ML17251A709
| ML17251A709 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 07/08/1986 |
| From: | Kober R ROCHESTER GAS & ELECTRIC CORP. |
| To: | Lear G Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.K.3.31, TASK-TM GL-83-35, NUDOCS 8607110002 | |
| Download: ML17251A709 (10) | |
Text
REQULATO INFORNATION DISTRIBUTION TEN (RIDS)
ACCESSION NBR: 8607110002 DOC. DATE: 86/07/11 NOTARIZED:
NO FACIL:50-.244 Robert Emmet Ginna Nuclear Planti Unit i. Rochester C
AUTH. NAIVE AUTHOR AFFILIATION KGB ER> R. W.
Rochester Qas 8c Electric Corp.
REC IP. NANE RECIPIENT AFFILIATION LEARN Q. E.
PNR Prospect Directorate 1
SUBJECT:
Advises that MCAP-11145 referenced to satisfy'eneric Ltr 83-35 re TNI Action Item II. K. 3. 31 requirements. Licensing basis conservative Zc valid for demonstrating adequacy of ECCB to mitigate small break LOCA.
DISTRIBUTION CODE:
A045D COPIES RECEIVED: LTR I
ENCL 0 SIZE:
TITLE: OR'ubmi tta1 Emer g enc g Prep Corr esp ond enc e NOTES:License Exp date in accordance with 10CFR2i 2. 109(9/19/72).
DOCKET I 05000244 05000244 RECIPIENT ID CODE/NAl'IE PLlR-A PD1 LA FAIRTILE> l1 01 CQP IEB LTTR ENCL RECIPIENT ID CODE/MANE PNR-A PD1 PD COP IEB LTTR ENCL INTERNAL: ~Q FIL EPl3 06 04 IE/DEPER/ IRB 12 RQN1 EXTERNAL: LPDR NSIC 03 NRC PDR 02 TOTAL NUNBER OF COP IEB REQUIRED:
LTTR 1 1 ENCL
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11A1E ROCHESTER, N. K 14649-0001 ROGER W. KOBER Vee PRESDERT ELECTRIC G STEAM PRODUCTION TELEPHONE ARE'A coDE TIE 546-2700 Director of Nuclear Reactor Regulation Attention:
Nr. George E. Lear
< Chief PWR Project Directorate No.
1 U.S. Nuclear Regulatory Commission Washingtoni D.C.
20555
Subject:
THI Action ITEN II.K.3.31 R.
E. Ginna Nuclear Power Plant Docket No. 50-244
Reference:
l.
NRC Generic Letter 83-35 from D. G. Eisenhuti "Clarification of TNI Action Plant Item II.K.3.31"I November 2I 1983 2.
L. D. Butterfield letter to J.
Lyons>
"Westinghouse Owners Group Transmittal of WCAP-11145I OG-190I June lli 1986
Dear Nr. Lear:
TNI Action Item II.K.3.31 requires Rochester Gas and Electric Corporation (RG6E) to submit a plant specific analysis utilizing the new NRC approved NOTRUMP Small Break LOCA (SBLOCA) Evaluation Hodel (EN).
In Reference (1)I the NRC Staff indicated that the resolution of TNI Action Plan Item II.K.3.31 may be accomplished by generic analyses to demonstrate that the previous NRC approved WFLASH SBLOCA EH results were conservative when compared with the new NOTRUNP SBLOCA EM.
Such generic studies were undertaken by the Westinghouse Owners Group (WOG) for participating members including RG6E.
The WOG has completed these generic studies and has submitted the results of the analyses to the NRC in the topical report WCAP-11145 (Reference 2).
The purpose of this letter is to inform you that RGSE is referencing topical report WCAP-11145 in order to satisfy the requirements of TNI Action Item II.K.3.31 for R. E. Ginna in a generic fashion in accordance with Reference l.
Topical report WCAP-11145 documents the results of a series of Small Break LOCA (SBLOCA) analyses performed with the NRC approved NOTRUNP SBLOCA Evaluation Hodel.
Cold leg break spectrum analyses were performed for the limiting SBLOCA plant from each of the Westinghouse 4-loop, 4-loop Upper Head Injection (UHI)I 3-loopi and 2-loop plant categories.
The limiting SBLOCA plant in each category was defined on the basis of previous SBLOCA analyses which were performed with the NRC approved WFLASH SBLOCA EN.
In addition to the cold leg break spectrums>
a hot leg and pump 8607110002 860711I 9
PDR ADOCK 05000244 p
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'ROCHESTER GAS AND ELECTRIC CORP.
DATE TO Nr. George E ~ Lear SHEET NO.
suction break were performed as part of the 4-loop plant analyses<
confirming that the cold leg was still the worst break location.
Comparison of the NOTRUNP cold leg break spectrum results with the previously generated WFLASH results<
showed that the WFLASH results were conservative for all plant categories.
The generic results documented in WCAP-lll45< demonstrate that a plant specific reanalysis of the 2-loop Ginna plant with the NOTRUNP SBLOCA EN would result in the calculation of a 0
limiting PCT which would be significantly lower than the 1092 F
PCT currently calculated with the WFLASH SBLOCA EM.
Hence>
the WFLASH SBLOCA EN results which currently form the licensing basis for Ginna are conservative and still valid for demonstrating the adequacy of the Emergency Core Cooling System to mitigate the consequences of a SBLOCA> as required by 10CFR50.46.
It is therefore concluded that a plant specific analysis is not needed in order for Ginna to comply with TNI Action Item II.K.3.31.
WCAP-11145>
on a generic basis<
should satisfy the requirements of NUREG 0737 as stated in reference l.
Ve truly yours<
Ro r W. Kober
Q 0
REQULAT INFORMATION DISTRIBUTION STEN LRIDS)
ACCESSION NBR: 8607110002 DOC. DATE: 86/07/08 NOTARIZED:
NO DOCKET ¹ FACXL: 50-244 Robert Emmet Cinna Nuclear Plan%i Unit ii Rochester C
05000244 AUTH. NANE AUTHOR AFFXLIATIGN KOBERi R. M.'oc h ester Gas 8c El ec tric Corp.
REC IP. NANE REC IP XENT AFF XLIATION LEAR. Q. E.
PMR Prospect Directorate 1
SUBJECT:
Advises that MCAP-11145 referenced to satisfg Generic Ltr 83-35 re THX Action Xtem XI. K. 3. 31 requirements. Licensing basis conservative Zc valid for demonstrating adequacy of ECCS to mitigate small break LOCA.
DISTRIBUTION CODE:
A045D COPIES RECEIVED: LTR ENCL SIZE:
TITLE:
OR Submittal Emergency Prep Correspondence NOTES:License Exp date in accordance with 10CFR2i 2. 109(9/19/72).
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LTTR 11 ENCL
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Director of Nuclear Reactor Regulation Attention:
Mr. George E. Leari Chief PWR Project Directorate No.
1 U.S. Nuclear Regulatory Commission Washington>
D.C.
20555
Subject:
TMI Action ITEM II.K.3.31 R.
E. Ginna Nuclear Power Plant Docket No.
50-244
Reference:
1.
NRC Generic Letter 83-35 from D.
G. Exsenhuti "Clarification of TMI Action Plant Item II.K.3.31" <
November 2I 1983 2.
L. D. Butterfield letter to J.
Lyonsi "Westinghouse Owners Group Transmittal of W AP-1114&I OG-190I June lli 1986
Dear Mr. Lear:
TMI Action Item II.K.3.31 requires Rochester Gas and Electric Corporation (RG&E) to submit a plant specific analysis utilizing the new NRC approved NOTRUMP Small Break LOCA (SBLOCA) Evaluation Model (EM).
In Reference (1) I the NRC Staff indicated that the resolution of TMI Action Plan Item II.K.3.31 may be accomplished by generic analyses to demonstrate that the previous NRC approved WFLASH SBLOCA EM results were conservative when compared with the new NOTRUMP SBLOCA EM.
Such generic studies were undertaken by the Westinghouse Owners Group (WOG) for participating members including RG&E.
The WOG has completed these generic studies and has submitted the results of the analyses to the NRC in the topical report WCAP-11145 (Reference
- 2).
The purpose of this letter is to inform you that RG&E is referencing topical report WCAP-11145 in order to satisfy the requirements of TMI Action Item II.K.3.31 for R.
E. Ginna in a generic fashion in accordance with Reference l.
Topical report WCAP-11145 documents the results of a series of Small Break LOCA (SBLOCA) analyses performed with the NRC approved NOTRUMP SBLOCA Evaluation Model.
Cold leg break spectrum analyses were performed for the limiting SBLOCA plant from each oi the Westinghouse 4-loop, 4-loop Upper Head Injection (UHI),
3-loopI and 2-loop plant categories.
The limxtxng SBLOCA plant in each category was defined on the basis of previous SBLOCA analyses which were performed with the NRC approved WFLASH SBLOCA EM.
In addition to.the cold leg break spectrumsi a hot leg and pump 860711000-'60/11 gng g1Se PDR ADQCY. OFOOO 44 PDf(
0
'I Q
b1r. Georg e E.
Lea r suction break were performed as part of the 4-loop plant analyses<
confirming that the cold leg was still the worst break location.
Comparison of the NOTRUHP cold leg break spectrum results. with the previously generated WFLASH results<
showed that the WFLASH results were conservative for all plant categories.
The generic results documented in WCAP-lll45r demonstrate that a plant specific reanalysis of the 2-loop Ginna plant with the NOTRUNP SBLOCA Et] would result in the calculation of a
limiting PCT which would be significantly lower than the 1092 F
0 PCT currently calculated with the WFJ ASH SBLOCA EN.
Hence>
the WFLASH SBLOCA E!0 results which currently form the licensing basis for Ginna are conservative and still valid for demonstrating the adequacy of the Emergency Core Cooling System to mitigate the consequences of a
SBLOCA< as required by 10CFR50.46.
It is therefore concluded that a plant specific analysis is not needed in order for Ginna to comply with TNI Action Item II.K.3.31.
WCAP-11145>
on a generic basis>
should satisfy the requirements of NUREG 0737 as stated in reference 1.
Ve truly yours'o
~r W. Kober