratories report produced for American Electric Power in May 1998 and provided to Westinghouse in June 1998. Westinghouse has further committed to inform our utilitycustomers whose plants incorporate ice condensers ofthe interactions between Westinghouse and the NRC on this issue.
Apreliminary schedule for completion ofthe Potential Issue (PI) Investigation is as follows:
Com letion Tar et 1.
Perform metallurgical evaluation ofD. C. Cook Sheet Metal Screws (200 supplied by utility) 7/1/98
- Preliminaryresults:
100screwsevaluated.
Only two screws contained cracks: one was indication of a quench crack and one had cracks at the apex of the thread. Approximately tcn (10) screws with screw heads broken offindicated failure duc to overtorquing. No service induced failures were apparent.
9807i30i77 980b2b PDR ADQCK 05000315 8
I H
,, Mr.'Robert L. Pettis c 2.
Review screw design including coatings.
I 3.
Investigation and confirmation ofthe failure mechanism and root cause.
7/15/98 7/15/98 4.
Review ofavailable reports and draft W technical position.
Includes:
7/22/98
- Evaluation ofGelles Report supplied by D. C. Cook.
- Review 1995 Westinghouse Evaluation ofTVA Central Lab Services Report 95-1021 (Preliminary and Final).
- Interface with Duke Power Company and TVA regarding previous metallurgical work.
5.
Investigate consequences ofhaving cracked screws.
- CAR 98-1157 "Design Documentation to assure correct screws specified".
i)
Review Vendor Purchase Order Documentation.
ii) Revise Ice Basket Dwg./Spec to include screw required mechanical properties.
iii) Issue report.
7/22/98
- CAR 98-1170 "W Report MSE-REE-1371 i)
Address TVACentral Lab Services Report 95-1021 ii) Address consequences ofejected ice baskets hitting air handling units.
iii) Address potential presence ofadditional cracked sheet metal screws.
6.
Conduct Test Program to establish load cariying capacity of Screws (ifdetermined to be necessary).
8/14/98 (7/31 Preliminary)
Additional Information on the Evaluation ofthe TVACentral Laboratory Services Report, June 1995 Westinghouse is continuing to assess the circumstances and decisions made in 1995 regarding the TVAreport and the potential impact on ice condenser equipment.
However, we do note that the issue ofice basket screw cracking was given a broad dissemination at the time ofits discovery in 1995 and at various times thercaAer.
For example, thc issue ofice basket sheet metal screw failures was discussed at length at the "International Ice Condenser UtilityGroup Symposium" held from June 26-28, 1995. This symposium, hosted by American Electric Power at their Cook Nuclear Plant facilityin Bridgman, Michigan was attended by all three domestic ice condcnscr utilitics. We also note that the NRC may have reviewed sheet metal screws issues during the course ofits oversight activities prior to issuing the Watts Bar OL in 1995 and again as a part of an inspection at TVAin 1997 (NRC Inspection Report 97-04).
~ 'r.'Robert L. Pettis h
~
I 3.'. C. Cook Gelles Report, June 1998 Finally, we would like to reiterate our position that, at the time ofthe NRC's recent inspection, the issue ofice basket screws cracked at D. C. Cook was being assessed by our cognizant engineering organization to reach the necessary engineering conclusions that are a prerequisite to determining whether to institute a Part 21 investigation. In accordance with the Part 21 regulations and our Part 21 procedure, these conclusions, as well as any other information available to us, including the fact and extent ofthe NRC's prior knowledge ofthe issue, would have then been taken into account in any decision to commence a formal Part 21 investigation. As was noted to the inspection team, the engineer responsible for conducting our preliminary evaluation ofthe Gelles report was only a short time away from completing his assessmcnt so that the appropriate determinations on this issue under Part 21 could be made.
Westinghouse is always willingto meet with the NRC to further discuss any facet ofthis issue.
Should you wish to discuss this further, please contact Mr. H. A. Sepp,
- Manager, Regulatory and Licensing Engineering at (412) 374-5282 at your convenience.
Very truly yours, N. J. Liparulo, Manager Equipmcnt Design and Regulatory Engineering Enclosures CC:
Mr. Melvin S. Holmberg Reactor Inspection NRC Region III 801 Warrenville Road Lisle, Il 60532
4
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