ML19332A226
| ML19332A226 | |
| Person / Time | |
|---|---|
| Site: | Zion File:ZionSolutions icon.png |
| Issue date: | 09/04/1980 |
| From: | Naughton W COMMONWEALTH EDISON CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| REF-GTECI-A-02, REF-GTECI-RV, TASK-A-02, TASK-A-2, TASK-OR NUDOCS 8009110300 | |
| Download: ML19332A226 (2) | |
Text
'
f
. Commonwealth Edison
/
) _One First National PIva. Chicago, Ilhnois 7 Addr.ss Reply t;: Post Othc2 Box 767 j Chicago, Ilknois 60690 s
September 4, 1980 Mr. Harold R. Denton, Director Of fice of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555
Subject:
Zion Station Units 1 and 2 Additional Information on Asymmetric Vessel Loads NRC Docket Nos. 50-295 and 50-304 References (a):
January 25, 1980 letter from V. Stello to All PWR Licensees (b):
February 14, 1980 letter from D. L. Peoples to A.
Schwencer
Dear Mr. Denton:
Per Reference (a), the NRC Staff requested Commonwealth Edison Company to evaluate asymmetric loads that could develop during a Loss of Coolant Accident (LOCA).
Per Reference (b),
Commonwealth Edison referenced for Zion Station all the Westinghouse Owners Group work performed on breaks outside the reactor cavity as well as the effect of breaks inside the cavity on the reactor vessel l
and supports and ECCS piping attached to the system.
Reference (b) also indicated that the results of evaluations of reactor interal structures, fuel and control rod drive mechanisms would be submitted for Staff review by July 1980.
This was accomplished for Zion Station per Westinghouse letter NS-TMA-2266 dated June 30, 1980 from T. M. Anderson to D. G.
Eisenhut.
This submittal contained WCAPs-9748 and -9749, the proprietary and non-proprietary versions of " Westinghouse Owner Group Asymmetric LOCA Load Evaluation - Phase C."
As indicated in the Westinghouse letter, the evaluations described in the WCAP reports demnnstrate the capability of the Zion plants to withstand the effects of the postulated reactor vessel nozzle rupture.
Additionally, the reports show that the appropriate systems and components will maintain their functional capability and insure a safe plant shutdown.
Additionally, on June 30, 1980 per Westinghouse letter NS-TMA-2264 from T.
M.
Anderson to D. G. Eisenhut, Revision 1 to WCAPs-9558 and -9570, were submitted.
These documents discuss the mechanistic fracture toughness of the rerct:ir coolant system.
They fod f// O 3 o o P
Commonwealth Edison Mr. Harold _R.
Denton, Director September 4, 1980 Page 2 are applicable to the subject dockets and supercede Revision 0 of the same WCAPs.
Please address any questions that you might have concerning this matter to this office.
One (1) signed original and thirty-nine (39) copies of this letter are provided for your use.
Very truly yours, L
William F. Naugh n
Nuclear Licensing Administrator Pressurized Water Reactors 6471A