ML12254B002
| ML12254B002 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 12/27/2012 |
| From: | Martin R Plant Licensing Branch II |
| To: | Ajluni M Southern Nuclear Operating Co |
| Karen Cotton | |
| References | |
| TAC ME7862 | |
| Download: ML12254B002 (11) | |
Text
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UNITED STATES
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<Ii' 01' NUCLEAR REGULATORY COMMISSION
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WASHINGTON, D.C. 20555-0001 0
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Mr. M. J. Ajluni Nuclear Licensing Director Southern Nuclear Operating Company, Inc.
P. O. Box 1295 Bin - 038 Birmingham, AL 35201-1295
SUBJECT:
JOSEPH M. FARLEY NUCLEAR PLANT, UNIT 2, ISSUANCE OF AMENDMENT REGARDING CHANGES TO SURVEILLANCE REQUIREMENTS (TAC NO. ME7862)
Dear Mr. Ajluni:
The U.S. Nuclear Regulatory Commission has issued the enclosed Amendment No. 186 to Renewed Facility Operating License No. NPF-8 for the Joseph M. Farley Nuclear Plant, Unit 2.
The amendment consists of changes to the Technical Specifications in response to your application dated January 18, 2012.
The amendment revises Technical Specification (TS) Surveillance Requirement (SR) 3.4.11.1 and SR 3.4.11.4 by removing requirements no longer applicable to Joseph M. Farley Nuclear Plant, Unit 2.
A copy of the related Safety Evaluation is also enclosed. A Notice of Issuance will be included in the Commission's biweekly Federal Register notice.
Sincerely,
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~E. Martin, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-364
Enclosures:
- 1. Amendment No. 186 to NPF-8
- 2. Safety Evaluation cc w/encls: Distribution via Listserv
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SOUTHERN NUCLEAR OPERATING COMPANY, INC.
ALABAMA POWER COMPANY DOCKET NO. 50-364 JOSEPH M. FARLEY NUCLEAR PLANT, UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 186 Renewed License No. NPF-8
- 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Southern Nuclear Operating Company, Inc.
(Southern Nuclear), dated January 18, 2012, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and 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 rules and 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; D.
The issuance of this license 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
- 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 Renewed Facility Operating License No. NPF-8 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.
186
, are hereby incorporated in the renewed license.
Southern Nuclear shall operate the facility in accordance with the Technical Specifications.
- 3.
This license amendment is effective as of its date of issuance and shall be implemented within 60 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Robert J. Pascarelli, Chief Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: December 27, 2012
ATTACHMENT TO LICENSE AMENDMENT NO. 186 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-8 DOCKET NO. 50-364 Replace the following pages of the License and Appendix A Technical Specifications (TSs) with the enclosed pages. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.
Remove Pages Insert Pages License License License No. NPF-8, page 3 License No. NPF-8, page 3 TSs TSs 3.4.11-3 3.4.11-3 3.4.11-4 3.4.11-4
-3 (2)
Alabama Power Company, pursuant to Section 103 of the Act and 10 CFR Part 50, "Licensing of Production and Utilization Facilities," to possess but not operate the facility at the designated location in Houston County, Alabama in accordance with the procedures and limitations set forth in this renewed license.
(3)
Southern Nuclear, pursuant to the Act and 10 CFR Part 70, to receive, possess and use at any time special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, as described in the Final Safety Analysis Report, as supplemented and amended; (4)
Southern Nuclear, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (5)
Southern Nuclear, pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form. for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (6)
Southern Nuclear. pursuant to the Act and 10 CFR Parts 30, 40 and 70.
to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.
C.
This renewed license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions speCified or incorporated below:
(1)
Maximum Power Level Southern Nuclear is authorized to operate the facility at reactor core power levels not in excess of 2775 megawatts thermal.
(2)
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 186 are hereby incorporated in the renewed license.
Southern Nuclear shall operate the facility in accordance with the Technical Specifications.
Farley - Unit 2 Renewed License No. NPF-8 Amendment No. 186
3.4.11 Pressurizer PORVs ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME F.
More than one block valve inoperable.
F.1 AND Place associated PORVs in manual control.
1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> F.2 AND Restore one block valve to OPERABLE status.
2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> F.3 Restore remaining block valve to OPERABLE status.
72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> G.
Required Action and associated Completion Time of Condition F not met.
G.1 AND Be in MODE 3.
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> G.2 Be in MODE 4.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> SURVEILLANCE REQUIREMENTS SURVEILLANCE SR 3.4.11.1
NOTES-------------
- 1. Not required to be met with block valve closed in accordance with the Required Action of Condition B or E.
- 2. Not required to be performed prior to entry into MODE 3.
Perform a complete cycle of each block valve.
FREQUENCY In accordance with the Surveillance Frequency Control
- Program Farley Units 1 and 2 3.4.11-3 Amendment No. 185 (Unit 1)
Amendment No. 186 (Unit 2)
3.4.11 Pressurizer PORVs SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.11.2
NOTE--------------------------
Not required to be performed prior to entry into MODE
- 3.
Perform a complete cycle of each PORV during MODE30r4.
In accordance with the Surveillance Frequency Control Program SR 3.4.11.3 Perform a complete cycle of each PORV using the backup PORV control system.
In accordance with the Surveillance Frequency Control Program Farley Units 1 and 2 3.4.11-4 Amendment No. 185 (Unit 1)
Amendment No. 186 (Unit 2)
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 186 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-8 SOUTHERN NUCLEAR OPERATING COMPANY, INC.
JOSEPH M. FARLEY NUCLEAR PLANT, UNITS 1 AND 2 DOCKET NOS. 50-348 AND 50-364
1.0 INTRODUCTION
By letter dated January 18, 2012, the Southern Nuclear Operating Company, Inc. (SNC) submitted a request for proposed changes to the Joseph M. Farley Nuclear Plant (FNP), Unit 2, amendment Technical Specifications (TSs).
The proposed changes would revise the TS Surveillance Requirements (SR) 3.4.11.1 and 3.4.11.4 by removing requirements no longer applicable to FNP, Unit 2.
2.0 REGULATORY EVALUATION
Title 10 of the Code of Federal Regulations (10 CFR), Section 50.36, "Technical Specifications,"
provides the regulatory requirements for the content required in a licensee's TSs.
Criterion 3 of 10 CFR 50.36(c)(2)(ii) requires a limiting condition for operation to be established for 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.
In particular, 10 CFR 50.36( d)(3) specifies that TS shall include SRs that are related to test, calibration or inspection to assure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits and that the limiting conditions for operation will be met. The licensee proposed to delete requirements no longer applicable to FI\\IP, Unit 2 TS. The NRC staff's evaluation of the proposed TS changes is provided below.
-2
3.0 TECHNICAL EVALUATION
3.1 Licensee's Basis for TS Changes As a basis for the proposed TS changes, the licensee provided the following information:
On June 13,2003, the U.S. Nuclear Regulatory Commission (NRC) issued Amendment No. 151 for FNP Unit 2, which added Note 3 to SR 3.4.11.1 and created a new SR 3.4.11.4. Note 3 to SR 3.4.11.1 eliminated the requirement to cycle the Unit 2 Pressurizer Power Operated Relief Valve (PORV) 02B31 MOV8000B during the remainder of operating Cycle 16.
This amendment also added SR 3.4.11.4 as a compensatory action for the PORV block valve while SR 3.4.11.1 was suspended.
This license amendment request proposes to delete Note 3 from SR 3.4.11.1 and delete SR 3.4.11.4 entirely from the FNP Unit 2 TS. This change is administrative in nature, because Cycle 16 for FNP Unit 2 has been completed, and FNP Unit 2 is currently operating in Cycle 22.
Therefore, SR 3.4.11.1 Note 3 and SR 3.4.11.4 are no longer applicable.
3.2 Evaluation of TS Changes The proposed change will remove Note 3 from SR 3.4.11.1 and delete SR 3.4.11.4 from the FNP Unit 2 TS. SR 3.4.11.1 Note 3 was incorporated into the FNP Unit 2 TS as a result of a license amendment request granted to SNC on June 3, 2003, which allowed SNC to suspend cycling the Unit 2 PORV Q2B31 MOV8000B only for the remainder of operating cycle 16. I n the same amendment, TS SR 3.4.11.4 was added to provide a compensatory action for the PORV block valve while SR 3.4.11.1 was suspended. SR 3.4.11.1 Note 3 and SR 3.4.11.1 were only applicable for the remainder of operating Cycle 16, which was completed in 2004. Since FNP Unit 2 is currently operating in Cycle 22, SR 3.4.11.1 Note 3 and SR 3.4.11.1 are no longer applicable and should be removed from TS. The NRC staff finds that the proposed changes to delete SR 3.4.11.1 Note 3 and SR 3.4.11.4 are administrative, do not affect any regulatory requirements and criteria, and are acceptable.
3.3 CONCLUSION
Based on the above evaluation, the NRC staff has concluded that the licensee has adequately justified the proposed changes to the TS for FNP Unit 2. Therefore, the proposed TS changes to SR 3.4.11.1 and SR 3.4.11.4 are acceptable for FNP Unit 2.
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the State of Alabama official was notified of the proposed issuance of the amendments. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendment changes a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 and changes the surveillance requirements. The NRC staff has determined that the amendments involve no significant
- 3 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 77 FR 60152. 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) there is reasonable assurance that 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: John Huang Date: December 27,2012
December 27,2012 Mr. M. J. Ajluni Nuclear Licensing Director Southern Nuclear Operating Company, Inc.
P. O. Box 1295 Bin - 038 Birmingham, AL 35201-1295
SUBJECT:
JOSEPH M. FARLEY NUCLEAR PLANT, UNIT 2, ISSUANCE OF AMENDMENT REGARDING CHANGES TO SURVEILLANCE REQUIREMENTS (TAC NO. ME7862)
Dear Mr. Ajluni:
The U.S. Nuclear Regulatory Commission has issued the enclosed Amendment No. 186 to Renewed Facility Operating License No. NPF-8 for the Joseph M. Farley Nuclear Plant, Unit 2.
The amendment consists of changes to the Technical Specifications in response to your application dated January 18, 2012.
The amendment revises Technical Specification (TS) Surveillance Requirement (SR) 3.4.11.1 and SR 3.4.11.4 by removing requirements no longer applicable to Joseph M. Farley Nuclear Plant, Unit 2.
A copy of the related Safety Evaluation is also enclosed. A Notice of Issuance will be included in the Commission's biweekly Federal Register notice.
Sincerely, IRA by V. Sreenivas forI Robert E. Martin, Senior Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-364
Enclosures:
- 1. Amendment No. 186 to NPF-8
- 2. Safety Evaluation cc w/encls: Distribution via Listserv DISTRIBUTION:
Public LPL2-1 RtF RidsNrrPMFarley Resource (hard copy)
RidsAcrsAcnw_MailCTR Resource RidsNrrLASFjgueroa Resource RidsNrrDeEptb Resource RidsOgcRp Resource RidsNrrDorlDpr Resource RidsRgn2MailCenter Resource RidsNrrDorlLpl2-1 Resource JHuang, NRR ADAMS Accession No.: ML12254B002