ML071060135: Difference between revisions
StriderTol (talk | contribs) (StriderTol Bot change) |
StriderTol (talk | contribs) (StriderTol Bot change) |
||
| Line 24: | Line 24: | ||
==Dear Mr. McKinney:== | ==Dear Mr. McKinney:== | ||
In reviewing your {{letter dated|date=October 11, 2006|text=letter dated October 11, 2006}}, concerning the request to increase the maximum steady-state power level at the SSES 1 and 2 from 3489 megawatts thermal (MWt) to 3952 MWt, the Nuclear Regulatory Commission staff has determined that additional information contained in the enclosure to this letter is needed to complete its review. These questions were discussed with your staff during a teleconference on April 10, 2007. As agreed to by your staff, we request you respond by May 31, 2007. | |||
In reviewing your letter dated October 11, 2006, concerning the request to increase the maximum steady-state power level at the SSES 1 and 2 from 3489 megawatts thermal (MWt) to 3952 MWt, the Nuclear Regulatory Commission staff has determined that additional information contained in the enclosure to this letter is needed to complete its review. These questions were discussed with your staff during a teleconference on April 10, 2007. As agreed to by your staff, we request you respond by May 31, 2007. | |||
If you have any questions, please contact me at 301-415-1030. | If you have any questions, please contact me at 301-415-1030. | ||
Sincerely, | Sincerely, | ||
/RA/ | |||
Richard V. Guzman, Senior Project Manager Plant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-387 and 50-388 | Richard V. Guzman, Senior Project Manager Plant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-387 and 50-388 | ||
==Enclosure:== | ==Enclosure:== | ||
RAI cc w/encl: See next page | RAI cc w/encl: See next page | ||
| Line 41: | Line 39: | ||
==Dear Mr. McKinney:== | ==Dear Mr. McKinney:== | ||
In reviewing your {{letter dated|date=October 11, 2006|text=letter dated October 11, 2006}}, concerning the request to increase the maximum steady-state power level at the SSES 1 and 2 from 3489 megawatts thermal (MWt) to 3952 MWt, the Nuclear Regulatory Commission staff has determined that additional information contained in the enclosure to this letter is needed to complete its review. These questions were discussed with your staff during a teleconference on April 10, 2007. As agreed to by your staff, we request you respond by May 31, 2007. | |||
In reviewing your letter dated October 11, 2006, concerning the request to increase the maximum steady-state power level at the SSES 1 and 2 from 3489 megawatts thermal (MWt) to 3952 MWt, the Nuclear Regulatory Commission staff has determined that additional information contained in the enclosure to this letter is needed to complete its review. These questions were discussed with your staff during a teleconference on April 10, 2007. As agreed to by your staff, we request you respond by May 31, 2007. | |||
If you have any questions, please contact me at 301-415-1030. | If you have any questions, please contact me at 301-415-1030. | ||
Sincerely, | Sincerely, | ||
/RA/ | |||
Richard V. Guzman, Senior Project Manager Plant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-387 and 50-388 | Richard V. Guzman, Senior Project Manager Plant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-387 and 50-388 | ||
==Enclosure:== | ==Enclosure:== | ||
RAI cc w/encl: See next page DISTRIBUTION: | RAI cc w/encl: See next page DISTRIBUTION: | ||
Public | Public RidsOgcMailCenter RidsNrrPmRGuzman RidsNrrCptbBC TScarbrough LPLI-1 R/F RidsNrrDorlLpl1-1 RidsAcrsAcnwMailCenter RidsNrrLaSLittle Accession Number: ML071060135 | ||
* RAI provided by memo. No substantive changes made. | * RAI provided by memo. No substantive changes made. | ||
OFFICE | OFFICE NRR/LPLI-1/PM NRR/LPLI-1/LA NRR/CPTB/BC NRR/LPLI-1/BC NAME RGuzman SLittle JMcHale* | ||
MKowal DATE 4/16/07 4/16/07 3/9/07 4/18/07 OFFICIAL RECORD COPY | |||
REQUEST FOR ADDITIONAL INFORMATION RELATING TO THE APPLICATION FOR EXTENDED POWER UPRATE (EPU) | Enclosure REQUEST FOR ADDITIONAL INFORMATION RELATING TO THE APPLICATION FOR EXTENDED POWER UPRATE (EPU) | ||
SAFETY-RELATED PUMPS AND VALVES, MECHANICAL EQUIPMENT ENVIRONMENTAL QUALIFICATION SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2 (SSES 1 AND 2) | SAFETY-RELATED PUMPS AND VALVES, MECHANICAL EQUIPMENT ENVIRONMENTAL QUALIFICATION SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2 (SSES 1 AND 2) | ||
PPL SUSQUEHANNA, LLC DOCKET NOS. 50-387 AND 50-388 The Nuclear Regulatory Commission (NRC) staff is reviewing the request from PPL Susquehanna, LLC (PPL, the licensee) to support the application of the EPU for SSES 1 and 2. | PPL SUSQUEHANNA, LLC DOCKET NOS. 50-387 AND 50-388 The Nuclear Regulatory Commission (NRC) staff is reviewing the request from PPL Susquehanna, LLC (PPL, the licensee) to support the application of the EPU for SSES 1 and 2. | ||
The NRC staff has determined that additional information requested below will be needed to complete its review. | The NRC staff has determined that additional information requested below will be needed to complete its review. | ||
1. | |||
The licensee is requested to provide a description of its plans to implement the Inservice Testing Program as it relates to the proposed EPU operating conditions. Discuss with examples, its evaluation of the impact of EPU conditions on the performance of safety-related pumps, power-operated valves, check valves, safety or relief valves, including consideration of changes in ambient conditions and power supplies (as applicable), and dynamic restraints; and to indicate any resulting component or support modifications, or adjustments to the Inservice Testing Program, resulting from that evaluation. | |||
2. | |||
increased ambient temperature on motor output. | In Section 4.1.4, Generic Letter (GL) 89-10 Program, of Enclosure 4, Susquehanna Steam Electric Station Units 1 and 2 Safety Analysis Report for Constant Pressure Power Uprate (CPPU), to its submittal dated October 11, 2006, the licensee states that process parameters of temperature, pressure, and flow for motor-operated valves (MOVs) were reviewed; and increases in design differential pressure due to operation at CPPU conditions were identified for some MOVs. The licensee also states that operation at CPPU conditions increases post-accident room temperatures where some MOVs are located, potentially reducing the actuator output torque. Based on its review, the licensee states that the GL 89-10 MOVs are capable of performing their design-basis safety functions at CPPU conditions. The licensee is requested to discuss with examples its evaluation of safety-related MOVs within the programs established in response to GL 89-10, Safety-Related Motor-Operated Valve Testing and Surveillance, and GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves, at SSES 1 and 2 for the potential impact from EPU operation, including the impact of increased process flows on operating requirements and increased ambient temperature on motor output. | ||
3. | |||
In Section 4.1.4 of Enclosure 4 to its submittal dated October 11, 2006, the licensee states that MOVs used as containment or high energy line break isolation valves, and air-operated valves (AOVs) used as containment isolation valves, were reviewed for effects of operations at CPPU conditions, including thermal binding and pressure locking as described in GL 95-07, "Pressure Locking and Thermal Binding of Safety-Related Power-Operated Gate Valves." The licensee is requested to discuss with examples, its evaluation of all safety-related power-operated gate valves and the potential for pressure locking or thermal binding resulting from EPU operation at SSES 1 and 2. | |||
4. | |||
In Section 4.1.4 of Attachment 4 to its submittal dated October 11, 2006, the licensee states the process parameters of temperature, pressure, and flow for AOVs were reviewed, and increases in design differential pressure due to operation at CPPU conditions have been identified for some AOVs. Based its review, the licensee states that all AOVs with active, safety-related or safety-significant functions are capable of performing their design-basis safety functions at CPPU conditions. The licensee is requested to discuss with examples, its evaluation of safety-related AOVs and solenoid-operated valves, as applicable, for potential impact from EPU operation at SSES 1 and 2. | |||
5. | |||
In Section 10.3, Environmental Qualification, of Enclosure 4 to its submittal dated October 11, 2006, the licensee indicates that safety-related components are required to be qualified for the environment in which they are intended to operate. In Section 10.3.2, Mechanical Equipment with Non-Metallic Components, the licensee states that accident temperature, pressure, and radiation level increase due to CPPU. The licensee states that the design control program ensures that non-metallic components (e.g., seals, gaskets, lubricants, and diaphragms) are specified and procured for the environment in which they are intended to function. The licensee is requested to identify the range of the non-metallic components in safety-related mechanical equipment with examples. The discussion of examples should include (1) applicable environmental conditions, (2) required operating life, (3) capabilities of the non-metallic components, (4) basis for the environmental qualification of mechanical equipment, and (5) the surveillance and maintenance programs to be developed to ensure functionality during their design life. | |||
6. | |||
In Section 10.3.3, Mechanical Component Design Qualification, of Enclosure 4 to its submittal dated October 11, 2006, the licensee states that mechanical design of equipment/components in certain systems is affected by operation at CPPU conditions due to increased temperatures and, in some cases, flow and pressure. The licensee is requested to (1) discuss the environmental qualification methods and approaches applied to mechanical equipment (including pumps, power-operated valves, safety-relief valves, and check valves) and their supports, (2) provide examples of the increased temperatures, flows, and loads resulting from EPU conditions, (3) indicate the impact on operating life of mechanical equipment from EPU operation, and (4) describe the surveillance and maintenance program for mechanical equipment to ensure functionality during their design life. | |||
Susquehanna Steam Electric Station, Unit Nos. 1 and 2 cc: | Susquehanna Steam Electric Station, Unit Nos. 1 and 2 cc: | ||
Robert A. Saccone | Robert A. Saccone Vice President - Nuclear Operations PPL Susquehanna, LLC 769 Salem Blvd., NUCSB3 Berwick, PA 18603-0467 Terry L. Harpster General Manager - Plant Support PPL Susquehanna, LLC 769 Salem Blvd., NUCSA4 Berwick, PA 18603-0467 Rocco R. Sgarro Manager - Nuclear Regulatory Affairs PPL Susquehanna, LLC Two North Ninth Street, GENPL4 Allentown, PA 18101-1179 Supervisor - | ||
Nuclear Regulatory Affairs PPL Susquehanna, LLC 769 Salem Blvd., NUCSA4 Berwick, PA 18603-0467 Michael H. Crowthers Supervising Engineer Nuclear Regulatory Affairs PPL Susquehanna, LLC Two North Ninth Street, GENPL4 Allentown, PA 18101-1179 Steven M. Cook Manager - Quality Assurance PPL Susquehanna, LLC 769 Salem Blvd., NUCSB2 Berwick, PA 18603-0467 Luis A. Ramos Community Relations Manager, Susquehanna PPL Susquehanna, LLC 634 Salem Blvd., SSO Berwick, PA 18603-0467 Bryan A. Snapp, Esq Assoc. General Counsel PPL Services Corporation Two North Ninth Street, GENTW3 Allentown, PA 18101-1179 Supervisor - Document Control Services PPL Susquehanna, LLC Two North Ninth Street, GENPL4 Allentown, PA 18101-1179 Richard W. Osborne Allegheny Electric Cooperative, Inc. | |||
212 Locust Street P.O. Box 1266 Harrisburg, PA 17108-1266 Director, Bureau of Radiation Protection Pennsylvania Department of Environmental Protection Rachel Carson State Office Building P.O. Box 8469 Harrisburg, PA 17105-8469 Senior Resident Inspector U.S. Nuclear Regulatory Commission P.O. Box 35, NUCSA4 Berwick, PA 18603-0035 Regional Administrator, Region 1 U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Board of Supervisors Salem Township P.O. Box 405 Berwick, PA 18603-0035 Dr. Judith Johnsrud National Energy Committee Sierra Club 443 Orlando Avenue State College, PA 16803}} | |||
Latest revision as of 01:56, 15 January 2025
| ML071060135 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 04/18/2007 |
| From: | Richard Guzman NRC/NRR/ADRO/DORL/LPLI-1 |
| To: | Mckinney B Susquehanna |
| Guzman R, NRR/DORL, 415-1030 | |
| References | |
| TAC MD3309, TAC MD3310 | |
| Download: ML071060135 (6) | |
Text
April 18, 2007 Mr. Britt T. McKinney Sr. Vice President and Chief Nuclear Officer PPL Susquehanna, LLC 769 Salem Blvd., NUCSB3 Berwick, PA 18603-0467
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION (RAI) - SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2 (SSES 1 AND 2) - EXTENDED POWER UPRATE APPLICATION RE: SAFETY-RELATED PUMPS AND VALVES AND MECHANICAL EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW (TAC NOS. MD3309 AND MD3310)
Dear Mr. McKinney:
In reviewing your letter dated October 11, 2006, concerning the request to increase the maximum steady-state power level at the SSES 1 and 2 from 3489 megawatts thermal (MWt) to 3952 MWt, the Nuclear Regulatory Commission staff has determined that additional information contained in the enclosure to this letter is needed to complete its review. These questions were discussed with your staff during a teleconference on April 10, 2007. As agreed to by your staff, we request you respond by May 31, 2007.
If you have any questions, please contact me at 301-415-1030.
Sincerely,
/RA/
Richard V. Guzman, Senior Project Manager Plant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-387 and 50-388
Enclosure:
RAI cc w/encl: See next page
April 18, 2007 Mr. Britt T. McKinney Sr. Vice President and Chief Nuclear Officer PPL Susquehanna, LLC 769 Salem Blvd., NUCSB3 Berwick, PA 18603-0467
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION (RAI) - SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2 (SSES 1 AND 2) - EXTENDED POWER UPRATE APPLICATION RE: SAFETY-RELATED PUMPS AND VALVES AND MECHANICAL EQUIPMENT ENVIRONMENTAL QUALIFICATION REVIEW (TAC NOS. MD3309 AND MD3310)
Dear Mr. McKinney:
In reviewing your letter dated October 11, 2006, concerning the request to increase the maximum steady-state power level at the SSES 1 and 2 from 3489 megawatts thermal (MWt) to 3952 MWt, the Nuclear Regulatory Commission staff has determined that additional information contained in the enclosure to this letter is needed to complete its review. These questions were discussed with your staff during a teleconference on April 10, 2007. As agreed to by your staff, we request you respond by May 31, 2007.
If you have any questions, please contact me at 301-415-1030.
Sincerely,
/RA/
Richard V. Guzman, Senior Project Manager Plant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-387 and 50-388
Enclosure:
RAI cc w/encl: See next page DISTRIBUTION:
Public RidsOgcMailCenter RidsNrrPmRGuzman RidsNrrCptbBC TScarbrough LPLI-1 R/F RidsNrrDorlLpl1-1 RidsAcrsAcnwMailCenter RidsNrrLaSLittle Accession Number: ML071060135
- RAI provided by memo. No substantive changes made.
OFFICE NRR/LPLI-1/PM NRR/LPLI-1/LA NRR/CPTB/BC NRR/LPLI-1/BC NAME RGuzman SLittle JMcHale*
MKowal DATE 4/16/07 4/16/07 3/9/07 4/18/07 OFFICIAL RECORD COPY
Enclosure REQUEST FOR ADDITIONAL INFORMATION RELATING TO THE APPLICATION FOR EXTENDED POWER UPRATE (EPU)
SAFETY-RELATED PUMPS AND VALVES, MECHANICAL EQUIPMENT ENVIRONMENTAL QUALIFICATION SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2 (SSES 1 AND 2)
PPL SUSQUEHANNA, LLC DOCKET NOS. 50-387 AND 50-388 The Nuclear Regulatory Commission (NRC) staff is reviewing the request from PPL Susquehanna, LLC (PPL, the licensee) to support the application of the EPU for SSES 1 and 2.
The NRC staff has determined that additional information requested below will be needed to complete its review.
1.
The licensee is requested to provide a description of its plans to implement the Inservice Testing Program as it relates to the proposed EPU operating conditions. Discuss with examples, its evaluation of the impact of EPU conditions on the performance of safety-related pumps, power-operated valves, check valves, safety or relief valves, including consideration of changes in ambient conditions and power supplies (as applicable), and dynamic restraints; and to indicate any resulting component or support modifications, or adjustments to the Inservice Testing Program, resulting from that evaluation.
2.
In Section 4.1.4, Generic Letter (GL) 89-10 Program, of Enclosure 4, Susquehanna Steam Electric Station Units 1 and 2 Safety Analysis Report for Constant Pressure Power Uprate (CPPU), to its submittal dated October 11, 2006, the licensee states that process parameters of temperature, pressure, and flow for motor-operated valves (MOVs) were reviewed; and increases in design differential pressure due to operation at CPPU conditions were identified for some MOVs. The licensee also states that operation at CPPU conditions increases post-accident room temperatures where some MOVs are located, potentially reducing the actuator output torque. Based on its review, the licensee states that the GL 89-10 MOVs are capable of performing their design-basis safety functions at CPPU conditions. The licensee is requested to discuss with examples its evaluation of safety-related MOVs within the programs established in response to GL 89-10, Safety-Related Motor-Operated Valve Testing and Surveillance, and GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves, at SSES 1 and 2 for the potential impact from EPU operation, including the impact of increased process flows on operating requirements and increased ambient temperature on motor output.
3.
In Section 4.1.4 of Enclosure 4 to its submittal dated October 11, 2006, the licensee states that MOVs used as containment or high energy line break isolation valves, and air-operated valves (AOVs) used as containment isolation valves, were reviewed for effects of operations at CPPU conditions, including thermal binding and pressure locking as described in GL 95-07, "Pressure Locking and Thermal Binding of Safety-Related Power-Operated Gate Valves." The licensee is requested to discuss with examples, its evaluation of all safety-related power-operated gate valves and the potential for pressure locking or thermal binding resulting from EPU operation at SSES 1 and 2.
4.
In Section 4.1.4 of Attachment 4 to its submittal dated October 11, 2006, the licensee states the process parameters of temperature, pressure, and flow for AOVs were reviewed, and increases in design differential pressure due to operation at CPPU conditions have been identified for some AOVs. Based its review, the licensee states that all AOVs with active, safety-related or safety-significant functions are capable of performing their design-basis safety functions at CPPU conditions. The licensee is requested to discuss with examples, its evaluation of safety-related AOVs and solenoid-operated valves, as applicable, for potential impact from EPU operation at SSES 1 and 2.
5.
In Section 10.3, Environmental Qualification, of Enclosure 4 to its submittal dated October 11, 2006, the licensee indicates that safety-related components are required to be qualified for the environment in which they are intended to operate. In Section 10.3.2, Mechanical Equipment with Non-Metallic Components, the licensee states that accident temperature, pressure, and radiation level increase due to CPPU. The licensee states that the design control program ensures that non-metallic components (e.g., seals, gaskets, lubricants, and diaphragms) are specified and procured for the environment in which they are intended to function. The licensee is requested to identify the range of the non-metallic components in safety-related mechanical equipment with examples. The discussion of examples should include (1) applicable environmental conditions, (2) required operating life, (3) capabilities of the non-metallic components, (4) basis for the environmental qualification of mechanical equipment, and (5) the surveillance and maintenance programs to be developed to ensure functionality during their design life.
6.
In Section 10.3.3, Mechanical Component Design Qualification, of Enclosure 4 to its submittal dated October 11, 2006, the licensee states that mechanical design of equipment/components in certain systems is affected by operation at CPPU conditions due to increased temperatures and, in some cases, flow and pressure. The licensee is requested to (1) discuss the environmental qualification methods and approaches applied to mechanical equipment (including pumps, power-operated valves, safety-relief valves, and check valves) and their supports, (2) provide examples of the increased temperatures, flows, and loads resulting from EPU conditions, (3) indicate the impact on operating life of mechanical equipment from EPU operation, and (4) describe the surveillance and maintenance program for mechanical equipment to ensure functionality during their design life.
Susquehanna Steam Electric Station, Unit Nos. 1 and 2 cc:
Robert A. Saccone Vice President - Nuclear Operations PPL Susquehanna, LLC 769 Salem Blvd., NUCSB3 Berwick, PA 18603-0467 Terry L. Harpster General Manager - Plant Support PPL Susquehanna, LLC 769 Salem Blvd., NUCSA4 Berwick, PA 18603-0467 Rocco R. Sgarro Manager - Nuclear Regulatory Affairs PPL Susquehanna, LLC Two North Ninth Street, GENPL4 Allentown, PA 18101-1179 Supervisor -
Nuclear Regulatory Affairs PPL Susquehanna, LLC 769 Salem Blvd., NUCSA4 Berwick, PA 18603-0467 Michael H. Crowthers Supervising Engineer Nuclear Regulatory Affairs PPL Susquehanna, LLC Two North Ninth Street, GENPL4 Allentown, PA 18101-1179 Steven M. Cook Manager - Quality Assurance PPL Susquehanna, LLC 769 Salem Blvd., NUCSB2 Berwick, PA 18603-0467 Luis A. Ramos Community Relations Manager, Susquehanna PPL Susquehanna, LLC 634 Salem Blvd., SSO Berwick, PA 18603-0467 Bryan A. Snapp, Esq Assoc. General Counsel PPL Services Corporation Two North Ninth Street, GENTW3 Allentown, PA 18101-1179 Supervisor - Document Control Services PPL Susquehanna, LLC Two North Ninth Street, GENPL4 Allentown, PA 18101-1179 Richard W. Osborne Allegheny Electric Cooperative, Inc.
212 Locust Street P.O. Box 1266 Harrisburg, PA 17108-1266 Director, Bureau of Radiation Protection Pennsylvania Department of Environmental Protection Rachel Carson State Office Building P.O. Box 8469 Harrisburg, PA 17105-8469 Senior Resident Inspector U.S. Nuclear Regulatory Commission P.O. Box 35, NUCSA4 Berwick, PA 18603-0035 Regional Administrator, Region 1 U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Board of Supervisors Salem Township P.O. Box 405 Berwick, PA 18603-0035 Dr. Judith Johnsrud National Energy Committee Sierra Club 443 Orlando Avenue State College, PA 16803