ML043350010
| ML043350010 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 12/03/2004 |
| From: | Richard Guzman NRC/NRR/DLPM/LPD1 |
| To: | Shriver B PPL Generation |
| Guzman R, NRR/DLPM 415-1030 | |
| References | |
| TAC MC1596, TAC MC1597 | |
| Download: ML043350010 (14) | |
Text
December 3, 2004 Mr. Bryce L. Shriver President, PPL Generation, LLC, and Chief Nuclear Officer PPL Generation, LLC 2 North Ninth Street Allentown, PA 18101
SUBJECT:
SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2 - ISSUANCE OF AMENDMENTS RE: REVISED MAIN TURBINE SYSTEM REQUIREMENTS TECHNICAL SPECIFICATION CHANGE (TAC NOS. MC1596 AND MC1597)
Dear Mr. Shriver:
The Nuclear Regulatory Commission has issued the enclosed Amendment No. 218 to Facility Operating License No. NPF-14 and Amendment No. 193 to Facility Operating License No.
NPF-22 for the Susquehanna Steam Electric Station, Units 1 and 2 (SSES 1 and 2). These amendments are in response to your application dated December 5, 2003, as supplemented by letter dated June 4, 2004.
These amendments revise SSES 1 and 2 Technical Specifications (TSs) by adding a requirement to apply linear heat generation (LHGR) limits if the main turbine bypass system becomes inoperable. The proposed changes clarify TS 3.7.6 to state that both minimum critical power ratio and LHGR limits for an inoperable main turbine bypass system are required if the system becomes inoperable.
A copy of our safety evaluation is also enclosed. The Notice of Issuance will be included in the Commission's Biweekly Federal Register Notice.
Sincerely,
/RA/
Richard V. Guzman, Project Manager, Section 1 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-387 and 50-388
Enclosures:
- 1. Amendment No. 218 to License No. NPF-14
- 2. Amendment No. 193 to License No. NPF-22
- 3. Safety Evaluation cc w/encls: See next page
December 3, 2004 Mr. Bryce L. Shriver President, PPL Generation, LLC, and Chief Nuclear Officer PPL Generation, LLC 2 North Ninth Street Allentown, PA 18101
SUBJECT:
SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2 - ISSUANCE OF AMENDMENTS RE: REVISED MAIN TURBINE SYSTEM REQUIREMENTS TECHNICAL SPECIFICATION CHANGE (TAC NOS. MC1596 AND MC1597)
Dear Mr. Shriver:
The Nuclear Regulatory Commission has issued the enclosed Amendment No. 218 to Facility Operating License No. NPF-14 and Amendment No. 193 to Facility Operating License No.
NPF-22 for the Susquehanna Steam Electric Station, Units 1 and 2 (SSES 1 and 2). These amendments are in response to your application dated December 5, 2003, as supplemented by letter dated June 4, 2004.
These amendments revise SSES 1 and 2 Technical Specifications (TSs) by adding a requirement to apply linear heat generation (LHGR) limits if the main turbine bypass system becomes inoperable. The proposed changes clarify TS 3.7.6 to state that both minimum critical power ratio and LHGR limits for an inoperable main turbine bypass system are required if the system becomes inoperable.
A copy of our safety evaluation is also enclosed. The Notice of Issuance will be included in the Commission's Biweekly Federal Register Notice.
Sincerely,
/RA/
Richard V. Guzman, Project Manager, Section 1 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-387 and 50-388
Enclosures:
- 1. Amendment No. 218 to DISTRIBUTION:
License No. NPF-14 PDI-1 R/F GMatakas, RGN-1
- Provided SE input by memo. No substantive changes made.
Accession No.: ML043350010 Package No.: ML TSs: ML OFFICE PDI-1/PM PDI-2/LA SRXB*
OGC PDI-1/SC NAME RGuzman SLitte for MO'Brien FAkstulewicz MWoods RLaufer DATE 11/24/04 11/24/04 07/07/04 11/29/04 12/2/04 OFFICIAL RECORD COPY
Susquehanna Steam Electric Station, Unit Nos. 1 and 2 cc:
Britt T. McKinney Vice President - Nuclear Site Operations PPL Susquehanna, LLC 769 Salem Blvd., NUCSB3 Berwick, PA 18603-0467 Robert A. Saccone Vice President - Nuclear Operations PPL Susquehanna, LLC 769 Salem Blvd., NUCSB3 Berwick, PA 18603-0467 Aloysius J. Wrape, III General Manager - Nuclear Assurance PPL Susquehanna, LLC Two North Ninth Street, GENPL4 Allentown, PA 18101-1179 Terry L. Harpster General Manager - Plant Support PPL Susquehanna, LLC 769 Salem Blvd., NUCSA4 Berwick, PA 18603-0467 Greg F. Ruppert General Manager - Nuclear Engineering PPL Susquehanna, LLC 769 Salem Blvd., NUCSB3 Berwick, PA 18603-0467 Rocco R. Sgarro Manager - Nuclear Regulatory Affairs PPL Susquehanna, LLC Two North Ninth Street, GENPL4 Allentown, PA 18101-1179 Walter E. Morrissey Supervising Engineer 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 Dale F. Roth Manager - Quality Assurance PPL Susquehanna, LLC 769 Salem Blvd., NUCSB2 Berwick, PA 18603-0467 Luis A. Ramos Special Office of the President 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 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
Susquehanna Steam Electric Station, Unit Nos. 1 and 2 cc:
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
PPL SUSQUEHANNA, LLC ALLEGHENY ELECTRIC COOPERATIVE, INC.
DOCKET NO. 50-387 SUSQUEHANNA STEAM ELECTRIC STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 218 License No. NPF-14 1.
The Nuclear Regulatory Commission (the Commission or the NRC) having found that:
A.
The application for the amendment filed by PPL Susquehanna, LLC, dated December 5, 2003, as supplemented by letter dated June 4, 2004, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the regulations of the Commission; C.
There is reasonable assurance: (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of the Facility Operating License No. NPF-14 is hereby amended to read as follows:
(2)
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 218 and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license. PPL Susquehanna, LLC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Richard J. Laufer, Chief, Section 1 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: December 3, 2004
ATTACHMENT TO LICENSE AMENDMENT NO. 218 FACILITY OPERATING LICENSE NO. NPF-14 DOCKET NO. 50-387 Replace the following pages of the Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
REMOVE INSERT TS / 3.7-15 TS / 3.7-15 3.7-16 TS / 3.7-16
PPL SUSQUEHANNA, LLC ALLEGHENY ELECTRIC COOPERATIVE, INC.
DOCKET NO. 50-388 SUSQUEHANNA STEAM ELECTRIC STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 193 License No. NPF-22 1.
The Nuclear Regulatory Commission (the Commission or the NRC) having found that:
A.
The application for the amendment filed by PPL Susquehanna, LLC, dated December 5, 2003, as supplemented by letter dated June 4, 2004, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, the provisions of the Act, and the regulations of the Commission; C.
There is reasonable assurance: (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of the Facility Operating License No. NPF-22 is hereby amended to read as follows:
(2)
Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 193 and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license. PPL Susquehanna, LLC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
This license amendment is effective as of its date of issuance and shall be implemented within 30 days.
FOR THE NUCLEAR REGULATORY COMMISSION
/RA/
Richard J. Laufer, Chief, Section 1 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: December 3, 2004
ATTACHMENT TO LICENSE AMENDMENT NO. 193 FACILITY OPERATING LICENSE NO. NPF-22 DOCKET NO. 50-388 Replace the following pages of the Appendix A Technical Specifications with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
REMOVE INSERT TS / 3.7-15 TS / 3.7-15 3.7-16 TS / 3.7-16
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 218 TO FACILITY OPERATING LICENSE NO. NPF-14 AND AMENDMENT NO. 193 TO FACILITY OPERATING LICENSE NO. NPF-22 PPL SUSQUEHANNA, LLC ALLEGHENY ELECTRIC COOPERATIVE, INC.
SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2 DOCKET NOS. 50-387 AND 388
1.0 INTRODUCTION
By application dated December 5, 2003 (Reference 3), as supplemented by letter dated June 4, 2004 (Reference 4), PPL Susquehanna, LLC (PPL, the licensee), requested changes to the Technical Specifications (TSs) for Susquehanna Steam Electric Station, Units 1 and 2 (SSES 1 and 2).
The proposed changes would revise SSES 1 and 2 TSs by adding a requirement to apply linear heat generation (LHGR) limits if the main turbine bypass system (MTBS) becomes inoperable.
The proposed changes clarify TS 3.7.6 to state that both minimum critical power ratio (MCPR) and LHGR limits for an inoperable MTBS are required if the system becomes inoperable. The supplemental letter dated June 4, 2004, provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change the staffs original no significant hazards consideration determination as published in the Federal Register on January 6, 2004 (69 FR 698).
2.0 REGULATORY EVALUATION
The Nuclear Regulatory Commission (NRC) finds that PPL in its December 5, 2003, submittal identified the applicable regulatory requirements. The regulatory requirements and guidance which the NRC staff considered in its review of the application are as follows:
- 1.
Title 10 of the Code of Federal Regulations (10 CFR) establishes the fundamental regulatory requirements with respect to the reactivity control systems. Specifically, General Design Criterion 10, Reactor design, in Appendix A to Part 50, General Design Criteria for Nuclear Power Plants, states, in part, that the reactor core and associated coolant, control, and protection systems shall be designed with appropriate margin to assure that specified acceptable fuel design limits are not exceeded during any condition of normal operation, including the effects of anticipated operational occurrences.
- 2.
GDC-13, Instrumentation and control, states, in part, that instrumentation shall be provided to monitor variables and systems over their anticipated ranges for normal operation, for anticipated operational occurrences, and for accident conditions as appropriate to assure adequate safety.
3.
Generic Letter 88-16 (Reference 1) allow licensees to include the cycle specific parameter limits such as LHGR in the Core Operating Limit Report (COLR), provided the changes in the parameter limits are determined using the NRC-approved methodology and consistent with all applicable limits of the final safety analysis report.
3.0 TECHNICAL EVALUATION
3.1 Background
The MTBS is designed to control steam pressure when reactor steam generation exceeds turbine requirements during turbine unit startup, sudden load reduction, and cooldown. It allows excess steam flow from the reactor to the condenser without going through the turbine. The full bypass capacity of the system is approximately 25 percent of the nuclear steam supply system rated steam flow. Sudden load reductions within the capacity of the steam bypass can be accommodated without a reactor scram. The MTBS consists of five valves (all five valves have the same capacity) connected to the main steam lines between the main steam isolation valves and the turbine stop valve bypass valve chest. Each of these valves is operated by hydraulic cylinders. The MTB valves are controlled by the pressure regulation function of the main turbine electro-hydraulic control system. The MTB valves are normally closed, and the pressure regulator controls the turbine control valves that direct all steam flow to the turbine. If the speed governor or the load limiter restricts steam flow to the turbine, the pressure regulator controls the system pressure by opening the MTB valves.
The LHGR is a measure of the heat generation rate of a fuel rod in a fuel assembly at any axial location. Limits on LHGR are specified to ensure that fuel design limits are not exceeded anywhere in the core during normal operation, including anticipated operational occurrences (AOOs).
The average planar linear heat generation rate (APLHGR) is a measure of the average LHGR of all the fuel rods in a fuel assembly at any axial location. Limits on APLHGR are specified to ensure that fuel design limits are not exceeded anywhere in the core during normal operation, including AOOs, and that the peak cladding temperature during the postulated loss-of-coolant accident (LOCA) does not exceed 2200 degrees Farenheit.
3.2 PPLs Proposed Change When PPL converted the SSES 1 and 2 TSs to Revision 1 of the Standard Technical Specifications (STS), the plant MTBS TS limiting condition for operation (LCO) 3.7.6 only included MCPR as the only appropriate thermal limit to be applied for an inoperable MTBS.
The current TSs for this LCO does not contain any reference to LHGR as applicable for an inoperable MTBS.
The MTBS fast opening feature is assumed to function during the turbine generator load rejection and during feedwater controller failure transients as discussed in the final safety analysis report. Opening the bypass valves during the pressurization event mitigates the increase in reactor vessel pressure, which affects the MCPR during the event. Therefore, an inoperable MTBS may result in an MCPR penalty. The proposed change adds a requirement to implement LHGR limits if the MTBS becomes inoperable. The proposed change parallels an already existing requirement for MCPR limits. Currently, the SSES 1 and 2 COLRs contain MCPR and LHGR limits when the MTBS becomes inoperable. This proposed change clarifies TS 3.7.6 to state that both the MCPR and LHGR limits are required by TSs if the MTBS become inoperable.
The cycle specific safety analyses assume a certain number of operable turbine bypass valves as an input (i.e., one through five). Therefore, the MTBS is considered operable when the number of operable bypass valves is greater than or equal to the number assumed in the safety analyses. The number of bypass valves assumed in the safety analyses is specified in the COLR. The MCPR and LHGR limits for the inoperable MTBS are also specified in the COLR.
In addition, LHGR values for each cycle are given in the COLR, and they are calculated using the NRC staff-approved methodology given in the SSES 1 and 2 TS Bases Section 3.2.3 (Reference 2).
In the STS, APLHGR is applicable for inoperable MTBS. This requirement is based on the assumption of General Electric (GE) fuel in the core and with GE analysis methods. Since SSES 1 and 2 is currently loaded with Framatome-ANP fuel, this requirement is not applicable to the current operating core.
The NRC staff requested a clarification from PPL for the basis of including the LHGR rather than APLHGR as an applicable thermal limit when the MTBS is inoperable. PPL in a letter dated June 4, 2004, submitted the necessary information. PPL stated that the APLHGR limits are derived from LOCA analyses, and the LOCA analyses results are unaffected by inoperability of MTBS. Hence, APLHGR limits are not affected. Limits on LHGR are specified to ensure that fuel design limits are not exceeded anywhere in the core during normal operation. The applicable safety analyses have determined that LHGR is the appropriate thermal margin limit to be used for MTBS operability since it protects against fuel damage and mechanical and thermal overpowering during a transient. Therefore, PPLs proposal to add LHGR rather than APLHGR, as an applicable thermal limit when the MTBS is inoperable, is acceptable.
3.3 Conclusion The NRC staff has reviewed PPLs justification for the proposed revision (Reference 3) and the response to the NRC staffs request for additional information (Reference 4) to revise SSES 1 and 2 TSs Section 3.7.6 to include LHGR in addition to MCPR limits as applicable thermal limits when the MTBS is inoperable. Based on the results of the review, the NRC staff finds the proposed changes are consistent with the guidance given in Generic Letter 88-16, Removal of Cycle-Specific Parameter Limits From Technical Specifications, and therefore, finds it acceptable.
4.0 STATE CONSULTATION
In accordance with the Commissions regulations, the Pennsylvania State Official was notified of the proposed issuance of the amendments. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendments change a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. The NRC staff has determined that the amendments involve no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the amendments involve no significant hazards consideration, and there has been no public comment on such finding (69 FR 698). Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendments.
6.0 CONCLUSION
The Commission has concluded based on the considerations discussed above that: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commissions regulations, and (3) the issuance of the amendments will not be inimical to the common defense and security or to the health and safety of the public.
7.0 REFERENCES
1.
Generic Letter 88-16, Removal of Cycle-Specific Parameter Limits From Technical Specifications, October 3, 1998.
2.
ANF-89-98(P)(A) Revision 1 and Revision 1 Supplement 1, Generic Mechanical Design Criteria for BWR Fuel Design, Advanced Nuclear Fuels Corporation, May 1995.
3.
B.L Shriver to U.S. NRC, Susquehanna Steam Electric Station Proposed Amendment No. 258 to License NPF-14 and Proposed Amendment No. 223 to License NFP-22:
Revised Main Turbine Bypass System Requirements PLA-5694, December 5, 2003 (ADAMS Accession No. ML033500447).
4.
B.L Shriver to U.S. NRC, Susquehanna Steam Electric Station Response to NRC Request for Additional Information Relative to Susquehanna Steam Electric Station, Units 1 and 2 Revised Main Turbine Bypass System Requirements (TAC Nos. MC1596 and MC1597) PLA-5759, June 4, 2004 (ADAMS Accession No. ML041670546).
Principal Contributor: G. Thomas Date: December 3, 2004