ML20056D096
| ML20056D096 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 07/13/1993 |
| From: | Edison G Office of Nuclear Reactor Regulation |
| To: | Sieber J DUQUESNE LIGHT CO. |
| References | |
| TAC-M86473, NUDOCS 9308030352 | |
| Download: ML20056D096 (5) | |
Text
{{#Wiki_filter:l j July 13, 1993 l Docket No. 50-334 Mr. J. D. Sieber, Senior Vice President and Chief Nuclear Officer Nuclear Power Division Post Office Box 4 Shippingport, Pennsylvania 15077-0004
Dear Mr. Sieber:
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION RELATED TO CHANGE REQUEST NO. 202 i (TAC NO. M84673) On November 2, 1992, Duquesne Light Company (DLC) submitted an application to amend the Appendix A Technical Specifications (TS) for Beaver Valley Power Station, Unit 1. The proposed change would revise the TS to permit an increase in spent fuel pool capacity. Our review of this application is underway, but for us to complete our review we require additional information. The required additional information is described in the Enclosure. DLC is i requested to provide a response within 30 days of receipt of this letter so that the staff can continue its review on the schedule you have requested. The questions in the enclosure were discussed with Mr. Vassello of your staff on July 2, 1993. The requirements of this letter affect fewer than 10 respondents, and, therefore, are not subject to the Office of Management and Budget review under PL 96-511. Sincerely, Original signed b Gordon E. Edison, y: Senior Project Manager Project Directorate I-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Enclosure:
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1J - f- ,Jv "'4 9 .e_ a i i El E UNITED STATES l %(1 - NUCLEAR REGULATORY COMMISSION %, v p WASHINGTON, D.C. 205554001 July 13, 1993 Docket No. 50-334 Mr. J. D. Sieber, Senior Vice President and Chief Nuclear Officer Nuclear Power Division Post Office Box 4 Shippingport, Pennsylvania 1S077-0004
Dear Mr. Sieber:
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION RELATED TO CHANGE REQUEST NO. 202 i (TAC NO. M84673) On November 2,1992, Duquesne Light Company (DLC) submitted an application to amend the Appendix A. Technical Specifications (TS) for. Beaver Valley Power 1 Station, Unit 1. The proposed change would revise the TS to permit an increase in spent fuel pool capacity. Our review of this application is underway, but for us to complete our review we require addittonal information. The required additional information is described in the Enclosure..DLC is requested to provide a response within 30 days of receipt of this letter so that the staff can continue its review on the schedule yqu have requested. The questions in the enclosure were discussed with Mr. Vassello of your staff. on July 2, 1993. The requirements of this letter affect fewer than 10 respondents, and, therefore, are not subject to the Office of Management and Budget review under + PL 96-511. Sincerely, ? Gordon E. Edison, Senior Project Manager Project Directorate I-3 Division of Reactor Projects - I/II '[ Office.of Nuclear Reactor Regulation i t
Enclosure:
i Request for Additional information i 1 f ( i [ - 6
a s s Mr. J. D. Sieber Beaver Valley Power Station Duquesne Light Company Units 1 & 2 cc: Jay E. Silberg, Esquire Bureau of Radiation Protection Shaw, Pittman, Potts & Trowbridge Pennsylvania Department of 2300 N Street, NW. Environmental Resources Washington, DC 20037 ATTN: R. Barkanic Post Office Box 2063 Nelson Tonet, Manager Harrisburg, Pennsylvania 17120 Nuclear Safety Duquesne Light Company Mayor of the Borrough of Post Office Box 4 Shippingport Shippingport, Pennsylvania 15077 Post Office Box.3 Shippingport, Pennsylvania 15077 Commissioner Roy M. Smith West Virginia Department of Labor Regional Administrator, Region I Building 3, Room 319 U.S. Nuclear Regulatory Commission . Capitol Complex 475 Allendale Road 1 Charleston, West Virginia 25305 King of Prussia, Pennsylvania 19406 John D. Borrows Resident Inspector - Director, Utilities Department U.S. Nuclear Regulatory Commission Public Utilities Commission Post Office Box 181 180 East Broad Street Shippingport, Pennsylvania 15077-Columbus, Ohio 43266-0573 Director, Pennsylvania Emergency George S. Thomas Management Agency Vice' President, Nuclear Services Post Office Box 3321 Nuclear Power Division Harrisburg, Pennsylvania 17105-3321 Dudquesne Light Company P.O. Box 4 Ohio EPA-DERR Shippingport, Pennsylvania 15077~ ATTN: Zack A. Clayton Post Office Box 1049 Columbus, Ohio 43266-0149
Enclosure d REQUEST FOR ADDITIONAL INFORMATION ON THE SPENT FUEL POOL STORAGE RACK APPLICATION AT BEAVER VALLEY UNIT NO. 1 A. HEAVY LOADS 1. Discuss how the temporary crane, which is to be used to move fuel racks complies with the guidelines of NUREG-0612, Section 5.1.1. (7) which is shown below: "The crane should be designed to meet the applicable criteria and guidelines of Chapter 2-1 of ANSI B30.2-1976, " Overhead and Gantry Cranes" and of CMAA-70, " Specifications for Electric Overhead Travelling be accepted in lieu of specific compliance if the intent of the specification is satisfied." Provide the ultimate load this crane is able to hold and carry before any crane component or part fails. Provide the necessary assurance that the crane will not fall in the event of an earthquake or that such fall will not violate any of the criteria proposed in Section 5.1 (I-IV) " Recommended Guidelines" of NUREG-0612. 2. You plan to use the cask crane, which is " designated" as having a 125 ton capacity but presently rated at 60 tons, to move rack modules in and out of the cask pit. Discuss such movements with regard to the following:
- a. Show that the paths followed by the cask crane when moving racks are
" safe load paths," i.e. paths which would not endanger dual trains of safe shutdown equipment, spent fuel, or the integrity of the spent fuel pool (SFP).
- b. Explain the reason for derating this crane and how such derating affects the reracking process.
3. Provide a sketch of the remotely engagable lift rig. Explain what the ultimate load bearing capability of this rig would be in the normal course of operation and in the event of the worst single failure. 4. Explain the meaning of the phrase "--3 feet lateral free zone clearance- " in paragraph 3 of page 2 - 10 of Holtec Report HI-92791. Show how such clearance is to be maintained. Further, show either (1) that such clearance has the potential for avoiding any contact between racks in the SFP containing fuel with racks moving in and out of the SFP, or (2) that contact between racks will not cause damage to stored fuel with resulting excessive offsite doses or tendency to increase SFP criticality above the specified limit; also show that contact between l racks during such movement will not damage the SFP. 5. Discuss whether the rotational or translational motion (vertical or horizontal) imparted to a heavy load (a rack) as a result of the worst single failure in the handling system will adversely affect either spent fuel, the SFP, or safe shutdown equipment.
s . i 4 B. THERMAL / HYDRAULIC OVEST10NS i e 1. In Holtec report HI 92791, page 5-12 shows a temperature of 161* F for the SFP coolant in case la. Show that this presents no problem for the SFP. 2. The Updated Final Safety Analysis Report (page 9.5-4) states that the following systems are capable of providing makeup water for the SFP:
- 1. Primary grade water supply
- 2. Refueling water storage tank cooling systems
- 3. River water seismic Class I lines
- 4. Engine driven fire pump
- 5. Return of fuel building air conditioning condensate to the fuel pool.
Explain the following with regard to these systems:
- a. What is the minimum flow rate expected from each sy' stem into the SFP?
- t. How long (approximately) will it take to initiate each system under normal circumstances?
- c. Finally, can any of these systems be operated with onsite power?
is any special arrangement required to operate such systems when offsite power is not available?
- 3. It appears that decontamination is usually conducted -in the decontamination facilities adjacent to the fuel building. With that in mind, discuss your plan to " hydrolase" racks in the SFP. How can maintenance of SFP coolant clarity be assured.
Discuss your ability to deal safety with radioactive and other debris in the SFP as a result of 1 the racks hydrolasing.
- 4. The UFSAR shows that the operating temperature of the fuel pool ion exchanger is 140 F, while the design temperature is 200 F.
At what temperature does the resin in the ion exchanger start to deteriorate? p r s t i i}}