ML071070217

License Amendment, Issuance of Amendment Technical Specification 3.8.1 and Figure 4.1-2 (TAC Nos. MD2142 and MD2143)

ML071070217
Person / Time
Site:	Susquehanna
Issue date:	04/26/2007
From:	Richard Guzman NRC/NRR/ADRO/DORL/LPLI-1
To:	Mckinney B Susquehanna
Guzman R, NRR/DORL, 415-1030
References
TAC MD2142, TAC MD2143
Download: ML071070217 (13)

Text

April 26, 2007Mr. Britt T. McKinneySr. Vice President and Chief Nuclear Officer PPL Susquehanna, LLC 769 Salem Blvd., NUCSB3 Berwick, PA 18603-0467

SUBJECT:

SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2 - ISSUANCE OFAMENDMENT RE: TECHNICAL SPECIFICATION 3.8.1 AND FIGURE 4.1-2 (TAC NOS. MD2142 AND MD2143)

Dear Mr. McKinney:

The Commission has issued the enclosed Amendment No. 243 to Facility Operating License No.NPF-14 and Amendment No. 221 to Facility Operating License No. NPF-22 for the Susquehanna Steam Electric Station, Units 1 and 2 (SSES 1 and 2). These amendments consist of changes to the Technical Specifications (TSs) in response to your application dated May 31, 2006.These amendments correct administrative errors in the SSES 1 and 2 TSs by adding a logical"AND" connector in Condition B of TS 3.8.1 for SSES 1, "AC Sources-Operating," and corrects the routing of Interstate Route 80 on Figure 4.1-2 of TSs 4.1.2, "Low Population Zone," for

SSES 1 and 2.

A copy of our safety evaluation is also enclosed. The Notice of Issuance will be included in the Commission's next regular Biweekly Federal Register Notice.Sincerely,/RA/Richard V. Guzman, Senior Project ManagerPlant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket Nos. 50-387 and 50-388

Enclosures:

1. Amendment No. 243 to License No. NPF-14

2. Amendment No. 221 to License No. NPF-22

3. Safety Evaluationcc w/encls: See next page Susquehanna Steam Electric Station, Unit Nos. 1 and 2 cc:

Robert A. SacconeGeneral Manager - Nuclear Operations PPL Susquehanna, LLC 769 Salem Blvd., NUCSB3 Berwick, PA 18603-0467Terry L. HarpsterGeneral Manager - Plant Support PPL Susquehanna, LLC 769 Salem Blvd., NUCSA4 Berwick, PA 18603-0467Rocco R. SgarroManager - Nuclear Regulatory Affairs PPL Susquehanna, LLC Two North Ninth Street, GENPL4 Allentown, PA 18101-1179Supervisor - Nuclear Regulatory Affairs PPL Susquehanna, LLC 769 Salem Blvd., NUCSA4 Berwick, PA 18603-0467Michael H. CrowthersSupervising Engineer Nuclear Regulatory Affairs PPL Susquehanna, LLC Two North Ninth Street, GENPL4 Allentown, PA 18101-1179Steven M. CookManager - Quality Assurance PPL Susquehanna, LLC 769 Salem Blvd., NUCSB2 Berwick, PA 18603-0467Luis A. RamosCommunity Relations Manager, Susquehanna PPL Susquehanna, LLC 634 Salem Blvd., SSO Berwick, PA 18603-0467Bryan A. Snapp, EsqAssoc. General Counsel PPL Services Corporation Two North Ninth Street, GENTW3 Allentown, PA 18101-1179Supervisor - Document Control ServicesPPL Susquehanna, LLC Two North Ninth Street, GENPL4 Allentown, PA 18101-1179Richard W. OsborneAllegheny Electric Cooperative, Inc.

212 Locust Street P.O. Box 1266 Harrisburg, PA 17108-1266Director - Bureau of Radiation ProtectionPennsylvania Department of Environmental Protection P.O. Box 8469 Harrisburg, PA 17105-8469Senior Resident InspectorU.S. Nuclear Regulatory Commission P.O. Box 35, NUCSA4Berwick, PA 18603-0035Regional Administrator, Region 1U.S. Nuclear Regulatory Commission

475 Allendale Road King of Prussia, PA 19406Board of SupervisorsSalem Township P.O. Box 405 Berwick, PA 18603-0035Dr. Judith JohnsrudNational Energy Committee Sierra Club 443 Orlando Avenue State College, PA 16803 April 26, 2007Mr. Britt T. McKinneySr. Vice President and Chief Nuclear Officer PPL Susquehanna, LLC 769 Salem Blvd., NUCSB3 Berwick, PA 18603-0467

SUBJECT:

SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2 - ISSUANCE OFAMENDMENT RE: TECHNICAL SPECIFICATION 3.8.1 AND FIGURE 4.1-2 (TAC NOS. MD2142 AND MD2143)

Dear Mr. McKinney:

The Commission has issued the enclosed Amendment No. 243 to Facility Operating License No.NPF-14 and Amendment No. 221 to Facility Operating License No. NPF-22 for the Susquehanna Steam Electric Station, Units 1 and 2 (SSES 1 and 2). These amendments consist of changes to the Technical Specifications (TSs) in response to your application dated May 31, 2006.These amendments correct administrative errors in the SSES 1 and 2 TSs by adding a logical"AND" connector in Condition B of TS 3.8.1 for SSES 1, "AC Sources-Operating," and corrects the routing of Interstate Route 80 on Figure 4.1-2 of TSs 4.1.2, "Low Population Zone," for

SSES 1 and 2.

A copy of our safety evaluation is also enclosed. The Notice of Issuance will be included in the Commission's next regular Biweekly Federal Register Notice.Sincerely,/RA/Richard V. Guzman, Senior Project ManagerPlant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket Nos. 50-387 and 50-388

Enclosures:

1. Amendment No. 243 to License No. NPF-14

2. Amendment No. 221 to License No. NPF-22

3. Safety Evaluationcc w/encls: See next page DISTRIBUTION

PUBLICRidsNrrDorlLpl1-1RidsNrrPMRGuzmanRidsNrrDirsItsb LPLI-1/R/FRidsNrrLASLittleRidsOGCRpRClark GHill (4)RidsAcrsAcnwMailCenterADAMS Accession Number: ML071070217

• SE inputs provided by memo. No substantive changes made.OFFICELPLI-1/PMLPLI-1/LAITSB/BCOGCLPLI-1/BCNAMERGuzmanSLittleTKobetz*SUttalMKowal DATE4/19/074/19/0711/9/064/23/074/25/07OFFICIAL RECORD COPY PPL SUSQUEHANNA, LLCALLEGHENY ELECTRIC COOPERATIVE, INC.DOCKET NO.50-387SUSQUEHANNA STEAM ELECTRIC STATION, UNIT 1AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 243 License No. NPF-141.The Nuclear Regulatory Commission (the Commission or the NRC) having found that:A.The application for the amendment filed by PPL Susquehanna, LLC, dated May 31, 2006, 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 thisamendment 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 andsecurity or to the health and safety of the public; andE.The issuance of this amendment is in accordance with 10 CFR Part 51 of theCommission's regulations and all applicable requirements have been satisfied. 2.Accordingly, the license is amended by changes to the Technical Specifications asindicated 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 PlanThe Technical Specifications contained in Appendix A, as revised throughAmendment No. 243 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 implementedwithin 30 days.FOR THE NUCLEAR REGULATORY COMMISSION/RA/Mark G. Kowal, Chief Plant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the License and Technical SpecificationsDate of Issuance: April 26, 2007 ATTACHMENT TO LICENSE AMENDMENT NO. 243FACILITY OPERATING LICENSE NO. NPF-14DOCKET NO. 50-387Replace the following page of the License with the attached revised page. The revised page isidentified by amendment number and contains marginal lines indicating the areas of change.REMOVEINSERT 33Replace the following pages of the Appendix A Technical Specifications with the attachedrevised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change. REMOVEINSERTTS/3.8-3TS/3.8-34.0-4TS/4.0-4 PPL SUSQUEHANNA, LLCALLEGHENY ELECTRIC COOPERATIVE, INC.DOCKET NO.50-388SUSQUEHANNA STEAM ELECTRIC STATION, UNIT 2AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 221License No. NPF-221.The Nuclear Regulatory Commission (the Commission or the NRC) having found that:A.The application for the amendment filed by PPL Susquehanna, LLC, dated May 31, 2006, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's regulations set forth in10 CFR Chapter I; B.The facility will operate in conformity with the application, the provisions of theAct, and the regulations of the Commission;C.There is reasonable assurance: (I) that the activities authorized by thisamendment 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 andsecurity or to the health and safety of the public; andE.The issuance of this amendment is in accordance with 10 CFR Part 51 of theCommission's regulations and all applicable requirements have been satisfied. 2.Accordingly, the license is amended by changes to the Technical Specifications asindicated 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 PlanThe Technical Specifications contained in Appendix A, as revised throughAmendment No. 221 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 implementedwithin 30 days. FOR THE NUCLEAR REGULATORY COMMISSION/RA/Mark G. Kowal, Chief Plant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the License and Technical SpecificationsDate of Issuance: April 26, 2007 ATTACHMENT TO LICENSE AMENDMENT NO. 221FACILITY OPERATING LICENSE NO. NPF-22DOCKET NO. 50-388Replace the following page of the License with the attached revised page. The revised page isidentified by amendment number and contains marginal lines indicating the areas of change.REMOVEINSERT 3 3Replace the following page of the Appendix A Technical Specifications with the attached revisedpage. The revised page is identified by amendment number and contains marginal lines indicating the areas of change. REMOVEINSERT4.0-4TS/4.0-4 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATIONRELATED TO AMENDMENT NO. 243 TO FACILITY OPERATING LICENSE NO. NPF-14AND AMENDMENT NO. 221 TO FACILITY OPERATING LICENSE NO. NPF-22PPL SUSQUEHANNA, LLCALLEGHENY ELECTRIC COOPERATIVE, INC.SUSQUEHANNA STEAM ELECTRIC STATION, UNITS 1 AND 2DOCKET NOS. 50-387 AND 38

81.0INTRODUCTION

By letter dated May 31, 2006, Agencywide Documents Access and Management System(ADAMS) Accession No. ML061590353, PPL Susquehanna, LLC (PPL, the licensee), requested changes to the Technical Specifications (TSs) for Susquehanna Steam Electric Station, Units 1and 2 (SSES 1 and 2). The proposed changes would correct administrative errors in the SSES 1 and 2 TSs by adding a logical "AND" connector in Condition B of TS 3.8.1 for SSES 1, "AC Sources-Operating," and correct the routing of Interstate Route 80 on Figure 4.1-2 of TSs 4.1.2, "Low Population Zone," for SSES 1 and 2.

2.0REGULATORY EVALUATION

The regulatory requirements and guidance which the Nuclear Regulatory Commission (NRC)staff considered in its review of the application are as follows: 1.Title 10 of the Code of Federal Regulations (10 CFR) Appendix A of Part 50, GeneralDesign Criterion (GDC) 17, "Electric power systems," requires, in part, that nuclear power plants must have onsite and offsite electric power systems to permit the functioning of structures, systems, and components that are important to safety. The onsite system is required to have sufficient independence, redundancy, and testability to perform its safety function, assuming a single failure. The offsite power system must be supplied by two physically independent circuits that are designed and located so as to minimize, to the extent practical, the likelihood of their simultaneous failure under operating and postulated accident and environmental conditions. In addition, this criterion requires provisions to minimize the probability of losing electric power from the remaining electric power supplies as a result of loss of power from the unit, the offsite transmission network, or the onsite power supplies.2. GDC-18, "Inspection and testing of electric power systems," requires that electric powersystems that are important to safety be designed to permit appropriate periodic inspection and testing. 3. Section 50.36, "Technical specifications," provides the regulatory requirements for thecontent required in a licensee's TSs. Section 50.36 states, in part, that the TSs will include surveillance requirements (SRs) to assure that the quality of systems and components is maintained, that facility operation will be within safety limits, and that the limiting conditions for operation (LCO) will be met. Specifically, 10 CFR 50.36(c)(2)(ii) sets forth four criteria to be used in determiningwhether an LCO is required to be included in the TSs. These criteria are as follows:(a)Installed instrumentation that is used to detect, and indicate in the control room, a significant abnormal degradation of the reactor coolant pressure boundary.(b)A process variable, design feature, or operating restriction that is an initialcondition of a design-basis accident or transient analysis that either assumes the failure of or presents a challenge to the integrity of a fission product barrier.(c)A structure, system, or component that is part of the primary success pathand which functions or actuates to mitigate a design-basis accident or transient that either assumes the failure of or presents a challenge to the integrity of a fission product barrier.(d)A structure, system, or component which operating experience or probabilistic risk assessment has shown to be significant to public health and safety.Existing LCOs and related surveillances included as TS requirements which satisfy anyof the criteria stated above must be retained in the TSs, while those requirements that do not fall within or satisfy these criteria may be relocated to licensee-controlled documents.

3.0TECHNICAL EVALUATION

3.1Background

By letter dated July 30, 1998 (ADAMS Accession No. ML010160119), the NRC staff approvedPPL's conversion of the TSs to the Improved TSs (ITS). During the conversion, a required "AND" logical connector was inadvertently left out of Condition B of LCO 3.8.1 in the SSES 1 TSs. The SSES 2 TSs correctly reflect the "AND" logical connector and do not need to be revised. During the ITS conversion, Figure 4.1-2 was also drawn incorrectly for both units.3.2PPL's Proposed Changes Proposed Changes to TS LCO 3.8.1 The proposed TS change would add a logical "AND" connector to Condition B, in LCO 3.8.1,between REQUIRED ACTIONS B.3.2 and B.4. The addition of the logical connector would be in accordance with ITS Section 1.2, "Logical Connectors." Proposed Changes to Figure 4.1-2 The proposed TS change would delete the connection between Interstate Route 80 (I-80) andInterstate Route 81 (I-81).3.3NRC Staff Evaluation Changes to TS LCO 3.8.1 The proposed change to LCO 3.8.1 corrects an administrative error in the ITS. The logical"AND" connector is needed to ensure that all REQUIRED ACTIONS are completed consistent with NUREG-1433, "Standard Technical Specifications, General Electric Plants, BWR/4 [boiling-water reactor/4]." With one required diesel generator (DG) inoperable, the operator must:1.Perform SR 3.8.1.1, and 2.Declare required feature(s), supported by the inoperable DG, inoperable when theredundant required feature(s) are inoperable, and 3.Determine operable DGs are not inoperable due to common cause failures or performSR 3.8.1.7 for operable DGs, and4.Restore required DG to OPERABLE status in 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

The NRC staff reviewed the administrative changes proposed by PPL and find them acceptablebecause they are compatible with the Standard TSs, do not result in any change in operating requirements, and are consistent with the 10 CFR 50.36.Changes to Figure 4.1-2 Figure 4.1-2 is a map of the Low Population Zone. The map incorrectly shows I-80 intersectingwith I-81 and becoming part of I-81. Figure 4.1-2 is redrawn to show the correct routing of I-80. The proposed changes to Figure 4.1-2 are acceptable because the changes correctly indicatethe routes by which state and local police departments can direct traffic in the event of an emergency. Inaccurate maps could cause unnecessary delays, confusion and needless radiation exposure to the local population if the surrounding areas are to be evacuated.

3.4NRC Staff Conclusion

Based on the review of the above changes, the NRC staff concludes that the proposed changesto TS 3.8.1 do not affect the safe and reliable operation of the plant, maintains compliance with requirements governing the design and operation of the electrical power system and, therefore, are acceptable. The proposed changes to Figure 4.1-2 are acceptable because they will ensure proper implementation of the Emergency Preparedness Plan, if necessary.

4.0STATE CONSULTATION

In accordance with the Commission's regulations, the Pennsylvania State official was notified ofthe proposed issuance of the amendments. The State official had no comments.

5.0ENVIRONMENTAL CONSIDERATION

The amendments change a requirement with respect to installation or use of a facilitycomponent 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. TheCommission has previously issued a proposed finding that the amendments involve no significant hazards consideration, and there has been no public comment on such finding (71 FR 75996). 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.

6.0CONCLUSION

The Commission has concluded, based on the considerations discussed above, that: (1) thereis 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 Commission's 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. Principal Contributor: R. Clark Date: April 26, 2007