ML20080D006
| ML20080D006 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 08/22/1983 |
| From: | Westafer G FLORIDA POWER CORP. |
| To: | Stolz J Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.E.1.1, TASK-TM 3F-0883-08, 3F-883-8, NUDOCS 8308290439 | |
| Download: ML20080D006 (3) | |
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August 22, 1983 i
Director of Nuclear Reactor Regulation Attention:
Mr. John F. Stolz, Chief Operating Reactors Branch No. 4 Division of Licensing U.S. Nuclear Regulatory Connission
Subject:
Crystal River Unit 3 Docket No. 50-302 Operating License No. DPR-72 NUREG-0737, Item II.E.1.1 Auxiliary Feedwater System Evaluation
Dear Mr. Stolz:
Florida Power Corporation (FPC) is providing responses to items 4 and 8 of your letter dated August 19, 1982.
FPC has provided a response to all other items of your letter on:
1.
November 19, 1982 (#3F-1182-06, P.
Y.
Baynard; Items 1, 2, 3,
5, 6, 7, and 9), and 2.
December 17,1982(#3F-1282-19, G. R. Westafer, Item 10)
In addition we are providing updated information on Items 5, 6 and 9.
Item 4 - Provide a means of eliminating the single failure potential in the recirculation lines of the EFS pumps.
Response 4 - FPC is considering the benefits that can be derived from installing flow sensors in the EFS recirc'ilation lines and tripping the EFS pumps on pre-set sensor limits. A uSedule will be determined and reported to you when a modification is approved.
Item 5 - Propose technical specifications which requi re a monthly inspection to verify that the locked open valves in the EFS flow path are locked and in the proper position.
Response 5 - FPC submitted a change to Technical Specification 4.7.1.2.a.(3) to require surveillance to verify, that valves in the EFS flow path are locked and in the proper position, at least once per 31 days.
The NRC issued this Technical Specification in License Amendment 64, dated July 12, 1983.
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PDR General Office 32o1 Thirty-fourth street soutn. P O Box 14o42. St. Petersburg. Florida 33733 813-866-5151 l
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August 22, 1983 3F-0883-08 Page 2 4
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Item 6 - Propose Technical Specifications which require that the normal flow path from the primary EFS water source to the steam genor-ators be verified following a refueling shutdown or any cold shutdown of longer than 30 days duration.
Response 6 - Since responding to this item in our letter of October 19, 1982, FPC has verbally reported intent to propose Technical Speci-fications that verify the normal EFS flow path by delivering feedwater to the steam generators. However, the water quality of the condensate storage tank (primary water source) is such that delivery of this water may cause potential degradation of the steam generator inter-nals.
Therefore, FPC will not propose Technical Specifications to verify the normal flow path of emergency feedwater by this method.
Item 8 - Revise your design to provide one of the alternatives out-lined in Recommendation GS-2 (Part III.c.2 - Recommendation GL-2).
Response 8 - In order to provide redundant parallel valves in the EFS, FPC is planning to:
1.
Remove the internals of valve number CDV-103; and 2.
Install parallel bypasses around pump suction valve numbers EFV-3 and EFV-4.
These modifications require "down-time" so they are planned for com-pletion in Refuel Outage V which is currently planned for the Spring of 1983.
Item 9 - Evaluate the design of the EFS water supply to determine if automatic protection of the pump is necessary following a tornado as stated in Recommendation GL-4.
Response 9 - In order to assure protection of the EFS pumps, FPC is evaluating the merits of tornado protection for the EFS water supply or construction of a dedicated back-up supply. When a modification is j
approved FPC will provide a completion schedule.
These Items are being evaluated with other discretionary projects based on future budget approval (s) and cost-benefits that can be derived from proposed modifications.
1 l-
August 22, 1983 3F-0883-08 Page 3 Responses to all (10) items of your letter dated August 19, 1982 are up-to-date. We will provide an update en these items in December, 1983.
Sincerely, i
LJ G. R. Westafer i
Manager, Nuclear Operations Licensing and Fuel Management l
Dicesaro(F01)C1-1 j
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