ML13338A169

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McGuire Nuclear Station, Unit 2, Technical Specifications and Technical Specifications Base Updates
ML13338A169
Person / Time
Site: Mcguire
Issue date: 11/21/2013
From: Beaver B C
Duke Energy Carolinas, Duke Energy Corp
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
DUK133250072
Download: ML13338A169 (37)
v • d • e


Text

PRIORITY NormalDISPOSITION OF THE ORIGINAL DOCUMENT WILL BE TOTHE TRANSMITTAL SIGNATURE UNLESS RECIPIENT ISOTHERWISE IDENTIFIED BELOW1) 02361 QATS-MG01MM

2) 02388 BOB SCHOMAKER
LYNCHBG, VA3) 02532 RESIDENT NRC INSPECT MG01NRC4) 03044 MCG DOC CNTRL MISC MAN MG05DM5) 03614 MCG OPS PROCEDURE GP MG01OP6) 03744 OPS TRNG MGR. MG03OT7) 03759 U S NUC REG WASHINGTON, DC8) 03796 SCIENTECH
CLEARWTR, FL9) 04698 D E BORTZ EC07R10) 04809 MCG PLANT ENG. UBR. MG05SE11) 05262 J L FREEZE MG011E12) 05606J C MORTON MG01EP13) 08103 WESTINGHOUSE ELECTRIC CO LLC14) 09665 JON H THOMPSON, USNRCDuke EnergyDOCUMENT TRANSMITTAL FORMREFERENCE MCGUIRE NUCLEAR STATIONTECHNICAL SPECIFICATIONS (TS)TECHNICAL SPECIFICATIONS BASES(TSB)RECORD RETENTION
  1. 421734Page 2 of 2Date: 11121/13Document Transmittal
  1. DUK133250072 QA CONDITION

[] Yes

  • NoOTHER ACKNOWLEDGEMENT REQUIRED 0 YesIF QA OR OTHER ACKNOWLEDGEMENT
REQUIRED, PLEASEACKNOWLEDGE RECEIPT BY RETURNING THIS FORM TO:Duke EnergyMcGuireDCRM MGO2DM13225 Hagers Ferry RoadHuntersville, N.C. 28078Rec'd ByDateDOCUMENT NOQACONDREV #/ DATEDISTR CODE12345678910 1112131415TOTALTS 1.1-5 AMEND NO. 269/249TS 3.7.1-3 AMDEND NO. 269/249TSB 3.7.1 ENTIRE SECTIONN/AN/AN/A96 05/16/1396 05/16113129 104113MADM-04BViV1V1ViV3V1V1Vi VlViVi29______________________________________________

-________

I _____________

I _______________

i ____ L ____ I. ____ +/- ____ £ ____ J ____ C ____ +/- ____ .1 ____ -____ C ____ .1 ____ +/- ____ 1 ____ ________REMARKS:

PLEASE UPDATE ACCORDINGLY.

FOL (U-2 ONLY) PLACE IN FRONT OF YOUR TS MANUALTS LOEP REVISION 96S D CAPPSVICE PRESIDENT MCGUIRE NUCLEAR STATIONBY:BCBEAVER MG01RC BCB/BRG)(f7 TSB LOES REVISION 118 October 31, 2013MEMORANDUM To: All McGuire Nuclear Station Technical Specification (TS) and Tech Spec Bases (TSB) Manual Holders

Subject:

McGuire TS and TSB UpdatesAttention:

Facility Operating License (FOL) IncludedThis distribution updates Unit 2 FOL only. Please place the updated copy in the front of your Technical Specification book. Please recycle your old Unit 2 copy. The FOL was updated to reflect Amendment 269/249.REMOVETS ManualINSERTUnit 2 FOLTS LOEP (rev 95)TS 1.1-5 (one page only)TS 3.7.1-3 (one page only)TS Bases ManualLOES (rev 117)TSB 3.7.1 (entire section)Please call me if you have questions.

Bonnie BeaverRegulatory Compliance 875-4180Unit 2 FOL (included in this package)TS LOEP (rev 96)TS 1.1-5 Amend No. 269/249 (one page only)TS 3.7.1-3 Amend No. 269/249 (one page only)LOES (rev 118)TSB 3.7.1 Rev 129 (entire section)

DUKE ENERGY CAROLINAS, LLCDOCKET NO. 50-370MCGUIRE NUCLEAR STATION, UNIT 2RENEWED FACILITY OPERATING LICENSERenewed License No. NPF-171. The U.S. Nuclear Regulatory Commission (Commission),

having previously made thefindings set forth in License No. NPF-17 issued on March 3, 1983, has now found that:A. The application for renewed operating license filed by the Duke EnergyCorporation*

complies with the standards and requirements of the Atomic EnergyAct of 1954, as amended (the Act), and the Commission's regulations set forth in10 CFR Chapter I and all required notifications to other agencies or bodies havebeen duly made;B. Actions have been identified and have been or will be taken with respect to (1)managing the effects of aging during the period of extended operation on thefunctionality of structures and components that have been identified to requirereview under 10 CFR 54.21(a)(1),

and (2) time-limited aging analyses that havebeen identified to require review under 10 CFR 54.21 (c), such that there isreasonable assurance that the activities authorized by the renewed operating license will continue to be conducted in accordance with the current licensing basis, as defined in 10 CFR 54.3, for the McGuire Nuclear Station, Unit 2 (facility or plant), and that any changes made to the plant's current licensing basis in orderto comply with 10 CFR 54.29(a) are in accord with the Act and the Commission's regulations; C. The facility will operate in conformity with the application, as amended, theprovisions of the Act, and the regulations of the Commission; D. There is reasonable assurance:

(i) that the activities authorized by this renewedoperating license can be conducted without endangering the health and safety ofthe public, and (ii) that such activities will be conducted in compliance with theCommission's regulations set forth in 10 CFR Chapter I;E. The licensee is technically qualified to engage in the activities authorized by thisrenewed operating license in accordance with the Commission's regulations setforth in 10 CFR Chapter I;Duke Energy Corporation converted to Duke Power Company LLC on April 3, 2006 and wasre-named Duke Energy Carolinas, LLC as of October 1, 2006. Duke Energy Carolinas, LLCis the owner and operator of McGuire Nuclear Station, Unit 2. References to the "licensee" or "Duke" are to Duke Energy Carolinas, LLC.Renewed License No. NPF-17Amendment No. 225 F. The licensee has satisfied the applicable provisions of 10 CFR Part 140,"Financial Protection Requirements and Indemnity Agreements",

of theCommission's regulations; G. The issuance of this renewed operating license will not be inimical to the commondefense and security or to the health and safety of the public;H. After weighing the environmental,

economic, technical, and other benefits of thefacility against environmental and other costs and considering available alternatives, the issuance of this Renewed Facility Operating License No. NPF-17is in accordance with 10 CFR Part 51, of the Commission's regulations and allapplicable requirements have been satisfied; and,I. The receipt, possession, and use of source, byproduct and special nuclearmaterial as authorized by this renewed operating license will be in accordance with the Commission's regulations in 10 CFR Parts 30, 40 and 70.2. Based on the foregoing findings and the Initial Decisions issued by the Atomic Safetyand Licensing Board dated April 18, 1979, and May 26, 1981, and the Decision of theAtomic Safety and Licensing Appeal Board dated March 30, 1982, regarding thisfacility, Renewed Facility Operating License No. NPF-17 is hereby issued to DukeEnergy Carolinas, LLC to read as follows:A. This renewed operating license applies to the McGuire Nuclear Station, Unit 2, apressurized water reactor and associated equipment (the facility) owned andoperated by Duke Energy Carolinas, LLC. The facility is located on the site inMecklenburg County, North Carolina, on the shore of Lake Normanapproximately 17 miles northwest of Charlotte, North Carolina, and is described in the Updated Final Safety Analysis Report, as supplemented and amended,and in the Environmental Report, as supplemented and amended.B. Subject to the conditions and requirements incorporated herein, the Commission hereby licenses Duke Energy Carolinas, LLC:(1) Pursuant to Section 103 of the Act and 10 CFR Part 50, to possess, use,and operate the facility at the designated location in Mecklenburg County,North Carolina, in accordance with the procedures and limitations set forthin this renewed operating license;(2) Pursuant to the Act and 10 CFR Part 70 to receive, possess and use atany time special nuclear material as reactor fuel, in accordance with thelimitations for storage and amounts required for reactor operation, asdescribed in the Updated Final Safety Analysis Report, as supplemented and amended;(3) Pursuant to the Act and 10 CFR Parts 30, 40 and 70 to receive, possessand use at any time any byproduct, source and special nuclear material assealed neutron sources for reactor startup, sealed sources for reactorinstrumentation and radiation monitoring equipment calibration, and asfission detectors in amounts as required; Renewed License No. NPF-17Amendment No. 225 (4) Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possessand use in amounts as required any byproduct, source or special nuclearmaterial without restriction to chemical or physical form, for sampleanalysis or instrument calibration or associated with radioactive apparatus or components; (5) Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but notseparate, such byproducts and special nuclear materials as may beproduced by the operation of McGuire Nuclear Station, Units 1 and 2; and,(6) Pursuant to the Act and 10 CFR Parts 30 and 40, to receive, possess andprocess for release or transfer such byproduct material as may beproduced by the Duke Training and Technology Center.C. This renewed operating license shall be deemed to contain and is subject to theconditions specified in the Commission's regulations set forth in 10 CFR ChapterI and is subject to all applicable provisions of the Act and to the rules,regulations, and orders of the Commission now or hereafter in effect; and issubject to the additional conditions specified or incorporated below:(1) Maximum Power LevelThe licensee is authorized to operate the facility at a reactor core fullsteady state power level of 3469 megawatts thermal (100%).(2) Technical Specifications The Technical Specifications contained in Appendix A, as revised throughAmendment No. 251, are hereby incorporated into this renewed operating license.

The licensee shall operate the facility in accordance with theTechnical Specifications.

(3) Updated Final Safety Analysis ReportThe Updated Final Safety Analysis Report supplement submitted pursuantto 10 CFR 54.21(d),

as revised on December 16, 2002, describes certainfuture activities to be completed before the period of extended operation.

Duke shall complete these activities no later than March 3, 2023, and shallnotify the NRC in writing when implementation of these activities iscomplete and can be verified by NRC inspection.

The Updated Final Safety Analysis Report supplement as revised onDecember 16, 2002, described above, shall be included in the nextscheduled update to the Updated Final Safety Analysis Report required by10 CFR 50.71(e)(4),

following issuance of this renewed operating license.Until that update is complete, Duke may make changes to the programsdescribed in such supplement without prior Commission

approval, provided that Duke evaluates each such change pursuant to the criteria setforth in 10 CFR 50.59, and otherwise complies with the requirements inthat section.Renewed License No. NPF-17Amendment No. 251 (4) Fire Protection ProgramDuke Energy Carolinas, LLC shall implement and maintain in effect allprovisions of the approved fire protection program as described in theUpdated Final Safety Analysis Report for the facility and as approved inthe SER dated March 1978 and Supplements 2, 5, and 6 dated March1979, April 1981, and February 1983, respectively, and the safetyevaluation dated May 15, 1989, subject to the following provisions:

The licensee may make changes to the approved fire protection program without prior approval of the Commission only if thosechanges would not adversely affect the ability to achieve andmaintain safe shutdown in the event of a fire.(5) Protection of the Environment Before engaging in additional construction or operational activities whichmay result in a significant adverse environmental impact that was notevaluated or that is significantly greater than that evaluated in the FinalEnvironmental Statement dated April 1976, the licensee shall providewritten notification to the Office of Nuclear Reactor Regulation.

(6) Additional Conditions The Additional Conditions contained in Appendix B, as revised throughAmendment No. 249, are hereby incorporated into this renewed operating license.

Duke Energy Carolinas, LLC shall operate the facility inaccordance with the Additional Conditions.

(7) Antitrust Conditions The licensee shall comply with the antitrust conditions delineated inAppendix C of this renewed operating license.(8) Mitigation Strategy License Condition Develop and maintain strategies for addressing large fires and explosions and that include the following key areas:A) Fire fighting response strategy with the following elements:

1. Pre-defined coordinated fire response strategy and guidance2. Assessment of mutual aid fire fighting assets3. Designated staging areas for equipment and materials
4. Command and control5. Training of response personnel B) Operations to mitigate fuel damage considering the following:
1. Protection and use of personnel assets2. Communications
3. Minimizing fire spreadRenewed License No. NPF-17Amendment No. 249 4. Procedures for implementing integrated fire response strategy5. Identification of readily-available pre-staged equipment
6. Training on integrated fire response strategy7. Spent fuel pool mitigation measuresC) Actions to minimize release to include consideration of:1. Water spray scrubbing
2. Dose to onsite responders D. Physical Protection Duke Energy Carolinas, LLC shall fully implement and maintain in effect allprovisions of the Commission-approved physical
security, training andqualification and safeguards contingency plans including amendments madepursuant to provisions of the Miscellaneous Amendments and SearchRequirements revisions to 10 CFR 73.55 (51 FR 27817 and 27822) and to theauthority of 10 CFR 50.90 and 10 CFR 50.54(p).

The combined set of plans,which contains safeguards information protected under 10 CFR 73.21, isentitled:

"Duke Energy Physical Security Plan" submitted by letter datedSeptember 8, 2004, and supplemented on September 30, 2004, October 15,2004, October 21, 2004, and October 27, 2004.Duke Energy Carolinas, LLC shall fully implement and maintain in effect allprovisions of the Commission-approved cyber security plan (CSP), including changes made pursuant to the authority of 10 CFR 50.90 and 10 CFR 50.54(p).

The Duke Energy Carolinas, LLC CSP was approved by License Amendment No. 244.E. Deleted by Amendment No. 215.F. The licensee shall have and maintain financial protection of such type and insuch amounts as the Commission shall require in accordance with Section 170of the Atomic Energy Act of 1954, as amended, to cover public liability claims.G. In accordance with the Commission's direction in its Statement of Policy,Licensing and Regulatory Policy and Procedures for Environmental Protection:

Uranium Fuel Cycle Impacts, October 29, 1982, this renewed operating licenseis subject to the final resolution of the pending litigation involving Table S-3.See, Natural Resources Defense Council v. NRC, No. 74-1586 (D.C. cir. April27,1982).

H. The licensee is authorized to receive from the Oconee Nuclear Station, Units 1,2, and 3, possess, and store irradiated Oconee fuel assemblies containing special nuclear material, enriched to not more than 3.24% by weight U-235subject to the following conditions:

a. Oconee fuel assemblies may not be placed in the McGuire Nuclear Station,Unit 1 and 2, reactors.
b. Irradiated fuel shipped to McGuire Nuclear Station, Units 1 and 2, fromOconee shall have been removed from the Oconee reactor no less than270 days prior to shipment.

Renewed License No. NPF-17Amendment No. 244 c. No more than 300 Oconee irradiated fuel assemblies shall be received forstorage at McGuire Nuclear Station.d. Burnup of Oconee fuel shipped shall be no greater than 36,000 MW daysper metric ton.e. Receipt of irradiated Oconee fuel shall be limited by the use of the NFS-4(NAC-1),

NLI-1/2, TN-8, or TN-8L spent fuel casks.f. The spent fuel pool crane travel shall be restricted by administrative controls to the paths required by Selected Licensee Commitment 16.9.20whenever a spent fuel cask is being handled.g. Oconee fuel assemblies may not be transferred from one McGuire spent fuelpool to the other.3. This renewed operating license is effective as of the date of issuance and shall expireat midnight on March 3, 2043.FOR THE NUCLEAR REGULATORY COMMISSION J.E. Dyer, DirectorOffice of Nuclear Reactor Regulation

Attachment:

1. Appendix A -Technical Specifications
2. Appendix B -Additional Conditions
3. Appendix C -Antitrust Conditions Date of Issuance:

December 5, 2003Renewed License No. NPF-17 APPENDIX BADDITIONAL CONDITIONS FACILITY OPERATING LICENSE NO. NPF-17Duke Energy Carolinas, LLC shall comply with the following conditions on the schedules noted below:Amendment Additional Implementation Number Conditions Date166 The schedule for the performance of new and Within 90 days ofrevised surveillance requirements shall be as the date of thisfollows:

amendment.

For surveillance requirements (SRs) that are new inAmendment No. 166 the first performance is due atthe end of the first surveillance interval that begins atimplementation of Amendment No. 166. For SRsthat existed prior to Amendment No. 166, including SRs with modified acceptance criteria and SRswhose intervals of performance are being extended, the first performance is due at the end of the firstsurveillance interval that begins on the date thesurveillance was last performed prior toimplementation of amendment No. 166. For SRsthat existed prior to Amendment No. 166, whoseintervals of performance are being reduced, the firstreduced surveillance interval begins uponcompletion of the first surveillance performed afterimplementation of Amendment No. 166.Renewed License No. NPF-17Amendment No. 238B-1 APPENDIX BADDITIONAL CONDITIONS FACILITY OPERATING LICENSE NO. NPF-17Duke Energy Carolinas, LLC shall comply with the following conditions on the schedules noted below:Amendment Additional Implementation Number Conditions Date229 Upon implementation of the Amendment adopting See Condition TSTF-448, Revision 3, the determination of control roomenvelope (CRE) unfiltered inleakage as required by SR3.7.9.4, in accordance with TS 5.5.16.c.(i),

theassessment of CRE habitability as required by TS5.5.16.c.(ii),

and the measurement of CRE pressure asrequired by TS 5.5.16.d, shall be considered met.Following implementation:

(a) The first performance of SR 3.7.9.4 in accordance with TS 5.5.16.c.(i),

shall be within the specified Frequency of 6 years, plus the 18 month allowance ofSR 3.0.2, as measured from October 2003, the date ofthe most recent successful tracer gas test, as stated inthe February 19, 2004 letter response to Generic Letter2003-01, or within the next 18 months if the time periodsince the most recent successful tracer gas test isgreater than 6 years.(b) The first performance of the periodic assessment ofCRE habitability, TS 5.5.16.c.(ii),

shall be within 3 years,plus the 9 month allowance of SR 3.0.2 as measuredfrom October 2003, the date of the most recentsuccessful tracer gas test, as stated in the February 19,2004 letter response to Generic Letter 2003-01, orwithin the next 9 months if the time period since themost recent successful tracer gas test is greater than 3years.(c) The first performance of the periodic measurement ofCRE pressure, TS 5.5.16.d, shall be within 18 months,plus the 138 days allowed by SR 3.0.2, as measuredfrom January 2007, the date of the most recentsuccessful pressure measurement test, or within 138days if not performed previously.

Renewed License No. NPF-17Amendment No. 229B-2 APPENDIX BADDITIONAL CONDITIONS FACILITY OPERATING LICENSE NO. NPF-17Duke Energy Carolinas, LLC shall comply with the following conditions on the schedules noted below:Amendment Additional Implementation Number Conditions Date249 The Licensee shall perform an analysis, in the form See Condition of either a topical report or site-specific

analysis, describing how the current P-T limit curves at 34Effective Full Power Years (EFPY) for McGuireUnit 2 and the methodology used to develop thesecurves considered all Reactor Vessel (RV)materials (beltline and non-beltline) and the lowestservice temperature of all ferritic Reactor CoolantPressure Boundary (RCPB) materials, asapplicable, consistent with the requirements of 10CFR Part 50, Appendix G. This analysis shall beprovided to the NRC within one year after NRCapproval of the March 5, 2012 McGuireMeasurement Uncertainty Recapture (MUR)License Amendment Request.Renewed License No. NPF-17Amendment No. 249IB-3 APPENDIX CANTITRUST CONDITIONS Pursuant to an Order by the Atomic Safety and Licensing Board, dated April 23, 1975, theNuclear Regulatory Commission incorporates in Operating License NPF-17 the following antitrust conditions:
a. The licensee makes the commitments contained herein, recognizing that bulkpower supply arrangements between neighboring entities normally tend to servethe public interest.

In addition, where there are net benefits to all participants such arrangements also serve the best interests of each of the participants.

Among the benefits of such transactions are increased electric system reliability, a reduction in the cost of electric power, and minimization of the environmental effects of the production and sale of electricity.

Any particular bulk power supply transaction may afford greater benefits to oneparticipant than to another.

The benefits realized by a small system may beproportionately greater than those realized by a larger system. The relativebenefits to be derived by the parties from a proposed transaction, however,should not be controlling upon a decision with respect to the desirability ofparticipating in the transaction.

Accordingly, the licensee will enter intoproposed bulk power transactions of the types hereinafter described which, onbalance, provide net benefits to the licensee.

There are net benefits in atransaction if the licensee recovers the cost of the transaction (as defined insubparagraph (1)(d) hereof) and there is no demonstrable net detriment to thelicensee arising from the transaction.

(1) As used herein:(a) "Bulk Power" means electric power and any attendant energy,supplied or made available at transmission or sub-transmission voltage by one electric system to another.(b) "Neighboring Entity" means a private or public corporation, agovernmental agency or authority, a municipality, a cooperative, or alawful association of any of the foregoing owning or operating, orproposing to own or operate, facilities for the generation andtransmission of electricity which meets each of the following criteria:

(1) its existing or proposed facilities are economically and technically feasible of interconnection with those of the licensee and (2) with theexception of municipalities, cooperatives, governmental agencies orauthorities, and associations, it is, or upon commencement ofoperations will be, a public utility and subject to regulation with respectto rates and service under the laws of North Carolina or SouthCarolina or under the Federal Power Act; provided,

however, that asto associations, each member of such association is either a publicutility as discussed in this clause (2) orC-1 a municipality, a cooperative or .a governmental agency or authority.

(c) Where the phrase "neighboring entity" is intended to include entitiesengaging or proposing to engage only in the distribution of electricity, this is indicated by adding the phrase "including distribution systems."

(d) "Cost means any appropriate operating and maintenance

expenses, together with all other costs, including a reasonable return on thelicensee's investment, which are reasonably allocable to a transaction.
However, no value shall be included for loss of revenue due to theloss of any wholesale or retail customer as a result of any transaction hereafter described.

(2) (a) The licensee will interconnect and coordinate reserves by means ofthe sale and exchange of emergency and scheduled maintenance bulk power with any neighboring entity(ies),

when there are netbenefits to each party, on terms that will provide for all of thelicensee's properly assignable costs as may be determined by theFederal Energy Regulatory Commission and consistent with such costassignment will allow the other party the fullest possible benefits ofsuch coordination.

(b) Emergency service and/or scheduled maintenance service to beprovided by each party will be furnished to the fullest extent available from the supplying party and desired by the party in need. Thelicensee and each party will provide to the other emergency serviceand/or scheduled maintenance service if and when available from itsown generation and, in accordance with recognized industry

practice, from generation of other to the extent it can do so without impairing service to its customers, including other electric systems to whom ithas firm commitments.

(c) Each party to a reserve coordination arrangement will establish itsown reserve criteria, but in no event shall the minimum installed reserve on each system be less than 15%, calculated as a percentage of estimated peak load responsibility.

Either party, if it has, or hasfirmly planned, installed reserves in excess of the amount called for byits own reserve criterion, will offer any such excess as may in fact beavailable at the time for which it is sought and for such period as theselling party shall determine for purchase in accordance withreasonable industry practice by the other party to meet such otherparty's own reserve requirements.

The parties will provide suchamounts of spinning reserve as may be adequate to avoid theimposition of unreasonable demands on the other part(ies) in meetingthe normal contingencies of operating its (their) system(s).

However,in no circumstances shall such spinning reserve requirement exceedthe installed reserve requirement.

(d) Interconnections will nof'6e limited to low voltages when highervoltages areC-2 available from the licensee's installed facilities in the area whereinterconnection is desired and when the proposed arrangement isfound to be technically and economically feasible.

(e) Interconnection and reserve coordination agreements will not embodyprovisions which impose limitations upon the use or resale of powerand energy sold or exchanged pursuant to the agreement.

Further,such arrangements will not prohibit the participants from entering intoother interconnection and coordination arrangements, but may includeappropriate provisions to assure that (i) the licensee receivesadequate notice of such additional interconnection or coordination, (ii)the parties will jointly consider and agree upon such measures, if any,as are reasonably necessary to protect the reliability of theinterconnected systems and to prevent undue burdens from beingimposed on any system, and (iii) the licensee will be fullycompensated for its costs. Reasonable industry practice asdeveloped in the area from time to time will satisfy this provision.

(3) The licensee currently has on file, and may hereafter file, with the FederalEnergy Regulatory Commission contracts with neighboring entity(ies) providing for the sale and exchange of short-term power and energy, limitedterm power and energy, economy energy, non- displacement energy, andemergency capacity and energy. The Licensee will enter into contracts providing for the same or for like transactions with any neighboring entity onterms which enable the licensee to recover the full costs allocable to suchtransaction.

(4) The licensee currently sells capacity and energy in bulk on a fullrequirements basis to several entities engaging in the distribution of electricpower at retail. In addition, the licensee supplies electricity directly toultimate users in a number of municipalities.

Should any such entity(ies) ormunicipality(ies) desire to become a neighboring entity as defined insubparagraph (1)(b) hereof (either alone or through combination withothers),

the licensee will assist in facilitating the necessary transition throughthe sale of partial requirements firm power and energy to the extent that,except for such transition, the licensee would otherwise be supplying firmpower and energy. The provision of such firm partial requirements serviceshall be under such rates, terms and conditions as shall be found by theFederal Energy Regulatory Commission to provide for the recovery of thelicensee's cost. The licensee will sell capacity and energy in bulk on a fullrequirements basis to any municipality currently served by the licensee whensuch municipality lawfully engages in the distribution of electric power atretail.(5) (a) The licensee will facilitate the exchange of electric power in bulk inwholesale transactions over its transmission facilities (1) between oramong two or more neighboring entities including distribution systems with which it is interconnected or may be interconnected inthe future, and (2) between any such entity(ies) and any other electricsystem engaging in bulk power supply between whose facilities thelicensee's transmission C-3 lines and other transmission lines would form a continuous electric path,provided that permission to utilize such other transmission lines has beenobtained.

Such transaction shall be undertaken provided that theparticular transaction reasonably can be accommodated by the licensee's transmission system from a functional and technical standpoint and doesnot constitute the wheeling of power to a retail customer.

Suchtransmission shall be on terms that fully compensate the licensee for itscost. Any entity(ies) requesting such transmission arrangements shallgive reasonable notice of its (their) schedule and requirements.

(b) The licensee will include in its planning and construction programsufficient transmission capacity as required for the transactions referredto in subparagraph (a) of this paragraph, provided that (1) the neighboring entity(ies) gives the licensee sufficient advance notice as may benecessary reasonably to accommodate its (their) requirements from afunctional and technical standpoint and (2) that such entity(ies) fullycompensate the licensee for its cost. In carrying out this subparagraph (b), however, the licensee shall not be required to construct or addtransmission facilities which (a) will be of no demonstrable present orfuture benefit to the licensee, or (b) which could be constructed by therequesting entity(ies) without duplicating any portion of the licensee's existing transmission lines, or (c) which would jeopardize the licensee's ability to finance or construct on reasonable terms facilities needed tomeet its own anticipated system requirements.

Where regulatory orenvironmental approvals are required for the construction or addition oftransmission facilities needed for the transactions referred to insubparagraph (a) of this paragraph it shall be the responsibility of theentity(ies) seeking the transaction to participate in obtaining suchapprovals, including sharing in the cost thereof.(6) To increase the possibility of achieving greater reliability and economy ofelectric generation and transmission facilities, the licensee will discuss loadprojections and system development plans with any neighboring entity(ies).

(7) When the licensee's plans for future nuclear generating units (for whichapplication will hereafter be made to the Nuclear Regulatory commission) have reached the stage of serious planning, but before firm decisions havebeen made as to the size and desired completion date of the proposednuclear units, the licensee will notify all neighboring entities including distribution systems with peak loads smaller than the licensee's that thelicensee plans to construct such nuclear units. Neither the timing nor theinformation provided need be such as to jeopardize obtaining the requiredsite at the lowest possible cost.The foregoing commitments shall be implemented in a manner consistent with the provisions of the Federal Power Act and all other lawful local, stateand Federal regulation and authority.

Nothing in these commitments isintended to determine in advance the resolution of issues which are properlyraised at the Federal Energy Regulatory Commission concerning suchcommitments, C-4 including allocation of costs or the rates to be charged.

The licensee willnegotiate (including the execution of a contingent statement of intent) withrespect to the foregoing commitments with any neighboring entity including distribution systems where applicable engaging in or proposing to engage inbulk power supply transactions, but the licensee shall not be required toenter into any final arrangement prior to resolution of any substantial questions as to the lawful authority of an entity to engage in the transactions.

In addition, the licensee shall not be obligated to enter into a given bulkpower supply transaction if: (1) to do so would violate, or incapacitate it fromperforming, and existing lawful contracts it has with a third party; (2) there iscontemporaneously available to it a competing or alternate arrangement which affords it greater benefits which would be mutually exclusive of sucharrangement; (3) to do so would adversely affect its system operations or thereliability of power supply to its customers, or (4) if to do so would jeopardize the licensee's ability to finance or construct on reasonable terms facilities needed to meet its own anticipated system requirements.

C-5 McGuire Nuclear Station Technical Specifications LOEPPage NumberAmendment iviiiiv1.1-11.1-21.1-31.1-41.1-51.1-61.1-71.2-11.2-21.2-31.3-11.3-21.3-31.3-41.3-51.3-61.3-71.3-81.3-91.3-101.3-111.3-121.3-131.4-11.4-21.4-31.4-42.0-1243/224237/219184/166184/166184/166266/246237/219194/175269/249261/241194/175184/166184/166184/166184/166184/166184/166184/166184/166184/166184/166184/166184/166184/166184/166184/166184/166184/166184/166184/166184/166219/201Revision Date7/26/073/1/079/30/989/30/989/30/986/25/123/1/079/18/005/16/133/29/119/18/009/30/989/30/989/30/989/30/989/30/989/30/989/30/989/30/989/30/989/30/989/30/989/30/989/30/989/30/989/30/989/30/989/30/989/30/989/30/989/30/981/14/04McGuire Units 1 and 2Page IRevision 96 Page NumberAmendment Revision Date3.0-13.0-23.0-33.0-43.0-53.1.1-13.1.2-13.1.2-23.1.3-13.1.3-23.1.3-33.1.4-13.1.4-23.1.4-33.1.4-43.1.5-13.1.5-23.1.6-13.1.6-23.1.6-33.1.7-13.1.7-23.1.8-13.1.8-23.2.1-13.2.1-23.2.1-33.2.1-43.2.1-53.2.2-13.2.2-23.2.2-33.2.2-43.2.3-1238/220221/203238/220205/186221/203261/241184/166261/241184/166184/166184/166184/166184/166261/241261/241184/166261/241184/166184/166261/241184/166184/166184/166261/241184/166184/166261/241261/241261/241184/166184/166261/241261/241261/2413/29/074/29/043/29/078/12/024/29/043/29/119/30/983/29/119/30/989/30/989/30/989/30/989/30/983/29/113/29/119/30/983/29/119/30/989/30/983/29/119/30/989/30/989/30/983/29/119/30/989/30/983/29/113/29/113/29/119/30/989/30/983/29/113/29/113/29/11McGuire Units 1 and 2Page 2Revision 96 Page Number3.2.4-13.2.4-23.2.4-33.2.4-43.3.1-13.3.1-23.3.1-33.3.1-43.3.1-53.3.1-63.3.1-73.3.1-83.3.1-93.3.1-103.3.1-113.3.1-123.3.1-133.3.1-143.3.1-153.3.1-163.3.1-173.3.1-183.3.1-193.3.1-203.3.2-13.3.2-23.3.2-33.3.2-43.3.2-53.3.2-63.3.2-73.3.2-83.3.2-93.3.2-10McGuire Units 1 and 2Amendment 184/166184/166184/166261/241184/166248/228248/228216/197250/230248/228248/228184/166261/241261/241261/241261/241261/241257/237257/237257/237268/248219/201219/201184/166184/166250/230248/228248/228248/228198/179198/179261/241261/241265/245Page 3Revision Date9/30/989/30/989/30/983/29/119/30/983/9/093/9/097/29/033/9/093/9/093/9/099/30/983/29/113/29/113/29/113/29/113/29/118/2/108/2/108/2/1010/1/121/14/041/14/049/30/989/30/983/9/093/9/093/9/093/9/094/12/014/12/013/29/113/29/119/1 2/11Revision 96 Page NumberAmendment Revision Date3.3.2-113.3.2-123.3.2-133.3.2-143.3.2-153.3.3-13.3.3-23.3.3-33.3.3-43.3.4-13.3.4-23.3.4-33.3.5-13.3.5-23.3.6-13.4.1-13.4.1-23.4.1-33.4.1-43.4.2-13.4.3-13.4.3-23.4.3-33.4.3-43.4.3-53.4.3-63.4.3-73.4.3-83.4.4-13.4.5-13.4.5-23.4.5-33.4.6-13.4.6-2265/245265/245265/245265/245265/245221/203227/209261/241227/209221/203261/241184/166184/166261/241Not Used -243/224219/201219/201261/241219/201184/166214/195261/241214/195214/195214/195214/195214/195214/195261/241216/197216/197261/241216/197261/2419/12/119/12/119/12/119/12/119/12/114/29/044/4/053/29/114/4/054/29/043/29/119/30/989/30/983/29/117/26/071/14/041/14/043/29/111/14/049/30/987/3/033/29/117/3/037/3/037/3/037/3/037/3/037/3/033/29/117/29/037/29/033/29/117/29/033/29/11McGuire Units 1 and 2Page 4Revision 96 Page NumberAmendment Revision Date3.4.7-13.4.7-23.4.7-33.4.8-13.4.8-23.4.9-13.4.9-23.4.10-13.4.10-23.4-11-13.4.11-23.4-11-33.4.11-43.4.12-13.4.12-23.4.12-33.4.12-43.4.12-53.4.12-63.4.13-13.4.13-23.4.14-13.4.14-23.4.14-33.4.14-43.4.15-13.4.15-23.4.15-33.4.15-43.4.16-13.4.16-23.4.17-13.4.18-13.4.18-2216/197216/197261/241216/197261/241184/166261/241184/166184/166221/203184/166184/166261/241184/166221/203214/195214/195261/241261/241237/219261/241184/166184/166261/241261/241235/217235/217235/217261/241266/246266/246261/241237/219237/2197/29/037/29/033/29/117/29/033/29/119/30/983/29/119/30/989/30/984/29/049/30/989/30/983/29/119/30/984/29/047/3/037/3/033/29/113/29/113/1/073/29/119/30/989/30/983/29/113/29/119/30/069/30/069/30/063/29/116/25/126/25/123/29/113/1/073/1/07McGuire Units 1 and 2Page 5Revision 96 Page NumberAmendment Revision Date3.5.1-1 218/200 12/23/033.5.1-2 261/241 3/29/113.5.2-1 184/166 9/30/983.5.2-2 261/241 3/29/113.5.2-3 261/241 3/29/113.5.3-1 221/203 4/29/043.5.3-2 184/166 9/30/983.5.4-1 184/166 9/30/983.5.4-2 9/12/11 9/12/113.5.5-1 184/166 9/30/983.5.5-2 261/241 3/29/113.6.1-1 207/188 9/4/023.6.1-2 207/188 9/4/023.6.2-1 184/166 9/30/983.6.2-2 184/166 9/30/983.6.2-3 184/166 9/30/983.6.2-4 184/166 9/30/983.6.2-5 261/241 3/29/113.6.3-1 243/224 7/26/073.6.3-2 184/166 9/30/983.6.3-3 184/166 9/30/983.6.3-4 184/166 9/30/983.6.3-5 261/241 3/29/113.6.3-6 261/241 3/29/113.6.3-7 207/188 9/4/023.6.4-1 261/241 3/29/113.6.5-1 184/166 9/30/983.6.5-2 261/241 3/29/113.6.6-1 9/12/11 9/12/113.6.6-2 9/12/11 9/12/113.6.7-1 Not Used -227/209 4/4/053.6.8-1 221/203 4/29/043.6.8-2 261/241 3/29/113.6.9-1 184/166 9/30/98McGuire Units 1 and 2Page 6Revision 96 Page NumberAmendment Revision Date3.6.9-23.6.10-13.6.10-23.6.11-13.6.11-23.6.12-13.6.12-23.6.12-33.6.13-13.6.13-23.6.13-33.6.14-13.6.14-23.6.14-33.6.15-13.6.15-23.6.16-13.6.16-23.7.1-13.7.1-23.7.1-33.7.2-13.7.2-23.7.3-13.7.3-23.7.4-13.7.4-23.7.5-13.7.5-23.7.5-33.7.5-43.7.6-13.7.6-23.7.7-1261/241184/166261/241261/241261/241261/241261/241261/241256/236261/241261/241228/210270/250261/241184/166261/241261/241261/241184/166184/166269/249184/166184/166184/166184/166221/203261/241221/203184/166261/241261/241184/166261/241184/1663/29/119/30/983/29/113/29/113/29/113/29/113/29/113/29/116/28/103/29/113/29/114/5/057/16/133/29/119/30/983/29/113/29/113/29/119/30/989/30/985/16/139/30/989/30/989/30/989/30/984/29/043/29/114/29/049/30/983/29/113/29/119/30/983/29/119/30/98McGuire Units 1 and 2Page 7Revision 96 Page NumberAmendment Revision Date3.7.7-23.7.8-13.7.8-23.7.9-13.7.9-23.7.9-33.7.10-13.7.10-23.7.11-13.7.11-23.7.12-13.7.12-23.7.13-13.7.14-13.7.15-13.7.15-23.7.15-33.7.15-43.7.15-53.7.15-63.7.15-73.7.15-83.7.15-93.7.15-10 3.7.15-11 3.7.15-12 3.7.15-13 3.7.15-14 3.7.15-15 3.7.15-16 3.7.15-17 3.7.15-18 3.7.15-19 3.7.15-20 261/241261/241261/241249/229249/229261/241184/166261/241229/211261/241261/241261/241261/241261/241225/207225/207225/207225/207225/207225/207225/207225/207225/207225/207225/207225/207225/207225/207225/207225/207225/207225/207225/207225/2073/29/113/29/113/29/111/30/091/30/093/29/119/30/983/29/116/2/053/29/113/29/113/29/113/29/113/29/113/17/053/17/053/17/053/17/053/17/053/17/053/17/053/17/053/17/053/17/053/17/053/17/053/17/053/17/053/17/053/17/053/17/053/17/053/17/053/17/05McGuire Units 1 and 2Page 8Revision 96 Page NumberAmendment Revision Date3.7.15-21 3.7.15-22 3.7.15-23 3.7.15-24 3.7.15-25 3.7.15-26 3.7.15-27 3.7.15-28 3.7.15-29 3.7.15-30 3.7.15-31 3.7.15-32 3.7.16-13.8.1-13.8.1-23.8.1-33.8.1-43.8.1-53.8.1-63.8.1-73.8.1-83.8.1-93.8.1-103.8.1-113.8.1-123.8.1-133.8.1-143.8.1-153.8.2-13.8.2-23.8.2-33.8.3-13.8.3-23.8.3-3225/207225/207225/207225/207225/207225/207225/207225/207225/207225/207225/207225/207261/241221/203184/166241/-184/166261/241261/241261/241261/241261/241261/241261/241261/241261/241261/241261/241184/166216/197184/166184/166267/247261/2413/17/053/17/053/17/053/17/053/17/053/17/053/17/053/17/053/17/053/17/053/17/053/17/053/29/114/29/049/30/986/8/079/30/983/29/113/29/113/29/113/29/113/29/113/29/113/29/113/29/113/29/113/29/113/29/119/30/987/29/039/30/989/30/989/29/123/29/11McGuire Units 1 and 2Page 9Revision 96 Page NumberAmendment Revision Date3.8.4-1 184/166 9/30/983.8.4-2 261/241 3/29/113.8.4-3 261/241 3/29/113.8.4-4 260/240 12/20/103.8.5-1 184/166 9/30/983.8.5-2 216/197 7/29/033.8.6-1 184/166 9/30/983.8.6-2 261/241 3/29/113.8.6-3 261/241 3/29/113.8.6-4 184/166 9/30/983.8.7-1 261/241 3/29/113.8.8-1 184/166 9/30/983.8.8-2 261/241 3/29/113.8.9-1 184/166 9/30/983.8.9-2 261/241 3/29/113.8.10-1 216/197 7/29/033.8.10-2 261/241 3/29/113.9.1-1 261/241 3/29/113.9.2-1 261/241 3/29/113.9.3-1 216/197 7/29/033.9.3-2 261/241 3/29/113.9.4-1 236/218 12/22/063.9.4-2 261/241 3/29/113.9.5-1 216/197 7/29/033.9.5-2 261/241 3/29/113.9.6-1 216/197 7/29/033.9.6-2 261/241 3/29/113.9.7-1 261/241 3/29/114.0.1 225/207 3/17/054.0.2 225/207 3/17/055.1-1 213/194 6/6/035.2-1 239/221 04/12/075.2-2 253/233 9/21/095.3-1 213/194 6/6/03McGuire Units 1 and 2Page 10Revision 96 Page Number5.4-15.5-15.5-25.5-35.5-45.5-55.5-65.5-75.5-85.5-95.5-105.5-115.5-125.5-135.5-145.5-155.5-165.6-15.6-25.6-35.6-45.6-55.7-15.7-2Amendment 184/166244/193212/193184/166184/166223/205252/232237/219237/219237/219237/219237/219237/219237/219249/229261/241261/241226/208226/208226/208230/212237/219213/194184/166Revision Date9/30/982/13/085/8/039/30/989/30/988/5/048/17/093/1/073/1/073/1/073/1/073/1/073/1/073/1/071/30/093/29/113/29/113/1/073/1/073/1/078/23/053/1/076/6/039/30/98McGuire Units 1 and 2Page I11Revision 96 Definitions 1.11.1 Definitions (continued)

QUADRANT POWER TILTRATIO (QPTR)RATED THERMAL POWER(RTP)REACTOR TRIPSYSTEM (RTS) RESPONSETIMESHUTDOWN MARGIN (SDM)QPTR shall be the ratio of the maximum upper excoredetector calibrated output to the average of the upper excoredetector calibrated

outputs, or the ratio of the maximum lowerexcore detector calibrated output to the average of the lowerexcore detector calibrated
outputs, whichever is greater.RTP shall be a total reactor core heat transfer rate to thereactor coolant of 3411 MWt.*The RTS RESPONSE TIME shall be that time interval fromwhen the monitored parameter exceeds its RTS trip setpointat the channel sensor until loss of stationary gripper coilvoltage.

The response time may be measured by means ofany series of sequential, overlapping, or total steps so thatthe entire response time is measured.

In lieu ofmeasurement, response time may be verified for selectedcomponents provided that the components and themethodology for verification have been previously reviewedand approved by the NRC.SDM shall be the instantaneous amount of reactivity by whichthe reactor is subcritical or would be subcritical from its presentcondition assuming:

a. All rod cluster control assemblies (RCCAs) are fullyinserted except for the single RCCA of highest reactivity worth, which is assumed to be fully withdrawn.

However,with all RCCAs verified fully inserted by two independent means, it is not necessary to account for a stuck RCCA inthe SDM calculation.

With any RCCA not capable of beingfully inserted, the reactivity worth of the RCCA must beaccounted for in the determination of SDM; andb. In MODES 1 and 2, the fuel and moderator temperatures are changed to the nominal zero power design level.A SLAVE RELAY TEST shall consist of energizing each slaverelay and verifying the OPERABILITY of each slave relay. TheSLAVE RELAY TEST shall include, as a minimum, a continuity check of associated testable actuation devices.ISLAVE RELAY TEST* Following implementation of MUR on the respective Unit, the value of RTP shall be3469 MWt.McGuire Units 1 and 21.1-5Amendment Nos. 269/249 MSSVs3.7.1Table 3.7.1-1 (page 1 of 1)OPERABLE Main Steam Safety Valves versusMaximum Allowable Power Range Neutron Flux HighSetpoints in Percent of RATED THERMAL POWERMINIMUM NUMBER OFMSSVs PER STEAMGENERATOR REQUIREDOPERABLEMAXIMUM ALLOWABLE POWER RANGE NEUTRONFLUXHIGH SETPOINTS

(% RTP)4 < 573 < 382 <19Table 3.7.1-2 (page 1 of 1)Main Steam Safety Valve Lift SettingsVALVE NUMBERLIFT SETTING(psig +/- 3%)STEAM GENERATOR A B C DSV-20 SV-14 SV-8 SV-2 1170SV-21 SV-15 SV-9 SV-3 1190SV-22 SV-16 SV-10 SV-4 1205SV-23 SV-17 SV-1 1 SV-5 1220SV-24 SV-18 SV-12 SV-6 1225McGuire Units 1 and 23.7.1-3Amendment Nos. 269/249 McGuire Nuclear Station Technical Specification BasesLOESTS Bases are revised by sectionPage Number Revision Revision DateBASES(Revised per section)i Revision 87 8/15/07ii Revision 87 8/15/07iii Revision 87 8/15/07B 2.1.1 Revision 51 01/14/04B 2.1.2 Revision 109 9/20/10B 3.0 Revision 81 3/29/07B 3.1.1 Revision 115 3/29/11B 3.1.2 Revision 115 3/29/11B 3.1.3 Revision 10 9/22/00B 3.1.4 Revision 115 3/29/11B 3.1.5 Revision 115 3/29/11B 3.1.6 Revision 115 3/29/11B 3.1.7 Revision 58 06/23/04B 3.1.8 Revision 115 3/29/11B 3.2.1 Revision 115 3/29/11B 3.2.2 Revision 115 3/29/11B 3.2.3 Revision 115 3/29/11B 3.2.4 Revision 115 3/29/11B 3.3.1 Revision 124 10/1/12B 3.3.2 Revision 122 10/25/12B 3.3.3 Revision 122 10/25/12B 3.3.4 Revision 115 3/29/11B 3.3.5 Revision 115 3/29/11B 3.3.6 Not Used -Revision 87 6/29/06B 3.4.1 Revision 115 3/29/11B 3.4.2 Revision 0 9/30/98B 3.4.3 Revision 115 3/29/11B 3.4.4 Revision 115 3/29/11B 3.4.5 Revision 115 3/29/11McGuire Units 1 and 2 Page 1 Revisioin118 Page NumberAmendment B 3.4.6B 3.4.7B 3.4.8B 3.4.9B 3.4.10B 3.4.11B 3.4.12B 3.4.13B 3.4.14B 3.4.15B 3.4.16B 3.4.17B 3.4.18B 3.5.1B 3.5.2B 3.5.3B 3.5.4B 3.5.5B 3.6.1B 3.6.2B 3.6.3B 3.6.4B 3.6.5B 3.6.6B 3.6.7B 3.6.8B 3.6.9B 3.6.10B 3.6.11B 3.6.12B 3.6.13B 3.6.14B 3.6.15B 3.6.16Revision 115Revision 115Revision 115Revision 115Revision 102Revision 115Revision 115Revision 126Revision 115Revision 115Revision 121Revision 115Revision 86Revision 115Revision 116Revision 57Revision 122Revision 115Revision 53Revision 115Revision 115Revision 115Revision 115Revision 122Not Used -Revision 63Revision 115Revision 115Revision 120Revision 122Revision 115Revision 115Revision 115Revision 125Revision 115Revision Date3/29/113/29/113/29/113/29/118/17/093/29/113/29/115/1/133/29/113/29/118/5/093/29/116/25/073/29/118/18/114/29/0410/25/123/29/112/17/043/29/113/29/113/29/113/29/1110/25/124/4/053/29/113/29/114/26/1210/25/123/29/113/29/113/29/1110/19/123/29/11McGuire Units 1 and 2Page 2Revision 118 Page NumberAmendment Revision DateB 3.7.1 Revision 129 10/24/13B 3.7.2 Revision 105 2/22/10B 3.7.3 Revision 102 8/17/09B 3.7.4 Revision 115 3/29/11B 3.7.5 Revision 115 3/29/11B 3.7.6 Revision 127 8/2/13B 3.7.7 Revision 115 3/29/11B 3.7.8 Revision 128 10/2/13B 3.7.9 Revision 120 4/26/12B 3.7.10 Revision 115 3/29/11B 3.7.11 Revision 115 3/29/11B 3.7.12 Revision 115 3/29/11B 3.7.13 Revision 115 3/29/11B 3.7.14 Revision 115 3/29/11B 3.7.15 Revision 66 6/30/05B 3.7.16 Revision 115 3/29/11B 3.8.1 Revision 115 3/29/11B 3.8.2 Revision 92 1/28/08B 3.8.3 Revision 123 9/29/12B 3.8.4 Revision 115 3/29/11B 3.8.5 Revision 41 7/29/03B 3.8.6 Revision 115 3/29/11B 3.8.7 Revision 115 3/29/11B 3.8.8 Revision 115 3/29/11B 3.8.9 Revision 115 3/29/11B 3.8.10 Revision 115 3/29/11B 3.9.1 Revision 115 3/29/11B 3.9.2 Revision 115 3/29/11B 3.9.3 Revision 115 3/29/11B 3.9.4 Revision 115 3/29/11B 3.9.5 Revision 115 3/29/11B 3.9.6 Revision 115 3/29/11B 3.9.7 Revision 115 3/29/11McGuire Units 1 and 2P ag 3-Revision 118 MSSVsB 3.7.1B 3.7 PLANT SYSTEMSB 3.7.1 Main Steam Safety Valves (MSSVs)BASESBACKGROUND The primary purpose of the MSSVs is to provide overpressure protection for the secondary system. The MSSVs also provide protection againstoverpressurizing the reactor coolant pressure boundary (RCPB) byproviding a heat sink for the removal of energy from the Reactor CoolantSystem (RCS) if the preferred heat sink, provided by the Condenser andCirculating Water System, is not available.

Five MSSVs are located on each main steam header, outsidecontainment, upstream of the main steam isolation valves, as described in the UFSAR, Section 10.3.1 (Ref. 1). The MSSV capacity criteria is110% of rated steam flow at 110% of the steam generator designpressure.

This meets the requirements of the ASME Code,Section III(Ref. 2). The MSSV design includes staggered setpoints, according toTable 3.7.1-2 in the accompanying LCO, so that only the needed valveswill actuate.

Each valve is orificed to a size of either 12.174 or 16.0square inches. Staggered setpoints reduce the potential for valvechattering that is due to steam pressure insufficient to fully open all valvesfollowing a turbine reactor trip.APPLICABLE SAFETY ANALYSESThe design basis for the MSSVs comes from Reference 2 and itspurpose is to limit the secondary system pressure to 5 110% of designpressure when passing 100% of design steam flow. This design basis issufficient to cope with any anticipated operational occurrence (AOO) oraccident considered in the Design Basis Accident (DBA) and transient analysis.

The events that challenge the relieving capacity of the MSSVs, and thusRCS pressure, are those characterized as decreased heat removalevents, which are presented in the UFSAR, Section 15.2 (Ref. 3). Ofthese, the full power turbine trip without steam dump is the limiting AOO.The transient response for turbine trip without a direct reactor trippresents no hazard to the integrity of the RCS or the Main Steam System.The reactor is tripped on high pressurizer pressure in the peak primarypressure case. In this case, the pressurizer safety valves open, and RCSpressure remains below 110% of the design value. The MSSVs alsoopen to limit the secondary steam pressure.

McGuire Units 1 and 2B 3.7. 1-1Revision No. 129 MSSVsB 3.7.1BASESAPPLICABLE SAFETY ANALYSES (continued)

For the peak secondary pressure case, the reactor is tripped onovertemperature AT. Pressurizer relief valves and MSSVs areactivated and prevent overpressurization in the primary andsecondary systems.The MSSVs satisfy Criterion 3 of 10 CFR 50.36 (Ref. 4).LCO The accident analysis assumes five MSSVs per steam generator to provide overpressure protection for design basis transients occurring at 3479 MWt. An MSSV will be considered inoperable ifit fails to open on demand. The LCO requires that five MSSVs beOPERABLE in compliance with Reference 2, even though this isnot a requirement of the DBA analysis.

This is because operation with less than the full number of MSSVs requires limitations onallowable THERMAL POWER (to meet ASME Coderequirements).

These limitations are according to Table 3.7.1-1 inthe accompanying LCO, and Required Action A.1 and A.2.The OPERABILITY of the MSSVs is defined as the ability to openwithin the setpoint tolerances, relieve steam generator overpressure, and reseat when pressure has been reduced.

TheOPERABILITY of the MSSVs is determined by periodicsurveillance testing in accordance with the Inservice TestingProgram.The lift settings, according to Table 3.7.1-2 in the accompanying LCO, correspond to ambient conditions of the valve at nominaloperating temperature and pressure.

This LCO provides assurance that the MSSVs will perform theirdesigned safety functions to mitigate the consequences ofaccidents that could result in a challenge to the RCPB.APPLICABILITY In MODE 1, the number of MSSVs per steam generator required to beOPERABLE must be according to Table 3.7.1-1 in the accompanying LCO. In MODES 2 and 3, only two MSSVs per steam generator arerequired to be OPERABLE.

In MODES 4 and 5, there are no credible transients requiring the MSSVs.The steam generators are not normally used for heat removal inMODES 5 and 6, and thus cannot be overpressurized; there is norequirement for the MSSVs to be OPERABLE in these MODES.McGuire Units I and 2B 3.7.1-2Revision No. 129 MSSVsB 3.7.1BASESACTIONS The ACTIONS table is modified by a Note indicating that separateCondition entry is allowed for each MSSV.A.1 and A.2With one or more MSSVs inoperable, reduce power so that theavailable MSSV relieving capacity meets Reference 2 requirements for the applicable THERMAL POWER.Operation with less than all five MSSVs OPERABLE for each steamgenerator is permissible, if THERMAL POWER is proportionally limited to the relief capacity of the remaining MSSVs. This isaccomplished by restricting THERMAL POWER so that the energytransfer to the most limiting steam generator is not greater than theavailable relief capacity in that steam generator.

For example, if oneMSSV is inoperable in one steam generator, the relief capacity ofthat steam generator is reduced by approximately 20%. To offsetthis reduction in relief capacity, energy transfer to that steamgenerator must be similarly reduced.

This is accomplished byreducing THERMAL POWER by the necessary amount toconservatively limit the energy transfer to all steam generators, consistent with the relief capacity of the most limiting steamgenerator.

The maximum power level specified for the power range neutronflux high trip setpoint with inoperable MSSVs must ensure thatpower is limited to less than the heat removal capacity of theremaining OPERABLE MSSVs. The reduced high flux trip setpointalso ensures that the reactor trip occurs early enough in the loss ofload/turbine trip event to limit primary to secondary heat transferand preclude overpressurization of the primary and secondary systems.

To calculate this power level, the governing equation isthe relationship q = m Ah, where q is the heat input from theprimary side, m is the steam flow rate and Ah is the heat ofvaporization at the steam relief pressure (assuming no subcooled feedwater).

The algorithm use is consistent with therecommendations of the Westinghouse Nuclear Safety AdvisoryLetter, NSAL-94-001, dated January 20, 1994 (Ref. 6).Additionally, the calculated values are reduced by 9% to accountfor instrument and channel uncertainties.

The allowed Completion Time of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> provides an acceptable time to reach the required power level from full power operation without allowing the plant to remain in an unacceptable condition foran extended period of time and provides sufficient time to reduce thetrip setpoints.

The adjustment of the trip setpoints is a sensitive operation that may inadvertently trip the Reactor Protection System.McGuire Units 1 and 2B 3.7.1-3Revision No. 129 MSSVsB 3.7.1BASESACTIONS (continued)

B.1 and B.2If the MSSVs cannot be restored to OPERABLE status within theassociated Completion Time, or if one or more steam generators haveless than two MSSVs OPERABLE, the unit must be placed in aMODE in which the LCO does not apply. To achieve this status, theunit must be placed in at least MODE 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and inMODE 4 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. The allowed Completion Times arereasonable, based on operating experience, to reach the required unitconditions from full power conditions in an orderly manner and withoutchallenging unit systems.SURVEILLANCE SR 3.7.1.1REQUIREMENTS This SR verifies the OPERABILITY of the MSSVs by theverification of each MSSV lift setpoint in accordance with theInservice Testing Program.

The ASME OM Code (Ref. 5) requiresthat safety and relief valve tests be performed.

According toReference 5, the following tests are required:

a. Visual examination;
b. Seat tightness determination;
c. Setpoint pressure determination (lift setting);
d. Compliance with seat tightness criteria; ande. Verification of the balancing device integrity on balanced valves.The ASME Standard requires that all valves be tested every5 years, and a minimum of 20% of the valves be tested every24 months. The ASME OM Code specifies the activities andfrequencies necessary to satisfy the requirements.

Table 3.7.1-2allows a + 3% setpoint tolerance for OPERABILITY;

however, thevalves are reset to + 1% during the Surveillance to allow for drift.This SR is modified by a Note that allows entry into and operation inMODE 3 prior to performing the SR. The MSSVs may be eitherbench tested or tested in situ at hot conditions using an assist deviceto simulate lift pressure.

If the MSSVs are not tested at hotconditions, the lift setting pressure shall be corrected to ambientconditions of the valve at operating temperature and pressure.

McGuire Units 1 and 2B 3.7.1-4Revision No. 129 MSSVsB 3.7.1BASESREFERENCES

1. UFSAR, Section 10.3.1.2. ASME, Boiler and Pressure Vessel Code,Section III,Article NC-7000, Class 2 Components.
3. UFSAR, Section 15.2.4. 10 CFR 50.36, Technical Specifications, (c)(2)(ii).
5. ASME Code for Operation and Maintenance of NuclearPower Plants.6. Westinghouse Nuclear Safety Advisory Letter, NSAL-94-001, Dated January 20, 1994.McGuire Units 1 and 2B 3.7.1-5Revision No. 129
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