ML19319B340
| ML19319B340 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 12/30/1974 |
| From: | Schwencer A Office of Nuclear Reactor Regulation |
| To: | Roe L TOLEDO EDISON CO. |
| References | |
| NUDOCS 8001150833 | |
| Download: ML19319B340 (3) | |
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L PDR Docket Files Docket No. 50-346 LWR 2-3 Rdg RDeYoung VAMoore FSchroeder The Toledo Edison Company AKenneke Attn Mr. Lowell E. Roe MWilliams Vice President, Facilities RKlecker Development OGC 300 Edison Plaza R0 (3)
Tolado, Ohio 43652 EGoulbourne LEngle TR BC's Gentlemen:
LWR BC's As a result of peu continuing review of the Final Safety Analysis Report (FSAR) for the Davis-Basse Nuclear Power Station, Unit 1, va have developed a Regulatory position and a number of requests for additional information. The Reguistory position is listad in and requests for additional information are listed in.
We request that you amend your FSAR to conform with the enclosed position and to provide the additional infornation requested.
In order to maintain our licensing schedule, we will need your responses to Enclosures 1 and 2 by February 28, 1975. If you cannot meet this date..please inform us within seven (7) days af ter receipt of this letter so that we may revise our scheduling.
If you plan to appeal to Licensing Management on the position specified in Enclosure 1, please advise us of your intentions within two weeks.
Please contact me or Mr. Leon Engle if you have any questions ret;ard-o ing the enclosed position and information raquests, g
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A. Schwencer, Chief Light Water Rasctors Branch 2-3 Directorate of Licensing bec:
J. R. Buchanan, ORNL Encine T. 3. Abernathy, DTIE 1.
Ragulatory Position 2.
Raquests for Additional Information
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EUCL0SURE 1
REGULATORY POSITION TOLEDO EDISON COMPANY DAVIS-BESSE NUCLEAR POUER STATION, UNIT 1 DOCKET No. 50-346 POSITION 16.05 Pursuant to Section 4.15.2.3.2 of Section 16 (Technical Specifications), it is the staff's position that the following penetrations should be included in the list of those penetrations which will be testad' ca potential bypass leak paths (penetration numbers correspond to thoce given in your Response 6.2.23):
1.
Eccause multiple valves in series are no assurance of non-leakage, include the follouing penetrations as potential bypass leah paths:
29, 49, 44A, 47A, 47B, 71C, 74C, 67, 69 2.
All penetrations uhich do not terminate in a treated region and.have been excluded fron the list of potential bypass leak paths because they have double gasket seals should be included in the list. Any leakage detected.during tests, or the sensitivity of the test if zero leakage is detected, should be included in the bypass leakage.
3.
The following penetrations should be included in. the list of potential bypass leak paths or provision should be made to assure that the pressure of the fluid in these lines will not drop below containment design
-- p ressure :
2, 18, 35, 36, 37, 38, 39, 40, 57, 58, 52, 53, 54, 55, 56 In addition, all boundaries.which interface with contain-
.4.. ment atmosphere and atmosphere outside the treated regions should be tested as potential bypass leak paths and any leakage (or the test sensitivity if zero leakage is measured) included in the bypass leakage fraction.
- Examples of such baundaries 'are guard pipes and the personnel locks.
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a ENCL 0SURE 2
REQUESTS FOR ADDITIONAL INFORMATION TOLEDO EDISON C0:iPANY DAVIS-BESSE NUCLEAR STATION, U'11T 1 DOCKET No. 50-346 REQUEST NO.
2.4.11 You have not demonstrated that the maximum temperature rise in the intake forebay crea (ulticate heat sink) during a LCCA vill be within the allawchle limits of safety related equiprcat as sugges ted in Rag ilatory Guide 1.27.
We request that you either furnish the required substantiations or provide an alternative Category I Water Supply.
2.4.12 You have not substantiated your analysis of the effect of a ground uater radmaste spill on the acarest potable water supply.
Provide calculations of travel tiae to the nearest water supply and include valuen, and bases thereof, for the gradient, permeability and ef fectiva porosity used in your calculations.
2.4.13 You have not denonstrated that the intake structure will be safe fron flooding and loss of function due to waves in the intake canal and reflected uaves of f the uave protection dike, due to an assumed loss of dike at the lake intercept of the canal during conditions of severe wave activity.
Provide substantiated analysis that demonstrates that the intake structure will remain functional under these postulated conditions.
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