ML17264A759
| ML17264A759 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 12/11/1996 |
| From: | Mecredy R ROCHESTER GAS & ELECTRIC CORP. |
| To: | Vissing G NRC (Affiliation Not Assigned), NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| TAC-M96529, NUDOCS 9612190258 | |
| Download: ML17264A759 (5) | |
Text
REGULA
'NFORMATION DISTRIBUTION SYSTEM (RIDS) 4p ACCESSION NBR:9612190258 DOC.DATE: 96/12/11 NOTARIZED: NO FACIL:50-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G
AUTH.NAME AUTHOR AFFILIATION MECREDY,R.C.
Rochester Gas !'lectric Corp.
RECIP.NAME RECIPIENT AFFILIATION VISSINGiG.
SUBJECT:
Transmits response to 960913 RAI.
DISTRIBUTION CODE:
A001D COPIES RECEIVED:LTR ENCL SIZE:
TITLE: OR Submittal: General Distribution NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).
DOCKET I 05000244 05000244T RECIPIENT ID CODE/NAME PD1-1 LA
.VISSINGiG.
01 EXTERNAL: NOAC INTERNAL:
NRR/DE/EMCB NRR/DSSA/SPLB NUDOCS-ABSTRACT
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1 RECIPIENT ID CODE/NAME PD1-1 PD NRR/DE/ECGB/A NRR/DRCH/HICB NRR/DSSA/SRXB OGC/HDS3 NRC PDR COPIES LTTR ENCL 1
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NOTE TO ALL "RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTE!
CONTACT THE DOCUMENT CONTROL DESK, ROOM OWFN 5D-5(EXT. 415-2083)
TO ELIMINATE YOUR NAME FROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
TOTAL NUMBER OF COPIES REQUIRED:
LTTR 13 ENCL' 12
4ND ROCHESTER GASANDF'IFQRIC CORJQRATIOJV
~ B9 FASTAYFIVVE,ROCHFSTFR PI. Y Idbf9 0001 ARFA CODE'716 546-2100 ROBERT C. MECREDY Vice President Nvcteor operations December 11, 1996 U.S. Nuclear Regulatory Commission Document Control Desk Attn:
Guy Vissing Project Directorate I-1 Washington, D.C.
20555
Subject:
Letter from Guy S. Vissing, NRC, to Robert C. Mecredy,
- RGE,
Subject:
"Request for Additional Information Relating to Rochester Gas and Electric Corporation (RG&E)", dated September 13, 1996 (TAC No. M96529)
R.E. Ginna Nuclear Power Plant Docket No. 50-244
Dear Mr. Vissing:
The purpose of this letter is to transmit the Rochester Gas and Electric (RG&E) response to the subject Request for Additional Information (RAI).
Attachment A to this letter provides that response.
Very truly yours, Attachment REZ(442 Robert C.
Me edy xc:
Mr. Guy Vissing (Mail Stop 14C7)
Project Directorate I-1 Washington, D.C.
20555 U.S. Nuclear Regulatory Commission Region I 475 Allendale Road King of Prussia, PA 19406 Ginna Senior Resident Inspector 96121ttt0258 961211 PDR'DQCK 05000244 P
Question 1:
Describe the basis for the copper and nickel values used (i.e., 0.25 and 0.56 respectively) for the reactor vessel circumferential weld seam SA-847.
In addition, describe how the coil-to-coil variability in the amount of copper in the filler wire is accounted for.
Response
(a)
.25 Cu
&.56 Ni came from PTS SER (3/22/96)
- p. '3, Sect.
2.2, 1st paragraph.
When the new sample data from WCAP-14684 Table 5-4A p.
55 were factored in, the new values would be '.248 Cu
& =.55 Ni.
Since.25 Cu
&.56 Ni were conservative we elected to not challenge the SER.
In effect an additional penalty was added into the chemistry factor (CF).
The Cu
& Ni in Table 5-4A p.
55 represent actual surveillance capsule chemistry data.
The values from Reference 54 of that table weren't available until after our PTS submittal.
(b)
As described in the PTS SER (3/22/96)
Ginna does not have coil-to-coil variability information.
Any discussion would be speculative and would not be. in accordance with 10CFR50.61.
Question 2:
It appears from Table 5-4A of WCAP-14684 that the copper and nickel values used for the Ginna surveillance program weld metal are 0.236 and 0.517 respectively.
In the staff's pressurized thermal shock evaluation forwarded by letter dated March 22, 1996, the staff concluded that the best estimate of the copper and nickel content in the surveillance weld was 0.2254 and 0.534, respectively.
In addition, it was reported that the licensee's best estimate for copper and nickel in the surveillance weld were 0.2144 and 0.504.
Discuss the basis for the values of copper and nickel in the surveillance weld reported in Table 5-4A.
Furthermore, discuss how the chemistry factor for the surveillance weld reported on page 56 of WCAP-14684 was determined (i.e.,
provide the interpolation).
Response
(a)
The PTS SER (3/22/96) did not have the benefit of additional chemistry sampling results of surveillance capsules as provided in WCAP-14684 Table 5-4A.
This information was added per GL 92-01, which indicated that we should provide the latest available information.
4, Section 2.3, there were only 2 points for the surveillance chemistry available.
The additional 8
points changed the mean chemistry values
- and, therefore, the Chemistry Factor.
I
(b)
CF = 159.4'F used Cu =.236 and Ni =.517 in its determination as follows:
From 10CFR50.61, Table 1:
(1)
For Ni =.4:
Cu 9.23 = 140 Cu 9.24 = 144 (144-140)(6)
+ 1'40 = 142.4 10 (2)
For Ni =.6:
Cu 9
Cu 9
.23 = 169
.24 = 173 (173-169)(6)
+ 169 = 171.4 10 (3)
For Ni =.517 ~
(171.4 142 20
.4)(11.7)
+ 142.4 159.4 F CF M CF = 159.4 Question 3:
Clarify the thickness of the reactor vessel.
On page 22 of WCAP-14684, it indicates that the vessel thickness is 16.83 cm (6.6 inches).
On page 52,
- however, the thickness reported as 6.5 inches.
Discuss the reason for the apparent discrepancy.
Response
The RG&E value used is the nominal 6.5" thickness value versus the specific 6.6" thickness.
RG&E considers that using the 6.5" nominal value is conservative with respect to fluence.