ML060190143
| ML060190143 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 02/06/2006 |
| From: | Richard Guzman Plant Licensing Branch III-2 |
| To: | Mckinney B Susquehanna |
| Guzman R, NRR/DLPM 415-1030 | |
| References | |
| TAC MC6205 | |
| Download: ML060190143 (11) | |
Text
February 6, 2006 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, UNIT 2 - ISSUANCE OF AMENDMENT RE: REVISION TO TECHNICAL SPECIFICATION TABLE 3.3.5.1-1 (TAC NO. MC6205)
Dear Mr. McKinney:
The Commission has issued the enclosed Amendment No. 206 to Facility Operating License No. NPF-22 for the Susquehanna Steam Electric Station, Unit 2 (SSES-2). This amendment consists of changes to the Technical Specification (TS) Table 3.3.5.1-1 in response to your application dated January 28, 2005.
This amendment revises the SSES-2 TS Table 3.3.5.1-1, Emergency Core Cooling System Instrumentation, Function 3.e, High Pressure Coolant Injection (HPCI) System, to change Condition D to C as the condition to reference from Required Action A.1. This is an editorial revision to correct a typographical error that had been present since the conversion to the Improved TSs in July 1998.
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 Plant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-388
Enclosures:
- 1. Amendment No. 206 to License No. NPF-22
- 2. Safety Evaluation cc w/encls: See next page
February 6, 2006 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, UNIT 2 - ISSUANCE OF AMENDMENT RE: REVISION TO TECHNICAL SPECIFICATION TABLE 3.3.5.1-1 (TAC NO. MC6205)
Dear Mr. McKinney:
The Commission has issued the enclosed Amendment No. 206 to Facility Operating License No. NPF-22 for the Susquehanna Steam Electric Station, Unit 2 (SSES-2). This amendment consists of changes to the Technical Specification (TS) Table 3.3.5.1-1 in response to your application dated January 28, 2005.
This amendment revises the SSES-2 TS Table 3.3.5.1-1, Emergency Core Cooling System Instrumentation, Function 3.e, High Pressure Coolant Injection (HPCI) System, to change Condition D to C as the condition to reference from Required Action A.1. This is an editorial revision to correct a typographical error that had been present since the conversion to the Improved TSs in July 1998.
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 Plant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-388
Enclosures:
- 1. Amendment No. 206 to License No. NPF-22
- 2. Safety Evaluation cc w/encls: See next page DISTRIBUTION PUBLIC RidsNrrPMRGuzman RidsAcrsAcnwMailCenter LPLI-1 RF RidsNrrLASLittle RidsNrrDorlLpla RidsNrrDorl DPR RidsRgn1MailCenter RidsNrrDirsItsb GHill(4)
RidsOGC Rp ADAMS Accession Number: ML060190143 OFFICE LPLI-1/PM LPLI-1/LA IROB OGC LPLI-1/BC NAME RGuzman SLittle TTjader for TBoyce MBupp Jboska for RLaufer DATE 1/18/06 1/23/06 1/31/06 1/30/06 2/02/06 OFFICIAL RECORD COPY
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 Aloysius J. Wrape, III General Manager - Performance Improvement and Oversight 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 Richard D. Pagodin 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 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
Susquehanna Steam Electric Station, Unit Nos. 1 and 2 cc:
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. 50-388 SUSQUEHANNA STEAM ELECTRIC STATION, UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 206 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 the PPL Susquehanna, LLC, dated January 28, 2005, 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. 206 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 Plant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: February 6, 2006
ATTACHMENT TO LICENSE AMENDMENT NO. 206 FACILITY OPERATING LICENSE NO. NPF-22 DOCKET NO. 50-388 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 TS/3.3-45 TS/3.3-45
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 206 TO FACILITY OPERATING LICENSE NO. NPF-22 PPL SUSQUEHANNA, LLC ALLEGHENY ELECTRIC COOPERATIVE, INC.
SUSQUEHANNA STEAM ELECTRIC STATION, UNIT 2 DOCKET NO. 50-388
1.0 INTRODUCTION
By application dated January 28, 2005 (Accession No. ML050390381), PPL Susquehanna, LLC (the licensee), requested changes to the Technical Specifications (TSs) for Susquehanna Steam Electric Station, Unit 2 (SSES-2).
The proposed changes would revise the SSES-2 TS Table 3.3.5.1-1, Emergency Core Cooling System Instrumentation, Function 3.e, High Pressure Coolant Injection (HPCI) System, to change Condition D to C as the condition to reference from Required Action A.1. This is an editorial revision to correct a typographical error that had been present since PPL converted to the Improved TSs in 1998.
2.0 REGULATORY EVALUATION
The Nuclear Regulatory Commission (NRC) finds that PPL, in its January 28, 2005, submittal, identified the applicable regulatory requirements. The regulatory requirement and guidance which the NRC staff considered in its review of the application are as follows:
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 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 PPLs Proposed Changes The licensee has proposed the following changes to the TSs:
1.
For TS Table 3.3.5.1-1, Emergency Core Cooling System Instrumentation, Function 3.e, High Pressure Coolant Injection (HPCI) System, Condition D would be changed to C as the condition to reference from Required Action A.1.
2.
In addition, interim administrative direction previously added to the TS Bases Section 3.3.5.1, Subsection for Action C.1 and C.2, and Action D.1, D.2.1, and D.2.2, would be removed upon approval of the requested change.
3.2 PPL Basis for the proposed change The proposed change to revise TS Table 3.3.5.1-1 is to correct a typographical error that occurred when preparing a response to an NRC Request for Additional Information (RAI) during the review of documents PPL submitted to the NRC for the conversion to the Improved TSs.
The error was documented in the PPL Corrective Action Process. PPLs corrective action was to correct the table and process a license amendment request for the associated TS deficiency under Administrative Letter 98-10, Dispositioning Specifications that are Insufficient to Assure Plant Safety. In accordance with Administrative Letter 98-10, PPL also revised their TS Bases to provide administrative direction to plant operators until the proposed TS change had been approved by the NRC as a license amendment.
PPLs original Improved TS submittal to the NRC established that Action C was the appropriate Action for TS Table 3.3.5.1-1 HPCI Manual Initiation Function on both Units 1 and 2. A subsequent submittal (to correct the table regarding Unit 2 Suppression Pool Water - High Level) resulted in an inadvertent change to make the required Action D for the HPCI Manual Initiation function in Unit 2 Table 3.3.5.1-1.
PPL reviewed their change history to Unit 2 TS Table 3.3.5.1-1 and confirmed that Action C is the correct Action to be referenced for HPCI Function 3.e Manual Initiation. Upon a loss of Manual Initiation capability for HPCI, Unit 2 Table 3.3.5.1-1 should direct that Action C is applicable, consistent with Unit 1 Table 3.3.5.1-1.
3.3
NRC Staff Evaluation
The proposed change to Unit 2 TS Table 3.3.5.1 provides a correction to a typographical error that occurred when preparing a change to Unit 2 TS Table 3.3.5.1-1 in response to an NRC RAI. The response was in support of PPLs request to convert to the Improved TSs which was approved by the NRC on July 30, 1998 (Agencywide Documents Access and Management System Accession No. ML010160119).
The NRC staff agrees that upon a loss of manual initiation capability for HPCI, Condition C is the applicable action, consistent with the original intent of the TSs and with NUREG-1433, Standard Technical Specification General Electric Plant BWR [boiling water reactor]/4, which was the approved basis for conversion to the Improved TSs. The proposed change is administrative in nature because it was originally submitted correctly and was inadvertantly changed in response to the RAI. Therefore, based on the review of the above changes, the NRC staff concludes that the above editorial correction to TS Table 3.3.5.1-1 and the associated bases page change are administrative in nature and do not affect the safe and reliable operation of the plant. Therefore, the licensees proposed changes as listed in Section 3.1 are acceptable.
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 amendment involves 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 amendment involves no significant hazards consideration, and there has been no public comment on such finding (70 FR 24655). Accordingly, the amendment meets 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. V. Guzman Date: February 6, 2006