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Line 3: |
Line 3: |
| | issue date = 10/05/1999 | | | issue date = 10/05/1999 |
| | title = Requests Approval for Use of Relief Request Number 43 to Address Volumetric Examination Limitations (Less than 90%) Associated with a & B RHR Heat Exchanger Outlet Nozzle to Shell Welds.Approval Is Requested by Dec 31,2000 | | | title = Requests Approval for Use of Relief Request Number 43 to Address Volumetric Examination Limitations (Less than 90%) Associated with a & B RHR Heat Exchanger Outlet Nozzle to Shell Welds.Approval Is Requested by Dec 31,2000 |
| | author name = MECREDY R C | | | author name = Mecredy R |
| | author affiliation = ROCHESTER GAS & ELECTRIC CORP. | | | author affiliation = ROCHESTER GAS & ELECTRIC CORP. |
| | addressee name = VISSING G S | | | addressee name = Vissing G |
| | addressee affiliation = NRC (Affiliation Not Assigned), NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) | | | addressee affiliation = NRC (Affiliation Not Assigned), NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| | docket = 05000244 | | | docket = 05000244 |
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML17250B3041999-10-20020 October 1999 Forwards Changes to Tech Specs Bases for Re Ginna Nuclear Power Plant.Change Bars Indicate Those Revs Which Have Been Incorporated IR 05000244/19990081999-10-14014 October 1999 Forwards Insp Rept 50-244/99-08 on 990809-0919.Severity Level IV Violation of NRC Requirements Occurred & Being Treated as non-cited Violation Consistent with App C of Enforcement Policy ML17265A7651999-10-0808 October 1999 Forwards Fifteen Relief Requests That Will Be Utilized for Ginna NPP Fourth Interval ISI Program That Will Start on Jan 1,2000.Attachment 1 Includes Summaries & Detailed Description of Each Relief Request ML17265A7631999-10-0505 October 1999 Requests Approval for Use of Relief Request Number 43 to Address Volumetric Examination Limitations (Less than 90%) Associated with a & B RHR Heat Exchanger Outlet Nozzle to Shell Welds.Approval Is Requested by Dec 31,2000 ML17265A7641999-10-0505 October 1999 Requests Approval for Use of Relief Request Number 42 to Address Volumetric Examinations Limitations (Less than 90%) Associated with Eight Class 1 Identified Welds or Areas of Reactor Pressure Vessel ML20212J3561999-09-30030 September 1999 Forwards Four Copies of Re Ginna NPP Training & Qualification Plan for Security Officers, Rev 7,dtd 990930. Synopsis of Changes,Encl.Encl Withheld Per 10CFR73.21 ML20212J3801999-09-30030 September 1999 Forwards Four Copies of Rev to Re Ginna NPP Security Plan.Rev Changes Contingency Weapons Available to Response Force to Those Most Effective in Current Defensive Strategy.Encl Withheld Per 10CFR73.21 IR 05000244/19990051999-09-24024 September 1999 Forwards More Detailed Response Re Main Steam Check Valve Performance Questions Arising from NRC Insp Rept 50-244/99-05 Following Completion of Independent Assessment Being Performed by Duke Engineering & Svcs ML17265A7571999-09-24024 September 1999 Forwards More Detailed Response Re Main Steam Check Valve Performance Questions Arising from NRC Insp Rept 50-244/99-05 Following Completion of Independent Assessment Being Performed by Duke Engineering & Svcs IR 05000244/19992011999-09-24024 September 1999 Forwards Insp Rept 50-244/99-201 (Operational Safeguards Response Evaluation) on 990621-24.No Violations Noted. Primary Purpose of Osre to Assess Licensee Ability to Respond to External Threat.Insp Rept Withheld ML17265A7461999-08-31031 August 1999 Submits Response to NRC Administrative Ltr 95-03,rev 2, Availability of Reactor Vessel Integrity Database,Version, Dtd 990726 ML17265A7401999-08-26026 August 1999 Requests Approval for Use of Relief Request Number 35 Re Use of ASME Section XI Code,1995 Edition,1996 Addenda.Code Will Be Used to Develop Plant Fourth 10-year Interval ISI Program on Class 1,2 & 3 Components ML17265A7411999-08-26026 August 1999 Forwards LER 99-004-01 Re Plant Being Outside Design Basis Due to Containment Recirculation Fan Moisture Separator Vanes Being Incorrectly Installed.Part 21 Notification of 990512 Is Being Rescinded ML17265A7451999-08-23023 August 1999 Forwards fitness-for-duty Performance Data Rept for Six Months Ending 990630,per 10CFR26.71(d) ML17250B3021999-08-23023 August 1999 Informs That Util & NRC Had Conference Call on 990816 to Review Approach in Responding to Questions,As Result of Questions Re Main Steam Check Valve Performance Included in Insp Rept 50-244/99-05,dtd 990806 ML17265A7271999-07-30030 July 1999 Forwards 10CFR21 Interim Rept Per Reporting of Defects & Noncompliance,Section 21 (a) (2).Interim Rept Prepared Because Evaluation Cannot Be Completed within 60 Days from Discovery of Deviation or Failure to Comply ML17265A7151999-07-23023 July 1999 Forwards LER 99-007-01 Re Personnel Error Which Caused Two Channels to Be in Tripped Condition,Resulting in Reactor Trip.Further Investigation of Event Identified Addl Corrective Actions ML17265A7061999-07-22022 July 1999 Forwards LER 98-003-02,re Actuations of CR Emergency Air Treatment Sys.All Creats Actuations,Including Those Originally Believed to Be Valid Actuations,Were,In Fact Invalid Actuations ML17265A7191999-07-21021 July 1999 Forwards Ginna Station ISI Rept for Refueling Outage Conducted in 1999 ML17265A7141999-07-21021 July 1999 Withdraws Relief Request 35 for Plant Inservice Insp Program Section XI Requirements,Submitted on 980806.Licensee Plans to Resubmit Relief Request,Which Includes Addl Level of Detail,In Near Future ML17265A7041999-07-16016 July 1999 Submits Info Re Specific Licensing Actions Which May Be Expected to Generate Complex Reviews,In Response to Administrative Ltr 99-02,dtd 990603 ML17265A6911999-06-30030 June 1999 Responds to NRC Request for Info Re Y2K Readiness at Nuclear Power Plants.Gl 98-01 Requested Response on Status of Facility Y2K Readiness by 990701.Readiness Disclosure Attached ML17265A6871999-06-22022 June 1999 Forwards Response to RAI Made During 990225 Telcon Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves. 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Encl ML17265A6841999-06-21021 June 1999 Informs That Util Wishes to Amend Extend of Alternate Exams Provided for Relief Request Re ISI Program ASME Section XI Require Exams for First 10-Yr Interval for Containment ML17265A6741999-06-15015 June 1999 Submits Annual ECCS Rept IAW 10CFR50.46(a)(3)(ii) Requirements.No Changes Have Been Made to Large Break LOCA PCT & Small Break LOCA PCT ML17265A6751999-06-11011 June 1999 Responds to NRC RAI Re Licensee GL 96-05 Program.Encl Info Verifies That Util Is Implementing Provisions of JOG Program on MOV Periodic Verification ML17309A6551999-06-0707 June 1999 Responds to NRC 990310 RAI Re Verification of Seismic Adequacy of Mechanical & Electrical Equipment ML17265A6671999-06-0101 June 1999 Requests Approval of Ginna QA Program for Radioactive Matl Packages,Form 311,approval Number 0019.Ginna QA Program for Station Operation, Was Most Recently Submitted to NRC by Ltr Dtd 981221 & Supplemented on 990301 ML17265A6641999-05-25025 May 1999 Forwards Addl Info on Use of GIP Method a for Re Ginna Nuclear Power Plant.Copy of Re Ginna Station USI A-46 Outlier Resolution Table as Requested ML17265A6611999-05-24024 May 1999 Forwards LER 99-007-00 Re Personnel Error Which Caused Two Channels to Be in Tripped Condition,Resulting in Rt.Util Is Planning to Submit Suppl to LER by 990730 ML20206U0921999-05-13013 May 1999 Forwards Four Copies of Rev R to Gnpp Security Plan,Per Provisions of 10CFR50.54(p).Rev Clarifies Armed Response Team Assignments & Does Not Degrade Physical Security Effectiveness.Rev Withheld,Per 10CFR73.21 ML17265A6461999-05-12012 May 1999 Forwards 1998 Annual Radioactive Effluent Release Rept & 1998 Annual Radiological Environ Operating Rept, for Re Ginna NPP ML17265A6411999-05-12012 May 1999 Forwards LER 99-004-00 IAW 10CFR50.73 & 10CFR21.Further Assessment Will Be Provided in Suppl to LER by 990630 ML20206E7221999-04-29029 April 1999 Forwards Four Copies of Rev Q to Re Ginna Nuclear Power Plant Security Plan,Per 10CFR50.54(p).Changes Do Not Degrade Physical Security Effectiveness.Encl Withheld,Per 10CFR73.21 ML20206H6911999-04-22022 April 1999 Forwards Info Requested During Informal Telcon on 980408 Concerning Upcoming Osre at Ginna Station.Info Requested Listed.Without Encls ML17265A6271999-04-19019 April 1999 Forwards Rev 0 & Rev 1 to Colr,Cycle 28 for Re Ginna NPP, Per TS 5.6.5 ML17309A6501999-04-14014 April 1999 Forwards Revised Ginna Station EOPs & Procedures Index ML17265A6121999-03-29029 March 1999 Forwards Rept on Status of Decommissioning Funding for Re Ginna Npp,For Which Rg&E Is Sole Owner,Per 10CFR50.75. 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[Table view] Category:INCOMING CORRESPONDENCE
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Calculation Encl. Encl ML17265A6841999-06-21021 June 1999 Informs That Util Wishes to Amend Extend of Alternate Exams Provided for Relief Request Re ISI Program ASME Section XI Require Exams for First 10-Yr Interval for Containment ML17265A6741999-06-15015 June 1999 Submits Annual ECCS Rept IAW 10CFR50.46(a)(3)(ii) Requirements.No Changes Have Been Made to Large Break LOCA PCT & Small Break LOCA PCT ML17265A6751999-06-11011 June 1999 Responds to NRC RAI Re Licensee GL 96-05 Program.Encl Info Verifies That Util Is Implementing Provisions of JOG Program on MOV Periodic Verification ML17309A6551999-06-0707 June 1999 Responds to NRC 990310 RAI Re Verification of Seismic Adequacy of Mechanical & Electrical Equipment ML17265A6671999-06-0101 June 1999 Requests Approval of Ginna QA Program for Radioactive Matl Packages,Form 311,approval Number 0019.Ginna QA Program for Station Operation, Was Most Recently Submitted to NRC by Ltr Dtd 981221 & Supplemented on 990301 ML17265A6641999-05-25025 May 1999 Forwards Addl Info on Use of GIP Method a for Re Ginna Nuclear Power Plant.Copy of Re Ginna Station USI A-46 Outlier Resolution Table as Requested ML17265A6611999-05-24024 May 1999 Forwards LER 99-007-00 Re Personnel Error Which Caused Two Channels to Be in Tripped Condition,Resulting in Rt.Util Is Planning to Submit Suppl to LER by 990730 ML20206U0921999-05-13013 May 1999 Forwards Four Copies of Rev R to Gnpp Security Plan,Per Provisions of 10CFR50.54(p).Rev Clarifies Armed Response Team Assignments & Does Not Degrade Physical Security Effectiveness.Rev Withheld,Per 10CFR73.21 ML17265A6461999-05-12012 May 1999 Forwards 1998 Annual Radioactive Effluent Release Rept & 1998 Annual Radiological Environ Operating Rept, for Re Ginna NPP ML17265A6411999-05-12012 May 1999 Forwards LER 99-004-00 IAW 10CFR50.73 & 10CFR21.Further Assessment Will Be Provided in Suppl to LER by 990630 ML20206E7221999-04-29029 April 1999 Forwards Four Copies of Rev Q to Re Ginna Nuclear Power Plant Security Plan,Per 10CFR50.54(p).Changes Do Not Degrade Physical Security Effectiveness.Encl Withheld,Per 10CFR73.21 ML20206H6911999-04-22022 April 1999 Forwards Info Requested During Informal Telcon on 980408 Concerning Upcoming Osre at Ginna Station.Info Requested Listed.Without Encls ML17265A6271999-04-19019 April 1999 Forwards Rev 0 & Rev 1 to Colr,Cycle 28 for Re Ginna NPP, Per TS 5.6.5 ML17309A6501999-04-14014 April 1999 Forwards Revised Ginna Station EOPs & Procedures Index ML17265A6121999-03-29029 March 1999 Forwards Rept on Status of Decommissioning Funding for Re Ginna Npp,For Which Rg&E Is Sole Owner,Per 10CFR50.75. Data Presented Herein,Current as of 981231 ML17265A6041999-03-24024 March 1999 Forwards LER 99-001-00,IAW 10CFR50.73(a)(2)(ii)(B) & 10CFR21.Addl Analyses Are Being Performed to Support Future Cycle Operation & Supplemental LER Is Scheduled to Be Submitted by 990618 ML17265A5641999-03-0101 March 1999 Forwards Response to NRC 990217 RAI Concerning Changes to QA Program for Re Ginna Station Operation.Rg&E Is Modifying Changes Requested in 981221 Submittal.Modified QA Program,Encl ML17265A5671999-03-0101 March 1999 Forwards Application for Amend to License DPR-18,to Revise TSs Battery Cell Parameters Limit for Specific Gravity (SR 3.8.6.3 & SR 3.8.6.6).Supporting Tss,Encl ML17265A5551999-02-25025 February 1999 Informs That Util Is in Process of Revising fitness-for-duty Program,Developed in Accordance with 10CFR26.Util Will Continue to Use Dept of Health & Human Svcs Certified Test Facility for Majority of Tests During Yr ML17265A5561999-02-22022 February 1999 Forwards FFD Performance Data Rept for Six Months Ending 981231,per 10CFR26.71(d) ML17265A5451999-02-12012 February 1999 Forwards Simulator Four Year Certification Rept,Per 10CFR55.45(b)(5)(ii) ML17309A6491999-02-12012 February 1999 Forwards Ginna Station EOPs ML17265A5431999-02-0909 February 1999 Supplements 980806 Relief Request with Attached Table.Util Third 10-Yr ISI of Reactor Vessel Being Performed During 1999 Refueling Outage,Beginning on 990301 ML17265A5361999-02-0202 February 1999 Forwards Response to NRC 981203 RAI Re Resolution of Unresolved Safety Issue USI A-46.Util Does Not Agree with NRCs Interpretation.Detailed Bases,Encl ML17311A0691999-01-25025 January 1999 Forwards Revs to Ginna Station Emergency Plan Implementing Procedures (Epips).Previous Rev Had Incorrect Effective Date ML17311A0671999-01-14014 January 1999 Forwards Revised Emergency Operating Procedures for Re Ginna NPP ML17265A5131999-01-12012 January 1999 Forwards Revised Cover Page for Ginna Station Technical Requirements Manual (Trm), Rev 7,correcting Error in Effective Date ML17265A5111999-01-11011 January 1999 Requests Relief Per 10CFR50.55a(a)(3)(ii) from Certain Requirements of Section XI of ASME Bp&V Code for ISI Program.Relief Requests 37,38 & 39 Encl ML17265A5101999-01-11011 January 1999 Requests Relief Per to 10CFR50.55a(a)(3)(ii) from Certain Requirements of Section XI of ASME B&PV Code for ISI Program.Relief Request 40 Encl 1999-09-30
[Table view] |
Text
REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)ACCESSION NBR:9910150168 DOC-DATE: 99/10/05 NOTARIZED:
NO>AC$~,"'5(>-244 Robert Emmet Ginna Nuclear Plant, Unit 1, Rochester G"'-PV'xd.c?SAME
-.AUTHOR AFFILIATION "94ECR06Y,R.C.
Rochester Gas&Electric Corp.RE@'IP.NAME RECIPIENT AFFILIATION VIS'SING,G.S.
SUBJECT:
Requests approval for use of Relief Request number 43 to address volumetric examination limitations (less than 90>)associated with A&B RHR heat exchanger outlet nozzle to shell.welds.Approval is requeSted by Dec 31,2000.DISTRIBUTION CODE(A047D COPIES RECEIVED:LTR ENCL SIZE: TITLE: OR Submittal:
Inservice/Testing/Relief from ASME Code NOTES:License Exp date in accordance with 10CFR2,2.109(9/19/72).
DOCKET I 05000244 E 05000244 G RECIPIENT ID CODE/NAME LITTLE,S INTERNAL: ILE CENTER 01 OGC RP RES/DET/MEB EXTERNAL: LITCO ANDERSON NRC PDR COPIES LTTR ENCL 1 1 1 1 1 0 1 1 1 1 1 1 RECIPIENT ID CODE/NAME VISSING,G NUDOCS-ABSTRACT RES/DET/ERAB NOAC COPIES LTTR ENCL 1 1 1 1 0 R E N NOTE TO ALL"RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE WASTETH TO HAVE YOUR NAME OR ORGANIZATION REMOVED FROM DISTRIBUTION LISTS OR REDUCE THE NUMBER OF COPIES RECEIVED BY YOU OR YOUR ORGANIZATION, CONTACT THE DOCUMENT CONTROL DESK (DCD)ON EXTENSION 415-2083 TOTAL NUMBER OF COPIES REQUIRED: LTTR 10 ENCL 9 AND~A Subsidiary of RGS Energy Group, Inc.ROCHESTER GAS AND ELECIIC CORPORATION
~89 EAST AVENUE, ROCHESTER, N.Y.IrI6r19CNOI
~716 5d6-2700 www.rge.corn ROBERT C.MECREDY Vice President Nvdeor Operations October 5, 1999 U.S.Nuclear Regulatory Commission Document Control Desk Attn: Guy S.Vissing Project Directorate I Washington, D.C.20555
Subject:
Inservice Inspection Program ASME Section XI Required Examinations Third 10-Year Interval Relief Request No.43 R.E.Ginna Nuclear Power Plant'Docket No.50-244
Dear Mr.Vissing:
The purpose of this letter is to seek approval for the use of Relief Request Number 43 to address volumetric examination limitations (less than 90%)associated with the A and B Residual Heat Removal Heat Exchanger Outlet Nozzle to Shell Welds.This Relief is requested for bvo (2)welds pursuant to the provisions of 10CFR50.55a (g)(5)(iii).
The required examination coverage for the identified items are impractical and would require redesign to allow examination or to be replaced to enable inspection.
Justification concerning limitations are included in the attachment to this letter.Since this relief request is for our 3rd 10-year interval ISI program, which ends December 31, 1999, approval, is requested by December 31, 2000 in accordance with 10CFR50.55a (g)(5)(iv).
Very truly yours, Robert C.Mecredy Attachment 99iQi5Qi68 99iQQS PDR ADOCK QSQQQ244 p Poa 0 C'
xc: Mr.Guy S.Vissing (Mail Stop 8C2)Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation U.S.Nuclear Regulatory Commission Washington, D.C.20555 Regional Administrator, Region I U.S.Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 U.S.NRC Ginna Senior Resident Inspector ATTACHMENT Rochester Gas and Electric Corporation Ginna Station Docket No.50/244 Third 10-Year Interval Request for Relief No.43 Residual Heat Removal (RHR)Heat Exchanger Outlet Nozzle Welds Examination Limitations System/Component(s) for Which Relief/Exemption is Requested:
This Relief Request pertains to two (2)Residual Heat Removal (RHR)Heat Exchanger Outlet Nozzle to Shell Welds, ASME Class 2, Category C-B, Item C2.32.There is one nozzle of this type associated with each of the two identical RHR Heat Exchangers.
The Code requires that the examination be performed when the component is opened.Both Heat Exchangers were opened and Volumetrically examined.Limited coverage is identified below.Sum~arur II Weld ID a c 169253 ONSRHE-1B 79%due to internal welded separation plate 169053 ONSRHE-1A 79%due to internal welded separation plate II.ASME Section XI Code Requirement:
ASME Section XI Code requires essentially 100%of the weld length or area to obtain coverage.ASME Section XI Code Case N-460 states that if the entire examination volume or area cannot be examined due to interference by another component or part geometry, a reduction in coverage is acceptable provided that the coverage (the lack of)is less than 10%.III.Requirement from Which Relief is Requested:
Relief is requested from examining 100%of the weld length or areas for these two (2)identified items.Examining 100%of the weld length or areas would be impractical due to original design interference.
page 1 of 3 h'equest for Relief No.43 IV.Basis for Relief/Exemption:
Relief is requested pursuant to the provisions of 10 CFR 50.55a(g)(5)(iii), the required examination coverage for the identified items are impractical and would require redesign to allow examination or to be replaced to enable inspection.
The two identical Residual Heat Removal (RHR)Heat Exchangers was designed and constructed to ASME Section VIII, 1965 Edition.This code did not contain requirements to ensure that items be accessible for future examinations.
The two (2)ASME Class 2 items identified above were installed utilizing this construction code which did not provide for accessibility for future ISI NDE.The ISI ASME Section XI volumetric requirement is identified within Table IWC-2500-1, Category C-B, Item Number C2.32.The Residual Heat Removal (RHR)Heat Exchangers is part of the ASME Section XI VT-2 Leakage Examination boundary.Leakage Examinations are performed each period as required by Category C-B, Item Number C2.33 of the Code to insure pressure boundary integrity.
In addition to the ASME Section XI leakage examinations, Operator walkdowns as specified by Plant Operating Procedures are also performed.
The combination of operator walkdowns and period leakage examinations that are performed provide additional assurances in maintaining plant safety.V.Alternate Examinations:
R.E.Ginna Nuclear Power Plant proposes that the volumetric examination coverage identified above be acceptable in fulfilling required volumetric examination coverage.VI.Justification for the Granting of Relief: The Residual Heat Removal (RHR)Heat Exchangers were designed and constructed to ASME Section VIII, 1965 Edition construction code.This code did not contain requirements to ensure that items be made accessible for future NDE examinations.
Due to the original limited design accessibility, examination coverage can not be obtained to the extent required by the current ASME Code.ASME Section XI periodic leakage examinations are performed as well as Operator walkdowns as specified by Plant Operating Procedures.
These operator walkdowns and periodic system leakage examinations provide additional assurances in maintaining plant safety.The identified volumetric examination coverage for these items should be acceptable in fulfilling coverage requirements.
page 2 of3 Request for Relief No.43 It should also be noted that Relief Request Number 43 is similar to RG&E's Relief Request Number 19 and 34, which were previously approved by the NRC.VII.Implementation Schedule: These examinations have been performed, and code credit shall be taken for the Third 10-year Interval inspection.
Page 3 of3 1 SHELL TO UPPER HEAD WELD CCW 10G-AC5-152 10F-AC5-152 SUPPORT LEG LOCATION 3-II-.75" A EAC02A 2 S 36.5 DIA.OUTLET 0 0 C-6 101-AC5-152 I OH AC5-152 INLET 44 HOLES 1,5" DIA.BOLTING O 1A-BT 1B-BT a I I I CCW I I g I FLANGE TO UPPER SHELL WELD CLASS 3 CLASS 2 LOWER SHELL TO FLANGE WELD LSFWRHE INLET NOZZLE TO SHELL INSRHE OUTLET NOZZLE TO SHELL ONSRHE 8E-AC-601 INLET 8C-AC-601 Pu TLP T BA-AC-601 BX-AC-601 INLET REINFORCING PLATE WELD IRPRHE RHEA-2A-AC-601 RHEB-2A-AC-601 RHEA-28-AC-601 RHEB-28-AC-601 UPPER 4 LOWER VESSEL SHELL 304 STAINLESS:
.75 THICK SUPPORT LEGS STAINLESS S..625 THICK A 8 C SOCKET WELD OUTLET REINFORCING PLATE WELD ORPRHE LOWER HEAD TO LOWER SHELL WELD LHLSWRHE RHEA-2C-AC-601 RHEB-2C-AC-601 LINE NO: CALIBRATION BLOCK: REF.DRAWING: WESTINGHOUSE 4807-1 33013-1247 DRAWN BY: ABG DATE: 11/I/95 REVIEWED BY: FAK DRAWING NUMBER REV.RESIDUAL HEAT REMOVAL HT EXCHANGERS FACILITY P E ggP7gg ROCHESTER GAS,hc ELECTRIC CORP.ROCHESTER.
NEW YORK