ML19344A815
| ML19344A815 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 08/09/1978 |
| From: | Dunn C DUQUESNE LIGHT CO. |
| To: | Stello V NRC OFFICE OF INSPECTION & ENFORCEMENT (IE), Office of Nuclear Reactor Regulation |
| References | |
| REF-GTECI-A-36, REF-GTECI-SF, TASK-A-36, TASK-OR TAC-07972, TAC-7972, NUDOCS 8008220267 | |
| Download: ML19344A815 (2) | |
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435 Sixth Avenue Pittsburgh, Pennsylvania August 9, 1978 Director, Nuclear Reactor Regulations Division of Operating Reactors United States Nuclear Regulatory Cor71ssion Attention: Victor Stello Jr., Dire: tor Washington, D. C.
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Reference:
Beaver Valley Power Station, Unit No.1 Docket No. 50-334 Response to May 17, 1978 Request On Overhead Handling Systems Gentlemen:
Your May 17, 1978 letter requesting information on the movement of heavy loads near spent fuel has been reviewed.
Our response is as follows:
1.
The physical relation between the reactor core fuel transfer canal, spent fuel and set down areas can be found in Beaver Valley Power Station Final Safety Analysis Report Figures 5.1-5, 5.1-1 and 1.2-10.
2.
No objects were identified that are required to be moved over the reactor core or spent fuel storage pool.
3.
Pres'.atly there has been no vendor identified to provide a shipping cask for spent fuel and this information is not available.
4.
Section 14.2 of the FSAR and Section 9.2 of the Nuclear Regulatory Commission Safety Evaluation Report describe a cask drop accident at Beaver Valley Power Station.
5.
No heavy loads can be identified that are moved over safety equipment required to operate during a safe shutdown. The conclusion is based on the physical arrangement of the Reactor Containment (Figure 1.2-10).
6.
Section 14.2 of the FSAR and Section 9.2 of the Nuclear Regulatory Commission Safety Evaluation Report describe a cask drop ar.ident at Beaver Valley Power Station.
' Beaver Valley Power Station, Unit No.1 Docket No. 50-334 Response to May 17, 1978 Request On Overhead Handling Systems Page 7.
Tbe Beaver Valley Power Station design features that affect the p'atential for a heavy load accident are dercribed in Sections 14.2 and 9.12 of the Final Safety Analysis Report.
8 As there has p en no_ identified._ load, there presently are no procedures. Procedures do exist for moving all reactor internals
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and can be furnished if required.
9.
The following sections of the Final Safety Analysis Report describe the design of the spent fuel storage f acility and the degree of compliance to Regulatory Guide 1.13:
Sections 9.5, 9.12 and 11.3.
If you have any further questions regarding this response, please contact my office.
Very truly yours,
/
t.n~
C. N. Dunn Vice President, Operations
/ cc: Director of Nuclear Reactor Regulation United 5tstes Nuclear Regulatory Commission Attention:
A. Schwencer, Chief Branch No. 1 Division of Operating Reactors Washington, D. C.
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