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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20217G2161999-10-15015 October 1999 Errata Pages 2 & 3 for Safety Evaluation Supporting Amend 168 Issued to FOL DPR-63 Issued on 990921.New Pages Change Description of Flow Control Trip Ref Cards to Be Consistent with Application for Amend ML20212D3611999-09-21021 September 1999 Safety Evaluation Supporting Amend 168 to License DPR-63 ML20210H7851999-07-29029 July 1999 Corrected SER Supporting Amend 167 to License DPR-63, Replacing Pages 4,5 & 11.New Pages Correct SE to Be Consistent with Application for Amend ML20207G2261999-06-0707 June 1999 SER Accepting Proposed Mod to Each of Four Core Shroud Stabilizers for Implementation During Current 1999 Refueling Outage at Plant,Unit 1 ML20206U5351999-05-17017 May 1999 SER Accepting GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Plant, Units 1 & 2 ML20204C8001999-03-16016 March 1999 Safety Evaluation Supporting Amend 165 to License DPR-63 ML20155E2001998-11-0202 November 1998 Safety Evaluation Approving NMP 980227 Request for Extension of Reinspection Interval for Core Shroud Vertical Welds at NMP1 from 10,600 Hours to 14,500 Hours of Hot Operation ML20154D8401998-10-0505 October 1998 Safety Evaluation Accepting Proposed Changes Related to PT Limits in Plant,Unit 1 TSs ML20217F4341998-03-19019 March 1998 SER Related to Proposed Restructuring New York State Electric & Gas Corp,Nine Mile Point Nuclear Station,Unit 2 ML20198H9941997-12-29029 December 1997 SE Supporting Approval of Application Re Long Island Power Authority Aquisition of Long Island Lighting Co,Subject to Discussed Condition ML20197C4771997-01-0303 January 1997 Safety Evaluation Supporting Nine Mile Point Unit 1 Reactor & Turbine Building Blowout Panels ML20197C4541997-01-0202 January 1997 Safety Evaluation Supporting Resolution of Nine Mile Point Reactor/Turbine Building Pressure Relief Panel Outside Design Basis Issue ML20081G5171995-03-20020 March 1995 Safety Evaluation Supporting Amend 154 to License DPR-63 ML20081A8211995-03-0303 March 1995 Safety Evaluation Supporting Amend 153 to License DPR-63 ML20080H2681995-02-14014 February 1995 Safety Evaluation Supporting Amend 63 to License NPF-69 ML20064E5841994-03-0808 March 1994 Safety Evaluation Supporting Amend 146 to License DPR-63 ML20056H4751993-08-27027 August 1993 Safety Evaluation Accepting Licensee Proposal for Continued Insp & Repair of Flaw in Weld Joining HPCS Nozzle Safe to safe-end Extension ML20035F9781993-04-19019 April 1993 SER Concluding That Relief Not Required for Inservice Tests Conducted,Per Operations & Maint (OM) Stds OM-6 & OM-10 ML20205R1311988-10-31031 October 1988 Safety Evaluation Supporting Amend 101 to License DPR-63 ML20153F3851987-05-0404 May 1987 SER Accepting Util 870301 & 0407 Requests for Rev to Tech Specs,Modifying MSIV Actuation Control Sys,Per IEEE Std 279 & GDC 21 ML20153F3671987-04-30030 April 1987 Safety Evaluation Accepting Util 870311 Proposed Changes to Tech Spec Tables 2.2.1-1,3.6.1.2-1 & 3.6.3-1 Re MSIV-closure Setpoint ML20238C7121987-04-0808 April 1987 Safety Evaluation Concluding That Facility May Resume Operation W/O Leakage Control Sys But w/post-accident Leakage Mgt ML20153F3511987-02-0707 February 1987 Safety Evaluation Accepting Util Latest Design Mods to MSIV Actuation Control Sys,Per IEEE 279 & GDC 21 ML20238C6501987-02-0505 February 1987 Safety Evaluation Accepting MSIVs for Facility Operation Up to First Refueling,Contingent on Successful Completion of Preoperational Tests & Prototype Testing Program.Briefing for Commissioner Asselstine Re MSIVs & SALP Input Also Encl ML20238C5801987-02-0202 February 1987 Safety Evaluation Concluding That Facility May Resume Startup Testing & Operation for First Operating Cycle W/ Installed Refurbished Msivs.Necessity of Addl Leak Testing to Be Determined After Review of Prototype Test Results ML20238C1331986-10-27027 October 1986 Safety Evaluation Accepting Refurbished MSIVs for Plant Use Up to First Refueling,Contingent on Prototype Test Performance.Conditions Stated ML20238C1161986-10-22022 October 1986 Safety Evaluation Supporting Schedular Exemption from GDC 54 & 55 Re MSIV Operability to Permit Fuel Load.Salp Input Also Encl ML20153F6291986-08-27027 August 1986 Safety Evaluation Concurring W/Applicant 860703 Exemption Request Re Testing of 16 Relief Valves,Per 10CFR50,App J ML20197C0511978-10-27027 October 1978 Safety Evaluation Rept Supporting Amend 1 to CPPR-112 ML20244E2701974-11-15015 November 1974 Suppl 1 to AEC SER Re Licensee Conversion from Provisional OL to full-term OL for Util 1999-09-21
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20217G2161999-10-15015 October 1999 Errata Pages 2 & 3 for Safety Evaluation Supporting Amend 168 Issued to FOL DPR-63 Issued on 990921.New Pages Change Description of Flow Control Trip Ref Cards to Be Consistent with Application for Amend ML20216J9251999-09-30030 September 1999 Suppl to Special Rept:On 990621,11 Containment Hydrogen Monitoring Sys Chart Recorder Was Indicating Below Normal Operating Range.Caused by Excessive Wear on Valve Body & Discs of Bypass Pump.Sample Pump Replaced ML20217K4631999-09-30030 September 1999 Monthly Operating Rept for Sept 1999 for Nine Mile Point, Unit 1.With ML20212F7301999-09-21021 September 1999 Special Rept:On 990907,CR Operators Declared 12 Containment Hydrogen Monitoring Sys Inoperable for Planned Maint.Cause of Low Flow Condition Was Determined to Be Foreign Matl. Replaced Sample Pump Valve Discs ML20212D3611999-09-21021 September 1999 Safety Evaluation Supporting Amend 168 to License DPR-63 ML20212B9081999-09-14014 September 1999 Special Rept:On 990901, 12 Containment Hydrogen Monitoring Sys Was Declared Inoperable for Planned Maint.Caused by Planned Maint Being Performed as Corrective Action.Check Valves with O Rings Were Replaced ML20212C4601999-08-31031 August 1999 Monthly Operating Rept for Aug 1999 for Nine Mile Point Nuclear Station,Unit 1.With ML20216F5141999-08-31031 August 1999 Rept on Status of Public Petitions Under 10CFR2.206 05000220/LER-1999-005-01, :on 990801,RT During Plant Startup on IRM Spiking Was Noted.Caused by electro-magnetic Interference. Inspected,Cleaned,Burnished & Tested IRM 11 Range Switch. with1999-08-30030 August 1999
- on 990801,RT During Plant Startup on IRM Spiking Was Noted.Caused by electro-magnetic Interference. Inspected,Cleaned,Burnished & Tested IRM 11 Range Switch. with
05000220/LER-1999-004-01, :on 990723,reactor Scram Was Noted.Caused by Mechanical Pressure Regulator Suppressor Valve Failure. Cleaned Pressure Suppressor Valve & Provided Guidance for Valve Disassembly & Insp.With1999-08-23023 August 1999
- on 990723,reactor Scram Was Noted.Caused by Mechanical Pressure Regulator Suppressor Valve Failure. Cleaned Pressure Suppressor Valve & Provided Guidance for Valve Disassembly & Insp.With
ML20210U4591999-07-31031 July 1999 Monthly Operating Rept for July 1999 for Nine Mile Point, Unit 1.With ML20210H7851999-07-29029 July 1999 Corrected SER Supporting Amend 167 to License DPR-63, Replacing Pages 4,5 & 11.New Pages Correct SE to Be Consistent with Application for Amend ML20209D0291999-07-0202 July 1999 Special Rept:On 990621,operator Identified That Number 11 Hydrogen Monitoring Sys (Hms) Chart Recorder Was Indicating Below Normal Operating Range.Cause Indeterminate.Licensee Will Complete Troubleshooting of Subject Hms by 990709 ML20210B9081999-06-30030 June 1999 Monthly Operating Rept for June 1999 for Nine Mile Point Unit 1.With ML20209F8811999-06-0808 June 1999 Rev 1 to NMP Unit 1 COLR for Cycle 14 ML20207G2261999-06-0707 June 1999 SER Accepting Proposed Mod to Each of Four Core Shroud Stabilizers for Implementation During Current 1999 Refueling Outage at Plant,Unit 1 ML20196E2111999-05-31031 May 1999 Monthly Operating Rept for May 1999 for Nmp,Unit 1.With ML20207B0241999-05-18018 May 1999 Safety Evaluation of Topical Rept TR-107285, BWR Vessel & Intervals Project,Bwr Top Guide Insp & Flaw Evaluation Guidelines (BWRVIP-26), Dtd December 1996.Rept Acceptable ML20206U5351999-05-17017 May 1999 SER Accepting GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Plant, Units 1 & 2 ML20196L2301999-04-30030 April 1999 Monthly Operating Rept for Apr 1999 for Nmp,Unit 1.With 05000220/LER-1999-003-01, :on 990320,noted That Plant Operated with Average Planear LHGR Exceeding TS Limits.Caused by Inadequate Interface Design Between Color Graphics Terminal & 3-D Monicore Sys.Lowered Reactor Power.With1999-04-22022 April 1999
- on 990320,noted That Plant Operated with Average Planear LHGR Exceeding TS Limits.Caused by Inadequate Interface Design Between Color Graphics Terminal & 3-D Monicore Sys.Lowered Reactor Power.With
ML20205L0541999-04-0101 April 1999 Nonproprietary Replacement Pages to HI-91738,consisting of Section 5.0, Thermal-Hydraulic Analysis ML20205S5701999-03-31031 March 1999 Monthly Operating Rept for Mar 1999 for NMP Unit 1.With 05000220/LER-1999-002, :on 990217,noted That ASME Code Preservice Exams Had Not Been Performed on Emergency Condensers.Caused by Misinterpretation of ASME Code Requirements.Required Preservice Exams Were Completed on 990218.With1999-03-19019 March 1999
- on 990217,noted That ASME Code Preservice Exams Had Not Been Performed on Emergency Condensers.Caused by Misinterpretation of ASME Code Requirements.Required Preservice Exams Were Completed on 990218.With
ML20204C8001999-03-16016 March 1999 Safety Evaluation Supporting Amend 165 to License DPR-63 ML20207M9231999-03-12012 March 1999 Amended Part 21 Rept Re Cooper-Bessemer Ksv EDG Power Piston Failure.Total of 198 or More Pistons Have Been Measured at Seven Different Sites.All Potentially Defective Pistons Have Been Removed from Svc Based on Encl Results ML20207G2671999-03-0101 March 1999 Special Rept:On 990315,Nine Mile Point,Unit 1 Declared Number 12 Containment Hydrogen Monitoring Sys Inoperable. Caused by Degraded Encapsulated Reed Switch within Flow Switch FS-201.2-1495.Technicians Replaced Flow Switch ML20204C9971999-02-28028 February 1999 Monthly Operating Rept for Feb 1999 for Nine Mile Point,Unit 1.With ML20207E9311999-02-26026 February 1999 Part 21 Rept Re Sprague Model TE1302 Aluminum Electrolytic Capacitors with Date Code of 9322H.Caused by Aluminum Electrolytic Capacitors.Affected Capacitors Replaced 05000220/LER-1999-001, :on 990125,noted That Plant Operated Outside Design Basis Due to Failure to Revise Satellite pre-fire Plans.Satellite Copies of pre-fire Plans Were Revised & Procedure Re pre-fire Plans Was Revised.With1999-02-24024 February 1999
- on 990125,noted That Plant Operated Outside Design Basis Due to Failure to Revise Satellite pre-fire Plans.Satellite Copies of pre-fire Plans Were Revised & Procedure Re pre-fire Plans Was Revised.With
ML17059C5501999-01-31031 January 1999 Rev 0 to MPR-1966(NP), NMP Unit 1 Core Shroud Vertical Weld Repair Design Rept. ML20199M0891999-01-22022 January 1999 Part 21 Rept Re Failure of Square Root Converters.Caused by Failed Aluminum Electrolytic Capacitory Spargue Electric Co (Model Number TE1302 with Mfg Date Code 9322H).Sent Square Root Converters Back to Mfg,Barker Microfarads,Inc ML20206P2391998-12-31031 December 1998 Special Rept:On 981222,operators Removed non-TS Channel 12 Drywell Pressure Recorder & Associated TS Pressure Indicator from Svc.Caused by Intermittent Measuring Cable Connection in non-TS Recorder Circuitry.Replaced Cable ML20199K9331998-12-31031 December 1998 Monthly Operating Rept for Dec 1998 for Nine Mile Point Nuclear Station,Unit 1.With ML20210R8441998-12-31031 December 1998 1998 Annual Rept for Energy East ML20206P2421998-12-30030 December 1998 Special Rept:On 981219,number 12 Hydrogen Monitoring Sys (Hms) Was Declared Inoperable When Operators Closed Valve 201.2-601.Caused by Indeterminate Failure of Valve 201.2-71. Supplemental Rept Will Be Submitted After Valve Is Repaired ML20198M3571998-12-23023 December 1998 Special Rept:On 981210,operators Declared Number 11 Inoperable,Due to Failure of CR Chart Recorder.Caused by Inverter Board in Power Supply Circuitry of Recorder Due to Component Aging.Maint Personnel Replaced Failed Inverter 05000220/LER-1998-019-01, :on 981110,ASME Section XI ISI Was Missed. Caused by Cognitive Error Involving Technical Inaccuracies. Util Will Revise Second 10-yr Interval ISI Program Plan to Incorporate Visual Exam Requirements.With1998-12-10010 December 1998
- on 981110,ASME Section XI ISI Was Missed. Caused by Cognitive Error Involving Technical Inaccuracies. Util Will Revise Second 10-yr Interval ISI Program Plan to Incorporate Visual Exam Requirements.With
ML20198D9361998-11-30030 November 1998 Monthly Operating Rept for Nov 1998 for Nine Mile Point,Unit 1.With 05000220/LER-1998-018-01, :on 981006,determined That Actual Total Crds Flow Exceeded Indicated Crds Total Flow.Caused by Degraded Crds Filter Bypass Valve.Plant Has Been Limited to 1847 Mwt & Shift Check Procedure Was Revised.With1998-11-0505 November 1998
- on 981006,determined That Actual Total Crds Flow Exceeded Indicated Crds Total Flow.Caused by Degraded Crds Filter Bypass Valve.Plant Has Been Limited to 1847 Mwt & Shift Check Procedure Was Revised.With
ML20155E2001998-11-0202 November 1998 Safety Evaluation Approving NMP 980227 Request for Extension of Reinspection Interval for Core Shroud Vertical Welds at NMP1 from 10,600 Hours to 14,500 Hours of Hot Operation ML20195J4141998-10-31031 October 1998 Monthly Operating Rept for Oct 1998 for Nine Mile Point Nuclear Station,Unit 1.With ML20154D8401998-10-0505 October 1998 Safety Evaluation Accepting Proposed Changes Related to PT Limits in Plant,Unit 1 TSs 05000220/LER-1998-017-01, :on 980902,breach of Primary Containment Was Noted.Caused by Personnel Error in 1994.Immediately Upon Discovery,Asss Directed That CS Heat Exchanger Vent Valves Be Closed.With1998-10-0202 October 1998
- on 980902,breach of Primary Containment Was Noted.Caused by Personnel Error in 1994.Immediately Upon Discovery,Asss Directed That CS Heat Exchanger Vent Valves Be Closed.With
ML20154P1821998-09-30030 September 1998 Monthly Operating Rept for Sept 1998 for Nine Mile Point Nuclear Station,Unit 1.With 05000220/LER-1998-016-01, :on 980820,determined That CS Pump Motor Bearing Cooling Flow Outside Design Basis Requirement.Caused by Error in Maint Reassembly That Crimped Cooling Coil.Cs Pump 122 Repaired.With1998-09-21021 September 1998
- on 980820,determined That CS Pump Motor Bearing Cooling Flow Outside Design Basis Requirement.Caused by Error in Maint Reassembly That Crimped Cooling Coil.Cs Pump 122 Repaired.With
05000220/LER-1998-015-01, :on 980804,breach of Primary Containment Was Noted.Caused by Personnel Error.Closed Heat Exchanger Vent Valves & Restored Torus Pressure.With1998-09-0303 September 1998
- on 980804,breach of Primary Containment Was Noted.Caused by Personnel Error.Closed Heat Exchanger Vent Valves & Restored Torus Pressure.With
ML20153B2001998-08-31031 August 1998 Monthly Operating Rept for Aug 1998 for Nmpns,Unit 1.With ML20237C6351998-07-31031 July 1998 Monthly Operating Rept for July 1998 for Nine Mile Point Nuclear Station,Unit 1 ML20236T5911998-07-20020 July 1998 LER 98-S01-00:on 980618,security Force Member Left Nine Mile Point,Unit 2 Vehicle Gate Unattended Without Ensuring,Gate Alarm Had Been Reactivated.Caused by Inadequate Work Practice.Vehicle Gate Alarm Was Activated 1999-09-30
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panseg UNITE 3 STATES y-a P;
NUCLEAR REGULATORY COMMISSION WASHINGTON. D.C. 3000H001
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SAFETY EVALL'ATION BY THE OFFICE OF NUOLEAR REACTOR REGULATION RELATED TO PROPOSED AC W ISITION AND RESTRUCTURING LONG ISLAND LIGHTING COMPANY NINE MILE POINT NUCLEAR STATION. UNIT 2 DOCKET NO. 50-410
1.0 INTRODUCTION
Under cover of a letter dated September 8,1997, from its counsel, the Long Island Lighting Company (LILCO) submitted an application for consent by the U.S. Nuclear Regulatory Comission (NRC or Commission), pursuant to 10 CFR 50.80, regarding 3roposed alternative restructuring actions, each of which would result in tie indirect transfer of the operating license for Nins Mile Point Nuclear Station, Unit 2 (NMP2), to the ev ent held by LILCO.
LILCO is licensed by the NRC to own and possess an 13-per ce,c interest in NMP2.
LILCO revised its application on October 8,1997, such L at the pending request for consent now involves only a proposed acquisition o. LILCO by Long Island Power Authority (LIPA).
LILCO supplemented the application on November 7,1997, to indicate that subsequent to the proposed acquisition by LIPA, LILCO would provide notification to the NRC regarding any future transfer of significant LILCO assets.
According to the apalication, LIPA proposes to acquire LILCO by purchasing its stock through a casi merger, at a time when LILC0 consists of its electric transmission and distribution system, its retail electric business, substantially all of its current electric regulatory assets, and its 18-percent share of NMP2. LILCO thereby would become a subsidiary of LIPA.
After this restructuring, LILCO would continue to exist as an " electric utility" as defined in 10 CFR 50.2, providing the same electric utility services it did immediately preceding the restructuring.
LILCO would continue to be a licensee of NMP2, and no direct transfer of tne operating license or interests in the station would result from the proposed restructuring.
The transaction would not involve any change to either the management organization or technical personnel of Niagara Mohawk Power Corporation, which has exclusive responsibility under the operating license for operating and maintaining NMP2, and which is not involved in the proposed restructuring.
Pursuant to 10 CFR 50.80, the Commission may approve the transfer of control of a license after notice to interested persons. Such action is contingent upon the Commission's determination that the holder of the license following the transfer is qualified to hold the license, and that the transfer is otherwise consistent with applicable provisions of law, regulations, and orders of the Commission.
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2.0 FINANCIAL QUALIFICATIONS ANALYSIS
. The New York State legislature established LIPA in 1986, authorizing it to acquire some or all of. LILCO's securities and assets in order.to achieve, among other. things, the provision of electric servica to long Island customers at reduced rates. Through LIPA's acquisition of LILCO, LIPA will be able to provide rate reductions from LIPA's issuance of tax-exempt bonds to finance the acquisition and from the fact that LIPA will be exempt from paying Federal income taxes.
Under this transaction, LILCO will remain financially qualified to hold an 18-percent interest in NMP2.
LILCO is and will continue to be an " electric utility" as defined by NRC regulations, 10 CFR 50.2, + hat "generetes (and) distributes electricity and... recovers the cost of t'ais electricity...through rates established by...itself or by a separate regstatory authority." LIPA will have the authority under New York State law '.o set the rates at which LILCO, its wholly owned subsidiary, sells power 'sith one limitation: When approving the LIPA transaction of July 16, 1997, the New York State Public Authorities Control Board imposed a condition on LIPA that it "not implement an increase in average customer rates exceeding two and one half percent over a twelve month period, nor extend or reestablish ar, portion of a temporary rate increase over two and one half percent without approval of the (New York State Public Service Commission) following a full evidentiary hearing."
LILCO's application to the NRC states that LIPA will ensure that LILCO can meet its obligations as an 18-percent owner of NMP2, including LILCO's arovision of decommissioning funds.
The existing decommissioning fund for
.ILCO's 18-percent interest in NNP2 will continue to be held by LILCO, and LILCO will continue to make annual deposits to the fund.
Pursuant to 10 CFR 50.33(f), LILCO, as an electric utility, is exempt from further financial qualifications review.
4 However, in view of the NRC's concern that a merger or restructuring could lead to a diminution of assets necessary for the safe operation and eventual decommissioning of a licensee's nuclear power plant, it is NRC practice to condition approvals of transfers of control of licenses involving mergers and restructuring actions upon a requirement that the subject licensee not transfer significant assets to an affiliate without notifying the NRC.
LILCO addressed this NRC concern by letter dated November 7, 1997, which provided the following:
... The Long Island-Lighting Company (LILCO) agrees that, subsaquent to the Long Island Power Authority's (LIPA's) acquisition of LILCO's stock, LILC0 will provide the Office of the Director of Nuclear Reactor Regulation a ecpy of any application, at the time it is filed to transfer (excluding grants of security interests or liens) from LILCO to LIPA, or to any other affiliated company, facilities for the production, trcnsmission, or distribution of electric energy having a depreciated h
6
- book value exceeding ten percent (O's book of accounts.-10%) of LILC0's consolida utility plant, as recorded on LILC The foregoing,'as a condition.to the NRC's approval of the indirect license transfer app ication, will. assist the NRC in assuring that LILC0 will contir.ue
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to maintain adequate resources to contribute to the saft operation and decommissiening of-the facility.
Based on tho' above information, the NRC staff finds that LILC0 will remain-
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financially qualified to hold the license for NMP2 following the proposed 4
acquisition of LILC0 by LIPA.
4 3.0-' IECHNICAL QUALIFICATIONS As stated earlier, Niagara Mohawk Power Corporation,.the licensed operator of' Lthe facility, is.not involved in the LIPA/LILC0 transaction and thus will undergo no changes regarding-its technical qualifications, as a result of the proposed transaction.
E LILCO stated in its application that the proposed merger will have no effect upon the management of LILC0's utility operations.
LILCO will remain a discrete.and wholly separate entity that will function just as it did prior to restructuring.
LILCO's management will continue to make its own decisions with regard to utility planning, w rations, financial requirements, purchasing, and sales. No LILCO nuclear management positions will be changed as a prerequisite or direct result of the merger.
4.0 ANTITRUST l
Section 105c of the. Atomic Energy Act of 1954, as amended (the Act), which provides-for antitrust reviews to be conducted by the NRC, applies to an application for a license to construct or operate a facility licensed under Section 103 of the Act. Although LIPA may become the holding company of an NMP2 licensee, i.e., may indirectly acquire control of the-license, it will not be performing activities for which a license is needed.
Since approval of the application would not involve the issuance of a license, the procedures under Section 105c do not apply, including the making.of any "significant changes" determination. Accordingly, no antitrust review is necessary in connection with this application.
e 5.0 FOREIGN OWNERSHIP. CONTROL OR DOMINATION LILCO indicated in'its submittal that after the acquisition is completed, LIPA will become the sole holder of LILCO's outstanding common stock.L LIPA is'a statutory creation-of New York State and is wholly controlled by_ trustees appointed by State officials.= According-to the application, there is no foreign hold on these trustees. LILCO represents-that-LIPA's acquisition of LILCO will entail no control or domination by foreign entities of LILCO's-
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interest in NMP2.-
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, The NRC staff does not know or have any reason to believe that the proposed acquisition will result in LILCO being owned, controlled, or dominated by foreign interests.
6.0 ENVIR0t#1 ENTAL CONSIDERATION Pursuant to 10 CFR 51.21 and 51.35, an environmental assessment and finding of no significant impact was published in the Federal Reaf ster on December 18, 1997 (62 FR 66400).
7.0 CONCLUSION
S In view of the foregoing, the staff concludes that the proposed action will not dversely affect the financial qualifications of LILCO with respect to the operation and decommissioning of NNP2. Also, there do not appear to be any problematic antitrust or foreign ownership considerations related to the NMP2 license that would result from the acquisition and restructuring. Thus, the proposed transaction will not affect the qualifications of LILC0 as a holder of the license of HMP2, and the transfer of control of the license, to the extent effected by the proposed acouisition and restructuring, is otherwise consistent with applicable provisions of law, regulations, and orders issued by the Commission. Accordingly, with the condition discussed above relating to significant asset transfers, the proposed action should be approved.
Principal Contributors:
M. Dusaniwskyj D. Hood Date:
December 29, 1997
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