ML16043A101
| ML16043A101 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 03/07/2016 |
| From: | Michael Orenak Plant Licensing Branch II |
| To: | Pierce C Southern Nuclear Operating Co |
| Orenak M, NRR-DORL 415-3229 | |
| References | |
| CAC MF6580, CAC MF6581 | |
| Download: ML16043A101 (18) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mil:dl 7 I 2016 Mr. C. R. Pierce Regulatory Affairs Director Southern Nuclear Operating Company, Inc.
P. 0. Box 1295, Bin - 1295 Birmingham, AL 35201-1295
SUBJECT:
EDWIN I. HATCH NUCLEAR PLANT, UNITS 1 AND 2, ISSUANCE OF AMENDMENTS REGARDING TYPOGRAPHICAL ERRORS IN THE FACILITY OPERATING LICENSE AND TECHNICAL SPECIFICATIONS (CAC NOS.
MF6580 AND MF6581)
Dear Mr. Pierce:
The U.S. Nuclear Regulatory Commission has issued the enclosed Amendment No. 276 to Renewed Facility Operating License (RFOL) DPR-57 and Amendment No. 220 to RFOL NPF-5 for the Edwin I. Hatch Nuclear Plant (HNP), Units 1 and 2, respectively.
The amendments consist of changes to the HNP, Unit 1, RFOL and the HNP, Units 1 and 2, Technical Specifications (TSs) in response to your application dated August 4, 2015.
Specifically, the amendments correct typographical errors in the HNP, Unit 1, RFOL, and HNP, Unit 2, TS, and add the term STAGGERED TEST BASIS to the HNP, Units 1 and 2, TS Section 1.1, "Definitions."
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.
Docket Nos. 50-321 and 50-366
Enclosures:
- 1. Amendment No. 276 to DPR-57
- 2. Amendment No. 220 to NPF-5
- 3. Safety Evaluation cc w/encls: Distribution via Listserv Sincerely,
~Ji~
Michael D. Orenak, Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SOUTHERN NUCLEAR OPERATING COMPANY, INC.
GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DAL TON. GEORGIA DOCKET NO. 50-321 EDWIN I. HATCH NUCLEAR PLANT. UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 276 Renewed License No. DPR-57
- 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment to the Edwin I. Hatch Nuclear Plant, Unit 1 (the facility) Renewed Facility Operating License No. DPR-57 filed by Southern Nuclear Operating Company, Inc. (the licensee), acting for itself, Georgia Power Company, Oglethorpe Power Corporation, Municipal Electric Authority of Georgia, and City of Dalton, Georgia (the owners), dated August 4, 2015, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as 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 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 1 O CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
- 2.
Accordingly, the license is hereby amended by page 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. DPR-57 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 276, are hereby incorporated in the license. Southern Nuclear 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 90 days from the date of issuance.
Attachment:
Changes to Renewed Facility Operating License No. DPR-57 and the Technical Specifications Date of Issuance: Mm:h 7, 2016 FOR THE NUCLEAR REGULATORY COMMISSION Michael T. Markley, Chief Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
ATTACHMENT TO LICENSE AMENDMENT NO. 276 RENEWED FACILITY OPERATING LICENSE NO. DPR-57 DOCKET NO. 50-321 Replace the following pages of the License and the Appendix A Technical Specifications (TSs) with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Remove Pages License 4
8 1.1-5 Insert Pages License 4
8 1.1-5 for sample analysis or instrumentation calibration, or associated with radioactive apparatus or components; (6)
Southern Nuclear, pursuant to the Act and 1 O CFR Parts 30 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 following Commission regulations in 1 O CFR Chapter I; Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Section 50.54 of Part 50, and Section 70.32 of Part 70; all applicable provisions of the Act and the rules, regulations, and orders of the Commission now or hereafter in effect; and the additional conditions specified or incorporated below:
(1)
Maximum Power Level Southern Nuclear is authorized to op~rate the facility at steady sate reactor core power levels not in excess of 2804 megawatts thermal.
(2)
Technical Specifications The Technical Specifications (Appendix A) and the Environmental Plan (Appendix B), as revised through Amendment No. 'ZJ76 are hereby incorporated in the renewed license. Southern Nuclear shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.
The Surveillance Requirement (SR) contained in the Technical Specifications and listed below, is not required to be performed immediately upon implementation of Amendment No. 195. The SR listed below shall be successfully demonstrated before the time and condition specified:
SR 3.8.1.18 shall be successfully demonstrated at its next regularly scheduled performance.
(3)
Fire Protection Southern Nuclear shall implement and maintain in effect all provisions of the fire protection program, which is referenced in the Updated Final Safety Analysis Report for the facility, as contained in the updated Fire Hazards Analysis and Fire Protection Program for the Edwin I. Hatch Nuclear Plant, Units 1 and 2, which was originally submitted by letter dated July 22, 1986. Southern Nuclear may make changes to the fire protection program without prior Commission approval only if the changes Renewed License No. DPR-57 Amendment No. Zl.6
- c.
The first performance of the periodic measurement of CRE pressure, Specification 5.5.14.d, shall be within 24 months, plus the 6 months allowed by SR 3.0.2, from the date of the most recent successful pressure measurement test.
(11)
Degraded Voltage Protection SNC shall implement the Degraded Voltage modifications to eliminate the manual actions in lieu of automatic degraded voltage protection to assure adequate voltage to safety-related equipment during design basis events by completion of the Unit 1 2020 Spring Outage, U1R29.
D.
Southern Nuclear shall not market or broker power or energy from Edwin I. Hatch Nuclear Plant, Unit 1.
- 3.
This renewed license is effective as of the date of issuance and shall expire at midnight, August 6, 2034.
FOR THE U.S. NUCLEAR REGULATORY COMMISSION
~irector Office of Nuclear Reactor Regulation Attachments:
Appendix A-Technical Specifications Appendix B - Environmental Protection Plan Date of Issuance: January 15, 2002 Renewed License No. DPR-57 Amendment No. Z76
Definitions 1.1 1.1 Definitions (continued)
SHUTDOWN MARGIN (SOM)
STAGGERED TEST BASIS SOM shall be the amount of reactivity by which the reactor is subcritical or would be subcritical throughout the operating cycle assuming that:
- a.
The reactor is xenon free;
- b.
The moderator temperature is<::: 68°F, corresponding to the most reactive state; and
- c.
All control rods are fully inserted except for the single control rod of highest reactivity worth, which is assumed to be fully withdrawn.
With control rods not capable of being fully inserted, the reactivity worth of these control rods must be accounted for in the determination of SOM.
A STAGGERED TEST BASIS shall consist of the testing of one of the systems, subsystems, channels, or other designated components during the interval specified by the Surveillance Frequency, so that all systems, subsystems, channels, or other designated components are tested during n Surveillance Frequency intervals, where n is the total number of systems, subsystems, channels, or other designated components in the associated function.
THERMAL POWER THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.
TURBINE BYPASS SYSTEM
RESPONSE
TIME HATCH UNIT 1 The TURBINE BYPASS SYSTEM RESPONSE TIME consists of two components:
- a.
The time from initial movement of the main turbine stop valve or control valve until 80% of the turbine bypass capacity is established; and
- b.
The time from initial movement of the main turbine stop valve or control valve until initial movement of the turbine bypass valve.
The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured.
1.1-5 Amendment No. Z76
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SOUTHERN NUCLEAR OPERATING COMPANY, INC.
GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON, GEORGIA DOCKET NO. 50-366 EDWIN I. HATCH NUCLEAR PLANT. UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 220 Renewed License No. NPF-5
- 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment to the Edwin I. Hatch Nuclear Plant, Unit 2 (the facility) Renewed Facility Operating License No. NPF-5 filed by Southern Nuclear Operating Company, Inc. (the licensee), acting for itself, Georgia Power Company, Oglethorpe Power Corporation, Municipal Electric Authority of Georgia, and City of Dalton, Georgia (the owners), dated August 4, 2015, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as 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 set forth in 1 O 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 hereby amended by page 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-5 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 220, are hereby incorporated in the license.
Southern Nuclear 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 90 days from the date of issuance.
Attachment:
Changes to Renewed Facility Operating License No. NPF-5 and the Technical Specifications Date of Issuance: M:rrd1 7, 2016 FOR THE NUCLEAR REGULATORY COMMISSION Michael T. Markley, Chief Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
ATTACHMENT TO LICENSE AMENDMENT NO. 220 RENEWED FACILITY OPERATING LICENSE NO. NPF-5 DOCKET NO. 50-366 Replace the following pages of the License and the Appendix A Technical Specifications (TSs) with the attached revised pages. The revised pages are identified by amendment number and contain marginal lines indicating the areas of change.
Remove Pages License 4
TSs 1.1-5 5.0-17 Insert Pages License 4
TSs 1.1-5 5.0-17
I.I (6)
Southern Nuclear; pursuant to the Act and 1 O.CFR Parts 30 and 70, to possess, but not separate, sueh 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 subje.ct to, the conditions
- specified in the following Commission regulations in 1 O CFR Chapter I: Part 20, Section 30.~4 of Part 30, Section 40.41 of Part 40, Section 50.54 of Part 50, and Section 70.32 of Part 70; all applicable provisions of the Act and the rules, regulations, and orders of the Commission now or hereafter in effect; and the additional conditions.2 specified or incorporated below:
(1-)
- Maximum Power Level Southern Nuctear is authorized to operate the facility at steady state reactor core power ~vels not in excess of 2,804 megawatts thermal, in accordanee with the conditions specified herein.
(2)
Technical Specifications The Technical Specifications (Appendix A) and the.E1:wironmental, Protection Plan (Appendix B); as revised through Amendment No:*:220 are hereby incorporated in the renewed license. Southern Nuclear snan operate the facility in accordance with the Technical Specifications and the Environmental Protec.tion Plan.
(3)
Additional Conditions The matters specified In the following conditions shall be completed to the satisfaction of the Commission within the stated time periods following the issuance of the renewed license or within the operational restrictions.
Indicated. The ~emoval o.f these conditions shall be made by an amendment to the license supported by a favorable evaluation by the Commission.
(a)
Fire Protection.
southern Nuclear shall implement and maintain In effect all provisions of the fire protection program, which is referenced in the Updated Final Safety Analysis Report for the facility, as contained 2 The original licensee authorized to possess, use, and operate the facility was Geprgia.
Power Company (GPC). Consequently, cer:taln historical references to GPC remain in certain license conditions.
- Renewe~ Llcens.e,No.. NPF*5 Amendment No.' 220
Definitions 1.1 1.1 Definitions (continued)
PHYSICS TESTS RA TED THERMAL POWER (RTP)
REACTOR PROTECTION SYSTEM (RPS)
RESPONSE TIME SHUTDOWN MARGIN (SOM)
STAGGERED TEST BASIS PHYSICS TESTS shall be those tests performed to measure the fundamental nuclear characteristics of the reactor core and related instrumentation. These tests are:
- a.
Described in Chapter 14, Initial Tests and Operation, of the FSAR;
- b.
Authorized under the provisions of 10 CFR 50.59; or
- c.
Otherwise approved by the Nuclear Regulatory Commission.
RTP shall be a total reactor core heat transfer rate to the reactor coolant of 2804 MWt.
The RPS RESPONSE TIME shall be that time interval from when the monitored parameter exceeds its RPS trip setpoint at the channel sensor until de-energization of the scram pilot valve solenoids. The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured.
SOM shall be the amount of reactivity by which the reactor is subcritical or would be subcritical throughout the operating cycle assuming that:
- a.
The reactor is xenon free;
- b.
The moderator temperature is~ 68°F, corresponding to the most reactive state; and
- c.
All control rods are fully inserted except for the single control rod of highest reactivity worth, which is assumed to be fully withdrawn.
With control rods not capable of being fully inserted, the reactivity worth of these control rods must be accounted for in the determination of SOM.
A STAGGERED TEST BASIS shall consist of the testing of one of the systems, subsystems, channels, or other designated components during the interval specified by the Surveillance Frequency, so that all systems, subsystems, channels, or other designated components are tested during n Surveillance Frequency intervals, where n is the total number of systems, subsystems, channels, or other designated components in the associated function.
THERMAL POWER THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.
(continued)
HATCH UNIT 2 1.1-5 Amendment No. 220
Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.12 5.5.13 5.5.14 Primary Containment Leakage Rate Testing Program (continued)
The provisions of SR 3.0.3 are applicable to the Primary Containment Leakage Rate Testing Program.
Surveillance Frequency Control Program This program provides controls for the Surveillance Frequencies. The program shall ensure that Surveillance Requirements specified in the Technical Specifications are performed at intervals sufficient to assure the associated Limiting Conditions for Operation are met.
- a.
The Surveillance Frequency Control Program shall contain a list of Frequencies of those Surveillance Requirements for which the Frequency is controlled by the program.
- b.
Changes to the Frequencies listed in the Surveillance Frequency Control Program shall be made in accordance with the NEI 04-10 "Risk-Informed Method for Control of Surveillance Frequencies," Revision 1.
- c.
The provisions of Surveillance Requirements 3.0.2 and 3.0.3 are applicable to the Frequencies established in the Surveillance Frequency Control Program.
Control Room Envelope Habitability Program A Control Room Envelope (CRE) Habitability Program shall be established and implemented to ensure that CRE habitability is maintained such that, with an OPERABLE Main Control Room Environmental Control (MCREC) System, CRE occupants can control the reactor safely under normal conditions and maintain it in a safe condition following a radiological event, hazardous chemical release, or a smoke challenge. The program shall ensure that adequate radiation protection is provided to permit access and occupancy of the CRE under design basis accident (OBA) conditions without personnel receiving radiation exposures in excess of 5 rem total effective dose equivalent (TEDE) for the duration of the accident. The program shall include the following elements:
- a.
The definition of the CRE and the CRE boundary.
- b.
Requirements for maintaining the CRE boundary in its design condition including configuration control and preventive maintenance.
- c.
Requirements for (i) determining the unfiltered air inleakage past the CRE boundary into the CRE in accordance with the testing methods and at the Frequencies specified in Sections C.1 and C.2 of Regulatory Guide 1.197, "Demonstrating Control Room Envelope Integrity at Nuclear Power Reactors," Revision 0, May 2003, and (ii) assessing CRE habitability at the (continued)
HATCH UNIT 2 5.0-17 Amendment No. 220
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 276 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-57 AND AMENDMENT NO. 220 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-5 SOUTHERN NUCLEAR OPERATING COMPANY, INC.
EDWIN I. HATCH NUCLEAR PLANT. UNITS 1 AND 2 DOCKET NOS. 50-321AND50-366
1.0 INTRODUCTION
By application dated August 4, 2015, (Agencywide Documents Access and Management System (ADAMS) Accession No. ML15216A602), Southern Nuclear Operating Company, Inc.
(SNC, the licensee), requested changes to the Technical Specifications (TSs) for the Edwin I.
Hatch Nuclear Plant (HNP), Units 1 and 2. The U.S. Nuclear Regulatory Commission (NRC) staff's original proposed no significant hazards consideration determination was published the Federal Register on November 10, 2015 (80 FR 69717).
The proposed changes would correct the HNP, Unit 1, Renewed Facility Operating License (RFOL) and the HNP, Units 1 and 2, TSs in response to the application dated August 4, 2015.
Specifically, the amendments correct typographical errors in the HNP, Unit 1, RFOL, and HNP, Unit 2, TS, and add the term STAGGERED TEST BASIS to TS Section 1.1, "Definitions," of the HNP, Units 1 and 2, TS.
2.0 REGULATORY EVALUATION
Section 182a of the Atomic Energy Act (Act) requires applicants for nuclear power plant operating licenses to include TSs as part of the license. These TSs are derived from the plant safety analyses. Title 10 of the Code of Federal Regulations (1 O CFR), Section 50.36, "Technical Specifications," contains the requirements for the content of TSs. Pursuant to 1 O CFR 50.36, TSs are required to include items in the following five specific categories related to station operation: ( 1) safety limits, limiting safety system settings, and limiting control settings; (2) limiting conditions for operation; (3) surveillance requirements; (4) design features; and (5) administrative controls.
The proposed amendment corrects typographical errors on HNP, Unit 1, RFOL page 8 and HNP, Unit 2, TS Page 5.0-17. The amendment also adds the term STAGGERED TEST BASIS to TS Section 1.1 of the HNP, Units 1 and 2, TS.
3.0 TECHNICAL EVALUATION
3.1 Correction to HNP, Unit 1, RFOL Condition 2.C(11)
On December 16, 2014, the NRC issued Amendment No. 271 to RFOL DPR-57 and Amendment No. 215 to RFOL NPF-5 for HNP, Units 1 and 2, respectively (ADAMS Accession No. ML14328A323). The amendments revised the RFOL to incorporate a degraded voltage protection modification schedule into the Hatch licenses. The second page of the "AMENDMENT TO RENEWED FACILITY OPERATING LICENSE" for Unit 2 correctly identifies the number for the newly issued license condition as 2.C(11 ), i.e., added condition number 11.
However, revised license page 8 in the attachment to the license amendment identifies the new license condition as number 10. This assignment of the number 10 on the new license condition page 8 inadvertently introduces a discrepancy into the issued license amendment package. The sequential numbering of the license conditions is an issue of administrative clarity and was not a subject of the NRC staff's proposed no significant hazards consideration finding nor of the staff's safety evaluation for the amendment. The NRC staff finds that this change does not change any functional aspect of the license amendments issued on December 16, 2014; therefore, the NRC staff concludes that the proposed change to the RFOL DPR-57 page 8 is acceptable.
3.2 Correction to HNP, Unit 2, TS Page 5.0-17 On August 29, 2014, the NRC issued Amendment No. 268 to RFOL DPR-57 and Amendment No. 212 to RFOL NPF-5 for the HNP, Units 1 and 2, respectively (ADAMS Accession No. ML14147A410). The amendments, among other things, added a new administrative controls program, Specification 5.5.14, "Control Room Envelope Habitability Program" beginning on page 5.0-17. For Hatch, Unit 1, page 5.0-17 is correctly identified as being for Hatch, Unit 1, Amendment No. 268. However for Hatch, Unit 2, page 5.0-17 for its Amendment No. 212 was incorrectly identified with Hatch, Unit 1. The NRC staff finds that this change does not alter any functional aspect of the license amendments issued on August 29, 2014; therefore, the NRC staff concludes that the proposed change to HNP, Unit 2, TS page 5.0-17 is acceptable.
3.3 Addition of STAGGERED TEST BASIS to TS Definitions On January 3, 2012, the NRC issued Amendment No. 266 to RFOL DPR-57 and Amendment No. 210 to ROFL NPF-5 for HNP, Units 1 and 2, respectively (ADAMS Accession No. ML11108A129). The amendments revise the TSs by relocating specific surveillance frequencies to a licensee-controlled program using a risk-informed justification, Technical Specification Task Force Traveler (TSTF)-425, Revision 3. This amendment also removed the term STAGGERED TEST BASIS from Section 1.1 of the TS.
On August 29, 2014, the NRC issued Amendment No. 268 to RFOL DPR-57 and Amendment No. 212 to ROFL NPF-5 for HNP, Units 1 and 2, respectively. The amendments, among other things, added a new administrative controls program, Specification 5.5.14, "Control Room Envelope Habitability Program." Contained within TS 5.5.14 was the defined term STAGGERED TEST BASIS; however, a revised TS Section 1.1 was not provided in the application that included a definition for the term STAGGERED TEST BASIS.
The NRC staff reviewed the licensee's reintroduction of the term STAGGERED TEST BASIS into TS Section 1.1. Because STAGGERED TEST BASIS is identified in TS 5.5.14 as a defined term, the definition must be included in TS Section 1.1. The provided definition of the STAGGERED TEST BASIS is appropriate for its use in TS 5.5.14. The NRC staff reviewed previous versions of the HNP, Units 1 and 2, TS and found that the definition of STAGGERED TEST BASIS provided in the August 4, 2015, application is identical to its definition in the TS prior to the approval of Amendment No. 266 to RFOL DPR-57 and Amendment No. 210 to ROFL NPF-5. Additionally, the NRC staff finds that the addition does not change any functional aspect of the license amendments issued on August 29, 2014.
Based on that the definition for STAGGERED TEST BASIS must be included in the TS, its definition is appropriate for TS 5.5.14, and that the definition is identical to the earlier TS versions, the NRC staff concludes that the addition of the defined term STAGGERED TEST BASIS to TS Section 1.1 for HNP, Units 1 and 2, is acceptable.
4.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Georgia State official was notified of the proposed issuance of the amendments on February 26, 2016. The State official had no comments.
5.0 ENVIRONMENTAL CONSIDERATION
The amendments change a requirement with respect to the installation or use of facility components 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 dated November 10, 2015 (80 FR 69717). 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: M. Orenak Date: Mm:h 7, 2016
Mr. C. R. Pierce Regulatory Affairs Director March 7, 2016 Southern Nuclear Operating Company, Inc.
P. 0. Box 1295, Bin - 1295 Birmingham, AL 35201-1295
SUBJECT:
EDWIN I. HATCH NUCLEAR PLANT, UNITS 1 AND 2, ISSUANCE OF AMENDMENTS REGARDING TYPOGRAPHICAL ERRORS IN THE FACILITY OPERATING LICENSE AND TECHNICAL SPECIFICATIONS (CAC NOS.
MF6580 AND MF6581)
Dear Mr. Pierce:
The U.S. Nuclear Regulatory Commission has issued the enclosed Amendment No. 276 to Renewed Facility Operating License (RFOL) DPR-57 and Amendment No. 220 to RFOL NPF-5 for the Edwin I. Hatch Nuclear Plant (HNP), Units 1 and 2, respectively.
The amendments consist of changes to the HNP, Unit 1, RFOL and the HNP, Units 1 and 2, Technical Specifications (TSs) in response to your application dated August 4, 2015.
Specifically, the amendments correct typographical errors in the HNP, Unit 1, RFOL, and HNP, Unit 2, TS, and add the term STAGGERED TEST BASIS to the HNP, Units 1 and 2, TS Section 1.1, "Definitions."
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.
Docket Nos. 50-321 and 50-366
Enclosures:
- 1. Amendment No. 276 to DPR-57
- 2. Amendment No. 220 to NPF-5
- 3. Safety Evaluation cc w/encls: Distribution via Listserv DISTRIBUTION Public LPL2-1 R/F RidsAcrs_MailCTR Resource RidsRgn2Mail Center Resource RidsNrrDorlDpr Resource RidsNrrDorllpl2-1 Resource Amendment No. ML16043A101 Sincerely, IRA/
Michael D. Orenak, Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation RidsNrrPMHatch Resource (hard copy)
RidsNrrLASFigueroa Resource RidsNrrDssStsb Resource RecordsAmend Resource OFFICE NRR/LPL2-1/PM NRR/LPL2-1 /LA NRR/DSS/STSB/BC OGC NLO NRR/LPL2-1/BC NAME MOrenak SFioueroa RElliott SF owler MMarklev DATE 2/17/16 2/17/16 2/22/16 2/25/16 3/7/16 OFFICE NRR/LPL2-1/PM NAME MOrenak DATE 3/7/16 OFFICIAL RECORD COPY