ML19253B278
| ML19253B278 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 09/21/1979 |
| From: | Reid R Office of Nuclear Reactor Regulation |
| To: | Lundvall A PACIFIC GAS & ELECTRIC CO. |
| References | |
| NUDOCS 7910100643 | |
| Download: ML19253B278 (4) | |
Text
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UNITEC STATE 3 g
J 7) e(y i NUCLEAR REGULATORY COMMISSION "4,\\
/.. E WASHINGTON, D. C. 20555
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September 21, 1979 Docket No.: 50-317 Mr. A. E. Lundvall, Jr.
Vice President - Supply Baltimore Gas & Electric Company P. O. Box 1475 Baltimore, Maryland 21203 Cear Mr. Lur.dvall:
In the continuation of our review of your July 3,1979 request regarding spent fuel pool modification for Calvert Cliffs t: nit No.1, we find that a second set of additional informa*. ion as detailed in the enclosure is needed to ccmplete our review.
In order to ccmplete our review in a timely ranner, please pro /ide the additional information at your earliest convenience.
Sincerely, s
j nobert W. Reid, Chief Operating Reactors Branch 14 Division of Operating Reactors
Enclosure:
Request for Additional Infor ation cc w/ enclosure.
See next page 7910100[@3 g
p 1124 092
Baltimore Gas & Electric Company cc:
Janes A. Biddison, Jr.
Mr. R. M. Douglass, Manager General Counsel Quality Assurance Department G and E Builcing Room 923 Gas & Electric Building Charles Center P. O. Box 1475 Baltimore, Maryland 21203 Baltimore, Maryland 21203 George F. Trowbridge, Esquire Shaw, Pittnan, Potts and Trowbridae 1800 M Street, N.u.
Washington, D. C.
20036
!!r. R. C... Ol son Baltimore Gas and Electric Company Room 922 - G and E Building Post Of fice Box 1475 Baltimore, Maryland 21203 Mr. Leon B. Russell, Chief Engineer Calvert Cliffs Huclear Power Plant Balticore Gas and Electric Company Lusoy, tiaryland 20657 Bechtel Power Corporation ATTH: tir. J. C. Judd Chief Nuclear Engineer 15740 Shady Grove Road Gaithersburg, Maryland 20760 Ccnbustion Engineering, Inc.
ATTH: fir. P. W. Kruse, Manager Engineering Services Post Office Box 500 Windsor, Connecticut 06095 Calvert County Library Prince Frederick, liaryland 20673 1124 093 a
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ENCLOSURE REQUEST FOR ACDITIONAL INFORMATION CALVERT CLIFFS NUCLEAR PCWER PLANT SPENT FUEL STORAGE POOL MODIFICATION 1.
Discuss the provisiens employed to limit the maximum height of a fuel assembly passing over the rack assembly to 24 inches.
2.
Provide sufficient details of the rack base supporting structure, sliding surfaces, ali gaps (clearance and expansien) of the rack structure, and fuel handling system.
3.
Discuss the effects of the increased loads due to i.he new rack structures on the fuel pcol liner and structures.
4.
Discuss the effects of postulating inclined fuel assembly drop cn top of the rack.
5.
Describe the provisions employed to prevent movement of heavy objects over the spent fuel assemblies.
Include a description of all items which may be moved over the spent fuel assemblies. State whether the consequences of dropping any of these items dnto the rack are more severe than the fuel drop accident.
6.
Discuss the inservice surveillance plans, if any, that you have developed to assure long-term corrosien protections for the fuel rack system in the pool environment.
7.
Provide discussion on the material, fabricatier, installation and quality control of the spent fuel racks.
Indicate whe:hrr these requirements are in conformance with Subsection NF of the ASME Code.
8.
Provide the damping values used in the non-linear sliding analysis and include any justificatien for any values higner than those specified in the FSAR.
9.
Discuss the effect of the temperature gradient across the rack structure due to differential thermal effect between a full and empty cell.
- 10. For the accident fuel assembly drop condition, describe in detail the assumptions, type of analysis, ductility ratios and allewable stresses used in the analysis to insure that the acceptance criteria for this case are satisfied.
Provide, also, your basis for concluding that the leak tightness of the fuel pool is maintained, 11.
Indicate whether tilting motien of the racks and rack medules under seismic effects (CEE and SSE) has been considered in the analysis.
If so, provide the factor of safety under all loading combinations.
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- 12. Provide sufficient details (disucssion and sketches) regarding the mathematical models used in the seismic analysis.
Indicate hcw the shear forces in each module is calculated and discuss the effect of sliding on the response.
13.
Indicate ' this proposed modification conforms with the NRC position on fuel pool modificatier.s entitled "0T Position for Review and Acceptance of Spent Fuel Storage and Handling Applications", issued on April 14, 1978, and later amended on January 18, 1979, copy enclosed.
14.
Discuss the possibility of swelling in the cell centaining the B4C composite (inward and outward) due to offgasing generating internal pressure and discuss the provisions emoloyed to prevent such swalling or the provision employed such that withdrawal of the fuel assembly is insured.
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