ML17262A573

Forwards Table Listing Projected Reactor Temp PTS for Reactor Vessel Beltline Matls,Per Rev 2 to Reg Guide 1.99. Info on Table Indicates That Reactor Temp PTS Maintained Below Screening Criteria for All Cases Up to 32 EFPYs

ML17262A573
Person / Time
Site:	Ginna
Issue date:	07/30/1991
From:	Mecredy R ROCHESTER GAS & ELECTRIC CORP.
To:	Andrea Johnson NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation
References
RTR-REGGD-01.099 NUDOCS 9108080006
Download: ML17262A573 (5)

Text

ACCELERATED DI UTION DEMONST CTION SYSTEM V

REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:9108080006 DOC.DATE: 91/07/30 NOTARIZED: NO FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G

AUTH.NAME AUTHOR AFFILIATION MECREDY,R.C.

Rochester Gas

& Electric Corp.

RECIP.NAME RECIPIENT AFFILIATION JOHNSON,A.R.

Project Directorate I-3

SUBJECT:

Forwards table listing projected reactor temp PTS for reactor vessel beltline matls,per Rev 2 to Reg Guide 1.99.

Info on table indicates that reactor temp PTS maintained below screening criteria for all cases up to 32 EFPYs.

DISTRIBUTION CODE:

ADOID COPIES RECEIVED: LTR Q ENCL J SIZE:

TITLE: OR Submittal:

General Distribution DOCKET 05000244 D

NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72)-

05000244 /

A RECIPIENT ID CODE/NAME PDl-3 LA JOHNSON,A INTERNAL: NRR/DET/ECMB 7D NRR/DOEA/OTSB11 NRR/DST/SELB 7E NRR/DST/SRXB 8E

- &/%P REG FILE 01 EXTERNAL: NRC PDR COPIES LTTR ENCL 1

1 2

2 1

1 1

1 1

1 1

1 1

0 1

1 1

1 RECIPIENT

~ ID CODE/NAME PD1-3 PD NRR/DET/ESGB NRR/DST 8E2 NRR/DST/SICB8H7 NUDOCS-ABSTRACT OGC/HDS1 RES/DSIR/EIB NSIC COPIES LTTR ENCL 1

1 1

1 1

1 1

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1 1

0 1

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D NOTE TO ALL"RIDS" RECIPIENTS:

A D

D PLEASE HELP US TO REDUCE WASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!

TOTAL NUMBER OF COPIES REQUIRED:

LTTR 18 ENCL 16

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~ uZir~ilN iiiiiiiIIII ROCHESTER GAS AND ELECTRIC CORPORATION o

89 EAST AVENUE, ROCHESTER N.K I4649-000I ROBERT C MECREDY Vice Prerident Cinna Nudear Production July 30, 1991 TELEPHONE AREACODE 71B 546 2700 U.S. Nuclear Regulatory Commission Document Control Desk Attn:

Allen R. Johnson Project Directorate I-3 Washington, D.C.

20555

Subject:

Regulatory Guide 1.99, Revision 2

PTS Screening R.E.

Ginna Nuclear Power Plant Docket No. 50-244

Dear Mr. Johnson:

Recently attention has been focused on the issue of reactor vessel weld materials and their susceptibility to neutron embrittlement.

The recent revision to 10CFR50.61 requires the use of Regulatory Guide 1.99, Revision 2 to perform the calculations of the projected RT for the Ginna Station reactor vessel beltline materials.

Although no specific'actions are required for Ginna Station at this time, Westinghouse has performed these calculations for RG&E and the results are being,.submitted for your information.

The attached Table 1 and Figure 1 are extracted.

from the "Rochester Gas and Electric Reactor, Vessel Life Attainment Plan," March 1990.

Table

1. indicates that the RT is maintained below the PTS screening criteria,'as required, for all cases up to 32 Effective Full Power Years '.

Very truly yours, GJW/179 Attachment Robert C. Mecredy xc: Mr. Allen R. Johnson (Mail Stop 14D1)

Project Directorate I-3 Washington, D.C.

20555 U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Ginna Senior Resident Inspector 9lOS080006 9l0730 PDR ADOCK 05000244 P,.

PDR

TABLE 1 PROJECTED RT~~~ FOR THE R.

E.

GINNA REACTOR VESSEL BELTLINE MATERIALS COMPONENT INT. SHELL FORGING LOW SHELL FORGING CIRC.

WELD INT. SHELL FORGING LOW SHELL FORGING CIRC.

WELD INT. SHELL EFPY 27.36

27. 36.

27.36 32 32 32 PROJECTED FLUENCE (1,2) 2.93 2.93 2.93 3.38 3.38 3.38 RT~~~

(REG.

GUIDE 1.99, REV.

2)

( F) 114 283 112 115 288 PTS SCREENING CRITERIA

( F) 270 270 300 270 270 300 (1)

Fluence is in 10 n/cm~.

(2)

Projected fluence from Congedo, T. V., Heinecke, C. C.,

Rens, T. E.,

Weaver, M.,

"R.

E.

Ginna Reactor Vessel Fluence and.

RT Evaluation,"

WCAP=11026, December 1985.

270 10.0" 3AH3

~ N-1$

270 Forgfny 125 PS%

1N 39.5'IGURE 1

IDENTIFICATION AND LOCATION OF BELTLINE REGION MATERIAL FOR THE GINNA REACTOR VESSEL

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