JPN-99-035, Forwards Comments on Version 2 of Reactor Vessel Integrity Database for Plant.Table Listing Recommended Changes to Info in Rvid,Encl as Attachment 1

Forwards Comments on Version 2 of Reactor Vessel Integrity Database for Plant.Table Listing Recommended Changes to Info in Rvid,Encl as Attachment 1

ML20217G289
Person / Time
Site:	FitzPatrick
Issue date:	10/15/1999
From:	James Knubel POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
JPN-99-035, NUDOCS 9910210251
Download: ML20217G289 (8)

Text

.

123 Main Street WNte Plains, New York 10$01 914 081 6950

, 914 287.3300 (Fax)

A NewWrk%er a - x #6 i

& Authority Ef"einTJl*ote"l*"

October 15,1999 JPN-99-035 i

United States Nuclear Regulatory Commission Attn: Document Control Desk Mail Station P1-137 i Washington, D.C. 20555

Subject:

James A. FitzPatrick Nuclear Power Plant Docket 50-333 Comments on the Reactor Vessel Intearity Database

References:

1. NRC Letter to J. Knubel, Regarding Closure of TAC NO. MA1190 -

Response to the Request for Additional Information to Generic Letter 92-01, Revision 1, Supplement 1, dated July 6,1999

2. NYPA Letter, J. Knubel to the NRC, " Comments on the Reactor Vessel Integrity Database (RVID)," (JPN-99-028), dated August 30, 1999

3. Regulatory Guide 1.99, " Radiation Embrittlement of Reactor Vessel Materials," Revision 2, May.1988

Dear Sir:

This letter forwards the Authority's comments on Version 2 of the Reactor Vessel Integrity Database {RVID) for the James A. FitzPatrick Nuclear Power Plant. In the Reference 1 letter, the NRC recommended that the Authority review the revised RVID and provide comments to the NRC no later than September 1,1999. The NRC was informed (Reference 2) that the Authority would require until October 15,1999 to forward j!

q comments on the RVID. j' Attachment 1 contains a table listing recommended changes to the information in the RVID. In addition, Attachment 1'contains a mark-up of the pertinent sections of the RVID

, to reflect these recommended changes.

The comments contained in this letter are based on information previously sent to the NRC '}

and are consistent with Regulatory Guide 1.99, Revision 2 (Reference 3). 0 9910210251 991015 PDR ADOCK 05000333 P pm

1 1

. There are no new commitments contained in this letter. If you have any questions concerning this matter, please contact Ms. C. Faison.

. t Very truly yours,

! l

/

W J. Knubel Senior Vice President and Chief Nuclear Officer cc: Regional Administrator U. S. Nuclear Regulatory Commission- _ l 475 Allendale Road King of Prussia, PA 19406 i

Office of the Resident inspector i U. S. Nuclear Regulatory Commission James A. FitzPatrick Nuclear Power Plant P.O. Box 136 Lycoming, NY 13093 Mr. G. Vissing, Project Manager Project Directorate i Division of Licensing Project Management U.'S. Nuclear Regulatory Commission Mail Stop OWFN 8C2 Washington, DC 20555

i 1

l Attachment I to JPN-99-035

. Recommended Changes to the Reactor Vessel integrity Database 1

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

E o

TABLE 1 RVID2 DATABASE RECOMMENDED CHANGES

. Material Entry Change to Notes C3103-2 Ni % 0.57 CMTR Check C3103-2 S% 0.015 CMTR Check C3103-2 CF 99 Cu = 0.14,Ni = 0.57, Table 2 of RG-1.99R2 (Reference 1)

C3103-2 fluence 0.161 2"d Capsule Report (Reference 2)

C3103-2 FF 0.519 Section 1.1 of RG-1.99R2 C3103-2 ARTuor 51.4 CF = 99,FF = 0.519, eq.2 of RG-1.99R2 C3103-2 EOL RTunr 83.4 Eq.1 of RG-1.99R2 ,

C3278-2 Cu % 0.11 2"d Capsule Report, Note a l C3278-2 06 8.0 c3 = 0.5'ARTuor, Section 1.1 RG-1.99R2 C3278-2 Margin 16 o, = 0, oa = 8.0, eq. 4 of RG-1.99R2 C3278-2 EOL RTunr 22.1 Eq.1 of RG 1.99R2 l C3301-1 Ni % 0.57 CMTR Check C3301 -1 P% 0.008 CMTR Check C3301-1 CF 131 Cu = 0.18,Ni= 0.57, Table 2 of RG-1.99R2 C3301-1 ARTuor 71.5 CF = 131,FF = 0.546, eq.2 of RG-1.99R2 C3301-1 EOL RTunt 87.5 Eq.1 of RG-1.99R2 C3368-1 Ni % 0.50 CMTR Check C3368-1 S% 0.017 CMTR Check C3368-1 CF 81 Cu = 0.12,Ni = 0.50, Table 2 of RG-1.99R2 C3368-1 ARTuor 44.2 CF = 81,FF = 0.546, eq.2 of RG-1.99R2 l

C3368-1 EOL Riunr 68.2 Eq.1 of RG-1.99R2 305414 Fluence 0.161 2"* Capsule Report 305414 FF 0.519 Section 1.1 of RG-1.99R2 305414 ARTuor 108.5 CF = 209.1,FF = 0.519, eq.2 of RG-1.99R2 305414 EOL RTunr 114.5 Eq.1 of RG-1.99R2 13253/ Initial USE EMA NEDO-32205A Rev.1 (Reference 3), NRC SER 12008 3/30/95 (Reference 4), Note b 13253/ USE Method EMA NEDO-32205A Rev.1, NRC SER 3/30/95 12008 13253/  % Drop in EMA NEDO-32205A Rev.1, NRC SER 3/30/95 12008 USE 13253/ EOL USE EMA NEDO-32205A Rev.1, NRC SER 3/30/95 12008 Low int  % T Fluence 0.131 RG-1.99 eq.3, thickness = 5.376in; Note c Plates, Welds Lower  % T Fluence 0.110 RG-1.99 eq.3, thickness = 6.375in; Note c Plates, Welds 305414  % T Fluence 0.117 RG-1.99 eq.3, thickness = 5.375in; Note c C3103-2 initial USE 82.6 Note d C3103-2  % Drop in 13.7 Fig.2 of RG-1.99R2 j USE

! C3103-2 EOL USE 71.3 = Initial USE *(1-% Drop in USE/100) l f

Continuation of Table from previous page l Material Entry Change to Notes ,

C3278-2 Initial USE 84.3 Note d l

. C3278-2  % Drop in 12 Note e USE C3278-2 EOL USE 74 = Initial USE *(1-% Drop in USE/100) l C3301-1 Initial USE 82.3 Note d C3301 1  % Drop in 16.8 Fig.2 RG-1.99R2 USE C3301 EOL USE 68.5 = Initial USE *(1 % Drop in USE/100) l C3368-1  % Drop in 13.0 Fig.2 RG-1.99R2 USE C3368-1 EOL USE 58.3 = fnitial USE *(1-% Drop in USE/100)

C3376-1 initial USE 77.4 Note d l C3376-1  % Drop in 13.1 Fig.2 RG-1.99R2 USE C33761 EOL USE 67.3 = lnitial USE *(1-% Drop in USE/100) l C3394-1 Initial USE 85.6 Ncte d l

C3394-1  % Drop in 11.9 Fig.2 RG-1.99R2 l USE C3394-1 EOL USE 75.4 = Initial USE *(1 % Drop in USE/100) i Notes for Table of Changes:

l a) Chemistry for all plates and welds provided using the following guidelines:

. Copper (Cu) from Lukens ladle analysis i e Nickel (Ni) from Certified Material Test Report (CMTR) Check analysis e Surveillance plate chemistry, C3278, obtained from analysis of capsule samples

. Weld chemistry is best estimate of CE NPSD 1039 (Reference 5). Phosphorous (P) and Sulfur (S) not reported in the Combustion Engineering (CE) reference, therefore, Phosphorous (P) and Sulfur (S) for welds should be Not Applicable (N/A) b) Current Reactor VesselIntegrity Database Version 2 (RVID2) entry was obtained from first surveillance capsule result projected back to zero fluence.

c) Current RVID2 entries, provided in JPN-98-039 (Reference 6) did not account for variations in fluence with axial position of plates and welds. The revised values are from second capsule report.

d) Initial Upper Shelf Energy (USE) of plate material was obtained as 65% (longitudinal to transverse correction) of the average of Charpy impact tests at the highest temperature reported in CMTRs. These values differ from current RVID2 database entries due to rounding.

e) Percent (%) Drop in USE for surveillance plate was estimated using second capsule results by placing a point on Figure 2 of Regulatory Guide (RG) 1.99 and drawing a line parallel to the nearest line on the figure. The point at which the drawn line passed through the Quarter Thickness (%T) End-of-Life (EOL) fluence is the estimated drop in USE.

i L

References:

1. Regulatory Guide 1.99, " Radiation Embrittlement of Reactor Vessel Materials," Revision

. 2, May 1988 I

2. General Electric report (GE-NE-B1100732-01), " Plant FitzPatrick RPV Surveillance

Materials Testing and Analysis of 120' Capsule at 13.4 EFPY," Revision 1, dated l February 1998 l

3. NEDO-32205-A, " 10 CFR 50 Appendix G Equivalent Margin Analysis for Low Upper Shelf Energy in BWR/2 Through BWR/6 Vessels," Revision 1, Feb.eary 1994

4. NRC Letter to W. J. Cahill, Jr., " Applicability of GE Topical Report NEDO-32205, Revision 1, for the James A. FitzPatrick Nuclear Power Plant (TAC NO. M89580),"

dated March 30,1995

5. CE NPSD-1039, "Best Estimate Copper and Nickel Values in CE Fabricated Reactor l Vessel Welds," CEOG Task 902, Revision 2, June 1997

6. NYPA Letter, J. Knubel to the NRC, " Request for Additional Information Regarding l Response to GL 92-01 Reactor Pressure Vessel Integrity (TAC NO. MA1190)," (JPN-98 039), dated August 31,1998

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