ML17334B810

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

ACCESSION NBR:9807130177 CATEGORY 2 I

REGULATORY INFORMATIONhDISTRIBUTION SYSTEM (RIDS)

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: E TITLE: Part 21 Rept (50 DKT)

NOTES:

RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD3-3 PD STANG, J INTERNA FILE CENT 01 NRR/DRPM/PECB NRR DRP /PECB/B PDR WARD, M.

RES/DET/EIB RGN1 RGN2 RGN3 RGN4 EXTERNAL: INPO RECORD CTR 1 NOAC SILVER,E 1 NRC PDR 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, Box 355 a division ot CBS Corporation ~ Pittsburgh Pennsylvania 152304355 NSD-NRC-98-5728 June 26, 1998 Mr. Robert L. Pettis Senior Reactor Engineer Of6ce of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC

Subject:

Supplemental Information Regarding the NRC Inspection of Westinghouse, 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 will include a review of both the TVA Central 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 utility customers whose plants incorporate ice condensers of the interactions between Westinghouse and the NRC on this issue.

A preliminary schedule for completion of the Potential Issue (PI) Investigation is as follows:

Com letion Tar et

l. Perform metallurgical evaluation of~D. C. C tngheet Metal 7/1/98 Screws (200 supplied by utility)

- 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 off indicated 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 of the failure mechanism and 7/15/98 root cause.

4. Review of available reports and draft W technical position. 7/22/98 Includes:

- Evaluation of Gelles Report supplied by D. C. Cook.

- Review 1995 Westinghouse Evaluation of TVA Central Lab Services Report 95-1021 (Preliminary and Final).

- Interface with Duke Power Company and TVA regarding previous metallurgical work.

5. Investigate consequences of having cracked screws. 7/22/98

- 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.

- CAR 98-1170 'W Report MSE-REE-1371 i) Address TVA Central Lab Services Report 95-1021 ii) Address consequences of ejected ice baskets hitting air handling units.

iii) Address potential presence of additional cracked sheet metal screws.

6. Conduct Test Program to establish load carrying capacity of 8/14/98 Screws (ifdetermined to be necessary). (7/31 Preliminary)

2. Additional Information on the Evaluation of the TVA Central Laboratory Services Report, Jun 1995 Westinghouse is continuing to assess the circumstances and decisions made in 1995 regarding the TVA report and the potential impact on ice condenser equipment. However, we do note that the issue of ice basket screw cracking was given a broad dissemination at the time of its discovery in 1995 and at various times thereafter. For example, the issue of ice 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 facility in 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 of its oversight activities prior to issuing the Watts Bar OL in 1995 and again as a part of an inspection at TVA in 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 of the NRC's recent inspection, the issue of ice 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 of the NRC's prior knowledge of the 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 of the 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 willing to meet with the NRC to further discuss any facet of this 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 +4 ~ CATEGORY 1~

~4 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) E NOTES:

RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL PD3- STANG, J INTERN  : FI E CENTER 01 NRR/DRPM/PECB R DRPM P PDR WARD, M.

RES/DET/EIB RGN1 RGN2 RGN3 RGN4 EXTERNAL: INPO RECORD CTR NOAC SILVER,E NRC PDR 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" '

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Westinghouse Electric Company, Box 355 a division of CBS Corporation Pittsburgh Pennsylvania 152304355 NSD-NRC-98-5728 June 26, 1998 Mr. Robert L. Pettis Senior Reactor Engineer Once of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC

Subject:

Supplemental Information Regarding tbe NRC Inspection of Westinghouse, 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 will include a review of both the TVA Central 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 utility customers whose plants incorporate ice condensers of the interactions between Westinghouse and the NRC on this issue.

A preliminary schedule for completion of the Potential Issue (PI) Investigation is as follows:

Com letion Tar et

1. Perform metallurgical evaluation of D. C. Cook Sheet Metal 7/1/98 Screws (200 supplied by utility)

- 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 off indicated failure duc to overtorquing. No service induced failures were apparent.

9807i30i77 980b2b PDR ', ADQCK 05000315 8 PDR

I H

c

,, Mr.'Robert L. Pettis 2. Review screw design including coatings. 7/15/98 I

3. Investigation and confirmation of the failure mechanism and 7/15/98 root cause.

4. Review of available reports and draft W technical position. 7/22/98 Includes:

- Evaluation of Gelles Report supplied by D. C. Cook.

- Review 1995 Westinghouse Evaluation of TVA Central Lab Services Report 95-1021 (Preliminary and Final).

- Interface with Duke Power Company and TVA regarding previous metallurgical work.

5. Investigate consequences of having cracked screws. 7/22/98

- 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.

- CAR 98-1170 "W Report MSE-REE-1371 i) Address TVA Central Lab Services Report 95-1021 ii) Address consequences of ejected ice baskets hitting air handling units.

iii) Address potential presence of additional cracked sheet metal screws.

6. Conduct Test Program to establish load cariying capacity of 8/14/98 Screws (ifdetermined to be necessary). (7/31 Preliminary)

Additional Information on the Evaluation of the TVA Central Laboratory Services Report, June 1995 Westinghouse is continuing to assess the circumstances and decisions made in 1995 regarding the TVA report and the potential impact on ice condenser equipment. However, we do note that the issue of ice basket screw cracking was given a broad dissemination at the time of its discovery in 1995 and at various times thercaAer. For example, thc issue of ice 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 facility in 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 of its oversight activities prior to issuing the Watts Bar OL in 1995 and again as a part of an inspection at TVA in 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 of the NRC's recent inspection, the issue of ice 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 of the NRC's prior knowledge of the 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 of the 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 of this 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

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