ML060680026

Issuance of License Amendment Emergency Core Cooling System Throttle Valve Surveillance Requirements

ML060680026
Person / Time
Site:	Indian Point
Issue date:	03/23/2006
From:	Boska J P Plant Licensing Branch III-2
To:	Kansler M Entergy Nuclear Operations
Boska J P, NRR, 301-415-2901
References
TAC MC8581, FOIA/PA-2016-0148
Download: ML060680026 (12)

Text

March 23, 2006Mr. Michael KanslerPresident Entergy Nuclear Operations, Inc.

440 Hamilton Avenue White Plains, NY 10601

SUBJECT:

INDIAN POINT NUCLEAR GENERATING UNIT NO. 3 - ISSUANCE OFAMENDMENT RE: EMERGENCY CORE COOLING SYSTEM THROTTLE VALVE SURVEILLANCE REQUIREMENTS (TAC NO. MC8581)

Dear Mr. Kansler:

The Commission has issued the enclosed Amendment No. 230 to Facility Operating LicenseNo. DPR-64 for the Indian Point Nuclear Generating Unit No. 3. The amendment consists of changes to the Technical Specifications (TSs) in response to your application dated October 3, 2005.The amendment revises TS Surveillance Requirement 3.5.2.6, which verifies the position stopfor Emergency Core Cooling System throttle valves, to add 9 throttle valves and to delete 2 throttle valves which are now locked closed.A copy of the related Safety Evaluation is enclosed. A Notice of Issuance will be included in theCommission's next regular biweekly Federal Register notice.Sincerely,/RA/John P. Boska, Senior Project ManagerPlant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket No. 50-286

Enclosures:

1. Amendment No. 230 to DPR-64

2. Safety Evaluationcc w/encls: See next page Indian Point Nuclear Generating Unit No. 3 cc:

Mr. Gary J. TaylorChief Executive Officer Entergy Operations, Inc.

1340 Echelon Parkway Jackson, MS 39213Mr. John T. HerronSenior Vice President and Chief Operating Officer Entergy Nuclear Operations, Inc.

440 Hamilton Avenue White Plains, NY 10601Mr. Fred R. DacimoSite Vice President Entergy Nuclear Operations, Inc.

Indian Point Energy Center 295 Broadway, Suite 1

P.O. Box 249 Buchanan, NY 10511-0249Mr. Paul RubinGeneral Manager, Plant Operations Entergy Nuclear Operations, Inc.

Indian Point Energy Center 295 Broadway, Suite 2

P.O. Box 249 Buchanan, NY 10511-0249Mr. Oscar LimpiasVice President Engineering Entergy Nuclear Operations, Inc.

440 Hamilton Avenue White Plains, NY 10601Mr. Brian O'GradyVice President, Operations Support Entergy Nuclear Operations, Inc.

440 Hamilton Avenue White Plains, NY 10601Mr. John F. McCannDirector, Licensing Entergy Nuclear Operations, Inc.

440 Hamilton Avenue White Plains, NY 10601Ms. Charlene D. FaisonManager, Licensing Entergy Nuclear Operations, Inc.

440 Hamilton Avenue White Plains, NY 10601Mr. Michael J. ColumbDirector of Oversight Entergy Nuclear Operations, Inc.

440 Hamilton Avenue White Plains, NY 10601Mr. James ComiotesDirector, Nuclear Safety Assurance Entergy Nuclear Operations, Inc.

Indian Point Energy Center 295 Broadway, Suite 1

P.O. Box 249 Buchanan, NY 10511-0249Mr. Patric ConroyManager, Licensing Entergy Nuclear Operations, Inc.

Indian Point Energy Center 295 Broadway, Suite 1

P. O. Box 249 Buchanan, NY 10511-0249Mr. Travis C. McCulloughAssistant General Counsel Entergy Nuclear Operations, Inc.

440 Hamilton Avenue White Plains, NY 10601Ms. Stacey LousteauTreasury Department Entergy Services, Inc.

639 Loyola Avenue Mail Stop: L-ENT-15E New Orleans, LA 70113Regional Administrator, Region IU.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Indian Point Nuclear Generating Unit No. 3 cc:

Senior Resident Inspector's OfficeIndian Point 3 U. S. Nuclear Regulatory Commission

P.O. Box 59 Buchanan, NY 10511Mr. Peter R. Smith, PresidentNew York State Energy, Research, and Development Authority 17 Columbia Circle Albany, NY 12203-6399Mr. Paul EddyElectric Division New York State Department of Public Service 3 Empire State Plaza, 10 th FloorAlbany, NY 12223Mr. Charles Donaldson, EsquireAssistant Attorney General New York Department of Law 120 Broadway New York, NY 10271Mayor, Village of Buchanan236 Tate Avenue Buchanan, NY 10511Mr. Ray AlbaneseExecutive Chair Four County Nuclear Safety Committee Westchester County Fire Training Center 4 Dana Road Valhalla, NY 10592Mr. William DiProfioPWR SRC Consultant 139 Depot Road East Kingston, NH 03827Mr. Daniel C. PoolePWR SRC Consultant

P.O. Box 579 Inglis, FL 34449Mr. William T. RussellPWR SRC Consultant 400 Plantation Lane Stevensville, MD 21666-3232Mr. Jim RiccioGreenpeace 702 H Street, NW Suite 300 Washington, DC 20001Mr. Phillip Mus egaasRiverkeeper, Inc.

828 South Broadway Tarrytown, NY 10591Mr. Mark JacobsIPSEC 46 Highland Drive Garrison, NY 10524 March 23, 2006Mr. Michael R. KanslerPresident Entergy Nuclear Operations, Inc.

440 Hamilton Avenue White Plains, NY 10601

SUBJECT:

INDIAN POINT NUCLEAR GENERATING UNIT NO. 3 - ISSUANCE OF AMENDMENT RE: EMERGENCY CORE COOLING SYSTEM THROTTLE VALVE SURVEILLANCE REQUIREMENTS (TAC NO. MC8581)

Dear Mr. Kansler:

The Commission has issued the enclosed Amendment No. 230 to Facility Operating LicenseNo. DPR-64 for the Indian Point Nuclear Generating Unit No. 3. The amendment consists of changes to the Technical Specifications (TSs) in response to your application dated October 3, 2005.The amendment revises TS Surveillance Requirement 3.5.2.6, which verifies the position stopfor Emergency Core Cooling System throttle valves, to add 9 throttle valves and to delete 2 throttle valves which are now locked closed.A copy of the related Safety Evaluation is enclosed. A Notice of Issuance will be included in theCommission's next regular biweekly Federal Register notice.Sincerely,/RA/John P. Boska, Senior Project ManagerPlant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationDocket No. 50-286

Enclosures:

1. Amendment No. 230 to DPR-64

2. Safety Evaluationcc w/encls: See next pageAccession Number: ML060680026*see safety evaluation dated February 3, 2006OFFICELPL1-1/PMLPL1-1/LASPWB/BCITSB/BCOGCLPL1-1/BCNAMEJBoskaSLittleJNakoski*TBoycePMouldingRLauferDATE3/15/063/16/062/3/063/17/063/21/063/22/06Official Record Copy DATED: March 23,2006AMENDMENT NO. 230 TO FACILITY OPERATING LICENSE NO. DPR-64 INDIAN POINTUNIT 3PUBLICLPL1-1 R/F RidsNrrDorlLpla RidsNrrLASLittle RidsNrrPMJBoska RidsOGCMailCenter GHill (2)

RidsNrrDirsItsb RidsAcrsAcnwMailCenter ECobey, RI KDesaicc: Plant Mailing list ENTERGY NUCLEAR INDIAN POINT 3, LLCENTERGY NUCLEAR OPERATIONS, INC.DOCKET NO. 50-286INDIAN POINT NUCLEAR GENERATING UNIT NO. 3AMENDMENT TO FACILITY OPERATING LICENSEAmendment No. 230License No. DPR-641.The Nuclear Regulatory Commission (the Commission) has found that:A.The application for amendment by Entergy Nuclear Operations, Inc. (thelicensee) dated October 3, 2005, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter I;B.The facility will operate in conformity with the application, the provisions of theAct, and the rules and regulations of the Commission;C.There is reasonable assurance (I) that the activities authorized by thisamendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with theCommission's regulations;D.The issuance of this amendment will not be inimical to the common defense andsecurity or to the health and safety of the public; andE.The issuance of this amendment is in accordance with 10 CFR Part 51 of theCommission's regulations and all applicable requirements have been satisfied.2.Accordingly, the license is amended by changes to the Technical Specifications asindicated in the attachment to this license amendment, and paragraph 2.C.(2) of FacilityOperating License No. DPR-64 is hereby amended to read as follows: (2)Technical SpecificationsThe Technical Specifications contained in Appendices A and B, as revisedthrough Amendment No. 230, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the TechnicalSpecifications.3.This license amendment is effective as of the date of its issuance and shall beimplemented within 30 days.FOR THE NUCLEAR REGULATORY COMMISSION/RA/Richard J. Laufer, ChiefPlant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical SpecificationsDate of Issuance: March 23, 2006 ATTACHMENT TO LICENSE AMENDMENT NO. 230FACILITY OPERATING LICENSE NO. DPR-64DOCKET NO. 50-286Replace the following page of the Appendix A Technical Specifications with the attachedrevised page. The revised page is identified by amendment number and contains marginal lines indicating the areas of change.Remove PageInsert Page3.5.2-33.5.2-3 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATIONRELATED TO AMENDMENT NO. 230 TO FACILITY OPERATING LICENSE NO. DPR-64ENTERGY NUCLEAR OPERATIONS, INC.INDIAN POINT NUCLEAR GENERATING UNIT NO. 3DOCKET NO. 50-28

61.0INTRODUCTION

By letter dated October 3, 2005, Agencywide Documents Access and Management Systemaccession number ML052900404, Entergy Nuclear Operations, Inc. (Entergy or the licensee),

submitted a request for changes to the Indian Point Nuclear Generating Unit No. 3 (IP3)

Technical Specifications (TSs). The proposed TS change will add 9 throttle valves (SI-2165, 2166, 2168, 2169, 2170, 2171, 2172, 856B and 856G) to the scope of the TS 3.5.2.6surveillance requirements (SRs). The proposed amendment will remove existing throttle valvesSI-856A and SI-856F from the scope of the SR, since they are now being maintained in a locked-closed position and no longer perform a throttle function. The high-head safety injection (HHSI) system was modified as part of the IP3 stretch power uprate (SPU) program to provide increased cold leg and hot leg flow capabilities, to support hot leg switchover as early as 6.5hours following a postulated loss-of-coolant accident (LOCA), to eliminate the potential fordebris accumulation during recirculation, and to reduce or eliminate the potential for cavitation damage to the throttle valves. Since the valves being added to the scope of the SR can change position when being set, this SR is appropriate and will enhance emergency core coolingsystem (ECCS) performance during plant operation.The Nuclear Regulatory Commission (NRC) staff had previously issued a license amendmentto IP3 for a 4.85 percent SPU and relocation of cycle specific parameters on March 24, 2005(Reference 2).

2.0REGULATORY EVALUATION

The Commission's regulatory requirements related to the contents of TSs are set forth inTitle 10 of the Code of Federal Regulations (10 CFR) Section 50.36, which assures the TSspecified limiting conditions for operation are consistent with assumed values of the initial conditions in the licensee's safety analyses. In accordance with 10 CFR 50.36, the NRC staffand the Westinghouse Owners group previously developed improved Standard Technical Specifications (ISTS) that meet 10 CFR 50.36(c)(2)(ii) and 10 CFR 50.36(c)(3) requirements. The licensee converted to ISTS on July 3, 2002. ISTS requires verification that each ECCS throttle valve's position stop is in the correct position to assure that realigned valves are in the proper position for adequate flow. 10 CFR 50.46 establishes acceptance criteria for the ECCS. The HHSI system was modifiedduring the SPU program. Nine throttle valves were added to trim system resistance duringsystem flow balance testing. These changes were made to enhance ECCS performance duringplant operation.

3.0TECHNICAL EVALUATION

The HHSI system utilizes three pumps discharging into two headers for safety injection. Priorto the SPU, the boric injection tank (BIT) header discharged to four cold legs through two motor-operated valves and two manual valves and discharged into one hot leg through one motor-operated valve. The non-BIT header discharged into four cold legs through two different motor-operated valves and two different manual valves and discharged into one hot leg through one different motor-operated valve. Thus, a total of eight cold leg valves were used to throttle flow, and two hot leg valves were closed and de-energized until hot leg recirculation was initiated. For hot leg injection, these two hot leg valves were then opened to a preset throttledposition. Since the SPU modification allows all valves except manual valves SI-856A and SI-856F to be used for trimming system resist ance based on system flow balance testing, thesevalves (856B, 856C, 856D, 856E, 856G, 856H, 856J, and 856K) could be used to perform throttling and therefore they will remain in TS SR 3.5.2.6. During this cycle, these valves (856B,856C, 856D, 856E, 856G, 856H, 856J, and 856K) have their limit switches adjusted so that they do not perform a throttle function.The HHSI system was modified as part of the SPU program to provide increased cold leg andhot leg flow capabilities, to support hot leg switchover as early as 6.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> following apostulated LOCA, to eliminate the potential for debris accumulation during recirculation, and toreduce or eliminate the potential for cavitation damage to the throttle valves. The modification included the addition of 6 cold leg throttle valves (valves SI-2165, 2166, 2169, 2170, 2171, and 2172) and 1 hot leg throttle valve (SI-2168). These valves are manual valves that are designed to be set in a locked, throttled position after adjustment during flow balance testing. The locked position will provide the required HHSI flow while also limiting pump run-out flow. Since theseseven valves can change position when being set, these valves are included within the scope of the SR.The hot leg valves SI-856B and SI-856G are also used to throttle flow during hot legrecirculation. The throttle position is achieved by adjusting the limit switch so that when a valve is opened for hot leg recirculation, it will open to the proper position to throttle flow. Since thesetwo hot leg valves perform a throttling function, they are also included within the scope of the SR. The existing throttle valves SI-856A and SI-856F are now being maintained in a locked-closed position and they will be removed from the SR, as the licensee's other administrativecontrols provide adequate assurance of proper valve position. The proposed TS change to SR 3.5.2.6 thus adds a total of 9 valves to the scope of the SR andremoves 2 valves in the HHSI system discharge lines from the scope. Alignment of valves inthe HHSI flow path is necessary for proper ECCS performance. The HHSI throttle valve positions will be established by flow testing, and the SR requires verification that identifiedECCS throttle valve position stops are in the correct position. By updating the SR to include the appropriate HHSI valves, the proposed TS change will enhance the ECCS performance duringplant operation. The NRC staff has reviewed the proposed TS changes and finds that these changes are incompliance with 10 CFR 50.36 criteria. These TS changes are consistent with the safety analyses and conform to NUREG-1431, Revision 3 guidelines (Reference 1). Therefore, theNRC staff concludes that the proposed TS changes are acceptable.

4.0STATE CONSULTATION

In accordance with the Commission's regulations, the New York State official was notified of theproposed issuance of the amendment. The State official had no comments.

5.0ENVIRONMENTAL CONSIDERATION

The amendment changes a requirement with respect to installation or use of a facilitycomponent located within the restricted area as defined in 10 CFR Part 20 and changes surveillance requirements. The NRC staff has determined that the amendment involves nosignificant increase in the amounts, and no significant change in the types, of any effluents thatmay 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 amendment involves no significant hazards consideration, and there has been nopublic comment on such finding (70 FR 72670). Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR51.22(b), no environmental impact statement or environmental assessment need be preparedin connection with the issuance of the amendment.

6.0CONCLUSION

The Commission has concluded, based on the considerations discussed above, that (1) there isreasonable assurance that the health and safety of the public will not be endangered byoperation in the proposed manner, (2) such activities will be conducted in compliance with theCommission's regulations, and (3) the issuance of the amendment will not be inimical to thecommon defense and security or to the health and safety of the public.

7.0REFERENCES

1. NUREG-1431, Revision 3, "Standard Technical Specifications, Westinghouse Plants," dated March 2004.2. Letter from USNRC to Michael Kansler of Entergy Nuclear Operations Inc., RegardingIP3 Issuance of Amendment RE: 4.85 percent stretch power uprate and relocation of cycle specific parameters (TAC. No. MC3552) dated March 24, 2005.Principal Contributor: K. Desai Date: March 23, 2006