ML20196D804
| ML20196D804 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 12/06/1988 |
| From: | Shelton D TOLEDO EDISON CO. |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| TAC-67394, TAC-68250, NUDOCS 8812090201 | |
| Download: ML20196D804 (2) | |
Text
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q TOLEDO EDISON 4 cm % cowy DONALD Cs SHEL JN UNsIeE7 t
Docket Number 50-346 License Number NPF-3 i
Serial Number 1578 December 6, 1988 l
United States Nuclear Regulatory Commission 1
Document Control Desk Vashington, D. C.
20555
Subject:
Designation of Davis-Besse Nuclear Power Station as the Lead B&V Plant Regarding the License Amendment Request to Revise the Main Steam Safety Valve Capacity /High Flux Trip Setpoint Relationship (TAC Number 68250)
Gentlemen:
This letter is being submitted to provide additional information regarding Toledo Edison's License Amendment Request (LAR) of March 4, 1988 (Serial i
Number 1487) and supplemented by letter dated May 4, 1988 (Serial Number 1520). This LAR concerned Technical Specification Section 3/4.7.1.1 (Main Steam Safety Valves) Table 3.7-1 (Maximum Allovable High Flux Trip Setpoint Vith Inoperable Steam Line Safety Valves). Table 4.7-1 (Main Steam Line Safety Valve Lift Settings), and Bases Section 3/4.7.1.1 (Turbine Cycle-Safety Valves).
A portion of this License Amendment Request was issued as Amendment Number 117, dated August 24, 1988 (TAC Number 67394). The additional proposed i
changes cited in the License Amendment Request related to revision of Technical Specification Section 3.7.1.1, Action b Bases Section 3/4.7.1.1, l
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and delettors of Table 3.7-1 to allov the high flux trip setpoint reduction due 1
to an inoperable safety valve (s) to directly reflect the actual loss of steam relieving capability versus the unnecessarily conservative relationship 4
(resulting in an increased reactor power penalty) presently employed in the l
Technical Specifications, and the revision of Technical Specification 4.7.1.1 and deletion of Table 4.7-1 to eliminate the specific safety valve setpoints and incorporation of ASME Section III requirements for setpoint adjustment
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vere not included with Amendment Number 117. Rather, the letter transmitting Amendment Number 117 stated these portions of the proposed amendment vere being reviewed separately, and a new TAC Number (68250) vas assigned to this
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j activity.
The NRC subsequently informed Toledo Edison that the request may be judged generic since the requested change deviates from the B&V Standard Technical i
specifications. This matter has been discussed with the B&V Ovners Group Technical Specification Committee. The Committee agrecs with Toledo Edison'
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if THE TOLEDO EDtSON COMPANY EDSON PLAZA 300 MAD:50N AVENUE TOLEDO OH'O 43652 ast2o9o2ot set 2o6 h!
PDR ADOCK 05000346 P
' Docket Nu ber 50-346 Liccnsa Nu;b:r NPF-3 Serial Number 1578 Page 2 position and, therefore, has no objections to the Davis-Besse Nuclear Power Station (DBNPS) pursuing this issue as the lead B&V plant.
It should be noted that the B&V0G plans to incorporate this issue in the revised B&V Standard Technical Specifications being developed as part of the NUMARC Technical Specification Vorking Group.
For this reason Toledo r,dison requests that you consider the above cited portion of the March 4, 1988 LAR as a project whereby DBNPS is the lead B&V plant for the issue.
If you have any questions, please contact Mr. R. V. Schrauder, Nuclear Licensing Manager, at (419) 249-2366.
Very truly yours, b'vv M RMC/dle Attachment cci P. M. Byron, DB-1 NRC Resident Inspector A. B. Davis, Regional Administrator, NRC Region III 3
1 A. V. DeAgazio, DB-1 NRC Senior Project Manager i
State of Ohio 4
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