JPN-94-041, Forwards Completed Applicability Verification Forms Contained in App B to NEDO-32205, BWROG Topical Rept on Use Equivalent Margin Analysis,Rev 1, in Response to NRC Request for Info Re Util Response to GL 92-01,Rev 1

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Forwards Completed Applicability Verification Forms Contained in App B to NEDO-32205, BWROG Topical Rept on Use Equivalent Margin Analysis,Rev 1, in Response to NRC Request for Info Re Util Response to GL 92-01,Rev 1
ML20072C735
Person / Time
Site: FitzPatrick Constellation icon.png
Issue date: 08/10/1994
From: Josiger W
POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
GL-92-01, GL-92-1, JPN-94-041, JPN-94-41, NUDOCS 9408180071
Download: ML20072C735 (16)
v • d • e


Text

, 123 Main Street

. WNte Plains, New York 10601 914 fA16200

-i

  1. > NewYorkPower l 4# Authority '

i August 10,1994 '

JPN-94-041 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Stop P1-137 Washington, DC 20555

Subject:

James A. FitzPatrick Nuclear Power Plant ,

Docket No. 50-333 Generic Letter 92-01, Revision 1,

" Reactor Vessel Structural Intearity"

References:

1. NYPA letter, W. A. Josiger to NRC, " Generic Letter 92-01, Revision 1, Reactor Vessel Structural Integrity," (JPN-94-021),

dated April 29,1994.

Following discussions with the NRC staff, the Authority is providing additional information regarding our response to " Generic Letter 92-01, Revision 1, Reactor Vessel Structural integrity," (Reference 1).

The NRC requested that the Authority complete and submit the plant applicability verification forms contained in Appendix B to NEDO-32205, "BWR  ;

Owners' Group Topical Report on Upper Shelf Energy Equivalent Margin Analysis,"

Revision 1. Because initial weld USE data is unavailable, a calculated value is used in lieu of the measured value. The NRC also requested that the Authority resubmit the corrections to the NRC's Reactor Vessel Integrity database.

Attachments I and ll to this letter contain the requested information.

If you have any questions, please contact Mr. J. A. Gray, Jr.

Very truly yours, i

~

" I j 'liam A Josig r j Acting xecutive iceEJ6sident Nuclear Generation ec: See next page rf40010007{ gDO 33 gDR ADOC PDR pg IIe

i

l. Appendix B to NEDO-32205, "BWR Owners' Group Topical Report on Upper I I

Shelf Energy Equivalent Margin Analysis," Revision 1.

II. Corrections to " Summary File for Pressure-Temperature Limits" and " Summary File for Upper Shelf Energy."

l l

l cc: Regional Administrator U.S. Nuclear Regulatory Commission  ;

475 Allendale Road )

King of Prussia, PA 19400 l Office of the Resident inspector U.S. Nuclear Regulate y Commission P.O. Box 136 Lycoming, NY 13093 Mr. John E. Menning ,

Project Directorate I-1  :

Division of Reactor Projects 1/11 U.S. Nuclear Regulatory Commission Washington, DC 20555 l

l l

I 1

Attachment I to JPN-94-041 Appendix B to NEDO-32205,"BWR Owners' Group Topical Report on Upner Shelf Energy Equivalent Margin Analysis," Revision 1

)

0 t

New York Power Authority ,

James A. FitzPatrick Nuclear Power Plant l Docket No. 50-333 l DPR-59 l l

\

i

i NEDO-32205-A l

EQUIVALENT MARGIN ANALYSIS PLANT APPLICABILITY VERIFICATION FORM FOR James A. FitzPatrick Plant BWR/3-6 PLATE ,

l Surveillance Plate U_S_E:

%Cu = .13 Capsule Fluence = 2.7 x lo l7 N/CM 2 Measured % Decrease = 7.0 (Charpy Curves)

R.G. 1.99 Predicted % Decrease - 9.2 (R.G. 1.99, Figure 2) ,

limitina Beltline Plate USE:

%Cu = .13 32 EFPY Fluence = 1. 3 x lol8N/CM 2 l

R.G.1.99 Predicted % Decrease = 14.0 (R.G. 1.99, Figure 2)

Adjusted % Decrease = 11.0 (R.G. 1.99, Position 2.2) ,

l n% 121%, so vessel plates are bounded by equivalent margin analysis

- - . + w.

. . _ . . _ = . . - . . _ _ - ..

NEDO-32205-A EQUIVALENT MARGIN ANALYSIS PLANT APPLICABILITY VERIFICATION FORN FOR James A. Fit 2Patr4ck plant BWR/2-6 WELD Surveillance Weld USE:

%Cu - .31 Capsule fluence - 2.7 x lol7N/cM2 M agp H 4 7. Decrease - 20 (Charpy Curves)

  • C a l c u la t e d R.G. 1.99 Predicted % Decrease - 20 (R.G. 1.99, Figure 2)

Limitina Beltline Weld USE:

%Cu = .25

'l 32 EFPY Fluence - 1.3 x lo18 N/cM 2 R.G.1.99 Predicted % Decrease - 26 (R.G. 1,99, Figure 2)

Adjusted % Decrease - 30 (R.G. 1.99, Position ?.2) n% 5 34%, so vessel welds are l i bounded by equivalent margin analysis

  • Measured % decrease is unavailable until next surveillance capsule is removed. calculated value used instead.

. . - = - . . . - . . - - . - . . . - .

J l

Attachment ll to JPN-94-041 Corrections to " Summary File for Pressure-Temperature Limits" and

" Summary File for Upper Shelf Energy" l

i f

1 l

l New York Power Authority James A. FitzPatrick Nuclear Power Plant Docket No 50-333 DPR-59

Enclostre 1 5

Summary File for Pressure-Temperature Limits Diant Batttine Neet No. 10 Neut. 1R7 method of Chemistry Method of ICu Inst meme Ident. Ident. Fluence et Determin. Factor Deternin.

EOL/EFPY IR T. CF Fita- Loiser C1394 1 1E18 10*F Plant 73.6 Table 0.11 0.54 potrick shett [/. 96 speelffe tot: 10/ Lower C3376 2 2 E18 24*F ' Plant 91 Table 0.13 0.60 1F/2014 sheLL [/. 96 spectfIe Lower C3103 2 E18 2'r

  • Plant 100 Table 0.14 0.60 thett  %./ 96 Specific Lower Int. C3368 1 %E18 10'F ' Plant 81.8 Tabte 0.12 0.54 sheti J.3J spec 1ffe Lower Int. C3301 1 E18 18'F ' Plant 134 Table 0.18 0.60 shett 2/.

J 3) Speelfle Lower Int. C3278 2 %E18 10'F ' Plant 91 Table 0.13 0.60 shell J.3J specific Lower Int. 13253/ J,dE18 -50'F Plant 223.9 Table 0.26 0.87 Amlet 14008 Specific Wolde O*M 1 233A/C Lower 27204/ %E18 -22'F '

Plant 241.3 Table 0.25 0.99 sheL1 12008 SpectfIc Axlet /

  • o#

WeIde 2 233A/C Circ. Weld 305414 2[E18 50'F Plant 203.75 Table 0.33 0.59 1 240 eJ. M spectfIc Reference for FitrPatrick IRT, fluence, and chemical coupesition dote are f rae July 9,1992, letter from R. E. Boedle (PASWY) to USNRC Occument Control Desk, adject: Response to Generic Letter 92 01, Revfolon 1 1

l i

l 6

I

' Additional information required to confirm value.

~  !

l

\

i Enclosure 2 l 5 Summary File for Upper Shelf Energy Plant ueen Bettllne Neet No. Neterial USE et 1/4T Unfrred. Method of Ident. Type EOL/EFPY Neutron USE Determin.

Fluence et Unirred.

80L/EFPY UEE Fit:Patric Leesor C5394 1 A 5334 1 M AI18 M ME k W LL }t, .3 EOL:

10/17/2014 Lenser shett C3376 2 A 5338 1 M %18 , 77 ME

/,3 Leeser C3105 2 A 5338 1 70 AI18 G ME thett }/. 3.

Leeser Int. C33 M 1 A 5338 1 58 1.M18 67 MIL shell Leeser Int. C3301 1 A 5338 1 68

  • 1.M18 83 ME sheli Lonser Int.

shelt C3275 2 A 533s 1 g73 1, MIS 85 651 Leeser Int. 13253/ Lfnde M 1.7158 104 Direct Antal 12008 1092, SAW Walde 1 233A/C Leeser 27204/ Linde EMA' 1 18 9848 ---

she!L 12008 1092, SAW Aalel /*3 Wolde

  • 2 233A/C Cire. Wold 305414 Linde 3 44 8

1.M18 m:t' ---

1 240 1092, SAW teference for PftzPetrick Fluence, chemicet coopeef tfen, and taJet date are free July 9,1992 Letter from t. E. Seedle LPA887) to UentC Document Centret peak, s eject: Response to senseic Letter 92 01, Revielen 1 l

1 2

Licensee must confirm applicability of Topical Report NED0-32205, Rev.1

1 l}. *,';t ^, ' e

,/$ P . .g - , f, 1 ?*; i

- s-

'94 l

  1. > NewYorkPower 4# Authority August 10,1994 JPN-94-041 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Stop P1-137 Washington, DC 20555

Subject:

James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 Generic Letter 92-01, Revision 1,

" Reactor Vessel Structural Intearity"

References:

1. NYPA letter, W. A. Josiger to NRC, " Generic Letter 92-01, Revision 1, Reactor Vessel Structural Integrity," (JPN-94-021),

dated April 29,1994.

Following discussions with the NRC staff, the Authority is providing additional information regarding our response to " Generic Letter 92-01, Revision 1, Reactor Vessel Structural Integrity," (Reference 1).

The NRC requested that the Authority ccmplete and submit the plant applicability verification forms contained in Appendix B to NEDO-32205, "BWR Owners' Group Topical Report on Upper Shelf Energy Equivalent Margin Analysis,"

Revision 1. Because initial weld USE data is unavailable, a calculated value is used in lieu of the measured value. The NRC also requested that the Authority resubmit the corrections to the NRC's Reactor Vessel Integrity database.

Attachments i and 11 to this letter contain the requested information.

If you have any questions, please contact Mr. J. A. Gray, Jr.

Very truly yours, g' /

ft ' ' li A Josig r j Acting' xecutive iceErdsident Nuclear Generation cc: See next page  ;

l l

J

l. Appendix B to NEDO-32205, "BWR Owners' Group Topical Report on Upper Shelf Energy Equivalent Margin Analysis," Revision 1.

II. Corrections to " Summary File for Pressure-Temperature Limits" and " Summary i File for Upper Shelf Energy."  !

1 cc: Regional Admi,;istrator U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19400 Office of the Resident inspector U.S. Nuclear Regulatory Commission P.O. Box 136 Lycoming, NY 13093 Mr. John E. Menning Project Directorate I-1 Division of Reactor Projects 1/II U.S. Nuclear Regulatory Commission Washington, DC 20555 i

Attachment I to JPN-94-041 Appendix B to NEDO-32205,"BWR Owners' Group Topical Report on Upper Shelf Energy Equivalent Margin Analysis," Revision 1 1

i

(

New York Power Authority James A. FitzPatrick Nuclear Power Plant l Docket No. 50-333 DPR-59 l

. . . . - . . - . . . .. - - . . . - . . _ . u .

NEDO-32205-A EQUIVALENT MARGIN ANALYSIS PLANT APPLICABILITY VERIFICATION FORM FOR James A. FitzPatrick Plant BWR/3-6 PLATE Surveillance Plate USE:

%Cu = .13 Capsule Fluence = 2.7 x lo l7 N/CM 2 Measured % Decrease = 7.o (Charpy Curves)

R.G. 1.99 Predicted % Decrease = 9.2 (R.G. 1.99, Figure 2)

Limitina Beltline Plate USE:

%Cu = .13 32 EFPY Fluence = 1. 3 x 10 18 N/CM 2 R.G.1.99 Predicted % Decrease = 14.0 (R.G. 1.99, Figure 2)

Adjusted % Decrease = 11.0 (R.G. 1.99,' Position 2.2) n % $ 21%, so vessel plates are bounded by equivalent margin analysis I

- i E' .

g

.-. . - . . . -. - . . -. -- - - . -. . - . . . =

NEDO-32205-A l

EQUIVALENT MARGIN ANALYSIS PLANT APPLICA8ILITY VERIFICATION FORM FOR James A. F i. t 2 P a t r i r- k Plant BWR/2-6 WELD I

Surveillance Weld USE:

%Cu = .31 Capsule fluence - 2.7 x lol7N/cM2 N(4q ff$ g. Decrease = 20 (Charpy Curves)

  • C a l c u l a t e d R.G. 1.99 Predicted % Decrease - 20 (R.G. 1.99, Figure 2)

Limitina Beltline Weld U_S1:

%Cu = .25 32 EFPY Fluence = 1.3 x lo18 N/cM 2 R.G.1.99 Predicted % Decrease - 26 (R.G. 1.99, figure 2)

Adjusted % Decrease - 30 (R.G. 1.99, Position 2.2) n% s 34%, so vessel welds- are l l bounded by equivalent margin analysisj

  • Measured % decrease is unavailable until next surveillance' capsule is removed. Calculated value used instead.

Attachment il to JPN-94-041 Corrections to " Summary File for Pressure-Temperature Limits" and

" Summary File for Upper Shelf Energy" New York Power Authority James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 DPR-59 l

l l

, Enclosure 1 5

Sumary File for Pressure-Temperature Limits Plant Belttine Meet No. 10 Neut. IRT Method of Chemistry Method of Ecu XHI i Name loont. Ident. Fluence et Deterein. Factor Detersin. l EOL/tFPY I R t. CF Fitt- Lower C33M 1 1E18 -10*F Plant 73.6 Teolo 0.11 0.56 Petrick thett [/. 96 speelfic Eot 10/ 24*F ' Plant Table 0.13 0.60 1 17/2014 Lower shell C3376 2

/E18 2

/, 96 spectfle 91 l

l Lower C3103 2 3,ME18 2'F ' Plant 100 Table 0.14 0.60 I tholt /. 96 spectfle I Lower Int. C3368 1 %E18 10'F ' Plant 81.8 Table 0.12 0.54 SheLL J. 3,,2 SpectfIe Lower Int. C3301 1 E - 18'F ' Plant 134 Table 0.18 0.60 thall 2/.j)18

,7 Specific Lower Int. C32TS 2 hE18 10*F ' Plant 91 Table 0.13 0.60 shett J.3J specific Lower Int. 13253/ -50*F Plant 223.9 Table 0.26 0.87 Antal 12008

%E18 Speelfic i Welde JM l 1 233A/C

' 0.25 0.99 Lower 27204/ hE18 22'F Plant 241.3 Table 2M j , pg W fic welde 2 233A/C Cire. Weld -50'F Plant 203.75 Table 0.33 0.59 305414 2[E18 o7, J? speeifte 1-240 Refererwe for FitrPatrick 1RT, fluence, and chemical compositten data are frcus July 9,1992, letter from R. E. Beedle (PASNY) to U$NRC Document controt Desk, s@ ject: Response to Generic Letter 92 01, Revielen 1 l

4 l

1

' Additional information required to confirm value.

4 Enclosure 2 5 Sussiary File for Upper Shelf Energy 1

l Plant Nome Selttine Meet No. Meteriet USE et 1/4T Untrred. Method of Ident. Type E0L/EFPY #eutron USE Deterein.

Fluence et unfrred. '

EOL/EFPY USE FItapetric Losser C3396 1 A 5338 1 75 86

% 18 651 k thett /, 3 EOL: Loiser C3376 2 A $338 1 d6 77 18 , 651 10/17/2014 shelt %j,3 Lower C3103 2 A 5338 1 70 1I18 83 651 theLt p/. 3 Lower Int. C3368 1 A 533s 1 58 1.7t18 47 655 shalt Lower Int. C3301 1 A 5330 1 68 1.7518 83 655 shott Lower Int.

thett C3278 2 A 5338 1

[73 1.7E18 45 655 Leuer Int. 13253/ Lfnde 76 1.7E18 104 0irect Axfai 12008 1092, SAW Weide 1 2EA/C Loiser 27204/ Linde B44' 1 18 EMA* *--

Sheit 12008 1092, SAW Aetet /3 Wolde 2 233A/C Cfre. Wold 305414 Linde gen' 1.7E18 ERA' ---

1*240 1002, SAW Reference for Ff12Petrick Fluence, cheelcel coopeef tf on, and uuSE dote ere from July 9,1992, letter from t. E. Boedte (PASNY) to Usunc Docueent Centret peak, e 4 jects aceperme to Generic Letter 92 01, Revielen 1 l

l l

2 Licensee must confirm applicability of Topical Report NEDO-32205, Rev.1

.

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