ML052840372: Difference between revisions

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RAI cc w/encl: See next page
RAI cc w/encl: See next page


OFFICE PDI-1/PM            PDI-1/LA          EMCB/SC              PDI-1/SC NAME PMilano                SLittle          ALund                RLaufer DATE      10/13/05          10/13/05          10/06/05            10/17/05
OFFICE PDI-1/PM            PDI-1/LA          EMCB/SC              PDI-1/SC NAME PMilano                SLittle          ALund                RLaufer DATE      10/13/05          10/13/05          10/06/05            10/17/05 REQUEST FOR ADDITIONAL INFORMATION REGARDING STEAM GENERATOR TUBE INTEGRITY CALVERT CLIFFS NUCLEAR POWER PLANT, UNIT NOS. 1 AND 2 DOCKET NOS. 50-317 AND 50-318 By letter dated July 13, 2005 (Agencywide Documents Access and Management System Accession No. ML051990345), Calvert Cliffs Nuclear Power Plant, Inc. (the licensee) submitted an application for changes to the technical specifications (TSs) for Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2. The licensee requested changes in accordance with TS Task Force (TSTF) Change Traveler 449, Steam Generator Tube Integrity (TSFT-449). The Nuclear Regulatory Commission (NRC) staff has reviewed the information that the licensee provided and determined that additional information is required in order to complete the evaluation.
 
REQUEST FOR ADDITIONAL INFORMATION REGARDING STEAM GENERATOR TUBE INTEGRITY CALVERT CLIFFS NUCLEAR POWER PLANT, UNIT NOS. 1 AND 2 DOCKET NOS. 50-317 AND 50-318 By letter dated July 13, 2005 (Agencywide Documents Access and Management System Accession No. ML051990345), Calvert Cliffs Nuclear Power Plant, Inc. (the licensee) submitted an application for changes to the technical specifications (TSs) for Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2. The licensee requested changes in accordance with TS Task Force (TSTF) Change Traveler 449, Steam Generator Tube Integrity (TSFT-449). The Nuclear Regulatory Commission (NRC) staff has reviewed the information that the licensee provided and determined that additional information is required in order to complete the evaluation.
On Page 2 of the July 13 application, the licensee stated that the operational primary-to-secondary leakage limit (measured at room temperature, cold conditions) is 100 gallons per day (gpd) per steam generator (SG), which is more conservative than the 150 gpd per SG operational leakage limit approved in TSTF-449. As stated in the TS Bases B 3.4.13 for reactor coolant system operational leakage (see TS page B 3.4.13-2), the initial primary-to-secondary leakage assumed in accident analyses is also defined as 100 gpd per SG. During a main steam line break (MSLB) accident (one of the postulated accident conditions analyzed), the differential pressure across the SG tubes is greater than the differential pressure during normal operation. As a result, the primary-to-secondary leakage may be greater during an MSLB accident than during normal operation. Since the plant could be operating with leakage as high as the normal operating leakage limit, the amount of leakage during an MSLB accident (or other postulated accidents) could be greater than that assumed in the accident analyses.
On Page 2 of the July 13 application, the licensee stated that the operational primary-to-secondary leakage limit (measured at room temperature, cold conditions) is 100 gallons per day (gpd) per steam generator (SG), which is more conservative than the 150 gpd per SG operational leakage limit approved in TSTF-449. As stated in the TS Bases B 3.4.13 for reactor coolant system operational leakage (see TS page B 3.4.13-2), the initial primary-to-secondary leakage assumed in accident analyses is also defined as 100 gpd per SG. During a main steam line break (MSLB) accident (one of the postulated accident conditions analyzed), the differential pressure across the SG tubes is greater than the differential pressure during normal operation. As a result, the primary-to-secondary leakage may be greater during an MSLB accident than during normal operation. Since the plant could be operating with leakage as high as the normal operating leakage limit, the amount of leakage during an MSLB accident (or other postulated accidents) could be greater than that assumed in the accident analyses.
Discuss the controls that are in place to ensure that the accident-induced leakage performance criteria are not exceeded as a result of operational leakage (i.e., operational leakage at or below TS limit). In addition, discuss whether the initial assumed leakage rate input for the MSLB accident is based on cold or hot plant conditions.
Discuss the controls that are in place to ensure that the accident-induced leakage performance criteria are not exceeded as a result of operational leakage (i.e., operational leakage at or below TS limit). In addition, discuss whether the initial assumed leakage rate input for the MSLB accident is based on cold or hot plant conditions.

Revision as of 13:31, 14 March 2020

Request for Additional Information Regarding Steam Generator Tube Integrity Requirements (TAC Nos. MC8067 and MC8068)
ML052840372
Person / Time
Site: Calvert Cliffs  Constellation icon.png
Issue date: 10/17/2005
From: Milano P
NRC/NRR/DLPM/LPD1
To: Vanderheyden G
Calvert Cliffs
Milano P, NRR/DLPM , 415-1457
References
TAC MC8067, TAC MC8068
Download: ML052840372 (4)


Text

October 17, 2005 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:

CALVERT CLIFFS NUCLEAR POWER PLANT, UNIT NOS. 1 AND 2 -

REQUEST FOR ADDITIONAL INFORMATION REGARDING STEAM GENERATOR TUBE INTEGRITY REQUIREMENTS (TAC NOS. MC8067 AND MC8068)

Dear Mr. Vanderheyden:

By letter dated July 13, 2005, Calvert Cliffs Nuclear Power Plant, Inc. (the licensee) requested a change to the technical specifications (TSs) for Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2 regarding steam generator tube integrity. Specifically, the licensee requested changes consistent with TS Task Force (TSTF) Change Traveler, TSTF-449, Steam Generator Tube Integrity, Revision 4.

The Nuclear Regulatory Commission (NRC) staff has reviewed the information provided in support of the application and has determined that additional information is needed to complete its review. Enclosed is the NRC staffs request for additional information (RAI). This RAI was discussed with your staff on October 13, 2005, and it was agreed that your response would be provided within 45 days from the date of this letter.

If you have any questions, please contact me at 301-415-1457.

Sincerely,

/RA/

Patrick D. Milano, Sr. Project Manager, Section 1 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-317 and 50-318

Enclosure:

RAI cc w/encl: See next page

OFFICE PDI-1/PM PDI-1/LA EMCB/SC PDI-1/SC NAME PMilano SLittle ALund RLaufer DATE 10/13/05 10/13/05 10/06/05 10/17/05 REQUEST FOR ADDITIONAL INFORMATION REGARDING STEAM GENERATOR TUBE INTEGRITY CALVERT CLIFFS NUCLEAR POWER PLANT, UNIT NOS. 1 AND 2 DOCKET NOS. 50-317 AND 50-318 By letter dated July 13, 2005 (Agencywide Documents Access and Management System Accession No. ML051990345), Calvert Cliffs Nuclear Power Plant, Inc. (the licensee) submitted an application for changes to the technical specifications (TSs) for Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2. The licensee requested changes in accordance with TS Task Force (TSTF) Change Traveler 449, Steam Generator Tube Integrity (TSFT-449). The Nuclear Regulatory Commission (NRC) staff has reviewed the information that the licensee provided and determined that additional information is required in order to complete the evaluation.

On Page 2 of the July 13 application, the licensee stated that the operational primary-to-secondary leakage limit (measured at room temperature, cold conditions) is 100 gallons per day (gpd) per steam generator (SG), which is more conservative than the 150 gpd per SG operational leakage limit approved in TSTF-449. As stated in the TS Bases B 3.4.13 for reactor coolant system operational leakage (see TS page B 3.4.13-2), the initial primary-to-secondary leakage assumed in accident analyses is also defined as 100 gpd per SG. During a main steam line break (MSLB) accident (one of the postulated accident conditions analyzed), the differential pressure across the SG tubes is greater than the differential pressure during normal operation. As a result, the primary-to-secondary leakage may be greater during an MSLB accident than during normal operation. Since the plant could be operating with leakage as high as the normal operating leakage limit, the amount of leakage during an MSLB accident (or other postulated accidents) could be greater than that assumed in the accident analyses.

Discuss the controls that are in place to ensure that the accident-induced leakage performance criteria are not exceeded as a result of operational leakage (i.e., operational leakage at or below TS limit). In addition, discuss whether the initial assumed leakage rate input for the MSLB accident is based on cold or hot plant conditions.

Enclosure

Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2 cc:

President Patricia T. Birnie, Esquire Calvert County Board of Co-Director Commissioners Maryland Safe Energy Coalition 175 Main Street P.O. Box 33111 Prince Frederick, MD 20678 Baltimore, MD 21218 Carey Fleming, Esquire Mr. Roy Hickok Sr. Counsel - Nuclear Generation NRC Technical Training Center Constellation Generation Group, LLC 5700 Brainerd Road 750 East Pratt Street, 17th floor Chattanooga, TN 37411-4017 Baltimore, MD 21202 Lou Larragoite 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. R. I. McLean, Administrator Radioecology Environ Impact Prog Department of Natural Resources Nuclear Evaluations 580 Taylor Avenue Tawes State Office Building 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 People's Counsel 6 St. Paul Centre Suite 2102 Baltimore, MD 21202-1631