ML103270096

License Amendment, Issuance of Amendments Regarding Revision of Technical Specification (TS) 3.8.4 DC (Direct Current) Sources - Operating.

ML103270096
Person / Time
Site:	McGuire, Mcguire
Issue date:	12/20/2010
From:	Jacqueline Thompson Plant Licensing Branch II
To:	Repko R Duke Energy Carolinas
Thompson Jon, NRR/DORL/LPL 2-1, 415-1119
References
TAC ME2936, TAC ME2937
Download: ML103270096 (17)

Text

{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 December 20, 2010 Mr. Regis 1. 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) 3.8.4 "DC [DIRECT CURRENT] SOURCES - OPERATING" (TAC NOS. ME2936 AND ME2937)

Dear Mr. Repko:

The Nuclear Regulatory Commission has issued the enclosed Amendment No. 260 to Renewed Facility Operating License NPF-9 and Amendment No. 240 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 14, 2009, as supplemented by letters dated September 8, 2010, and October 28, 2010. The amendments revise TS Surveillance Requirements (SRs) 3.8.4.2 and 3.8.4.5 of TS 3.8.4, "DC [Direct Current] Sources - Operating." These TS SRs address battery connection resistance values. 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. 260 to NPF-9

2. Amendment No. 240 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. 260 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 14, 2009, as supplemented by letters dated September 8,2010, and October 28,2010, 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.

                                                   -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-9 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 260 ,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 60 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION G'(~ Gloria Kulesa, Chief Plant 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: December 20, 2010

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 DUKE ENERGY CAROLI NAS, LLC DOCKET NO. 50-370 MCGUIRE NUCLEAR STATION, UNIT 2 AMENDMENT TO RENEWED FACILITY OPERATING LICENSE Amendment No. 240 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 14,2009, as supplemented by letters dated September 8,2010, and October 28,2010, 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.

                                                    -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-17 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 240 ,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 60 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION C-{~ Gloria Kulesa, Chief 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: December 20, 2010

ATIACHMENT TO LICENSE AMENDMENT NO. 260 RENEWED FACILITY OPERATING LICENSE NO. NPF-9 DOCKET NO. 50-369 AND LICENSE AMENDMENT NO. 240 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 License Pages License Pages NPF-9, page 3 NPF-9, page 3 NPF-17, page 3 NPF-17, page 3 TS Pages TS Pages 3.8.4-2 3.8.4-2 3.8.4-4

                                        -3
  '(4)     Pursuant to the Act and 10 CFR Parts 30,40 and 71>, to recelYe.. PQssess and use In amounts as requiAld I1rt byPfO(iuct, source or spedel nuclear rna.ria' without ",s~UOn to c:hemlc:al or physical form, Jo~ sampe .NI~

or instrument calibration or asSOCiated wtth rBdloacttw appa\'1lU or components; (5) Pursuant 10 the Act and 10 CFR Pam 30,40 and 70. to POSIINS, but not separate, such byprodUC* and IJ)eClal ~lear IT8lerials as may be produced by the operalton of McGuIre Nuclear Station, Un~5 l' and Z and'

                                                                * *               '    t (8)   Pu~uant to tile Act and 10 a:R Parts 30 and 40: to receive, poIseS5 and process for rele81e or transfer IUCh byproduct mater1al IS may be produced by U. Duke Training If1d Tuchnology Center.

C. This renewed operating license shell be deemed' to contain and is sUbjecl to. the , condltJOf1I specified In the Commission's regulaUol'l$ sot foi1h In 10 CFR Chapter J and Is lubject to allapplcable Provisions of the Act and to the Nlal. or regulaUons, and ordent of the Commtallon now hereafter" effect; and Is subject to the addiUonal condltions.apedl'ed or incorporated below; (1 ) Maximum Power Level The ficensee Is authorized to opendelhe facinty at a reacrtor core fuji steady state power level of 3411 rneg8W8tt1 thermal (100%). (2) Technical S pec~lC8tions The Technical SDeClflcatlor1$ contained in Appendlx'A, as revIsed through Amendment No. 260 ,are hereby Incorporated Into this renewed operating license. Tne licensee shall operate !he facility In ace0rd8nce with the Technical Specifications. (3) Updated Final Safety AnalYSis Report

          *The  Updated Finel Safety Anelysls Report supplement submitted pu~u.nt to 10 CFR 54.21(<3). n reviled on OoQcmbor 16, 2002, doacntHts ceMIn future activities to be completed before the partocl of extendecl  ~,..tIon.

Duke shBI! complete these ~Iv.~ no later lhllln Juno 12, 2021. and shall notify the NRC In WYtllng when Implementation of these ectlvltlel Is complete and can be verined by NRC lnspec1ion. The Updated Final Safety AnBIysi$ 'Repon supptomerit 81 revtled On December 16.2002. doacribod above. shall be included In the next scheduled update to the Updated Final Safety Anelysll Report required by 10 CFR 5O.71(e)(4), following Issuance of ttlis renewed operaUng license. Until that update Is complete I Duke may make ch8'9'S to the programs described in such supplement without prior Com~lsslon approvel, provi<led that Duke evaluates each such change pursuant to the aiteria 38t forth In 10 eF'R 50.59 aoo othcrwloo compli03 with the l'DOulramonl;, In !hDt section. Renewed L1cenae No. NPF-9 Amendment No, 260

(4) Pursuant to the Act and 10 CFR Pal'tl 30. 40 lind 70",.to nteeNe. pollHSI and ule In amounla al ~ulred'any byproduct, 10UfQ8 or apecJal nuclear materiel without restriction to chemk;el or physical farm, for umple ."elyels or Instrument celbr8l/on or associated with radioactive epperatus or components; (5) P\nuant to the Act and 10 CFR Per1s 30,40 end 70. to POSlelS~ but riot separate, such bypfvducla and'lpeclal nuclear materlalslS may be produced by the operation of McGuire Nuclear Station, units , and 2; Ind, (6) Pursuant to the Acland 10 CFR'P1l1I30 and 40, to rec<elve, possess and process for release or tr8nsfer such byproduct materiel n mey be prodUced by the Duke Training end Technology Conter. C. This renewed operating license shell be deemed to contain and Is subject to the condltlonllpecifled In the Commllllon'l regulations set forth n 10 CFR Chapter 0' I and Is subject to ell applicable provtsions the Act and to the ""lei, regulation" end ordef1 of the commission now or hereaner In effect; Ind Is

   ,ubJKt to the addlUonel condltlonl lpeclfied or Incorporated below:

(1) M,xlmum Powgr Level The licensee is authoriZed to operate the facifity at a reactor core full steady sIBte power level of 3411 megawlltts thermal (100%). (2) Iechnlcal Speciflcatlons

        . The Technical SPAr.lI"qVOns contained In AppendiX A, IS reviled through Amendment No. 240,         ,re hereby Incorporated Into this renewed operaUng license. ,I ne licensee shall operate the faQlty In accordance with the TechnIcal SpecifICations.

(3) Updated Final Strety AnIItys/s Report The Updated Floal Safety Anelysls Report supplement submitted pursu8nt to 10 CFR 54.21(d), 81 revised on December '6,2002. deeCliboe eerl.}n future aetMtJes to be comploted befo,. 'he period of e~.nded opel1ltlon. Duke .han complete lheI8 activities no .18ter than MIWch 3, 2023, and lhall notify the NRC In wrltrng when implementation of theae BcU.,ltles is complete and can be verined P)' NRC InlJpection. The Updvted Flnel Safety Anv/yail Repor1 supplement al revlaed on December 18, 2002, dellcrl~d ebow, IheR be Included In tt. neXf scheduled update to thu Upclated Final Safety Analysis Report rvqulred by 10 CFR 50. 71 (e)(4), following Isluance of thll renewed opefl~ng license. Until thet updete Is complete, Duke may make ch8nges to the programs described In suCh supplement without prior CommissiOn approve I, provided that Duke evaluates each luch change pursuant to tho criteria let fOf1h In 10 CFR 50.59. and otherwtse Compiles with the requirements in thst sectIon. Re"ewed license No. NPF*17

                                                       . Amendment No. 240

DC Sources - Operating 3.8.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.4.1 Verify battery terminal voltage is ~ 125 V on float charge. 7 days SR 3.8.4.2 Verify no visible corrosion at battery terminals and 92 days connectors. OR Verify connection resistance of specific connection(s) meets Table 3.8.4-1 limit. SR 3.8.4.3 Verify battery cells, cell plates, and racks show no visual 18 months indication of physical damage or abnormal deterioration that could degrade battery performance. SR 3.8.4.4 Remove visible terminal corrosion, verify battery cell to 18 months cell and terminal connections are clean and tight, and are coated with anti-corrosion material. SR 3.8.4.5 Verify all battery connection resistance values meet 18 months Table 3.8.4-1 limits. SR 3.8.4.6 Verify each battery charger supplies ~ 400 amps at 18 months

             ~ 125 V for ~ 1 hour.

(continued) McGuire Units 1 and 2 3.8.4-2 Amendment Nos. 260, 240

DC Sources - Operating 3.8.4 Table 3.8.4-1 (page 1 of 1) Battery Connection Resistance Limits PARAMETER LIMIT (micro-ohms) Single intercell connection ~ 81.1 Single interrack connection ~ 170.0 Single intertier connection ~ 170.0 Single terminal connection ~ 187.6 Average intercell connection ~46.9 McGuire Units 1 and 2 3.8.4-4 Amendment Nos. 260, 240

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 260 TO RENEWED FACILITY OPERATING LICENSE NPF-9 AND AMENDMENT NO. 240 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 14,2009 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML093500597), as supplemented by letters dated September 8, 2010 (ADAMS Accession No. ML102560066), and October 28, 2010 (ADAMS Accession No. ML103070122), 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 September 8, 2010, and October 28, 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 the Federal Register on August 10, 2010 (75 FR 48375). The proposed changes would revise TS Surveillance Requirements (SRs) 3.8.4.2 and 3.8.4.5 of TS 3.8.4, "DC [Direct Current] Sources - Operating." These TS SRs address battery connection resistance values.

2.0 REGULATORY EVALUATION

The regulatory framework which the U.S. Nuclear Regulatory Commission (NRC) staff applied in the review of the application includes: Title 10 of the Code of Federal Regulations (10 CFR), Part 50, Appendix A, "General Design Criteria [GDG] for Nuclear Power Plants," Criterion 17 (GDC 17), "Electric power systems requires, in part:

                                                  -2 An onsite electric power system and an offsite electric power systems shall be provided to permit functioning of structures, systems, and components important to safety ...

The onsite electric power supplies, including the batteries, and the onsite electric distribution system, shall have sufficient independence, redundancy, and testability to perform their safety functions assuming a single failure. In addition, GDC 17 requires provisions for minimizing the probability of losing electric power from the remaining electric power supplies as a result of loss of power from the unit, the offsite transmission network, or the onsite power supplies. GDC 18, "Inspection and testing of electric power systems," requires that "Electric power systems important to safety shall be designed to permit appropriate periodic inspection and testing of important areas and features ... " 10 CFR 50.36(c)(3), "Surveillance requirements," requires that TSs include SRs, which are "requirements relating to test, calibration, or inspection to assure that the necessary quality of systems and components is maintained, that facility operation will be within safety limits, and that the limiting conditions for operation will be met." 10 CFR 50.63, "Loss of all alternating current power," requires that each light-water cooled nuclear power plant licensed to operate must be able to withstand for a specified duration and recover from a station blackout (S80).

3.0 TECHNICAL EVALUATION

The station DC electrical power system provides the alternating current (AC) emergency power system with control power. It also provides both motive and control power to selected safety-related equipment and preferred AC vital bus power (via inverters). The DC electrical power system is designed to have sufficient independence, redundancy, and testability to perform its safety functions, assuming a single failure. The proposed license amendment request (LAR) would revise the battery connection resistance acceptance criteria in the TS SRs to ensure that the safety-related batteries will remain operable and can perform their safety functions during postulated design basis events. The licensee proposed the following battery connection resistance acceptance criteria for the safety-related batteries:

                                                  - 3 New McGuire 1 and 2 TS Table 3.8.4-1 Baery tt    C onneclon t'      R  '

eSlstance L**t Iml s PARAMETER LIMITS (Micro Ohms) Single intercell connection ~81.1 Single interrack connection ~170.0 Single intertier connection ~170.0 Single terminal connection ~187.60 Average intercell connection ~46.9 The McGuire 1 and 2 Updated Final Safety Analysis Report (UFSAR), Section 8.4.5, states that McGuire 1 and 2 have "four Class 1E batteries which are shared between Units." The station's 125 Volt (V) DC electrical power system consists of two independent and redundant safety-related Class 1E DC electrical power subsystems (Train A and Train B). Each subsystem (Train) consists of two channels of 125 V DC batteries, the associated battery charger(s) for each battery, and all the associated control equipment and interconnecting cabling. Train A and Train B DC electrical power subsystems provide the control power for its associated Class 1E AC power load group, 4.16 kilovolt (kV) switchgear and 600 V load centers. The DC electrical power subsystems also provide DC electrical power to the inverters, which in turn power the AC vital buses. Each safety-related battery at McGuire 1 and 2 has adequate storage capacity to carry the required loads for a 1-hour duty cycle after the loss of the battery charger output during loss-of-offsite power (LOOP)/loss-of-coolant accident (LOCA) and for a 4-hour duty cycle during an SBO event. In addition, the safety-related batteries are capable of supplying power for the operation of anticipated momentary loads during the 1-hour period for a LOOP/LOCA event. During normal operation, the 125 V DC load is powered from the battery chargers with the batteries floating on the system. In case of loss of normal power to the battery charger, the DC load is automatically powered from the station batteries. Each of the station's 125 V DC safety-related batteries is separately housed in a ventilated room apart from its charger and distribution centers. Each channel is located in an area separated physically and electrically from the other channel to ensure that a single failure in one subsystem does not cause a failure in a redundant subsystem. The batteries for the channels of vital DC are sized to produce the required capacity at 80 percent of nameplate rating, corresponding to warranted capacity at end-of-life cycles and the 1OO-percent design demand (i.e., a 1.25 aging factor is used to size the safety-related batteries). In the LAR, the licensee stated that the battery charger for each channel of DC has sufficient capacity for the steady state operation of connected loads required during normal operation while at the same time maintaining its battery bank fully charged. Each battery charger also has sufficient capacity to restore the batteries from the design minimum charge to its fully-charged state within 8 hours while supplying normal steady state loads discussed in Chapter 8 of the McGuire 1 and 2 UFSAR. The existing McGuire 1 and 2 TS SRs 3.8.4.2 and 3.8.4.5 currently require the licensee to verify the battery connection resistances on the safety-related batteries. The existing TS SR acceptance criteria are less conservative than the specified limits for the individual parts of the

                                                    -4 safety-related batteries (i.e., intercell, intertier, interrack, and terminal connections). As a result, the total resistance of the battery, as determined by summing the individual values of the battery connection resistance, could exceed the value of total battery resistance reflected in the load and voltage study calculations. In the LAR, the licensee stated that the battery manufacturer acceptance criteria in terms of maximum intercell voltage drop was applied in the analysis of battery connection resistance and the analysis established the proposed battery resistance acceptance criteria for the TS SRs. As such, the licensee has proposed modifying McGuire 1 and 2 TS SRs 3.8.4.2 and 3.8.4.5. The licensee also proposed adding an additional acceptance criterion to verify average intercell connection resistance which is within the proposed established limits that ensure the safety-related batteries can perform their safety functions and will remain operable during postulated design basis events. The licensee has proposed these TS SRs changes to restore the required conservatism to their TSs and to ensure the availability of adequate DC power as specified in the McGuire 1 and 2 safety analyses. The licensee stated that this change is necessary since the parameters currently specified in the existing SRs do not, by themselves, ensure that the batteries will be maintained in a condition such that they will be able to perform their safety function.

The NRC staff reviewed the LAR and the responses to the NRC staff's RAls to determine the technical adequacy of the proposed changes. The McGuire 1 and 2 UFSAR, Section 8.3.2.1.4.2, states that each safety-related battery is "sized to carry the continuous emergency load of its own vital buses and also assume the loads of another battery in a "backup" capacity, if required, for a period of one hour." Emergency loads include those during LOOP and LOCA. These batteries also carry shutdown loads for 4 hours during an SBO. Section 8.3.2.1.4.2 also states that "In addition, the battery is capable of supplying power for the operation of anticipated momentary loads during the one-hour period." The licensee's evaluation included verifying the values of resistance for intercell, interrack, intertier, terminal connections, and the average intercell connection resistance of the battery by calculation. The licensee also uses these resistance values to calculate the acceptable voltages at the devices powered by safety-related batteries. It is the NRC staff's understanding that the licensee used the revised battery connection resistance limits in the DC system voltage drop calculation and verified that minimum-required voltage and current exist for the devices fed from the safety-related batteries to perform their safety function for the LOOP/LOCA and SBO events. To validate the licensee's proposed new resistance acceptance criteria, the NRC staff requested the licensee to provide a summary of the resistance calculation which established the proposed TS battery connection resistance limits. Specifically, the NRC staff requested the licensee to provide the technical basis and a summary of the calculation for the proposed TS resistance values (i.e., resistance values for intercell, intertier, interrack, terminal, and the average battery intercell connections). In response to the NRC staff's request, the licensee provided a detailed discussion on how the various battery connection resistances were derived including how the battery manufacturer's acceptance limits were applied. Based on its review of the licensee's response, the NRC staff finds that the licensee has adequately incorporated the battery manufacturer's acceptance limits in establishing the proposed battery connection resistance values. Additionally, the licensee opted to add an additional parameter, "average intercell connection resistance," in the proposed TS SR for effectively monitoring the intercell resistances. However, the NRC staff did not find any definition of this new parameter in the LAR. Therefore the NRC

                                                  -5 staff requested the licensee to provide a definition of this new parameter and a regulatory commitment to incorporate this definition in the TS bases. In a letter dated September 8, 2010, the licensee provided the following definition for "average intercell connection resistance" Average intercell connection resistance is defined as the battery manufacturer's maximum allowed intercell connection voltage drop divided by the maximum battery duty cycle load current. The maximum allowable battery total intercell connection resistance can then be defined as the average intercell connection resistance times the total number of intercell connectors in the battery string. Intercell connection is referring to the (56) copper connection straps between the battery jar posts and the battery terminal connections.

In its letter dated September 8, 2010, the licensee also provided a regulatory commitment to include this definition in the TS Bases. The NRC staff finds the licensee's response adequate and acceptable. The NRC staff evaluated the licensee's request to modify SR 3.8.4.2 and SR 3.8.4.5 for the intercell, interrack, intertier and terminal connections acceptance criteria and by adding an additional acceptance criterion for the average intercell connection resistance within pre-established limits. Based on the above evaluation, the NRC staff finds that the proposed changes to the McGuire 1 and 2 TSs provide 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 10 CFR 50.63 and meet the intent of GDCs 17 and 18. Therefore, the NRC staff finds the proposed changes acceptable.

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 the SRs. 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 (75 FR 48375). 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

                                               -6 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: P. Sahay Date: December 20, 2010

ML103270096 provided b>y memo d at ed 11/18/2010 ML103190111 OFFICE NRRlLPL2-1/PM NRRlLPL2-1/LA DIRSIITSB/BC DE/EEEB/ABC OGC NLO NRRlLPL2-1/BC NRRlLPL2-1/PM RElliotl NAME JThompson MO'Brien (MHamm for) RMathew* MWright GKulesa JThompson DATE 11/22110 11/30/10 12/06/10 11118110 12/14/10 12/17/10 12/20/10}}