ML19098B436
| ML19098B436 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 04/06/1977 |
| From: | Stallings C Virginia Electric & Power Co (VEPCO) |
| To: | Reid R, Rusche B Office of Nuclear Reactor Regulation |
| References | |
| Serial No. 045/020177 | |
| Download: ML19098B436 (3) | |
Text
e VIRGINIA ELECTRIC AND RICHMOND, VIRGINIA 23261 April 6, 1977,.
Mr. Benard C. Rusche Director of Nuclear Reactor Regulation U. s. Nuclear Regulatory Cormnission Washington, D. C. 20555 Attn: Mr. Robert W. Reid, Chief Operating Reactors Branch 4
Dear Mr. Rusche:
Serial No. 045/020171 P08M/ALH:dgt Docket Nos. 50~280 50-281 License Nos. DPR-32 ffegtlJR~y We have been conducting a re-evaluation of the radiological consequences of a Loss of Coolant Accident (LOCA), at the Surry Power Station. We have en-countered a great deal of difficulty in that Surry was licensed and built to standards that have since changed. As a result, there are no firm guidelines to be used in conducting our examination. Your *Staff has been very cooperative in that several meetings, site visits and conference phone conversations have been required of them, and they have helped us to understand the basic con-cerns which must be addressed.
We have tried our utmost to find a satisfactory analytical solution to the problem, but have been unable to do so. We have concluded that certain plant modifications will be necessary to provide confidence that 10CFRlOO guidelines are met using present and future guidelines. Without the plant modifications, our analysis would be weak and very difficult to defend with present day guidelines.
The changes that we are planning to make are being engineered at this time. Preliminary design is nearly completed, but extensive final design work, implementation procedures and testing procedures still must be develop-ed and approved. These changes are being implemented to: 1) Improve contain-ment spray coverage; 2) Eliminate time delays associated with the gravity feed chemical addition system; 3) Assure that contairunent temperature is al-ways maintained at its design value or less; 4) Reduce the radiation dose to control room personnel during a LOCA. We are not able to describe the equip-ment changes in detail at this time since the design work is still in pro-gress. However, we will provide you with this information at our earliest opportunity.
Since we have spent a great deal of time attempting to find a solution to the problem, we have not been able to give much attention to your recent request for information. Until recently, we were of the opinion that we could meet an April 5, 1977 deadline for providing answers to your questions. At this time, it is obvious that we cannot meet this deadline. We intend to meet the following schedule: 1) Complete preliminary design by April 30, 1977; 2)
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" VIRGINIA ELECTRIC AND POWER COMPANY TO Mr. Benard c. Rusche Page No. 2 Provide the information requested by your staff,not later than May 10, 1977;
- 3) Complete final design by ilJ.f~~ 1,, 1977.; *4) Start field fabrication by October 1977.
We believe that this approach is most satisfactory, and that it will pro-vide a reasonable long term solution to the problem.
Very truly yours,
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- c. M. Stallings Vice President-Power Supply and Production Operations
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