Text

Issuance of Amendments Regarding the Control Room Air Conditioning System
	ML14279A261
Person / Time
Site:	Hatch
Issue date:	12/10/2014
From:	Martin R; Plant Licensing Branch II
To:	Pierce C; Southern Nuclear Operating Co
	Martin R
References
	TAC MF3374, TAC MF3375
	Download: ML14279A261 (23)
	v • d • e

UNITED srAr*es NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 December 10, 2014

SUBJECT:

EDWIN I. HATCH NUCLEAR PLANT, UNIT NOS. 1 AND 2, ISSUANCE OF AMENDMENTS REGARDING THE CONTROL ROOM AIR CONDITIONING SYSTEM (TAC NOS. MF3374 AND MF3375)

Dear Mr. Pierce:

The U.S. Nuclear Regulatory Commission has issued the enclosed Amendment No. 270 to Renewed Facility Operating License DPR-57 and Amendment No. 214 to Renewed Facility Operating License NPF-5 for the Edwin I. Hatch Nuclear Plant, Unit Nos. 1 and 2, respectively.

The amendments revise the Technical Specifications (TSs) in response to your application dated January 16, 2014, as supplemented May 2 and July 22, 2014.

These amendments revise the TS 3.7.5, Control Room Air Conditioning (AC) System, to provide new Required Actions for one, two, or three main control room AC subsystems inoperable, and make other required corresponding changes.

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, l;L~F/l11P0-Lp

{/ Robert Martin, Senior Project 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. 270 to DPR-57

2. Amendment No. 214 to NPF-5

3. Safety Evaluation cc w/encls: Distribution via Listserv

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. 270 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 No. 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), January 16, 2014, as supplemented May 2 and July 22, 2014, 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.

Enclosure 1

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. 270, 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.

FOR THE NUCLEAR REGULATORY COMMISSION Robert Pascarelli, 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: December 10, 2014

ATTACHMENT TO LICENSE AMENDMENT NO. 270 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 DPR57, Page 4 DPR-57, Page 4 TSs TSs 3.7-12 3.7-12 3.7-13 3.7-13 3.7-14 3.7-14

for sample analysis or instrument calibration, or associated with radioactive apparatus or components; (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 1: 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 th*e 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 operate the *facility at steady state reactor core power levels not in excess of 2804 megawatts thermal.

(2) Technical Specifications The Technical Specifications (Appendix A) and the Environmental Protection Plan (Appendix B), as revised through Amendment No .. 2.70 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. ~70 *1

Control Room AC System '.

. 3.7.5

3. 7 PLANT SYSTEMS 3.7.5 Control Room Air Conditioning (AC) System LCO 3.7.5 Three control room AC subsystems shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3, During movement of irradiated fuel assemblies in the secondary containment, During CORE ALTERATIONS, During operations with a potential for draining the reactor vessel (OPDRVs).

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One control room AC A.1 Restore control room 30 days subsystem inoperable. AC subsystem to OPERABLE status.

B. Two c:;ontrol room AC B.1 Verify control room area Once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months subsystems inoperable. temperature< gooF.

AND B.2 Restore one control 7 days room AC subsystem to OPERABLE status.

c. Three control room AC C.1 Verify control room area Once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months subsystems inoperable. temperature < gooF.

AND C.2 Restore one control 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months room AC subsystem to OPERABLE status.

(continued)

HATCH UNIT 1 3.7-12 Amendment No. 270 J

Control Room AC System

. 3.7.5 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and D.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, or AND C not met in MODE 1, 2, or

3. D.2. Be in MODE4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months E. Required Action and ,.----------------N 0 T E-----------------

associated Completion LCO 3.0.3 is not applicable.

Time of Condition A not met during movement of "\

irradiated fuel assemblies in E.1 Place OPERABLE ~ Immediately the secondary containment, control room AC during CORE subsystems in ALTERATIONS, or during operation.

OPDRVs.

OR-E.2.1 Suspend movement of Immediately irradiated fuel assemblies in the secondary containment. .,

AND E.2.2 Suspend CORE Immediately ALTERATIONS.

AND E.2.3 .. Initiate action to lilnnediately suspend OPDRVs.

(continued)

HATCH UNIT 1 3.7-13 Amendment No. 270 I

Control Room AC System 3.7.5 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME F. Required Action and -----,------------N0 TE------------------

associated Completion LCO 3.0.3 is not applicable.

Time of Condition B or C not met during movement of irradiated fuel F.1 Suspend movement of

Immediately assemblies in the irradiated fuel assemblies secondary containment in the secondary during CORE containment.

ALTERATIONS, or during OPDRVs. AND F.2 Suspend CORE Immediately ALTERATIONS.

F.3 Initiate actions to Immediately suspend OPDRVs.

HATCH UNIT 1 3.7-14 Amendment No.27Q 1

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. 214 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 No.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 January 16, 2014, as supplemented May 2 and July 22, 2014, 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 issuan.ce of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

Enclosure 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. 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 8, as revised through Amendment No. 214 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.

FOR THE NUCLEAR REGULATORY COMMISSION Robert Pascarelli, Chief Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to Renewed Facility .

Operating License No. NPF-5 and the Technical Specifications Date of Issuance: December 10, 2014

ATTACHMENT TO LICENSE AMENDMENT NO. 214 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 NPF-5, Page 4 NPF-5, Page 4 TSs TSs 3.7-12 3.7-12 3.7-13 3.7-13 3.7-14 3.7-14

.J (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 1: 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 f(icility 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 Erwironmental, Protection Plan (Appendix B); as revised through Amendment No:2t4 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 Updated Final Safety Analysis Report for the facility, as contained 2 The original licensee authorized to possess, use, and operate the facility was Georgia, I Power Company (GPC). Consequently, certain historical references to GPC remain in certain license conditions.

Renewed License No. NPF*5 Amendment No ..*, 2'14

Control Room AC System 3.7.5 3.7 PLANT SYSTEMS 3.7.5 Control Room Air Conditioning (AC) System LCO 3.7.5 Three control room AC subsystems shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3, During movement of irradiated fuel assemblies in the secondary containment, During CORE ALTERATIONS, During operations with a potential for draining the reactor vessel (OPDRVs).

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One control room AC A.1 Restore control room 30 days subsystem inoperable. AC subsystem to OPERABLE status.

B. Two control room AC B.1 Verify control room area Once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months subsystems inoperable. temperature < gooF.

AND B.2 Restore one control 7 days room AC subsystem to OPERABLE status.

C. Three control room AC C.1 Verify control room area Once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months subsystems inoperable. temperature< gooF.

AND C.2 Restore one control 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months room AC subsystem to OPERABLE status.

(contmued)

HATCH UNIT 2 3.7-12 Amendment No.214

Control Room AC System 3.7.5 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and D.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, or AND C not met in MODE 1, 2, or

3. D.2. Be in MODE 4. 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months E. Required Action and ------'--------NOTE---,-----------

associated Completion LCO 3.0.3 is not applicable.

Time of Condition A not met during movement of irradiated fuel assemblies in E.1 Place OPERABLE Immediately the secondary containment, control room AC during CORE subsystems in ALTERATIONS, or during operation.

OPDRVs.

OR E.2.1 Suspend movement of Immediately .

irradiated fuel assembli!3S in the secondary containment.

AND

-~

E.2.2 Suspend CORE Immediately ALTERATIONS.

AND E.2.3 Initiate action to Immediately suspend OPDRVs.

(continued)

HATCH UNIT 2 3.7-13 Amendment No. 214 I

Control Room AC System 3.7.5 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME F. Requited Action and -----------------NOTE-------------------

associated Completion LCO 3.0.3 is not applicable.

Time of Condition B or C not met during movement of irradiated fuel F.1 Suspend movement of Immediately assemblies in the irradiated fuel assemblies secondary containment in the secondary during CORE containment.

ALTERATIONS, or during OPDRVs.

F.2 Suspend CORE Immediately ALTERATIONS.

F.3 Initiate actions to Immediately suspend OPDRVs.

HATCH UNIT 2 3.7-14 Amendment No. 214 1

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 270 TO RENEWED FACILITY OPERATING LICENSE NO. DPR-57 AND AMENDMENT NO. 214 TO RENEWED FACILITY OPERATING LICENSE NO. NPF-5 SOUTHERN NUCLEAR OPERATING COMPANY, INC.

EDWIN I. HATCH NUCLEAR PLANT, UNIT NOS. 1 AND 2 DOCKET NOS. 50-321 AND 50-366 1.0. INTRODUCTION By license amendment request (LAR) dated January 16, 2014, as supplemented by letters dated May 2 and July 22, 2014, (Agencywide Documents Access and Management System (ADAMS), .

Accession Nos. ML14016A202, ML14122A339 and ML14203A160, Southern Nuclear Operating Company, Inc. (SNC, the licensee), requested changes to the Technical Specification (TS) for the Edwin I. Hatch Nuclear Plant, Unit Nos. 1 and 2 (HNP). These amendments revise the TS 3.7.5, Control Room Air Conditioning (AC) System, to provide new Required Actions (RAs) for one, two, or three main control room (MCR) AC subsystems inoperable, and make other required

corresponding changes. The RA Completion Times (CTs) for two or three MCR AC subsystems inoperable would be based on the ambient temperature within the MCR area rather than the ambient air temperature outside the building.

The supplement dated May 2, 2014, provided additional information that clarified the application, did not expand the scope of the application as originally noticed, and did not change the staff's original proposed no significant hazards consideration determination as published in the Federal Register on August 19, 2014 (79 FR 4911 0).

Technical Specification Task Force Traveler 477 (TSTF-477), "Add Action for Two Inoperable Control Room AC Subsystems" allows Boiling Water Reactor (BWR) plants to have a Technical Specification Condition for two inoperable control room AC subsystems out of service for up to 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months provided the control room area ambient temperature does not exceed some plant analyzed temperature limit.

Enclosure 3

TSTF-477, Revision 3, modified the Actions of the Control Room AC System to provide a new Action for both control room AC subsystems that are inoperable. The new Action allows a finite time to restore one control room AC subsystem to operable status and requires verification that control room temperature is maintained< 90 °F once every 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months . TSTF-477, Revision 3 changes were incorporated into the standard Technical specifications (STS). The CT provided in NUREG-1433 Rev 4, Standard Technical Specifications General Electric BWR/4 Plants is 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months . The CT provided in NUREG-1434 Rev 4, Standard Technical Specifications General Electric BWR/6 Plants, is 7 days.

2.0 REGULATORY EVALUATION

The NRC staff's review evaluates the licensee's assessment of the impact of the proposed changes to the HNP TS with respect to the design basis of the plant. The NRC staff evaluated the licensee's application based on the requirements of Title 10 of the Code of Federal Regulation, Part 50, Appendix A (1 0 CFR 50 Appendix A), General Design Criterion (GDC) 19 "Control Room,"

as supplemented by Sections 6.4 and 9.4.1 of NUREG-0800, "Standard Review Plan", the guidance of Regulatory Guide 1.52, "Design, Testing , And Maintenance Criteria For Post Accident Engineered-Safety-Feature Atmosphere Cleanup System Air Filtration And Adsorption Units Of Light-Water-Cooled Nuclear Power Plants", and TSTF-477.

GDC 19, "Control Room," requires that a control room be provided from which action can be taken to operate the nuclear reactor safety under normal conditions and to maintain the reactor in a safe condition under accident conditions, including a loss-of-coolant accident (LOCA). Adequate radiation protection is to be provided to permit access and occupancy of the control room under accident conditions without personnel receiving radiation exposures in excess of specified values.

3.0 TECHNICAL EVALUATION

This amendment is requested pursuant to TSTF-477, Revision 3, therefore the licensee is expected to provide information demonstrating that requested changes to HNP control room AC

. system are consistent with the system described in TSTF-477 Revision 3, which states that:

The Control Room AC System provides temperature control for the control room following isolation of the control room. The Control Room AC System

consists of two independent, redundant subsystems that provide cooling and heating of recirculated control room air. Each subsystem consists of heating coils, cooling coils, fans, chillers, compressors, ductwork, dampers and instrumentation and controls to provide for control room temperature control."

In its January 16, 2014 letter, the licensee stated that the revised TS RAs and CTs for one or three MCR AC subsystems that are inoperable are consistent with those for the corresponding Condition's RAs and CTs in TSTF-477, Revision 3. HNP has three 50% capacity subsystems versus the common configuration with two 100% capacity subsystems assumed in NUREG-1433 and TSTF-477 Revision 3. Because of this difference, the revised TS for two MCR AC subsystems that are inoperable represent a condition not explicitly addressed by TSTF-477, Revision 3. However, the revised RAs and CTs for three HNP MCR AC subsystems that are inoperable are consistent with the RAs and CTs from TSTF-477, Revision 3 for zero operable MCR AC subsystems as they both represent conditions where no AC subsystem capability is

available. This is in accordance with the original primary intent of TSTF-477, Revision 3, which was to provide some reasonable CT for restoring a 100% capacity AC subsystem without defaulting to commencing the immediate shutdown of the operating units affected and the risks involved with unscheduled large plant transients. The revised RAs and CTs for two HNP 50%

capacity MCR AC subsystems that are inoperable would differ from the TSTF-447, Revision 3, two 100% MCR AC subsystems because there would still be a third operable subsystem of 50%

capacity for HNP. The 50% capacity HNP MCR AC subsystem would be sufficient for the actual cooling needs for a significant portion of the time when the other two 50% capacity subsystems are inoperable. In that condition an intermediate CT duration of 7 days would be allowed reflecting an intermediate level of risk.

Conditions for the LCO not being met during movement of irradiated fuel assemblies in the secondary containment, during CORE ALTERATIONS, or during operations with the potential for draining a reactor vessel (OPDRVs) are also modified or added and they are consistent with TSTF-477, Revision 3. With the exception of the MCR AC subsystem differences discussed above, the licensee's proposed changes are consistent with TSTF-477, Revision 3.

TS 3.7.5, Control Room Air Conditioning (AC) System addresses control room .temperature control; while TS 3.7.4, Main Control Room Environmental Control (MCREC) System, (which is not being modified per this amendment request) addresses control room radiological control.

The following changes are proposed to HNP, Unit 1 and Unit 2, TS 3.7.5:

Combine current Conditions A and B by deleting the option to operate indefinitely with one MCR AC subsystem that is inoperable if outside air temperature is less than or equal to 65°F.

SNC requests to revise the CTs such that they are not directly dependent upon the outside air temperature. The proposed completion times would be dependent on the MCR ambient temperature which is more directly comparable to limits for ensuring reliable equipment and personnel performance.

Revise new Condition B (current Condition C) so that the RAs and CTs align with TSTF- 477, Revision 3. As noted above, the STS assume two 100% capacity control room AC subsystems, whereas HNP has three 50% capacity MCR AC subsystems. Therefore, in proposed Condition B (two control room AC subsystems inoperable); the STS addresses the condition where no control room AC subsystems are operable, while HNP would still have one 50% capacity MCR AC subsystem operable. Based on this difference, HNP is requesting seven days to restore one MCR AC subsystem to OPERABLE status instead of the 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months identified in TSTF-477, Revision 3.

Add Condition C for three control room AC subsystems that are inoperable with RAs and CTs that align with the comparable Condition from TSTF-477, Revision 3 (Condition B). Both the new HNP Condition C (three control room AC subsystems inoperable) and the TSTF-477, Revision 3 Condition B (two control room AC subsystems inoperable) involve zero OPERABLE subsystems. In this regard the RAs and CTs for proposed HNP TS 3.7.5 Condition C and the corresponding TSTF-477, Revision 3 Condition are consistent.

Revise Condition D to include Conditions A, B, or C. Revised Condition D is similar to Condition C from TSTF-477, Revision 3.

Revise ConditionE to align with Condition Din TSTF-477, Revision 3.

Add new Condition F that is consistent with ConditionE in TSTF-477, Revision 3. In both the proposed HNP Condition F and iri ConditionE in TSTF-477, Revision 3, less than 100%

cooling capacity is available during movement of irradiated fuel assemblies in the secondary containment, during CORE ALTERATIONS, or during OPDRVs. The RAs and CTs. are*

therefore consistent with those in TSTF-477, Revision 3.

Delete current Conditions F and G. These Conditions are no longer necessary with implementation of the changes discussed above.

In accordance with HNP's UFSAR, the MCR air-conditioning and filtration system is designed to provide an environment with controlled temperature to ensure both the comfort and safety of the operators and the integrity of the MCR components, and to minimize the possibility of exhaust air recirculation into the air intake. The MCR is a shared facility divided into two adjacent open areas; one area serves HNP, Unit 1, and the other area serves HNP, Unit 2: The MCR is fully air-conditioned and maintained at- 72 to 79°F dry bulb throughout the year. The air-conditioning system consists of three 50% capacity condensing units (chillers) and three 50% capacity corresponding air-handing units (AHUs). Two of the three AHUs have op13rable electric heaters in the associated rooni air supply duct. Wall-mounted thermostats in the MCR control operation of the heaters for winter heating.

The air-conditioning system is operated with one or two AHUs in service such that upon failure of a normally operating AHU, at least one AHU will remain in operation, or the designated standby AHU will automatically start to assist the MCREC system pressurization mode in maintaining ;::

0.1-in. water gauge (WG) positive pressure relative to the turbine building. Upon failure of an operating AHU and low-flow subsequent automatic start of the designated standby unit, the associated dampers will reposition, and an alarm will annunciate in the MCR.

The MCR is protected in part from high radiation due to airborne radioactivity by pressurization and filtration.

When operated, as above, the MCRECS normally maintains MCR temperature between 72 and 79°F dry bulb with outside air temperature variations from 20 to 95°F dry bulb. MCR relative humidity is not directly controlled but will not exceed 75%. For purging, the air-conditioning systems have the capability of meeting 50% supply and 100% exhaust air requirements of the MCR. The exhaust fan discharge is directed to the reactor building exhaust plenum. The flow rate is -14,000 fetmin for supply and 11,500 fetmin for exhaust during purging.

If the outside air supply is shut off and the MCR is placed into the isolation mode, the MCR will remain habitable in the isolation mode for -14 people for at least 50 hours5.787037e-4 days 0.0139 hours 8.267196e-5 weeks 1.9025e-5 months .

By letter dated May 2, 2014, in response to a NRC staff request for additional information, the licensee stated the following:

The design basis of the MCR AC System is to maintain the MCR temperature for a 30 day

_continuous occupancy. During emergency operation, the MCR AC System maintains a habitable environment and ensures the OPERABILITY of components in the MCR. The MCR AC system consists of three 50% capacity subsystems, and it functions to maintain controlled temperature in the MCR for the comfort of the operators and to maintain the integrity of the MCR components. The airs ide of the MCR AC system is also a part of the MCR environmental control (MCREC) system which consists of redundant filtration units.

During normal plant operation, the MCREC is maintained in a standby condition, and is only activated during accident conditions to maintain habitability in the MCR. Also during normal plant operation, the outside air supply to the MCR bypasses the MCREC system.

During accident conditions, the MCREC system provides filtered outside air for pressurization of the MCR. A single failure of a component of the MCR AC System does not impair the ability of the system to perform its design function. The MCR AC System is designed in accordance with Seismic Category I requirements.

The MCR AC units are required to be Operable in Modes 1, 2, or 3 to ensure that the control room is habitable, from a temperature perspective, should a design basis event such as LOCA/LOSP occur. Additionally, the MCR AC units ensure that the controls necessary for mitigating DBA events remain Operable. The MCR AC units are also required to be Operable during activities such as Core Alterations where the radiological consequences of other DBAs, such as the Fuel Handling Accident, could be significant.

The MCR AC system design information is described in Chapter 9.4.1 of the Unit 2 FSAR.

This section is common to both units.

In its letter dated July 22, 2014, the licensee indicated that the current RA temperature basis of not exceeding 65 °F outside ambient temperature during the previous 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months period correlated to a MCR area ambient temperature of 1as-oF with one MCR AC subsystem in operation and that this temperature bases change represented a more conservative RA restriction.

Further, the licensee discussed the compensatory measures considered in case the MCR area temperature approximates the equipment temperature limit of 105 °F. Specifically the licensee stated that in the event of a loss of all three MCR AC subsystems, operators are currently directed to open doors on the back of various Control Room Panels within 30 minutes. Additionally, in this event, if the control room temperature exceeds outside air temperature, the operators are directed to place the MCR environmental control in purge mode.

The licensee also states that alternate methods of maintaining control room temperature, such as non-safety grade air conditioning systems or fans, can also be used to maintain control room temperature. SNC currently has portable AC units on site that could be tied into the existing MCREC ventilation duct. SNC is evaluating alternate cooling methods that can be implemented expeditiously in order to reduce the required installation time. However, should the MCR area ambient temperature exceed 90°F (with or without alternate cooling in place), the plant will be required to be in Mode 3 within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in Mode 4 within 36 hours4.166667e-4 days 0.01 hours 5.952381e-5 weeks 1.3698e-5 months .

Finally, if the shift supervisor determines that continued operation of the unit from the MCR is not conducive to safe plant operation, the plant can be brought to a shutdown condition from a steady state normal operating condition by manipulating plant controls outside of the MCR. Prior to evacuating the MCR, the plant operator is directed to scram the reactor. Unit 1 LCO 3.3.3.2 and

Unit 2 LCO 3:3.3.2 states that the Remote Shutdown System Functions shall be OPERABLE and contains Actions and Surveillance Requirements for the Remote Shutdown System Operability.

Based on the NRC staff's review as described above, the staff concludes that the changes requested by the licensee are consistent with the intent and basis for the TSTF-477, Revision 3 changes that were incorporated into to the STS, and are therefore acceptable. A reasonable CT is provided for the condition where there is no MCR AC cooling capability operable. This is in consideration of the risks of not having that cooling capability during the CT period should an accident occur and those incurred by commencing unscheduled immediate reactor shutdown(s) as would otherwise be required by Limiting Condition for Operation (LCO) 3.0.3. Additionally, as explained above, given HNP's three 50% AC subsystem arrangement, the condition of two 50%

subsystems being inoperable is not as limiting as having both AC subsystems of a two-1 00%

. capacity AC subsystem configuration inoperable. Finally, the proposed CT and MCR ambient temperature limitation for the condition of two-50% AC subsystems being inoperable is reasonable considering that the MCR equipment and personnel environmental conditions would be acceptable for the allowed duration and the low probability of an event occurring during that

time.

4.0 :

SUMMARY

Based on the information provided by the licensee and evaluated by the NRC staff as discussed above: (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.

5.0 STATE CONSULTATION

In accordance with the Commission's regulations, the Georgia State official was notified of the

. proposed issuance of the amendments. The State official had no comments.

6;0 ENVIRONMENTAL CONSIDERATION The amendments change a requirement with respect to the installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20. The NRC staff has determined that the amendments involve no significant increase in the amounts and no significant change in the types of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure. The Commission has previously issued a proposed finding that the *amendments involve no significant hazards considerations, and there has been no p\Jblic comment on the finding (79 FR 49110, August 19, 2014 ). 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.

7.0 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: J. Bettie Date: December 10, 2014

December 10, 2014 Mr. C. R. Pierce Regulatory Affairs Director Southern Nuclear Operating Company, Inc.

Post Office Box 1295, Bin - 038 Birmingham, AL 35201-1295

SUBJECT:

EDWIN I. HATCH NUCLEAR PLANT, UNIT NOS. 1 AND 2, ISSUf.NCE OF AMENDMENTS REGARDING THE CONTROL ROOM AIR CONDITIONING SYSTEM (TAC NOS. MF3374 AND MF3375)

Dear Mr. Pierce:

The U.S. Nuclear Regulatory Commission has issued the enclosed Amendment No. 270 to Renewed Facility Operating License DPR-57 and Amendment No. 214 to Renewed Facility Operating License NPF-5 for the Edwin I. Hatch Nuclear Plant, Unit Nos. 1 and 2, respectively.

The amendments revise the Technical Specifications (TSs) in response to your application dated January 16, 2014, as supplemented May 2 and July 22, 2014.

These amendments revise the TS 3.7.5, Control Room Air Conditioning (AC) System, to provide new Required Actions for one, two, or three main control room AC subsystems inoperable, and make other required corresponding changes.

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,

/RAJ Robert Martin, Senior Project 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. 270 to DPR-57

2. Amendment No. 214 to NPF-5

3. Safety Evaluation cc w/encls: Distribution via Listserv DISTRIBUTION:

PUBLIC RidsNrrDoriDpr Resource RidsNrrPMHatch Resource LPL2-1 R/F RidsNrrDorllpl2-1 Resource RidsRgn2MaiiCenter Resource RidsAcnw_MaiiCTR Resource RidsNrrDssSrxb Resource ADAMS A ccess1on N0. ML14279A261 *SEt ransm1*uedb)Y memo dated OFFICE NRR/LPL2-1/PM NRR/LPL2-1/LA NRR/DSS/SRXB/BC N RR/DSS/STS B/BC NAME RMartin SFigueroa UShoop REIIiott DATE 12/08/14 11/18/14 09/25/14* 12/09/14 OFFICE OGC NRR/LPL2-1/BC NRR/LPL2-1/PM NAME AGhosh RPascarelli RMartin DATE 12/05/14 12/10/14 12/10/14 OFFICIAL RECORD COPY

v t e Letter Sequence Approval
TAC:MF3374, Add Action for Two Inoperable Control Room AC Subsystems (Approved, Closed) TAC:MF3375, Add Action for Two Inoperable Control Room AC Subsystems (Approved, Closed)
Initiation Request Acceptance... Administration Questions 3 April 2014 23 June 2014 Answers 2 May 2014 22 July 2014 Results Approval Other:
MONTHYEAR2014-04-03 [Table View]

ML14279A261

Text

SUBJECT:

Dear Mr. Pierce:

Enclosures:

Attachment:

Attachment:

2.0 REGULATORY EVALUATION

3.0 TECHNICAL EVALUATION

SUMMARY

5.0 STATE CONSULTATION

7.0 CONCLUSION

SUBJECT:

Dear Mr. Pierce:

Enclosures:

Navigation menu

Search