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e TOLEDO EDISON Docket No. 50-346 JOE VVILUAMs JR. | |||
s-, v.a net . w M19) 249 2300 License No. NPF-3 sisi 24a sen Serial No. 1293 July 29, 1986 Director of Nuclear Reactor Regulation Attention: Mr. John F. Stolz PWR Project Directorate #6 - | |||
Division of PWR Licensing-B United States Nuclear Regulatory Commission Washington, D. C. 20555 | |||
==Dear Mr. Stolz:== | |||
NUREG-0737, TMI Action Item II.K.3.31 requested each licensee to submit to the NRC its plant-specific small-break-loss-of-coolant accident (SBLOCA) calculations to demonstrate compliance with 10 CFR 50, Appendix K, ECCS Evaluation Models., Davis-Besse Nuclear Power Station Unit No. 1 is participating in the Babcock and Wilcox (B&W) Owners Group effort currently preparing a SBLOCA spectrum study for raised and lowered loop plant configurations. The analysis is being performed using the modified CRAFT 2 computer code (BAW-10092) and the SBLOCA ECCS evaluation model (BAW-10154) approved by the NRC under Item II.K.3.30 (Log No. 1782). | |||
In a letter from Mr. C. H. Turk, Chairman of the Analysis Committee, to Mr. W. Paulson, NRC, dated June 18, 1986, the B&W Owners Group notified the NRC of a delay in submitting the analysis. B&W has recently encountered several difficulties in performing the required computer analyses due to the conversion of computer link-ups between Lynchburg, Virginia and Dallas, Texas. As a result, B&W is projecting a two-month delay in the submittal of the Item II.K.3.31 analysis. Therefore, Toledo Edison confirms that the projected submittal date is revised from July 31, 1986 (Serial No. 1176) to September 30, 1986. | |||
Very truly yours, fC) 166 y , | |||
:DRW:p1f If cc: DB-1 NRC Resident Inspector 8608120197 860729 > | |||
PDR ADOCK 05000346 C P PDR 5 TOLEDO, OH:0 43652 | |||
\D THE TOLEDO EDISON COMPANY ED! SON PLAZA 300 Maul 50N AVENUE | |||
. . . .}} | |||
Revision as of 05:45, 30 December 2020
| ML20205B872 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 07/29/1986 |
| From: | Williams J TOLEDO EDISON CO. |
| To: | Stolz J Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.K.3.31, TASK-TM 1293, NUDOCS 8608120197 | |
| Download: ML20205B872 (1) | |
Text
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e TOLEDO EDISON Docket No. 50-346 JOE VVILUAMs JR.
s-, v.a net . w M19) 249 2300 License No. NPF-3 sisi 24a sen Serial No. 1293 July 29, 1986 Director of Nuclear Reactor Regulation Attention: Mr. John F. Stolz PWR Project Directorate #6 -
Division of PWR Licensing-B United States Nuclear Regulatory Commission Washington, D. C. 20555
Dear Mr. Stolz:
NUREG-0737, TMI Action Item II.K.3.31 requested each licensee to submit to the NRC its plant-specific small-break-loss-of-coolant accident (SBLOCA) calculations to demonstrate compliance with 10 CFR 50, Appendix K, ECCS Evaluation Models., Davis-Besse Nuclear Power Station Unit No. 1 is participating in the Babcock and Wilcox (B&W) Owners Group effort currently preparing a SBLOCA spectrum study for raised and lowered loop plant configurations. The analysis is being performed using the modified CRAFT 2 computer code (BAW-10092) and the SBLOCA ECCS evaluation model (BAW-10154) approved by the NRC under Item II.K.3.30 (Log No. 1782).
In a letter from Mr. C. H. Turk, Chairman of the Analysis Committee, to Mr. W. Paulson, NRC, dated June 18, 1986, the B&W Owners Group notified the NRC of a delay in submitting the analysis. B&W has recently encountered several difficulties in performing the required computer analyses due to the conversion of computer link-ups between Lynchburg, Virginia and Dallas, Texas. As a result, B&W is projecting a two-month delay in the submittal of the Item II.K.3.31 analysis. Therefore, Toledo Edison confirms that the projected submittal date is revised from July 31, 1986 (Serial No. 1176) to September 30, 1986.
Very truly yours, fC) 166 y ,
- DRW:p1f If cc: DB-1 NRC Resident Inspector 8608120197 860729 >
PDR ADOCK 05000346 C P PDR 5 TOLEDO, OH:0 43652
\D THE TOLEDO EDISON COMPANY ED! SON PLAZA 300 Maul 50N AVENUE
. . . .