ML031980609
| ML031980609 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 07/25/2003 |
| From: | Vissing G NRC/NRR/DLPM/LPD1 |
| To: | Vanderheyden G Calvert Cliffs |
| Vissing G, NRR/DLPM, 415-1441 | |
| References | |
| TAC MB8896 | |
| Download: ML031980609 (6) | |
Text
July 25, 2003 Mr. George Vanderheyden, Vice President Calvert Cliffs Nuclear Power Plant, Inc.
Calvert Cliffs Nuclear Power Plant 1650 Calvert Cliffs Parkway Lusby, MD 20657-4702
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION, TECHNICAL SPECIFICATION CHANGE TO INCREASE SPENT FUEL POOL MAXIMUM ENRICHMENT LIMIT WITH SOLUBLE BORON CREDIT (TAC NO. MB8896)
Dear Mr. Vanderheyden:
By letter dated May 1, 2003, you submitted a license amendment to incorporate changes into the Technical Specifications for Calvert Cliffs Nuclear Power Plant, Unit No. 1. The proposed changes would increase the maximum enrichment limit of the fuel assemblies that can be stored in the Unit 1 spent fuel pool by taking credit for soluble boron in maintaining acceptable margins of subcriticality.
The U.S. Nuclear Regulatory Commission staff has reviewed the information provided and determined that additional information is required in order to complete the evaluation. The additional information being requested is enclosed. We have discussed this with your staff who indicated that you could provide a response within 60 days from the date of this letter.
Sincerely,
/RA/
Guy S. Vissing, Senior Project Manager, Section 1 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-317
Enclosure:
As stated cc w/encl: See next page
- Memo from KManoly dated 7/8/03 OFFICE PDI-1/PM PDI-1/LA EMEB/SC SRXB/DSSA PDI-1/SC NAME GVissing SLittle KManoly* JUhle**
RLaufer DATE 07/24/03 07/24/03 07/8/03 07/09/03 07/24/03
Calvert Cliffs Nuclear Power Plant Unit Nos. 1 and 2 cc:
President Calvert County Board of Commissioners 175 Main Street Prince Frederick, MD 20678 James M. Petro, Esquire Counsel Constellation Energy Group, Inc.
750 East Pratt Street, 5th floor Baltimore, MD 21202 Jay E. Silberg, Esquire Shaw, Pittman, Potts, and Trowbridge 2300 N Street, NW Washington, DC 20037 Mark Geckle Calvert Cliffs Nuclear Power Plant 1650 Calvert Cliffs Parkway Lusby, MD 20657-4702 Resident Inspector U.S. Nuclear Regulatory Commission P.O. Box 287 St. Leonard, MD 20685 Mr. Richard I. McLean, Manager Nuclear Programs Power Plant Research Program Maryland Dept. of Natural Resources Tawes State Office Building, B3 Annapolis, MD 21401 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Kristen A. Burger, Esquire Maryland Peoples Counsel 6 St. Paul Centre Suite 2102 Baltimore, MD 21202-1631 Patricia T. Birnie, Esquire Co-Director Maryland Safe Energy Coalition P.O. Box 33111 Baltimore, MD 21218 Mr. Loren F. Donatell NRC Technical Training Center 5700 Brainerd Road Chattanooga, TN 37411-4017
Enclosure REQUEST FOR ADDITIONAL INFORMATION FOR CALVERT CLIFFS NUCLEAR POWER PLANT, INC.
TECHNICAL SPECIFICATION AMENDMENT REQUEST RELATED TO THE INCREASE OF MAXIMUM ENRICHMENT LIMIT WITH SOLUBLE BORON CREDIT CALVERT CLIFFS NUCLEAR POWER PLANT, UNIT NO. 1 DOCKET NO. 50-317 1.
In your letter of May 1, 2003, you proposed increasing the maximum enrichment for standard fuel assemblies to 5.0 weight percent, while the current Technical Specification of Calvert Cliffs Nuclear Power Plant (CCNPP) limits the maximum enrichment for standard fuel assemblies to 4.52 weight percent. Indicate whether the weight of the fuel assemblies supported by the spent fuel racks will increase as result of the enrichment.
If the weight of the fuel assemblies is increased, what are the affects on the spent fuel racks and the spent fuel pool structure due to the increased weight?
2.
In consideration of the possibility for increased loads from spent fuel racks, discuss your past operation, inspection and maintenance experience of the CCNPP spent fuel racks and spent fuel pool structures. As applicable, discuss any pool wall/bottom slab cracking, settlement and/or pool water leakages observed to date and repair measures taken to remedy them.
3.
What is the maximum bulk pool temperature at a full core off-load during a refueling outage? If the temperature exceeds 150 F, provide technical justifications for exceeding a gross temperature of 150 F in accordance with the guidance in the American Concrete Institute Code 349 for long term-operation.
4.
In Section 7.0, Technical Assumptions, of the license amendment request, the licensee cites that the NRC acknowledged commitment in Section 2.1.3.7 of the license renewal application for CCNPP. In this commitment, the licensee stated it would perform an analysis on carborundum to demonstrate that it can perform its criticality control function for 70 years. According to Section 3.10.2.4, Time-Limited Aging Analysis, of the Final Safety Evaluation Report regarding the license renewal of CCNPP Unit Nos. 1 and 2, the licensees analysis was to be completed in 2000.
If the licensee proposes to credit this analysis for its amendment request, CCNPP should provide the analysis to support the amendment request.
5.
In Attachment (1), under Background and Analysis in the System Design section, the licensee states that CCNPP has a coupon surveillance program to test the condition of the carborundum material. Also, the licensee indicates that as a result of License Renewal, that the boron loss from the carborundum between 40 and 70 years has been analyzed. The staff requests the licensee explain how the coupon surveillance program will be modified to account for boron depletion due to the added neutron fluence of fuel with a greater enrichment as well as the increased plant operating lifespan.