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, 2007 Mr. Britt T. McKinney Sr. 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 OF AMENDMENT 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 Manager Plant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket 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 Evaluation cc w/encls: See next page

Susquehanna Steam Electric Station, Unit Nos. 1 and 2 cc:

Robert A. Saccone Bryan A. Snapp, Esq General Manager - Nuclear Operations Assoc. General Counsel PPL Susquehanna, LLC PPL Services Corporation 769 Salem Blvd., NUCSB3 Two North Ninth Street, GENTW3 Berwick, PA 18603-0467 Allentown, PA 18101-1179 Terry L. Harpster Supervisor - Document Control Services General Manager - Plant Support PPL Susquehanna, LLC PPL Susquehanna, LLC Two North Ninth Street, GENPL4 769 Salem Blvd., NUCSA4 Allentown, PA 18101-1179 Berwick, PA 18603-0467 Richard W. Osborne Rocco R. Sgarro Allegheny Electric Cooperative, Inc.

Manager - Nuclear Regulatory Affairs 212 Locust Street PPL Susquehanna, LLC P.O. Box 1266 Two North Ninth Street, GENPL4 Harrisburg, PA 17108-1266 Allentown, PA 18101-1179 Director - Bureau of Radiation Protection Supervisor - Pennsylvania Department of Nuclear Regulatory Affairs Environmental Protection PPL Susquehanna, LLC P.O. Box 8469 769 Salem Blvd., NUCSA4 Harrisburg, PA 17105-8469 Berwick, PA 18603-0467 Senior Resident Inspector Michael H. Crowthers U.S. Nuclear Regulatory Commission Supervising Engineer P.O. Box 35, NUCSA4 Nuclear Regulatory Affairs Berwick, PA 18603-0035 PPL Susquehanna, LLC Two North Ninth Street, GENPL4 Regional Administrator, Region 1 Allentown, PA 18101-1179 U.S. Nuclear Regulatory Commission 475 Allendale Road Steven M. Cook King of Prussia, PA 19406 Manager - Quality Assurance PPL Susquehanna, LLC Board of Supervisors 769 Salem Blvd., NUCSB2 Salem Township Berwick, PA 18603-0467 P.O. Box 405 Berwick, PA 18603-0035 Luis A. Ramos Community Relations Manager, Dr. Judith Johnsrud Susquehanna National Energy Committee PPL Susquehanna, LLC Sierra Club 634 Salem Blvd., SSO 443 Orlando Avenue Berwick, PA 18603-0467 State College, PA 16803

April 26, 2007 Mr. Britt T. McKinney Sr. 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 OF AMENDMENT 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 Manager Plant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket 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 Evaluation cc w/encls: See next page DISTRIBUTION:

PUBLIC RidsNrrDorlLpl1-1 RidsNrrPMRGuzman RidsNrrDirsItsb LPLI-1/R/F RidsNrrLASLittle RidsOGCRp RClark GHill (4) RidsAcrsAcnwMailCenter ADAMS Accession Number: ML071070217

• SE inputs provided by memo. No substantive changes made.

OFFICE LPLI-1/PM LPLI-1/LA ITSB/BC OGC LPLI-1/BC NAME RGuzman SLittle TKobetz* SUttal MKowal DATE 4/19/07 4/19/07 11/9/06 4/23/07 4/25/07 OFFICIAL RECORD COPY

PPL SUSQUEHANNA, LLC ALLEGHENY ELECTRIC COOPERATIVE, INC.

DOCKET NO. 50-387 SUSQUEHANNA STEAM ELECTRIC STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 243 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 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 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. 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 implemented within 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 Specifications Date of Issuance: April 26, 2007

ATTACHMENT TO LICENSE AMENDMENT NO. 243 FACILITY OPERATING LICENSE NO. NPF-14 DOCKET NO. 50-387 Replace the following page of the License with the attached revised page. The revised page is identified by amendment number and contains marginal lines indicating the areas of change.

REMOVE INSERT 3 3 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/3.8-3 TS/3.8-3 4.0-4 TS/4.0-4

PPL SUSQUEHANNA, LLC ALLEGHENY ELECTRIC COOPERATIVE, INC.

DOCKET NO. 50-388 SUSQUEHANNA STEAM ELECTRIC STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 221 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 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 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. 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 implemented within 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 Specifications Date of Issuance: April 26, 2007

ATTACHMENT TO LICENSE AMENDMENT NO. 221 FACILITY OPERATING LICENSE NO. NPF-22 DOCKET NO. 50-388 Replace the following page of the License with the attached revised page. The revised page is identified by amendment number and contains marginal lines indicating the areas of change.

REMOVE INSERT 3 3 Replace the following page of the Appendix A Technical Specifications with the attached revised page. The revised page is identified by amendment number and contains marginal lines indicating the areas of change.

REMOVE INSERT 4.0-4 TS/4.0-4

SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 243 TO FACILITY OPERATING LICENSE NO. NPF-14 AND AMENDMENT NO. 221 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 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 1 and 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.

2.0 REGULATORY 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, General Design 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 power systems 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 the content required in a licensees 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 determining whether 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 initial condition 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 path and 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 any of 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.

3.0 TECHNICAL EVALUATION

3.1 Background By letter dated July 30, 1998 (ADAMS Accession No. ML010160119), the NRC staff approved PPLs 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.

3.2 PPLs 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) and Interstate Route 81 (I-81).

3.3 NRC 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 the redundant required feature(s) are inoperable, and

3. Determine operable DGs are not inoperable due to common cause failures or perform SR 3.8.1.7 for operable DGs, and

4. 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 acceptable because 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 intersecting with 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 indicate the 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.

3.4 NRC Staff Conclusion

Based on the review of the above changes, the NRC staff concludes that the proposed changes to 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.

4.0 STATE CONSULTATION

In accordance with the Commission's 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 (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.

6.0 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 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