Text

Issuance of Amendments Regarding Completion Time for Inoperable Swing Diesel Generator (Tac Nos. MD6947 and MD6948)
	ML082280076
Person / Time
Site:	Hatch
Issue date:	10/02/2008
From:	Martin R; Plant Licensing Branch II
To:	Madison D; Southern Nuclear Operating Co
	Martin R, NRR/DORL, 415-1493
Shared Package
ML082280065	List: ML082280076;
References
	TAC MD6947, TAC MD6948
	Download: ML082280076 (12)
	v • d • e

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555*0001 October 2, 2008 Mr. Dennis R. Madison Vice President - Hatch Edwin I. Hatch Nuclear Plant 11028 Hatch Parkway North Baxley, GA 31513

SUBJECT:

EDWIN I. HATCH NUCLEAR PLANT, UNIT NOS. 1 AND 2, ISSUANCE OF AMENDMENTS REGARDING COMPLETION TIME FOR INOPERABLE SWING DIESEL GENERATOR (TAC NOS. MD6947 AND MD6948)

Dear Mr. Madison:

The U.S. Nuclear Regulatory Commission has issued the enclosed Amendment No. 259 to Renewed Facility Operating License DPR-57 and Amendment No. 203 to Renewed Facility Operating License NPF-5 for the Edwin I. Hatch Nuclear Plant, Units 1 and 2, respectively. The amendments consist of changes to the Technical Specifications (TSs) in response to your application dated October 5,2007.

The amendments revise the TSs completion times (CTs) for TS Limiting Condition of Operation (LCO) 3.8.1, Conditions Band C, by specifying when maintenance restrictions need to be met and by adding a 72-hour CT for the swing DG 1B.

A copy of the related Safety Evaluation is also enclosed. A Notice of Issuance will be included in the Commission's next biweekly Federal Register notice.

Sincerely, f/~o::k!/!1*ct Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-321 and 50-366

Enclosures:

1. Amendment No. 259 to DPR-57

2. Amendment No. 203 to NPF-5

3. Safety Evaluation cc w/encls: See next page

October 2, 2008 Mr. Dennis R. Madison Vice President - Hatch Edwin I. Hatch Nuclear Plant 11028 Hatch Parkway North Baxley, GA 31513 SUB..IECT: EDWIN I. HATCH NUCLEAR PLANT, UNIT NOS. 1 AND 2, ISSUANCE OF AMENDMENTS REGARDING COMPLETION TIME FOR INOPERABLE SWING DIESEL GENERATOR (TAC NOS. MD6947 AND MD6948)

Dear Mr. Madison:

The U.S. Nuclear Regulatory Commission has issued the enclosed Amendment No. 259 to Renewed Facility Operating License DPR-57 and Amendment No. 203 to Renewed Facility Operating License NPF-5 for the Edwin I. Hatch Nuclear Plant, Units 1 and 2, respectively. The amendments consist of changes to the Technical Specifications (TSs) in response to your application dated October 5, 2007.

The amendments revise the TSs completion times (CTs) for TS Limiting Condition of Operation (LCO) 3.8.1, Conditions Band C, by specifying when maintenance restrictions need to be met and by adding a 72-hour CT for the swing DG 1B.

A copy of the related Safety Evaluation is also enclosed. A Notice of Issuance will be included in the Commission's next biweekly Federal Register notice.

Sincerely, IRA!

Robert E. Martin, Senior Project lVIanager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-321 and 50-366

Enclosures:

1. Amendment No. 259 to DPR-57

2. Amendment No. 203 to NPF-5

3. Safety Evaluation cc w/encls: See next page DISTRIBUTION:

PUBLIC/NON-Sensitive RidsAcrsAcnwMailCenter Resource LPL2-1 R/F RidsNrrPMRMartin Resource RidsOgcRp Resource RidsNrrDirsltsb Resource RidsRgn2MailCenter Resource RidsNrrLAGLappert RidsNrrDorlLPL2-1 Resource G.Hill, OIS (4)

RidsNrrDorl Resource Amendment No ML082280076

By Memo OFFICE NRR/LPL2-1/PM NRR/LPL2-1/LA DE/EEB/BC OGC NLO NRR/LPL2-1/BC w/ comments NAME RMartin GLappert GWilson

RHolmes LOlshan for MWong DATE 09/03/08 09/03/08 08/01/08 09/10/08 10/01/08 OFFICIAL RECORD COpy

Edwin I. Hatch Nuclear Plant, Units 1 & 2 September 3, 2008 cc:

Mr. Dennis R. Madison Arthur H. Domby, Esq.

Vice President - Hatch Troutman Sanders Edwin I. Hatch Nuclear Nations Bank Plaza 11028 Hatch Parkway North 600 Peachtree St, NE, Suite 5200 Baxley, GA 31513 Atlanta, GA 30308-2216 Laurence Bergen Chairman Oglethorpe Power Corporation Appling County Commissioners 2100 E. Exchange Place County Courthouse P.O. Box 1349 Baxley, GA 31513 Tucker, GA 30085-1349 Mr. Jeffrey 1. Gasser Mr. R. D. Baker Executive Vice President Manager - Licensing Southern Nuclear Operating Company, Inc.

Southern Nuclear Operating Company, Inc. P.O. Box 1295 P.O. Box 1295 Birmingham, AL 35201-1295 Birmingham, AL 35201-1295 Mr. K. Rosanski Resident Inspector Resident Manager Plant Hatch Oglethorpe Power Corporation 11030 Hatch Parkway N. Edwin I. Hatch Nuclear Plant Baxley, GA 31531 P.O. Box 2010 Baxley, GA 31515 Harold Reheis, Director Department of Natural Resources 205 Butler Street, SE., Suite 1252 Atlanta, GA 30334 Steven M. Jackson Senior Engineer - Power Supply Municipal Electric Authority of Georgia 1470 Riveredge Parkway, NW Atlanta, GA 30328-4684 Mr. Reece McAlister Executive Secretary Georgia Public Service Commission 244 Washington St., SW Atlanta, GA 30334

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. 50-321 EDWIN I. HATCH NUCLEAR PLANT. UNIT NO.1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No.259 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 l\Iuclear 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 October 5,2007, 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 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

-2

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. 259 ,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 30 days from the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

/[}Ji-yQf Melanie C. Wong, Chief Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to Renewed Facility Operating License No. DPR-57 and the Technical Specifications Date of Issuance: October 2. 2008

ATTACHMENT TO LICENSE AMENDMENT NO. 259 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 Insert Pages License License Page 4 Page 4 TSs 3.8-3 3.8-3 3.8-4 3.8-4 3.8-5 3.8-5 3.8-6 3.8-6

4*

. for sample analysis or Instrument calibration. or associated with radioactive apparatus or components; .

(6) Sou1hern Nuclear, pursuanllo the Act and 10 CFA Parts 30 and 70, to possess, but not separalelsuch byproduct end special nuclear materials as may be produced by the operation of the iacllily.

C. This renewed license shall be deemed to contain and Is SUbject to the conditions*

.specified In the following Oommlssion regulations In 10 CFA 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 appncable provlstonsof the Act and the rules, regulalions. and orders of. the Commission no~ or hereafter In effect; and the additional conditions specified or Incorporated below:

(1) Maximum power Level Southern Nuclear Is Buthorfzed 10 operate the faclllty at steady slate reactor core power levels not In excess of 2804 megawatts thermal.

(2) I Technlcal Specifications The Technical Spectficatlons (Appendix A) and the Enviro.nmental .I Protection Plan (Appendix B), as revised through Amendment No*.

are hereby Incorporated In .the renawed license. Southern Nuclear shall operata the facility In accordance with the Technical Specifications and the Environmental Protection Plan.

The Survel1lance ReqUirement (SR) contaIned In the Techn~cal Specifications and fisted below, Is not reqUired to be performed .

Immediately upon Implementation of Amendment No. 195. The SR nsted below shan be successfully demon'stratedprJor to the Urne and conditIon specified:

SR 3.8.1.18 stuin be successfully demonstrated at Its next regUlarly scheduled per10nnance .

(3) Are 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 Are Protection Program for Edwln 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 protecUon program without prior Commission approval only If the changes Renewed Ucense No. DPR-57 Amendment No 259

AC Sources - Operating 3.8.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. (continued) B.2 Declare required 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months from discovery feature(s), supported by of Condition B the inoperable DG, concurrent with inoperable when the inoperability of redundant required redundant required feature(s) are feature(s) inoperable.

AND B.3.1 Determine OPERABLE 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months DG(s) are not inoperable due to common cause failure.

OR B.3.2 Perform SR 3.8.1.2.a 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for OPERABLE DG(s).

AND B.4 Restore DG to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months for a OPERABLE status. Unit 1 DG with the swing DG not inhibited or maintenance restrictions not met 14 days for a Unit 1 DG with the swing DG inhibited from automatically aligning to Unit 2 and maintenance restrictions met AND 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months for the swing diesel with maintenance restrictions not met (continued)

HATCH UNIT 1 3.8-3 Amendment No. 259

AC Sources - Operating 3.8.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. (continued) B.4 (continued) AND 14 days for the swing diesel with maintenance restrictions met AND 17 days from discovery of failure to meet LCO 3.8.1.a, b, or c C. One required Unit 2 DG C.1 Perform SR 3.8.1.1 for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable OPERABLE required offsite circuit(s). AND Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter AND C.2 Declare required 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months from discovery feature(s), supported by of Condition C the inoperable DG, concurrent with inoperable when the inoperability of redundant required redundant required feature(s) are inoperable. feature(s)

AND C.3.1 Determine OPERABLE 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months DG(s) are not inoperable due to common cause failure.

OR C.3.2 Perform SR 3.8.1.2.a for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months OPERABLE DG(s).

(continued)

HATCH UNIT 1 3.8-4 Amendment No.259

AC Sources - Operating 3.8.1 ACTIOI\IS CONDITION REQUIRED ACTION COMPLETION TIME C. (continued) AND CA Restore required DG to 7 days with the OPERABLE status. swing DG not inhibited or maintenance restrictions not met AND 14 days with the swing DG inhibited from automatically aligning to Unit 1 and maintenance restrictions met D. Two or more required D.1 Declare required 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months from discovery offsite circuits inoperable. feature(s) with no offsite of Condition D power available concurrent with inoperable when the inoperability of redundant required redundant required feature(s) are feature(s) inoperable.

AND D.2 Restore all but one 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months required offsite circuit to OPERABLE status.

E. One required offsite circuit ------------------NOTE-----------------

inoperable. Enter applicable Conditions and Required Actions of LCO 3.8.7, AND "Distribution Systems Operating," when Condition E is One required DG entered with no AC power source inoperable. to one 4160 V ESF bus.

E.1 Restore required offsite 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months circuit to OPERABLE status.

(continued)

HATCH UNIT 1 3.8-5 Amendment No. 259

AC Sources - Operating 3.8.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. (continued) OR E.2 Restore required DG 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months to OPERABLE status.

F. Two or more (Unit 2 and F.1 Restore all but one 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months swing) DGs inoperable. Unit 2 and swing DGs to OPERABLE status.

G. No DGs capable of G.1 Restore one DG 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months supplying power to any capable of supplying Unit 2 LPCI valve load power to Unit 2 LPCI center. valve load center to OPERABLE status.

H. Required Action and H.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Associated Completion Time of Condition A, B, C, AND D, E, F, or G not met.

H.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months I. One or more required 1.1 Enter LCO 3.0.3. Immediately offsite circuits and two or more required DGs inoperable.

OR Two or more required offsite circuits and one required DG inoperable.

HATCH UNIT 2 3.8-6 Amendment No. I 259

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 NO.2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 203 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 October 5,2007, 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 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

-2

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. I\IPF-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. 203 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 30 days from the date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

!!t.,~

-rQ)

Melanie C. Wong, Chief Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of l\Iuclear Reactor Regulation

Attachment:

Changes to Renewed Facililty Operating License No. NPF-5 and the Technical Specifications Date of Issuance: October 2, 2008

ATTACHMENT TO LICENSE AMENDIVIENT NO. 203 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 Insert Pages License License Page 4 Page 4 TSs TSs 3.8-3 3,8-3 3.8-4 3.8-4 3.8-5 3.8-5 3.8-6 3.8-6

-4 (6) Southern Nuclear, pursuant to the Act and 10 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 10 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 2 specified or incorporated below:

(1) Maximum Power Level Southern Nuclear is authorized to operate the facility at steady state reactor core power levels not in excess of 2,804 megawatts thermal, in accordance with the conditions specified herein.

(2) Technical Specifications The Technical Specifications (Appendix A) and the Environmental Protection.

Plan (Appendix B), as revised through Amendment No. , are hereby incorporated in the renewed license. Southern Nuclear shall operate the facility in accordance with the Technical Specifications and the Environmental Protection 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 removal of 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 the Updated Final Safety Analysis Report for the facility, as contained 2 The original licensee authorized to possess, use, and operate the facility was Georgia Power Company (GPC). Consequently, certain historical references to GPC remain in certain license conditions.

Renewed License No. NPF-5 Amendment No. 203

AC Sources - Operating 3.8.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME

8. (continued) 8.2 Declare required 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months from discovery feature(s), supported by of Condition B the inoperable DG, concurrent with inoperable when the inoperabilityof redundant required redundant required feature(s) are feature(s) inoperable.

AND 8.3.1 Determine OPERABLE 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months DG(s) are not inoperable due to common cause failure.

OR 8.3.2 Perform SR 3.8.1.2.a for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months OPERABLE DG(s)

AND B.4 Restore DG to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months for a OPERABLE status. Unit 2 DG with the swing DG not inhibited or maintenance restrictions not met 14 days for a Unit 2 DG with the swing DG inhibited from automatically aligning to Unit 1 and maintenance restrictions met 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months for the swing diesel with maintenance restrictions not met (continued)

HATCH UNIT 2 3.8-3 Amendment No. 203

AC Sources - Operating 3.8.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. (continued) B.4 (continued) AND 14 days for the swing diesel with maintenance restrictions met AND 17 days from discovery of failure to meet LCO 3.8.1 .a, b, or c C. One required Unit 1 DG C.1 Perform SR 3.8.1.1 for 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months inoperable. OPERABLE required offsite circuit(s). AND Once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter AND C.2 Declare required 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months from feature(s), supported by discovery the inoperable DG, of Condition C inoperable when the concurrent with redundant required inoperability of feature(s) are redundant required inoperable. feature(s)

AND C.3.1 Determine OPERABLE 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months DG(s) are not inoperable due to common cause failure.

OR C.3.2 Perform SR 3.8.1 .2.a for 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months OPERABLE DG(s).

(continued)

HATCH UNIT 2 3.8-4 Amendment No. 203

AC Sources - Operating 3.8.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME C. (continued) AND C.4 Restore required DG to 7 days with the OPERABLE status. swing DG not inhibited or maintenance restrictions not met AND 14 days with the swing DG inhibited from automatically aligning to Unit 2 and maintenance restrictions met D. Two or more required 0.1 Declare required 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months from discovery offsite circuits inoperable. feature(s) with no offsite of Condition 0 power available concurrent with inoperable when the inoperability of redundant required redundant required feature(s) are feature(s) inoperable.

Af\ID 0.2 Restore all but one 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months required offsite circuit to OPERABLE status.

E. One required offsite circuit -------------------NOTE----------------

inoperable. Enter applicable Conditions and Required Actions of LCO 3.8.7, AND "Distribution Systems Operating," when Condition E is One required DG entered with no AC power source inoperable. to one 4160 V ESF bus.

E.1 Restore required offsite 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months circuit to OPERABLE status.

(continued)

HATCH UNIT 2 3.8-5 Amendment NO.203

AC Sources - Operating 3.8.1 ACTIONS (continued)

CONDITION REQUIRED ACTIOI\J COMPLETION TIME E. (continued) OR E.2 Restore required DG 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months to F. Two or more (Unit 2 and F.1 Restore all but one 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months swing) DGs inoperable. Unit 2 and swing DGs to OPERABLE status.

G. No DGs capable of G.1 Restore one DG 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months supplying power to any capable of supplying Unit 2 LPCI valve load power to Unit 2 LPCI center. valve load center to OPERABLE status.

H. Required Action and H.1 Be in MODE 3. 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Associated Completion Time of Condition A, B, C, AND D, E, F, or G not met.

H.2 Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months I. One or more required 1.1 Enter LCO 3.0.3. Immediately offsite circuits and two or more required DGs inoperable.

OR Two or more required offsite circuits and one required DG inoperable.

HATCH UNIT 2 3.8-6 Amendment No. I 203

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMEI'JDMENT NO. 259 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-57 AND AMENDMENT NO. 203 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-5 SOUTHERN NUCLEAR OPERATING COMPANY, II'JC.

EDWIN I. HATCH NUCLEAR PLANT, UNIT NOS. 1 AND 2 DOCKET NOS. 50-321 AND 50-366

1.0 INTRODUCTION

By application dated October 5,2007 to the U.S. Nuclear Regulatory Commission (NRC)

(Agencywide Documents and Management System (ADAMS) Accession No. ML072820115),

Southern Nuclear Operating Company, Inc. (SNC, the licensee), requested changes to the Technical Specifications (TSs) for the Edwin I. Hatch Nuclear Plant, Unit Nos. 1 and 2 (HNP).

The proposed changes would revise the TSs Completion Time (CT) requirements related to an inoperable emergency diesel generator (DG). Specifically, the licensee proposed to modify the CTs for TS Limiting Condition of Operation (LCO) 3.8.1, Conditions Band C, by specifying when maintenance restrictions need to be met and by adding a 72-hour CT for the swing DG 1B.

2.0 REGULATORY EVALUATION

The NRC staff used the following NRC requirements, guidance, and documents to review the licensee amendment request:

10 CFR Part 50 includes the NRC's requirement that TS shall be included by applicants for a license authorizing operation of a production or utilization facility. 10 CFR 50.36 (d) requires that TS include items in five specific categories related to station operation. These categories are (1) safety limits, limiting safety system settings, and limiting control settings; (2) LCOs; (3) surveillance requirements (SRs); (4) design features; and (5) administrative controls. The proposed change to TS 3.8.1 is within category 2.

General Design Criterion (GOG) 17, "Electric Power Systems," of Appendix A, "General Design Criteria for Nuclear Power Plants," to Title 10, Part 50, of the Code of Federal Regulations (10 CFR Part 50), "Domestic Licensing of Production and Utilization Facilities" requires that onsite electric power systems have sufficient independence, capacity, capability, redundancy, and testability to ensure that (1) specified acceptable nuclear fuel design limits and design conditions of the reactor coolant pressure boundary are not exceeded as a result of anticipated operational

-2 occurrences, and (2) the core is cooled and containment integrity and other vital functions are maintained in the event of postulated accidents, assuming a single failure.

GDC 18, "Inspection and Testing of Electric Power Systems," of Appendix A to 10 CFR Part 50 requires that electric power systems important to safety be designed to permit appropriate periodic inspection and testing to assess the continuity of the systems and the condition of their components.

10 CFR 50.65, "Requirements for monitoring the effectiveness of maintenance at nuclear power plants," requires that preventive maintenance activities must not reduce the overall availability of the systems, structures, and components.

NRC Regulatory Guide (RG) 1.93, "Availability of Electric Power Sources," dated December 1974, describes operating procedures and restrictions acceptable to the NRC staff which should be implemented if the available electric power sources are less than the LCO.

3.0 TECHNICAL EVALUATION

3.1 Design Considerations LCO 3.8.1 of the Unit 1 and 2 Hatch TS contains the operating LCO, Conditions, Required Actions, and CTs for the alternating current (AC) electrical system including the DGs. The Hatch Plant has a total of six safety related 4 kilovolt (kV) emergency electrical busses and five DGs which supply those busses with emergency power. The busses are normally supplied from off-site power via two start-up transformers, one normally in service and the other a back-up. Two DGs are dedicated to each unit and one DG can "swing" to either unit. The dedicated DGs 1A and 1C for Unit 1 and 2A and 2C for Unit 2 are not rated to supply a complete train of shutdown equipment.

When any of the dedicated EDGs is considered inoperable, the swing DG is aligned to supplement the operating unit to support shutdown loads and maintain compliance with RG 1.93.

The primary focus of the TS change request is the swing DG 1B.

3.2 Evaluation The licensee proposed to amend Conditions Band C of TS LCO 3.8.1 for an inoperable DG by clarifying when maintenance restrictions needed to be met and by adding a 72-hour CT for the swing DG. Specifically, for Condition B, Required Action BA, the licensee proposed to change the current CT requirement, which states:

"72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months for a Unit 1[2] DG with the sWing DG not inhibited AND 14 days for a Unit 'I [2]

DG with the swing DG inhibited from automatically aligning to Unit 2[1] AND 14 days for the swing DG AND 17 days from discovery of failure to meet LCO 3.8.1.a, b, or c" to state:

"72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months for a Unit 1[2] DG with the swing DG not inhibited or maintenance restrictions not met AND 14 days for a Unit 1[2] DG with the swing DG inhibited from automatically aligning to Unit 2[1] and maintenance restrictions met AND 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months for the swing diesel with maintenance restrictions not met AND 14 days for the swing diesel with maintenance restrictions met AND 17 days from discovery of failure to meet LCO 3.8.1.a, b, or c".

-3 For Condition C, Required Action CA, the licensee proposed to change the current CT requirement, which states:

"7 days with the swing DG not inhibited AND 14 days with the swing DG inhibited from automatically aligning to Unit 1[2]"

to state:

"7 days with the swing DG not inhibited or maintenance restrictions not met AND 14 days with the swing DG inhibited from automatically aligning to Unit 1[2] and maintenance restrictions met".

The licensee has requested this change because the current TS do not explicitly state that the swing DG can be inoperable for 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months with the maintenance restrictions not being met. The amendment also clarifies when the maintenance restrictions need to be met. Regulatory Position C.1 of RG 1.93 states that if the available AC sources are one less than the LCO, power operation may continue for a period that should not exceed 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months if the system stability and reserves are such that a subsequent single failure (including a trip of the unit's generator, but excluding an unrelated failure of the remaining offsite circuit if this degraded state was caused by the loss of an offsite source) would not cause total loss of offsite power. If these conditions for continued power operation are met and the affected source is restored within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , unrestricted operation may resume. If the conditions for continued power operation are met but the source is not restored within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , the unit should be brought to a cold shutdown state within the next 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

In Amendment Nos. 231 to DPR-57 and 172 to NPF-5, issued May 17, 2002 (ADAMS Accession No. ML021060531), the NRC staff approved the addition of 14-day CTs for an inoperable DG provided that certain maintenance restrictions were met. DGs 1A, 1C, 2A, and 2C were approved 72-hour CTs without maintenance restrictions, and all DGs (inclUding the swing DG) were approved 14-day CTs provided that maintenance restrictions were in place. These amendments did not address the 72-hour CT without having to meet maintenance restrictions for the swing DG 1B. The licensee's proposed amendment clarifies the CT for the swing DG 1B.

The amendments issued on May 17, 2002 and subsequent changes in the TS have resulted in requiring additional clarifications to the maintenance restrictions for DG 1B. The proposed amendment is reasonable and does not change the intent of the May 17, 2002 amendment with respect to extending the CT to 14 days for the 1A, 1C, 2A, and 2C DGs. The proposed amendment clarifies when the maintenance restrictions need to be implemented for DG 1B.

The proposed amendment requested a more restrictive 72-hour CT for the swing diesel generator.

Prior to the May 17, 2002 amendment, the licensee had a 7-day CT without maintenance restrictions having to be met. Therefore, the staff finds the proposed amendment reasonable to allow 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , without maintenance restrictions having to be met, for an unexpected entry into the Required Action or to ensure that the maintenance restrictions can be met in order to apply the 14-day CT.

3.3

SUMMARY

The NRC staff has reviewed the licensee's proposed TS changes and supporting documentation.

Based on the evaluation discussed above, the NRC staff determined that the proposed amendment to TS 3.8.1 is acceptable because the facility will continue to be operated in

-4 accordance with RG 1.93 and the requirements of 10 CFR 50.36(d) and meet the intent of Amendments 231 to DPR-57 and 172 to NPF-5.

4.0 STATE CONSULTATION

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

5.0 ENVIRONMENTAL CONSIDERATION

The amendments change surveillance requirements. The NRC staff 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 (November 6,2007,72 FR 62691). 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: G. Matharu Date: October 2, 2008

v t e Letter Sequence Approval
TAC:MD6947, (Approved, Closed) TAC:MD6948, (Approved, Closed)
Initiation Acceptance... Administration Questions Answers Results Approval Other:
MONTHYEAR2008-10-02 [Table View]

ML082280076

Text

SUBJECT:

Dear Mr. Madison:

Enclosures:

Dear Mr. Madison:

Enclosures:

Attachment:

Attachment:

1.0 INTRODUCTION

2.0 REGULATORY EVALUATION

3.0 TECHNICAL EVALUATION

SUMMARY

4.0 STATE CONSULTATION

5.0 ENVIRONMENTAL CONSIDERATION

6.0 CONCLUSION

Navigation menu

Search