ML15223A805

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NRC000169 - Indian Point, Unit 2 Technical Specifications (Excerpt)
ML15223A805
Person / Time
Site: Indian Point  Entergy icon.png
Issue date: 08/10/2015
From:
NRC/OGC
To:
SECY RAS
References
RAS 28149, ASLBP 07-858-03-LR-BD01, 50-247-LR, 50-286-LR
Download: ML15223A805 (10)
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Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, O.C. 20555-0001 ENTERGY NUCLEAR INDIAN POINT 2. LLC AND ENTERGY NUCLEAR OPERATIONS, INC. DOCKET NO. 50-247 INDIAN POINT NUCLEAR GENERATING UNIT NO. 2 AMENDED FACILITY OPERATING LICENSE License No. DPR-26 Amendment No. 220 1. 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 Entergy Nuclear Operations, Inc. (ENO) submitted under cover letter dated December 12, 2000, as supplemented by letters dated April 12, 2001, from Con Edison and dated April 16, May 24, June 6, and June 8, 2001, from ENIP2 and ENO 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. Construction of the Indian Point Nuclear Generating Unit No. 2 (IP2 or facility) has been substantially completed in conformity with provisional Construction Permit No. CPPR-21, as amended, and the application, as amended, the provisions of the Act arid the rules and regulations of the Commission; C. The facility will operate in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Commission; D. There is reasonable assurance: (i) that the activities authorized by this operating license 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 and regulations of the Commission; E. ENO is technically and financially qualified and ENIP2 is financially qualified to engage in the activities authorized by this amended license in accordance with the rules 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 the Commission's regulations; Amendment No. 220 G. The issuance of this amended license will not be inimical to the common defense and security or to the health and safety of the public; H. After weighing the environmental, economic, technical, and other benefits of the facility against environmental costs and considering available alternatives, the issuance of this amendment to Facility Operating License No. DPR-26, subject to the conditions for the protection of the environment set forth herein, is in accordance with 10 CFR Part 50, Appendix D, of the Commission's regulations and all applicable requirements of said Appendix D have been satisfied; and I. The receipt, possession, and use of source, byproduct and special nuclear material as authorized by this amended license will be in accordance with the Commission's regulations in 1 O CFR Part 30, 40 and 70, including 1 O 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, a pressurized water nuclear reactor and associated equipment (the facility), which is owned by ENIP2 and operated by ENO. The facility is located in Westchester County, New York, and is described in the "Final Facility Description and Safety Analysis Report", as supplemented and amended. B. Subject to the conditions and requirements incorporated herein, the Commission hereby licenses:

(1) Pursuant to Section 104b of the Act and 1 O CFR Part 50, "Licensing of Production and Utilization Facilities", (a) ENIP2 to possess and use, and (b) ENO to possess, use and operate, the facility at the designated location in Westchester County, New York, in accordance with the procedures and limitations set forth in this amended license; (2) (3) ENO pursuant to the Act and 10 CFR Part 70, to receive, possess, and use, at any time special nuclear material as reactor fuel, in accordance with the limitations for storage and amounts required for reactor operation, as described in the Final Facility Description and Safety Analysis Report, as supplemented and amended and as described in the Commission's authorization through Amendment No. 75 to this license. ENO pursuant to the Act and 10 CFR Parts 30, 40, and 70, to receive, possess and use, at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor Arndt. 75 1-11-82 Arndt. 42 10-17-78 Amendment NO. 220 (4) (5) instrumentation and radiation monitoring equipment calibration , and as fission detectors in amounts as required; ENO pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess, and use in amounts as required any byproduct , source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components

ENO pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility. Arndt. 42 10-17-78 Arndt. 220 09-06-01 C. This amended license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter I
Part 20 , Section 30.34 of Part 30 , Section 40.41 of Part 40, Sections 50.54 and 50.59 of Part 50 , and Section 70.32 of Part 70; is subject to all applicable provisions of the Act and to the rules , regulations , and orders o.f the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below: (1) Maximum Power Level ENO is authorized to operate the facility at steady state reactor core power levels not in excess of 3216 megawatts thermal. (2) Technical Specifications Arndt. 241 10-27-04 The Technical Specifications contained in Appendices A , B , and C, as revised through Amendment No. 281, are hereby incorporated in the license. ENO shall operate the facility in accordance with the Technical Specifications. (3) The following conditions relate to the amendment approving the conversion to Improved Standard Technical Specifications
1. This amendment authorizes the relocation of certain Technical Specification requirements and detailed information to licensee controlled documents as described in Table R, "Relocated Technical Specifications from the CTS ," and Table LA, "Removed Details and Less Restrictive Administrative Changes to the CTS" attached to the NRG staffs Safety Evaluation enclosed with this amendment.

The relocation of requirements and detailed information shall be completed on or before the implementation of this amendment.

Amendment No. 281 APPENDIX A TO FACILITY OPERATING LICENSE DPR-26 FOR ENTERGY NUCLEAR INDIAN POINI' 2 I LLC AND ENTERGY NUCLEAR OPERATIONS, INC. INDIAN POINT NUCLEAR GENERATING PLANT UNIT NO. 2 DOCKET NO. 50-247 TECHNICAL SPECIFICATIONS AND BASES Amendment No. 220

3.4 REACTOR

COOLANT SYSTEM (RCS) 3.4.17 Steam Generator (SG) Tube Integrity LCO 3.4.17 SG tube integrity shall be maintained. SG Tube Integrity I 3.4.17 All SG tubes satisfying the tube plugging criteria shall be plugged in accordance with the Steam Generator Program. APPLICABILITY

MODES 1 , 2 , 3, and 4. ACTIONS -------------------------------------------------------------NOTE---------------------------------------------------------__________________

_ CONDITION REQUIRED ACTION TIME A. One or more SG tubes A.1 Verify tube integrity of the 7 days satisfying the tube affected tube(s) is plugging criteria and not maintained until the next plugged in accordance refueling outage or SG with the Steam tube inspection.

Generator Program. AND A.2 Plug the affected tube(s) in Prior t? entering accordance with the MODS 4 following the Steam Generator next rJfueling outage Program. or SG inspection B. Required Action and B.1 Be in MODE 3. I 6 hour6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> j associated Completion Time of Condition A not met. AND OR SG tube integrity not B.2 Be in MODE 5. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> maintained. I INDIAN POINT 2 3.4.17-1 Amendment No. 281 SURVEILLANCE REQUIREMENTS SURVEILLANCE SR 3.4.17.1 Verify SG tube integrity in accordance with the Steam Generator Program. SR 3.4.17.2 Verify that each inspected SG tube that satisfies the tube plugging criteria is plugged in accordance with the Steam Generator Program. INDIAN POINT 2 3.4. 17 -2 I I I . SG Tube Integrity 3.4.17 f REQUENCY In/I ccordance with th Steam Gterator Pr t gram to entering Mg>DE 4 following a 1_G tube ins l pection Amendment No. 281 Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.6 lnserv i ce Testing Program (continued)

b. c. d. The provisions of SR 3.0.2 are appl i cable to the above requ f ed Frequenc i es and to other normal and accelerated Frequencies specified . s 2 years or less in the lnservice Testing Program for performing inservice te ting activit i es , The provisions of SR 3.0.3 are applicable to inservice testin b activities , and Nothing in the ASME OM Code shall be construed t d supersede the requirements of any TS. 5.5.7 Steam Generator (SG) Program A Steam Generator Program shall be established and implementrd to ensure that SG tube integrity is maintained. In addition , the Steam Generat r Program shall include the following: a. b. INDIAN POINT 2 Provisions for condition monitoring assessments. Con , ition monitoring assessment means an evaluat i on of the " as found" condition of the tubing with respect to the performance criteria for structural integrity and accident induced leakage. The " as found" condit i on refers to the condition of he tubing during an SG inspection outage , as determined from the inservice i r.spection resu l ts or by other means , pr i or to the plugging of tubes. Condition monitor i ng assessments shall be conducted during each outage which the SG tubes are inspected or plugged , to confirm that the perfor ance criteria are being met. Performance criteria for SG tube integrity.

SG tube i m tegrity shall be maintained by meeting the performance criteria for tube st uctural integrity , accident induced leakage , and operational LEAKAGE. 1. Structural integrity performance criterion: All in-service steam generator tubes shall retain structural i ntegrity over the full ange of normal operating conditions (including startup , operation in the power range, hot standby, and cool down), all anticipated transients incl y ded in the design specification and design basis accidents. This includes 1 retaining a safety factor of 3.0 against burst under normal steady state fu'l power operation primary-to-secondary pressure differential and a saf r ty factor of 1 .4 aga i nst burst applied to the design basis accident primary-to

-secondary pressure differentials. Apart from the above require r ents , additional loading conditions associated with the des i gn basis accidents , or combination of accidents in accordance with the desi b n and licensing basis , shall also be evaluated to determine if the assobated loads 5.5 -6 Am r dmen1 No. 2a1 Programs and Manuals 5.5 Programs and Manuals I 5.5 5.5.7 Steam Generator (SG) Program (continued}

c. d. INDIAN POINT 2 contribute significantly to burst or collapse. In the assessment of tube integrity , those loads that do significantly affect burst or i collapse shall be determined and assessed in combination with the loads due to pressure with a safety factor of 1.2 on the combined primary load b and 1.0 on axial secondary loads. 2. Accident induced leakage performance criterion: The primary to secondary accident induced leakage rate for any desigr basis accident , other than a SG tube rupture , shall not exceed the rate assumed in the accident analysis in terms of total leakage rate for all SGs and leakage rate for an individual SG. Leakage is not to ex ct eed 150 gpd per SG. I 3. The operational LEAKAGE performance criterion is pecified in LCO 3.4.13 , " RCS Operational LEAKAGE." Provisions for SG tube plugging criteria. Tubes found by inspection to contain flaws with a depth equal to or exceeding 40% of t i he nominal tube wall thickness shall be plugged. The following SG tube alternate plugging criteria shall be applied as an alternative to the preceding criteria. Tubes with service-induced flaws located greater than 18.9 inches below the top of the tubesheet do not require plugging. Tubes with induced flaws located in the portion of the tube from the top l of the tubesheet to 18.9 inches below the top of the tubesheet be plugged upon detection. I Provisions for SG tube inspections. Periodic SG tube inspections shall be performed. The number and portions of the tubes and methods of inspection shall be performed with the objective of detecting flaws of any type (e.g., volumetric flaws , axial and circumferential cracks that may be present along the length of the tube, from 18.9 inches the top of the tubesheet on the hot leg side to 18.9 inches below the top f the tubesheet on the cold leg side , and that may satisfy the applicable tub plugging criteria.

The tube-to-tubesheet weld is not part of the tube. I In addition to meeting the requirements of d.1 , d.2, and d.3 below , the inspection scope , inspection methods , and inspection intervals shall be such to ensure that SG tube integrity is maintained until the next SG inspe 1 tion. A degradation assessment shall be performed to determine t e type and I 5.5 -7 I Am ndment No. 281 Progr j ms and Manuals 5.5 Programs and Manuals I 5.5 5.5.7 Steam Generator (SG) Program (continued)

INDIAN POINT 2 location of flaws to which the tubes may be susceptible a d, based on this assessment , to determine which inspection methods need t be employed and at what locations. I 1. Inspect 100% of the tubes in each SG during the first refueling outage following SG installation. I 2. After the first refueling outage following SG inspect each SG at least every 48 effective full power months or at least every other refueling outage (whichever results in more frequent nspections). In addition , the minimum number of tubes inspected at scheduled inspection shall be the number of tubes in all SGs div i ded by the number of SG inspection outages scheduled in each r nspection period as defined in a , b , and c below. If a degradation asse r sment indicates the potential for a type of degradation to occur at a location not previously inspected with a technique capable of this type of degradation at this location and that may satisfy the 9 pplicable tube plugging criteria , the minimum number of locations inspected with I such a capable inspection technique during the rema f nder of the inspection period may be prorated.

The fraction of locations to be inspected for this potential type of degradation at this l location at the end of the inspection period shall be no less than the ratio of the number of times the SG is scheduled to be inspected i in the inspection period after the determ i nation that a new form of deg l adation could potentially be occurring at this location divided by the total number of times the SG i s scheduled to be inspected in the insp 1 ection period. Each inspection period defined below may be extended up to 3 effective full power months to include a SG outage in an i nspection period and the subsequent inspection peribd begins at the conclusion of the i ncluded SG inspection outage. a) After the first refueling outage following SG instal ation , inspect 100% of the tubes during the next 120 effrctive full power months. This constitutes the first inspectio I period; b) During the next 96 effective full power months, i n pect 100% of the tubes. This constitutes the second i 1 1 spection period; and c) During the remaining life of the SGs, inspect 1 OOQo of the tubes every 72 effective full power months. This constitutes the third and subsequent inspection p riods. 5.5 -8 A l endment No. 281 Progr ms and Manuals 5.5 5.5 Pro rams and Manuals 5.5.7 Steam Generator (SG) Program (continued)

3. If crack indications are found in any SG tube, then the inspection for each affected and potentially affected SG for the mechanism that caused the crack indication shall not exceed 24 e 1.ffective full power months or one refueling outage (whichever results in more frequent inspections). If definitive information, such as from examination of a pulled tube , diagnostic non-destructive testing , or engi?eering evaluation indicates that a crack-line indication is not associateti with a crack(s), then the indication need not be treated as a crack. e. Provisions for monitoring operational primary to secondary LEAKAGE. INDIAN POINT 2 5.5 -Ba A endment No. 281
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