ML20211P021
| ML20211P021 | |
| Person / Time | |
|---|---|
| Site: | Mcguire, Catawba, McGuire, 05000000 |
| Issue date: | 07/01/1986 |
| From: | Tucker H DUKE POWER CO. |
| To: | Harold Denton, Youngblood B Office of Nuclear Reactor Regulation |
| References | |
| TASK-2.K.3.31, TASK-TM GL-83-35, NUDOCS 8607110250 | |
| Download: ML20211P021 (3) | |
Text
DUKE Poimn GOMPANY P.O. BL 4 33189 CHARLOTTE, N.C. 28242 HAL B. TUCKER rat.myssons W503 PRESIDENT (704 GNO31 Ntt0 LEAR PRODUCTION i
July 1, 1986 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C.
20555 ATTENTION:
B.J. Youngblood, Director PWR Project Directorate #4
Subject:
McGuire Nuclear Station Catawba Nuclear Station
)
Docket Nos. 50-369, -370, -413, -414
Reference:
1.
TMI Action Item II.K.3.31 2.
NRC Generic Letter 83-35 from D.G. Eisenhut,
" Clarification of TMI Action Plant Item II.K.3.31", November 2, 1983 3.
L.D. Butterfield letter to J. Lyons,
" Westinghouse Owners Group Transmittal of WCAP-11145, OG-190, June 11, 1986 4.
D. Hood (NRC) letter to H.B. Tucker (Duke)
Dated May 13, 1986, transmitting Amendment No. 57 to NPF-9 and Amendment No. 38 to NPF-17
Dear Mr. Denton:
TMI Action Item II.K.3.31 requires that Duke Power Company submit a plant specific analysis utilizing the new NRC approved NGTRUMP Small Break LOCA (SBLOCA)
Evaluation Model (EM). In Reference (2), 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) of which Duke Power is a participating member. 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 3). The purpose of this letter is to inform you that Duke is n-9607110250 860701 DR ADOCK 0500 9
4 H.R. Denton July 1, 1986 Page 2 referencing topical report WCAP-11145 in order to satisfy the requirements of TMI Action Item II.R.3.31 for Catawba Nuclear Station in a generic fashion, in accordance with Reference 2.
For McGuire, the NRC Staff is directed to the plant specific analyses conducted in support of the removal of the Upper Head Injection System which has been reflected in amendments to the McGuire license (Reference 4).
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 of the Westinghouse 4-loop 4-loop Upper Head Injection (UHI), 3-loop, and 2-loop plant categories. The limiting SBLOCA plant in each category was defined en the basis of previous SBLOCA analyses which were performed with the NRC approved WFLASH SBLOCA EM.
In addition to the cold leg break spectrums, a hot leg and pump 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 j
the NOTRUNP cold leg break spectrum results with the previously generated WFLASH results, showed that the WFLASH results were conservative for all plant categories.
Additionally, the 4-loop UHI plant category results showed that the NOTRUNT SBLOCA EM calculated no core uncovery for any of the SBLOCA transients analyzed, whereas the previous WFLASH analysis calculated partial core uncovery with a limiting Peak Clad Temperature of 1499 degrees F."
The generic results documented in WCAP-11145, demonstrate that a plant specific reanalysis of Catawba with the NOTRUMP SBLOCA EM would result in the calculation of a limiting PC7 which would be significantly lower than the 1218 degrees F PCT currently calcuk.ed with the WFLASH SBLOCA EM.
Hence, the WFLASH SBLOCA EM results which currently form the licensing basis for Catawba are conservative and still valid for demonstrating the adequacy of the Emergency Core Cooling System (including the Upper Head Injection System) to mitigate the consequences of a SBLOCA, as required by 10CFR 50.46.
It is therefore concluded that a plant specific analysis is not needed in order for Catawba to conply with TMI Action Item II.K.3.31.
Rather, D ke references WCAP-11145 in order to comply with TMI Action Item II.K.3.31 on a generic basis, in accordance with Reference 2.
For McGuire Nuclear Station, the current licensing basis SBLOCA evaluation was performed with the NOTRUMP EM.
The results of the plant specific NOTRUMP SBLOCA analysis were provided to the NRC in support of the license amendments related to the disconnection of the Upper Head Injection System (Reference 4).
The resulting maximum PCT calculated for McGuire without the UEIS using NOTRUMP was 1488 degrees F for the break equivalent to a 3 inch diameter hole.
Since the analysis was performed with the approved NOTRUMP EM, the requirements of TMI Action Item II.K.3.31 have been satisfied on a plant specific basis for the McGuire Nuclear Station. This item was deliberately not reviewed and approved by the NRC Staff during the review of UHI removal.
It is appropriate at this time for the Staff to complete the review of the submittals with respect to the requirements of TMI Action Plan Item II.K.3.31.
e e
H.R. Denton July 1, 1986 Page 3 If there are any questions, please contact c r licensing representative directly.
i Very truly yours, i
L/B.kA W
Hal B. Tucker i
RLG/69/jgm Attachments xc:
Mr. W.T. Orders t
NRC Resident Inspector McGuire Nuclear Station Dr. J. Nelson Grace U.S. Nuclear Regulatory Commission - Region II
{
101 Marietta Street, NW, Suite 2900 l
l Atlanta, Georgia 30323
)
Mr. Darl Hood, Project Manager Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission j
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Washington, D.C.
20555 Dr. K.N. Jabbour i
j U.S. Nuclear Regulatory Commission 7920 Norfolk Avenue f
j Bethesda, Maryland 20814 i
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