ML20134K791
| ML20134K791 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs |
| Issue date: | 02/13/1997 |
| From: | Dromerick A NRC (Affiliation Not Assigned) |
| To: | Cruse C BALTIMORE GAS & ELECTRIC CO. |
| References | |
| TAC-M97855, TAC-M97856, NUDOCS 9702140232 | |
| Download: ML20134K791 (4) | |
Text
February 13, 1997 Mr. Charles H. Cruse Vice President - Nuclear Energy Balitmore Gas and Electric Company Calvert Cliffs Nuclear Power Plant 1650 Calvert Cliffs Parkway Lusby, MD 20657-4702
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION - PROPOSED TECHNICAL SPECIFICATION CHANGES TO REACTOR COOLANT SYSTEM FLOW LIMIT, CALVERT CLIFFS NUCLEAR POWER PLANT, UNITS 1 AND 2 (TAC NOS. M97855 AND M97856)
Dear Mr. Cruse:
By letter dated January 31, 1997, the Baltimore Gas and Electric Company, the licensee, pursuan.t to 10 CFR 50.90, requested an amendment to Facility Operating License DPR-53 and DPR-69 for the Calvert Cliffs, Units 1 and 2, respectively. The amendment proposed a modification to Technical Specifications for a reduction of the total reactor coolant system flow rate lower limit by 30,000 gallons per minute (gpm) from 370,000 gpm. The NRC staff is reviewing your submittal and has determined that additional information is required for us to complete our review. The information requested is addressed in the enclosure.
In order to meet your schedule, the staff requests that the additional information be provided by March 1,1997.
If you have any questions regarding this matter, please contact me at 301-415-3473.
Sincerely,
/S/
Alexander W. Dromerick, Senior Project Manager Project Directorate I-l Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Docket Nos. 50-317 and 50-318
Enclosure:
Request for Additional Information cc w/ encl:
See next page DISTRIBUTION:
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\\.....[2 February 13, 1997 Mr. Charles H. Cruse Vice President - Nuclear Energy Balitmore Gas and Electric Company Calvert Cliffs Nuclear Power Plant 1650 Calvert Cliffs Parkway Lusby, MD 20657-4702
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION - PROPOSED TECHNICAL SPECIFICATION CHANGES TO REACTOR COOLANT SYSTEM FLOW LIMIT, CALVERT l
CLIFFS NUCLEAR POWER PLANT, UNITS 1 AND 2 (TAC NOS. M97855 AND M97856)
Dear Mr. Cruse:
By letter dated January 31, 1997, the Baltimore Gas and Electric Company, the licensee, pursuant to 10 CFR 50.90, requested an amendment to Facility Operating License DPR-53 and DPR-69 for the Calvert Cliffs, Units 1 and 2, respectively. The amendment proposed a modification to Technical Specifications for a reduction of the total reactor coolant system flow rate lower limit by 30,000 gallons per minute (gpm) from 370,000 gpm. The NRC staff is reviewing your submittal and has determined that additional information is required for us to complete our review. The information requested is addressed in the enclosure.
In order to meet your schedule, the staff requests that the additional information be provided by March 1,1997.
If you have any questions regarding this matter, please contact me at 301-415-3473.
Sincerely, Y
d'W Alexander W. Dromerick, Senior Project Manager Project Directorate I-l Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Docket Nos. 50-317 and 50-318
Enclosure:
Request for Additional Information cc w/ encl: See next page
RE0 VEST FOR ADDITIONAL INF0MAHQN PROPOSED AMENDMENT FOR REDUCED RLE FLOW CALVERT CLIFFS NUCLEAR POWER PLANT. UNITS 1 AND 2
Reference:
Baltimore Gas and Electric Company letter to NRC, dated January 31, 1997, " License Amendment Request; Change to Reactor Coolant System Flow Requirements to Allow Increased Steam Generator Tube Plugging."
1.
On page 1 of Attachment 1 of the transmittal, it is stated that "The primary effects of plugging Steam Generator (SG) tubes are to reduce SG heat transfer area and increase the Reactor Coolant System (RCS) flow resistance." These effects result in reduced SG steam pressure, reduced RCS flow rate, and increase hot leg temperature.
Provide a comparison of key parameters (e.g. RCS pressure, T average, T cold, T hot, steam pressure, SG outlet temperature) between the proposed operation and the design basis analysis.
2.
The decrease in steam pressure results in the increase in the primary-to-secondary pressure difference and break flow.
Provide evaluation of the effect of decreased steam pressure on the design basis analysis of SGs with respect to the stresses and fatigue usage.
3.
On page 2 of the transmittal, you stated that the reduced RCS flow rate results in an increase in the temperature rise (delta-T) between the cold leg and the hot leg.
Provide evaluation of the effect of increased delta-T on the reactor vessel and internals, piping, the CRDM housing, the pressurizer (lower head and upper shell), surge line (stratification), pressurizer spray nozzles, and the reactor coolant pumps, with respect to stresses and fatigue analysis.
Enclosure
I I
Mr. Charles H. Cruse Calvert Cliffs Nuclear Power Plant Calvert Cliffs Nuclear Power Plant Unit Nos. I and 2 cc:
President Mr. Joseph H. Walter, Chief Engineer Calvert County Board of Public Service Commission of Commissioners Maryland 175 Main Street Engineering Division Prince Frederick, MD 20678 6 St. Paul Centre Baltimore, MD 21202-6806 D. A. Brune, Esquire General Counsel Kristen A. Burger, Esquire Baltimore Gas and Electric Company Maryland People's Counsel P.O. Box 1475 6 St. Paul Centre Baltimore, MD 21203 Suite 2102 Baltimore, MD 21202-1631 Jay E. Silberg, Esquire Shaw, Pittman, Potts, and Trowbridge Patricia T. Birnie, Esquire 2300 N Street, NW Co-Director Washington, DC 20037 Maryland Safe Energy Coalition P.O. Box 33111 Mr. Terrence J. Camilleri, Director, Baltimore, MD 21218 NRM Calvert Cliffs Nuclear Power Plant Mr. Larry Bell 1650 Calvert Cliffs Parkway NRC Technical Training Center Lusby, MD 20657-47027 5700 Brainerd Road Chattanooga, TN 37411-4017 Resident Inspector U.S. Nuclear Regulatory Commission P.O. Box 287 St. Leonard, MD 20685 Mr. Richard I. McLean Administrator - Radioecology Department of Natural Resources 580 Taylor Avenue 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
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