ML15223A783

NRC000228 - Indian Point Unit 2 Technical Specifications 3.1.4

ML15223A783
Person / Time
Site:	Indian Point
Issue date:	08/10/2015
From:	NRC/OGC
To:
SECY RAS
References
RAS 28148, ASLBP 07-858-03-LR-BD01, 50-247-LR, 50-286-LR
Download: ML15223A783 (7)

Text

-I., -oNUCLA UNITED STATESNUCLEAR REGULATORY COMMISSIONWASHINGTON, D.C. 20555-0001*;sENTERGY NUCLEAR INDIAN POINT 2, LLCAND ENTERGY NUCLEAR OPERATIONS, INC.DOCKET NO. 50-247INDIAN POINT NUCLEAR GENERATING UNIT NO. 2AMENDED FACILITY OPERATING LICENSELicense No. DPR-26Amendment No. 2201. The Nuclear Regulatory Commission (the Commission) having found that:A. The application for amendment by the Consolidated Edison Company of New York,Inc. (Con Edison), Entergy Nuclear Indian Point 2, LLC (ENIP2), and EntergyNuclear Operations, Inc. (ENO) submitted under cover letter dated December 12,2000, as supplemented by letters dated April 12, 2001, from Con Edison and datedApril 16, May 24, June 6, and June 8, 2001, from ENIP2 and ENO complies with thestandards and requirements of the Atomic Energy Act of 1954, as amended (theAct), and the Commission's rules and regulations as set forth in 10 CFR Chapter I;B. Construction of the Indian Point Nuclear Generating Unit No. 2 (IP2 or facility) hasbeen substantially completed in conformity with provisional Construction Permit No.CPPR-21, as amended, and the application, as amended, the provisions of the Actand the rules and regulations of the Commission;C. The facility will operate in conformity with the application, as amended, theprovisions of the Act, and the rules and regulations of the Commission;D. There is reasonable assurance: (i) that the activities authorized by this operatinglicense can be conducted without endangering the health and safety of the public,and (ii) that such activities will be conducted in compliance with the rules andregulations of the Commission;E. ENO is technically and financially qualified and ENIP2 is financially qualified toengage in the activities authorized by this amended license in accordance with therules and regulations of the Commission;F. ENIP2 and ENO have satisfied the applicable provisions of 10 CFR Part 140,"Financial Protection Requirements and Indemnity Agreements," of theCommission's regulations;Amendment No. 220 G. The issuance of this amended license will not be inimical to the common defenseand security or to the health and safety of the public;H. After weighing the environmental, economic, technical, and other benefits of thefacility against environmental costs and considering available alternatives, theissuance of this amendment to Facility Operating License No. DPR-26, subject tothe conditions for the protection of the environment set forth herein, is in accordancewith 10 CFR Part 50, Appendix D, of the Commission's regulations and all applicablerequirements of said Appendix D have been satisfied; and1. The receipt, possession, and use of source, byproduct and special nuclear materialas authorized by this amended license will be in accordance with the Commission'sregulations in 10 CFR Part 30, 40 and 70, including 10 CFR Section 30.33, 40.32,70.23, and 70.31.2. Facility Operating License No. DPR-26, as amended, (previously issued to Con Edison)issued to ENIP2 and ENO, is hereby amended in its entirety to read as follows:A. This amended license applies to the Indian Point Nuclear Generating Unit No. 2, apressurized water nuclear reactor and associated equipment (the facility), which isowned by ENIP2 and operated by ENO. The facility is located in WestchesterCounty, New York, and is described in the "Final Facility Description and SafetyAnalysis Report", as supplemented and amended.B. Subject to the conditions and requirements incorporated herein, the Commissionhereby licenses:(1) Pursuant to Section 1 04b of the Act and 10 CFR Part 50, "Licensing ofProduction and Utilization Facilities", (a) ENIP2 to possess and use, and(b) ENO to possess, use and operate, the facility at the designatedlocation in Westchester County, New York, in accordance with theprocedures and limitations set forth in this amended license;(2) ENO pursuant to the Act and 10 CFR Part 70, to receive, Amdt. 75possess, and use, at any time special nuclear material as 1-11-82reactor fuel, in accordance with the limitations for storageand amounts required for reactor operation, as describedin the Final Facility Description and Safety Analysis Report,as supplemented and amended and as described in theCommission's authorization through Amendment No. 75 tothis license.(3) ENO pursuant to the Act and 10 CFR Parts 30, 40, and 70, Amdt. 42to receive, possess and use, at any time any byproduct, 10-17-78source and special nuclear material as sealed neutronsources for reactor startup, sealed sources for reactorAmendment NO. 220 Rod Group Alignment Limits3.1.4KJ 3.1 REACTIVITY CONTROL SYSTEMS3.1.4 Rod Group Alignment LimitsLCO 3.1.4All shutdown and control rods shall be OPERABLE.ANDIndividual indicated rod positions shall be within the following limits:a. When THERMAL POWER is > 85% RTP, the difference betweeneach individual indicated rod position and its group step counterdemand position shall be within the limits specified inTable 3.1.4-1 for the group step counter demand position: andb. When THERMAL POWER is < 85% RTP, the difference betweeneach individual indicated rod position and its group step counterdemand position shall be < 24 steps.APPLICABILITY:MODES I and 2.ACTIONSCONDITION REQUIRED ACTION COMPLETION TIMEA. One or more rod(s) A.1.1 Verify SDM to be within 1 hourinoperable. the limits specified in theCOLR.ORA.1.2 Initiate boration to restore 1 hourSDM to within limit.ANDA.2 Be in MODE 3. 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />sB. One rod not within B.1 Restore rod to within 1 houralignment limits. alignment limits.ORINDIAN POINT 23.1.4 -1Amendment No. 238 Rod Group Alignment Limits3.1.4ACTIONS (continued)CONDITION REQUIRED ACTION COMPLETION TIMEB.2.1.1 Verify SDM to be withinthe limits specified in theCOLR.ORB.2.1.2 Initiate boration to restoreSDM to within limit.ANDB.2.2 Reduce THERMALPOWER to s 75% RTP.ANDB.2.3 Verify SDM is within thelimits specified in theCOLR.ANDB.2.4 Perform SR 3.2.1.1.ANDB.2.5 Perform SR 3.2.2.1.ANDB.2.6 Re-evaluate safetyanalyses and confirmresults remain valid forduration of operation underthese conditions.1 hour1 hour2 hoursOnce per12 hours72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />s72 hours5 daysC. Required Action and C.1 Be in MODE 3. 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />sassociated CompletionTime of Condition B notmet.INDIAN POINT 23.1.4-2Amendment No. 238 Rod Group Alignment Limits 3.1.4 ACTIONS (continued) CONDITION REQUIRED ACTION COMPLETION TIME D. More than one rod not D.1.1 Verify SOM is within the 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> within alignment limit. limits specified in the COLR. OR D.1.2 Initiate boration to restore 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> required SOM to within limit. AND D.2 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> SURVEILLANCE REQUIREMENTS SR 3.1.4.1 SR 3.1.4.2 SR 3.1.4.3 SURVEILLANCE -NOTE-Not required to be met for individual control rods until 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after completion of control rod movement. Verify individual rod positions within alignment limit. Verify rod freedom of movement (trippability) by moving each rod* not fully inserted in the core ;:::: 10 steps in one direction. Verify rod drop time of each rod, from the fully withdrawn position, is ::::: 2.4 seconds from the gripper release to dashpot entry, with: a. Tavg;:::: 500°F and b. All reactor coolant pumps operating. FREQUENCY 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 92 days Prior to criticality after each removal of the reactor head *Control Rod G-3 need not be moved until repaired in the next forced outage of sufficient duration prior to the refuel outage of 2016 or during the refuel outage in 2016. INDIAN POINT 2 3.1.4 -3 Amendment No. 280 Rod Group Alignment Limits3.1.4Table 3.1.4-1Maximum Permissible Rod Misalignment when > 85% RTP(IRPI Rod Position minus Group Step Counter Demand Position)Maximum Positive Deviation Maximum Negative DeviationGroup Step Counter (IRPIs reading greater than (IRPIs reading less thanDemand Position Group Step Counter Group Step Counter(steps) Demand Position) Demand Position)S 209 +12 -12210 to 221 +16 -12222 +16 -13223 +16 -14224 * +16 -152225 +16 -16INDIAN POINT 23.1A -4Amendment No. 238 Shutdown Bank Insertion Limits3.1.53.1 REACTIVITY CONTROL SYSTEMS3.1.5 Shutdown Bank Insertion LimitsLCO 3.1.5APPLICABILITY:Each shutdown bank shall be within insertion limits specified in the COLR.MODES I and 2.-NOTE-This LCO is not applicable while performing SR 3.1.4.2.ACTIONSCONDITION REQUIRED ACTION COMPLETION TIMEA. One or more shutdown A.1.1 Verify SDM is within the 1 hourbanks not within limits. limits specified in theCOLR.ORA.1.2 Initiate boration to restore 1 hourSDM to within limit.ANDA.2 Restore shutdown banks 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />sto within limits.B. Required Action and B.1 Be in MODE 3. 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />sassociated CompletionTime not met.INDIAN POINT 23.1.5 -1Amendment No. 238