ML101060044

Issuance of Amendments Regarding Revision of Technical Specification (TS) 3.8.1, AC Sources - Operating (TAC Nos. ME0231 and ME0232)

ML101060044
Person / Time
Site:	McGuire, Mcguire
Issue date:	05/05/2010
From:	Jacqueline Thompson Plant Licensing Branch II
To:	Repko R Duke Energy Carolinas
Thompson Jon, NRR/DORL/LPL 2-1, 415-1119
References
TAC ME0231, TAC ME0232
Download: ML101060044 (16)

Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 May 5, 2010 Mr. Regis T. Repko Vice President McGuire Nuclear Station Duke Energy Carolinas, LLC 12700 Hagers Ferry Road Huntersville, NC 28078

SUBJECT:

MCGUIRE NUCLEAR STATION, UNITS 1 AND 2, ISSUANCE OF AMENDMENTS REGARDING REVISION OF TECHNICAL SPECIFICATION (TS) 3.8.1, "AC SOURCES - OPERATING" (TAC NOS. ME0231 AND ME0232)

Dear Mr. Repko:

The Nuclear Regulatory Commission has issued the enclosed Amendment No. 254 to Renewed Facility Operating License NPF-9 and Amendment No. 234 to Renewed Facility Operating License NPF-17 for the McGuire Nuclear Station, Units 1 and 2. The amendments consist of changes to the TSs in response to your application dated December 1, 2008, as supplemented by letters dated July 30, 2009, December 2, 2009, and March 10, 2010.

The amendments revise Surveillance Requirement (SR) 3.8.1.4 to increase the minimum required amount of fuel oil for the Emergency Diesel Generators fuel oil day tank as read on the local fuel gauge used to perform the surveillance.

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.

If you have any questions, please call me at 301-415-1119.

Sincerely, Jon Thompson, Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-369 and 50-370

Enclosures:

1. Amendment No. 254 to NPF-9

2. Amendment No. 234 to NPF-17

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

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 DUKE ENERGY CAROLINAS, LLC DOCKET NO. 50-369 MCGUIRE NUCLEAR STATION, UNIT 1 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 254 Renewed License No. NPF-9

1. The Nuclear Regulatory Commission (the Commission) has found that:

A. The application for amendment to the McGuire Nuclear Station, Unit 1 (the facility),

Renewed Facility Operating License No. NPF-9, filed by the Duke Energy Carolinas, LLC (licensee), dated December 1,2008, as supplemented by letters dated July 30, 2009, December 2, 2009, and March 10, 2010, 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.

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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-9 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 254 . are hereby incorporated into this renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.

3. This license amendment is effective as of its date of issuance and shall be implemented within 30 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION JA oria Kulesa, Chief ~V' ant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to License No. NPF-9 and the Technical Specifications Date of Issuance: May 5, 2010

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 DUKE ENERGY CAROLINAS, LLC DOCKET NO. 50-370 MCGUIRE NUCLEAR STATION, UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 234 Renewed License No. NPF-17

1. The Nuclear Regulatory Commission (the Commission) has found that:

A. The application for amendment to the McGuire Nuclear Station, Unit 2 (the facility),

Renewed Facility Operating License No. NPF-17, filed by the Duke Energy Carolinas, LLC (the licensee), dated December 1, 2008, as supplemented by letters dated July 30, 2009, December 2, 2009, and March 10, 2010, 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.

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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-17 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendix At as revised through Amendment No. 234 t are hereby incorporated into this renewed operating license. The licensee shall operate the facility in accordance with the Technical Specifications.

3. This license amendment is effective as of its date of issuance and shall be implemented within 30 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

~UI~ief ~ov Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to License No. NPF-17 and the Technical Specifications Date of Issuance: May 5, 2010

ATTACHMENT TO LICENSE AMENDMENT NO. 254 RENEWED FACILITY OPERATING LICENSE NO. NPF-9 DOCKET NO. 50-369 AND LICENSE AMENDMENT NO. 234 RENEWED FACILITY OPERATING LICENSE NO. NPF-17 DOCKET NO. 50-370 Replace the following pages of the Renewed Facility Operating Licenses 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 Insert License Pages License Pages NPF-9, page 3 NPF-9, page 3 NPF-17, page 3 NPF-17, page 3 TS Pages TS Pages 3.8.1-6 3.8.1-6

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'(4) Pursuant to the Act and 10 CFR Pal1s 30,40 and 70', to receMt,.poNess.

and use In amounts IS requlrvd efty byproduct, source or specie, nucleilr me"'ria' without res~Uon to chembli or phYslc8l form. for. SImple lnalysls or instrument callbrlUon or allClCleted with nJdloactlw appal'ldUl or components; (5) Pursuent to the Act end 10 CFR Parts 30,40 and 70. to pos'"s, but not separate, such byproc:tUC1l and tpeelal ru;lear rreteriBls IS mey be prgduced by the operettan of McGutre Nuclear SI8~n, Units l' end 2', and~

(6) Pursuant to the Act and 10 CFR Pens 30 and 40: to receive, possess and process for release or tr.nsfer IUCh byproduct mater1al as may be produced by the Duke TflJlning 'nd Technology Center, C. This renewed operating 'lcense shull be deemed'to contain and is sUb)ect to, the .

condlUona spec;med In the Commlalon', regulations lOt fol1h In 10 CFR Chapter land is subject to all applicable provisions of the Act and to the rvlls, regulaUons, and orders of the Commtukm now or hereafter In effect; and Is subject to the additional condltionlsptdf'ed or incorporated below; (1) Maximum Power Level The Ncensee is authorized to operete the facility at a relGtor core full steady stete power level of 3411 megawatts thermal (100%).

(2) Techn)<:a' SpeC~lC8tiOns The Technical SORCIflcaUons contained in Appendlx'A, as revised through Amendment No. 254 ,are hereby Incorporated into this renewed operating license. Tne Ucemee shall operate the facility In accordanoe with the Technical Specification,.

(3) Updated Final Safety Analysis Report

,The Updated Fin81 Safety Analysis Report su~lement submitted pu~u.nt to 10 CFR 54.21(d), n ",vised on Oo<:ember 16, 2002, dqCrtt1e8 cerUllo futuro 8ctlvitle8 to be completed before the pertod of extended lJP"nttlon.

Duke shall complote these activit'" no I.tor than Juno 12, 2021. and 'hall nollfy the NRC In wntlng when Implemenlallon of these actlvnlet Is complete and can be verlfled by NRC tnapection.

The Updated Final Safety Analysis 'Rupon supplemenlal reviled on December 16,2002, d05cribed &bov., shall be included in lhe next scheduled update 10 the Updaled Finel Sefety Analysts Report required by 10 CFR 50.71(e)(4), following Issuance of this renewed operaUng license.

Until that update Is comptote, Duke may make changes to the programs described In such supplement wtthout prior Commission approval. provided that Duke evalUBtes each such change pursuant to the criteria set forth In 10 CFR 5059 and othcrwl3D compl~ With the r~Ulromo". In thot sectiOn, ReneWed L1C*l1e No, NPF.9 Amendment No. 254

(4) Pursuant to the Act and to CFR Parts 30.40 and 70',.to recetve, possess and use In amounts as required' any byproduct. source or special nuclear material without rntrlctlon to chemical or ph~1c81 form, for SImple a"alyels or Instrument celbratlon or 8ssoc181ed wtth radioactive epperatus or components; (5) P\nuant to the Act and 10 CFR Parts 30, 40 end 70, to poans'~ but not sep8rate, such bypnJducbs and' special nuclear mater1als as msy be produced by the operation of McGuire Nuclear Station, Units , and 2; Ind, (6) Pursuant to the Act and 10 CFR'Par1l 30 and 40, to receive, possess and process for retease or transfer such byproduct material as mey be produced by the Duke Tralnfng and Technology Center.

C. This renewed operating license shell be deemed to contain and Is subject to the conditions specified In the Commission's regUlations set fOf1h In 10 CFR Chapter I and Is subject to all applicable provtsions of the Act and to the rule.,

regulations, and ord8f1 of the commission now or hereaner In effea; and Is subject to the additional cond~lons specified or Incorporated below:

(1) M,xlmum PewIt Level The licensee is authorized to operate the facility at a reactor core full steady state power level of 3411 megawatts thermal (100%).

(2) Iechnical Se!9f!ca tions

. The Technical SpAcifir.utlOns contained in Appendix A, as revised through Amendment No. 234 ,~re hereby Incorponlted Into this renewwd operating license. ;The licensee shall Operate the fBdlty In accordance with the Technical SpeclflC8tions.

(3) Updated Final S,fetv Analysis Report The Updated Final S8fetyAnatysls Report supplement submitted PU~U8I'H

'0 '0 CFR 54.21(d), a8 revisad on December 16, 2002, delcrtbet certain future actMtle~ to be completed ~fo,.., the period of e~ende<l operetlun.

Duke .hall complete these activities no later than March 3. 2023, and shall notify the NRC In writing when imJ1lementatlon ot theae activities is complete and cun be verlned by NRC Inspection.

The Updated Final Safety Anelysil Report supplement al reVised on December 16, 2002, described above. shall be Included In the ne~

schedUled update to the Updated Final Safety Analylla Report ",qulred by

'0 CFR 50.71 (e)(4), followmg Issuance of thls renewed operlltlng license.

until thet update Is complete, Duke may make changes to the program described In suCh supplement without prior CommissiOn approval, provided that Duke evaluates each such change pursuant to the crt1er1a eet forth in 10 CFR 50,59, and otherw\se eomplles with the requirements in thet section.

Rer'lewed License No. NPF*17 Amendment No. 234

AC Sources - Operating 3.8.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.8. 1.3 --------------------------------NOTES-------------------------------

1. DG loadings may include gradual loading as recommended by the manufacturer.

2. Momentary transients outside the load range do not invalidate this test.

3. This Surveillance shall be conducted on only one DG at a time.

4. This SR shall be preceded by and immediately follow without shutdown a successful performance of SR 3.8.1.2 or SR 3.8.1.7.

Verify each DG is synchronized and loaded and operates 31 days for ~ 60 minutes at a load ~ 3600 kW and ~ 4000 kW.

SR 3.8.1.4 Verify each day tank contains ~ 39 inches of fuel oil. 31 days SR 3.8.1.5 Check for and remove accumulated water from each day 31 days tank.

SR 3.8.1.6 Verify the fuel oil transfer system operates to 31 days automatically transfer fuel oil from storage tank to the day tank.

(continued)

McGuire Units 1 and 2 3.8.1-6 Amendment Nos. 254, 234

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 254 TO RENEWED FACILITY OPERATING LICENSE NPF-9 AND AMENDMENT NO. 234 TO RENEWED FACILITY OPERATING LICENSE NPF-17 DUKE ENERGY CAROLINAS, LLC MCGUIRE NUCLEAR STATION, UNITS 1 AND 2 DOCKET NOS. 50-369 AND 50-370

1.0 INTRODUCTION

By application dated December 1, 2008 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML083440422), as supplemented by letters dated July 30, 2009 (ADAMS Accession No. ML092230343), December 2, 2009 (ADAMS Accession No. ML093440061) and March 10, 2010 (ADAMS Accession No. ML100750344), Duke Energy Carolinas, LLC (Duke, the licensee), requested changes to the Technical Specifications (TSs) for the McGuire Nuclear Station, Units 1 and 2 (McGuire 1 and 2). The supplements dated July 30, 2009, December 2, 2009, and March 10, 2010, 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 May 19, 2009 (74 FR 23442).

The proposed changes would revise McGuire 1 and 2 TS 3.8.1.4 to increase the minimum required amount of fuel oil for the Emergency Diesel Generators (EDGs) fuel oil day tank as read on the local fuel gauge used to perform the surveillance. Each EDG fuel oil system at McGuire 1 and 2 has an independent day tank with a nominal capacity of 275 gallons. The day tank, if filled to capacity, does not hold enough fuel for 60-minute operation of one EDG operating at 4000 kilowatts (kW). The day tanks are filled from the respective fuel oil storage tanks (FOST), each with a nominal 50,000-galion capacity. The plant TS SR 3.8.3.1 requires 39,500 gallons in each FOST which corresponds to 5 days supply per EDG operating at 4000kW.

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2.0 REGULATORY EVALUATION

The McGuire 1 and 2 Updated Final Safety Analysis Report (UFSAR), Section 8.1, states that the offsite power system and the onsite power systems have adequate redundancy, independence and testability to perform their safety functions and conform to Title 10 of the Code of Federal Regulations (10 CFR), Part 50 (10 CFR Part 50), General Design Criterion (GDC) 17.

"The Offsite Power System and the Onsite Power Systems have adequate redundancy, independence and testability to perform their safety functions and to conform with the 10 CFR 50

[Title 10 of the Code of Federal Regulations, Part 50, Appendix A, "General Design Criteria for Nuclear Power Plants"] General Design Criterion 17 [Criterion 17, "Electric Power Systems"] and other design criteria listed in Section 8.1.4.

Criterion 17, "Electric Power Systems," of 10 CFR Part 50, Appendix A, requires, in part, that "An onsite electric power system ... shall be provided to permit functioning of structures, systems, and components important to safety." It also requires that "The onsite electric power supplies ... and the onsite electric distribution system, shall have sufficient independence, redundancy, and testability to perform their safety functions assuming a single failure." In addition, Criterion 17 has provisions that require mitigation of the risk of losing electric power from any of the remaining supplies as a result of the loss of power from the unit, the transmission network, or the onsite electric power supplies. At McGuire 1 and 2 fuel oil is supplied to the EDGs by the fuel oil system.

The day tank provides sufficient capacity to successfully start the EDG and allow for the orderly shutdown of the EDG in the event of a loss of fuel from the FOST or a fuel oil transfer pump problem.

Criterion 18, "Inspection and testing of electric power systems," of 10 CFR Part 50, Appendix A, requires that "Electric power systems important to safety shall be designed to permit appropriate periodic inspection and testing ... to assess the continuity of the systems and the condition of their components." Other provisions of Criterion 18 require that periodic inspection and testing can ensure operability and functional performance.

The regulation at 10 CFR 50.36, "Technical specifications," subsection (c)(2)(ii) requires that "A technical specification limiting condition for operation of a nuclear reactor must be established" for equipment that is required for safe operation of a nuclear reactor.

The regulation at 10 CFR 50.65, "Requirements for monitoring the effectiveness of maintenance at nuclear power plants," subsection (a)(3) requires that for preventative maintenance activities "Adjustments shall be made where necessary to ensure that the objective of preventing failures of structures, systems, and components through maintenance is appropriately balanced against the objective of minimizing unavailability of structures, systems, and components due to monitoring or preventive maintenance."

In addition to these regulatory requirements, regulatory gUidance and industry standards are also available to assist in evaluation of these systems.

The Regulatory Guide (RG) series provides guidance to licensees and applicants on implementing specific parts of the Nuclear Regulatory Commission's (NRC's) regulations, techniques used by the NRC staff in evaluating specific problems or postulated accidents, and

-3 data needed by the NRC staff in its review of applications for permits or licenses. RG 1.137, Rev. 1 , "Fuel-Oil Systems for Standby Diesel Generators," Regulatory Position 1, states that "The requirements for the design of fuel-oil systems for diesel generators that provide standby electrical power for a nuclear power plant that are included in ANSI [American National Standards Institute] N195-1976, "Fuel Oil Systems for Standby Diesel-Generators," provide a method acceptable to the NRC staff for complying with the pertinent requirements of General Design Criterion 17 of Appendix A to 10 CFR Part 50 ... ," subject to eight provisions (Le, the following provisions a-h).

Provision "c." of Regulatory Position 1 states that "Section 5.4, 'Calculation of Fuel Oil Storage Requirements,' of the standard [ANSI N195-1976] sets forth two methods for the calculation of fuel-oil storage requirements. These two methods are (1) calculations based on the assumption that the diesel generator operates continuously for 7 days at its rated capacity, and (2) calculations based on the time-dependent loads of the diesel generator. For the time-dependent load method, the minimum required capacity should include the capacity to power the engineered safety features."

ANSI N195-1976, Section 6, describes component performance requirements. Section 6.1 states that each diesel shall be equipped with day or integral tank or tanks whose capacity is sufficient to maintain at least 60 minutes of operation at the level where oil is automatically added to the day or integral tank or tanks. This capacity shall be based on the fuel consumption at a load of 100% of the continuous rating of the diesel plus a minimum margin of 10%. An overflow line from the day or integral tank to the supply tank shall be provided. Suction from the day or integral tank or tanks shall be from above the tank bottom.

3.0 TECHNICAL EVALUATION

3.1 Description of the McGuire 1 and 2 Electrical Power System McGuire 1 and 2 UFSAR, Section 8.1.4, "Design Criteria," states that the entire onsite power system for the two nuclear units is designed to provide reliable power for all necessary equipment during startup, normal operation, shutdown and all emergency situations. The design of all essential auxiliary power systems in the two nuclear units is in compliance with the criteria set forth in GDC 17, GDC 18, and RGs 1.6, 1.9 (with the exceptions identified) and 1.32.

The onsite power system for each of the McGuire 1 and 2 units consists of two independent EDG units rated at 4000 kW, 0.8 Power Factor, and 4160 Volts. Each EDG is rated for continuous operation at 4000 kW (100 percent rating) with added capacity to operate between 4200 - 4400 kW for a period of 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> out of every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of operation without adversely affecting the life of the unit. The design-basis accident load level for each of the redundant systems does not exceed the 4000 kW continuous rating of the EDG assigned to each system.

The EDG fuel oil system maintains a minimum supply of fuel oil onsite for four EDGs, two engines per each nuclear unit. Each EDG has an associated FaST and day tank. Fuel oil is transferred from the FaST by the fuel oil transfer pump through the fuel oil filter to the day tank. Each EDG is supplied by independent fuel systems, complete with separate underground FaSTs and locally

- 4 mounted day tanks. Each FOST is required to store enough fuel oil for operation of each EDG operating at 100-percent rating for a minimum of 5 days without refueling. The day tanks are sized to hold approximately 275 gallons up to the overflow lines.

3.2 Detailed Description of the Proposed Change TS SR 3.8.1.4 currently requires that the EDG day tank contain at least 120 gallons of fuel oil.

The licensee has determined that this volume is inadequate for a 30-minute operation of the EDG.

The proposed amendment seeks to correct this non-conservative TS SR by revising SR 3.8.1.4 to increase the minimum required amount of fuel oil in the day tank to approximately 160 gallons.

The proposed amendment further seeks to revise the manner in which this minimal amount of fuel oil is expressed, substituting "39 inches of fuel oil" as read on the local gauge used to perform the surveillance for the previous value of 160 gallons. The licensee has stated that approximately 160 gallons of fuel is adequate for a 30-minute operation of the EDG. The licensee considers this adequate for orderly shutdown of the EDG in case the transfer pumps fail to start.

3.3 Deterministic Evaluation The current SR 3.8.1.4 for McGuire 1 and 2 requires 120 gallons of fuel oil in the day tank to support operation of an EDG for approximately 30 minutes. This is significantly less than the 60-minute fuel oil storage requirement recommended in ANSI N195-1976 which is endorsed by RG 1.137. The 120-gallon requirement was incorporated by the licensee in the TS submitted as part of the original licensing basis.

In order to maintain defense-in-depth, the design of EDG systems should ensure a high level of reliability and the availability of redundant EDGs required for plant shutdown. EDG manufacturers recommend an orderly shutdown of the machine following an operational run to minimize component degradation. Industry standard ANSI N195-176 recommends a 60-minute supply of fuel oil in the day tank to provide adequate time for operator action to achieve an orderly shutdown in case of problems with the fuel oil transfer system.

By letter dated October 29, 2009, the NRC staff requested additional information related to the difference between the ANSI N195-1976 requirements and the fuel oil stored in the day tanks at McGuire 1 and 2. In a letter dated December 2,2009, the licensee quoted a previous correspondence during the plant licensing process that documented exceptions taken to some portions of the ANSI Standard. In a letter dated April 3, 1980, the licensee stated that the day tank for each diesel had capacity sufficient to maintain approximately 60 minutes of operation. Fuel oil is automatically added to the day tank at approximately one-half this level. ANSI N195-176 indicates that upon transfer pump failure, the day tank should have 60 minutes of fuel available.

At McGuire 1 and 2, the tank has half that amount (30 minutes) of fuel available. The licensee stated that 30 minutes is adequate time for operator action to shut down an operating EDG in the event of fuel oil transfer problems.

The NRC staff reviewed the communications between the licensee and the NRC during the licensing phase of McGuire 1 and 2 and concluded that 30 minutes was sufficient time for plant operators to take corrective action upon indication of low level in the day tank resulting from a failure of the fuel oil transfer system.

-5 The licensee has identified that the existing SR 3.8.1.4 value of 120 gallons is inadequate to support 30-minute operation of the EDG and proposes to change the SR value to 160 gallons of usable fuel oil. In the response to a requests for additional information dated December 2, 2009, the licensee has indicated that the proposed value of 160 gallons of fuel oil requirement was conservatively calculated based on minimum specific gravity of 0.805 corresponding to minimum heat content per gallon at the maximum calculated EDG room temperature. The NRC staff finds the proposed change to be acceptable as it is in agreement with the existing licensing basis and provides assurance that each EDG can operate for 30 minutes in the event of a transfer pump failure.

The amendment also proposes to revise the manner in which this minimal amount of fuel oil is expressed by changing 160 gallons (usable fuel oil) to 39 inches of fuel oil as read on the local gauge used to perform the surveillance. The use of inches in the proposed change for the surveillance requirement rather than gallons deviates from NUREG-1431, "Standard Technical Specifications-Westinghouse Plants," Revision 3, issued June 2004, which lists this value in gallons. The licensee has justified this change by noting that the instrumentation installed on the EDG day tank reads in inches. The use of inches rather than gallons avoids human error in converting the reading to different units and therefore is acceptable to the NRC staff.

In the application and supplements, the licensee indicated that the effects of temperature and specific gravity variations, vortexing, unusable volume, instrument inaccuracies and measurement uncertainties associated with establishing tank levels have been conservatively added to the level measurement (39 inches) proposed in the amendment. The licensee has further stated that the fuel oil transfer pump starts at 43 inches tank level (approximately 178 gallons) and the low-level alarm is actuated at 40 inches (approximately 165 gallons) prior to the tank level reaching the minimum volume of approximately 160 gallons of usable fuel. The NRC staff finds this approach for verification of usable fuel oil in the day tank acceptable.

3.4 Technical Evaluation Summary The NRC staff evaluated the licensee's request to revise SR 3.8.1.4 associated with EDG fuel oil storage in the day tank and corresponding method of verifying the adequacy of the fuel oil in the tank from a deterministic perspective. The NRC staff concurs with the proposed revision of the SR for the EDG day tank storage requirement from 120 gallons to approximately 160 gallons.

The NRC staff's conclusion is based on the licensee's confirmation that corrective actions will be taken within 30 minutes in the event of fuel oil level in the day tank dropping below the allowed limit when the corresponding EDG is operating. This will assure that the EDG can be shutdown in an orderly manner to preclude component degradation. The NRC staff also concludes that required volume in the day tank can be established by level measurement of 39 inches.

Based on the above evaluation, the NRC staff finds the proposed changes to the McGuire 1 and 2 TS provides reasonable assurance of the continued availability of the required electrical power to shut down the reactor and to maintain the reactor in a safe condition after an anticipated operational occurrence or a postulated design-basis accident. Furthermore, the NRC staff concludes that the proposed TS changes are in accordance with 10 CFR 50.36 and meet the intent of GDCs 17 and 18. Therefore, the NRC staff finds the proposed changes acceptable.

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4.0 STATE CONSULTATION

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

5.0 ENVIRONMENTAL CONSIDERATION

The amendments change a requirement with respect to the installation or use of facility components located within the restricted area as defined in 10 CFR Part 20 and change surveillance requirements. 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 (74 FR 23442). 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 Contributors: H. Garg, NRR G. Matharu, NRR Date: May 5, 2010

Mr. Regis T. Repko Vice President McGuire Nuclear Station Duke Energy Carolinas, LLC 12700 Hagers Ferry Road Huntersville, NC 28078

SUBJECT:

MCGUIRE NUCLEAR STATION, UNITS 1 AND 2, ISSUANCE OF AMENDMENTS REGARDING REVISION OF TECHNICAL SPECIFICATION (TS) 3.8.1, "AC SOURCES - OPERATING" (TAC NOS. ME0231 AND ME0232)

Dear Mr. Repko:

The Nuclear Regulatory Commission has issued the enclosed Amendment No. 254 to Renewed Facility Operating License NPF-9 and Amendment No. 234 to Renewed Facility Operating License NPF-17 for the McGuire Nuclear Station, Units 1 and 2. The amendments consist of changes to the TSs in response to your application dated December 1, 2008, as supplemented by letters dated July 30, 2009, December 2, 2009, and March 10, 2010.

The amendments revise Surveillance Requirement (SR) 3.8.1.4 to increase the minimum required amount of fuel oil for the Emergency Diesel Generators fuel oil day tank as read on the local fuel gauge used to perform the surveillance.

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.

If you have any questions, please call me at 301-415-1119.

Sincerely, IRA!

Jon Thompson, Project Manager Plant Licensing Branch 11-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-369 and 50-370

Enclosures:

1. Amendment No. 254 to NPF-9

2. Amendment No. 234 to NPF-17

3. Safety Evaluation DISTRIBUTION:

Public LPL2-1 RlF RidsAcrsAcnw_MailCTR Resource RidsNrrDirsltsb Resource RidsNrrDeEeeb Resource RidsNrrDeEicb Resource RidsNrrDorlDpr Resource RidsNrrDorlLpl2-1 Resource RidsOgcRp Resource GWilson, NRR RidsRgn2MailCenter Resource HGarg, NRR WKemper, NRR GMatharu, NRR RidsNrrPMMcGuire Resource RidsNrrLAMOBrien Resource ADAMS Accession No ML101060044 *no change to SE inputs provided ML093450571 and ML091390197 OFFICE NRRlLPL2-1/PM NRR/LPL2-1/LA DIRS/ITSB/BC DE/EEEB/BC NAME JThompson MO'Brien RElliott GWilson*

DATE 04/26/10 04/26/10 04/27/10 12/15/09 OFFICE DE/EICB/BC OGC NRR/LPL2-1/BC NRR/LPL2-1/PM CKanatas NAME WKemper* (NLO subject to comments) GKulesa (JStang for) JThompson DATE 06/15/09 05/04/10 05/05/10 05/05/10 OFFICIAL RECORD COpy