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| {{#Wiki_filter:.f fc-*.]4*Ju n.ROCHESTER GAS AND ELECTRIC CORFCeATION 8'? EAST AVENUE, ROCHESTER, N.Y.146J9 | | {{#Wiki_filter:* |
| .. ,"l H.s > , a May 29, 1979 Mr. Boyce H. | | . |
| Grier, Director Office of Inspection and Enforcement, Region I U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406 | | f fc- |
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| | ]4* |
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| | ROCHESTER GAS AND ELECTRIC CORFCeATION 8'? EAST AVENUE, ROCHESTER, N.Y.146J9 |
| | .. , "l H.s > , a May 29, 1979 Mr. Boyce H. Grier, Director Office of Inspection and Enforcement, Region I U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| IE Bulletin 79-07 RLNRC-0029 Docket No. 50-485 | | IE Bulletin 79-07 RLNRC-0029 Docket No. 50-485 |
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| ==Dear Mr. Grier:== | | ==Dear Mr. Grier:== |
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| Your letter dated April 14, 1979 forwarded IE Bulletin 79-07 concerning seismic stress analysis of safety related piping. | | Your letter dated April 14, 1979 forwarded IE Bulletin 79-07 concerning seismic stress analysis of safety related piping. The following information is provided in response to your letter. |
| The following information is provided in response to your letter. | | The items below are numbered to correspond to the Bulletin action items. |
| The items below are numbered to correspond to the Bulletin action items.1.All of the seismic analyses for safety related piping were performed properly. | | : 1. All of the seismic analyses for safety related piping were performed properly. None of the methods specified in the bulletin were used in the analyses. |
| None of the methods specified in the bulletin were used in the analyses. | | : 2. This item is not applicable because proper analysis techniques were used. Computer program listings need not be provided. |
| 2.This item is not applicable because proper analysis techniques were used. | | : 3. All computer codes used in the seismic analysis of safety-related piping have verified as shown below: |
| Computer program listings need not be provided. | | (a) ME 632: Verified using PISOL (EDS Nuclear Inc.), |
| 3.All computer codes used in the seismic analysis of safety-related piping have verified as shown below: (a)ME 632: Verified using PISOL (EDS Nuclear Inc.), PIPESD (URS/ John A. | | PIPESD (URS/ John A. Blum and Associates, Engineers), and TPIPE (PMB Systems Engineering Inc.). |
| Blum and Associates, Engineers), and TPIPE (PMB Systems Engineering Inc.).(b)ME 101: Verified using ME 632, TPIPE and SUPERPIPE (EDS Nuclear Inc.).(c)TPIPE: Verified using PISOL (EDS Nuclear Inc.) and ME 632.27'L 158 (d)BSAP: Verified using ME 101.( e)WESTDYN: Refer to WCAP 8252, Rev. | | (b) ME 101: Verified using ME 632, TPIPE and SUPERPIPE (EDS Nuclear Inc.). |
| 1," Documentation of Selected Westinghouse Structural Analysis 79070204'67 | | (c) TPIPE: Verified using PISOL (EDS Nuclear Inc.) and ME 632. |
| / | | (d) BSAP: Verified using ME 101. 27'L 158 |
| ,'ROCHESTER GAS AtJO ELECTRIC CORP. | | ( e) WESTDYN: Refer to WCAP 8252, Rev. 1, " Documentation of Selected Westinghouse Structural Analysis 79070204'67 |
| SHEET No.04TE May 29, 1979 To Mr. Boyce H. | | / |
| Grier 2 Computer Codes", May 1977, which is currently under NRC ceview. | | |
| 4.Because all seismic stress analyses for safety related piping were performed using proper techniques no corrective action plan is necessary. | | , |
| Sincerely yours, t r.O n E.A thur.ief Engineer xc: '.C.R.Anderson Lex K.Larson.N.A.Petrick.Gerald Charnoff | | ' |
| .J.L.Turdera.U.S.Nuclear Regulatory Commission | | ROCHESTER GAS AtJO ELECTRIC CORP. SHEET No. |
| .Office of Inspection and Enforcement Division of Reactor Construction Inspection Washington, DC 20555 272 159}}
| | 04TE May 29, 1979 To Mr. Boyce H. Grier 2 Computer Codes", May 1977, which is currently under NRC ceview. |
| | : 4. Because all seismic stress analyses for safety related piping were performed using proper techniques no corrective action plan is necessary. |
| | Sincerely yours, t r. |
| | O n E. A thur. |
| | ief Engineer xc: '. C. R. Anderson |
| | . Lex K. Larson |
| | . N. A. Petrick |
| | . Gerald Charnoff |
| | . J. L. Turdera |
| | . U.S. Nuclear Regulatory Commission Office of Inspection and Enforcement Division of Reactor Construction Inspection Washington, DC 20555 272 159}} |
|
|---|
Category:CORRESPONDENCE-LETTERS
MONTHYEARML20202D4861998-02-12012 February 1998
Ack Receipt of & Check in Amount of $55,000 in Payment for Civil Penalty Proposed by NRC in . Corrective Actions Will Be Examined During Future Insps
IR 05000485/19960241997-03-0505 March 1997
Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-485/96-24
IR 05000485/19850711986-06-17017 June 1986
Ack Receipt of 851204 & s Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-485/85-71
ML18037A3791982-05-27027 May 1982
Forwards Annual Financial Repts 1981 for Niagara Mohawk Power Corp,Ny State Electric & Gas Corp,Lilco,Rochester Gas & Electric Corp & Central Hudson Gas & Electric Corp
ML17258A1861981-09-22022 September 1981
Forwards Endorsements 73 & 74 to ANI Policy NF-170
ML20003G2671981-04-22022 April 1981
Forwards Second Draft Safety Evaluation of Snupps 10.1,10.2, 10.3,10.4.1 & 10.4.4, Steam & Power Conversion Sys.
ML17258A7951981-02-10010 February 1981
Forwards Summary of Actual Cash Flow for 1980,projected Cash Flow for 1981 & Financial Statement for 3 & 12 Months Ended 801231.Info Supports Util Guarantee to Pay Retrospective Premiums Required by Secondary Financial Protection Sys
ML17258A7371981-01-14014 January 1981
Forwards Public Version of Upgraded Evacuation Time Estimates for Facilities in Response to NRC 801209 Ltr
ML17250A7161980-10-29029 October 1980
Informs of Changes in Organizational Structure Per FE Drake Retirement as Board Chairman & Chief Executive Officer. Corporate Organization Chart,Effective 801001,encl
ML19338C4601980-08-11011 August 1980
Requests Info Re Basis for Denial of Certificate for Facility
ML19320A5831980-06-16016 June 1980
Responds to IE Bulletin 80-09, Hydramotor Actuator Deficiencies. Two safety-related Uses of Itt General Controls Models AH-90 & NH-90 Series Hydramotor Actuators Have Been Identified.Itt Is Testing Actuators
ML17250A3321980-06-12012 June 1980
Comments on 800506 Presentation to NRC Commissioners Re Status of SEP & Description of Difficulty as Lack of Aggression by Licensees.Nrc Has Not Provided Guidelines. Issues W/Higher Priorities Have Arisen
ML19323H2791980-06-0606 June 1980
Responds to IE Bulletin 80-05 Re Vacuum Condition Resulting in Damage to Chemical Vol Control Sys Holdup Tanks.Tank Damage Due to Vacuum Conditions Precluded by Design Provisions or Suitable Vent Connections
ML19318C1861980-06-0202 June 1980
Responds to IE Bulletin 79-28, Possible Malfunction of Namco Model EA180 Limit Switches at Elevated Temps. Top Cover Gaskets on Switches W/Applicable Date Codes Will Be Replaced on Valves Listed in Encl
ML17249A9111980-04-30030 April 1980
Forwards Response to IE Bulletin 80-04. Analysis of PWR Main Steam Line Break W/Continued Feedwater Addition. Auxiliary Feedwater Flow Becomes Dominant Factor in Determining Duration & Magnitude of Steam Flow Transient
ML20003H9601980-04-18018 April 1980
Advises That Licensee Considers 800320 Deficiency Rept Final.No Addl Action Planned Unless Required by New Info
ML19309G0821980-03-20020 March 1980
Responds to IE Bulletin 80-03 Re Charcoal Tray Adsorber Cells.Design & Manufacturer of Adsorber Cells Planned to Be Used Are Different than Type Described in Bulletin
ML19305C3721980-03-20020 March 1980
Informs That Snupps Utils Are Investigating Hardware Changes to Preclude Need for Tests to Correct Deficiency in Engineered Safety Features Actuation Sys.Tests Will Be Made Part of Plant Procedures If Changes Are Not Feasible
ML19305D5111980-03-20020 March 1980
Discusses Undetectable Failure in Engineered Safety Features Actuation Sys.Utils Are Investigating Hardware Changes That May Preclude Further Testing,Provided That Changes Are Feasible.Otherwise,Tests Will Continue
ML19305C3751980-03-20020 March 1980
Informs That C-E 791026 Amend to Rept on IE Bulletin 78-12, Atypical Weld Matl in Reactor Pressure Vessel Welds, Should Be Considered Part of Util Bulletin Response
ML19323D2451980-03-20020 March 1980
Responds to IE Bulletins 78-12,12A & 12B, Atypical Weld Matl in Reactor Pressure Vessel Welds. Util 790629 Ltr & C-E 791026 Ltr to NRC Constitutes Response to Bulletin
ML19323C4271980-03-0606 March 1980
Responds to IE Bulletin 79-28, Possible Malfunction of Namco Model EA180 Limit Switches at Elevated Temps. Identification of Switches Has Required More Time than Anticipated.Util Will Respond as Soon as Possible
ML19309D3451980-03-0606 March 1980
Responds to IE Bulletin 79-28.Investigation Re Planned Use of Namco EA180 Switches,Identification in Snupps Design & Development of Plans for Corrective Action Requires More Time than Anticipated.Will Forward Response Later
ML19294B1451980-02-22022 February 1980
Disagrees W/Nrc Plans Re ATWS Issue.New Plans May Not Serve Best Interests of Public Health & Safety.Nrc Should Not Impose Requirements Before Thorough Review of Mass of Technical Info Supplied Last Year
ML19296C5711980-02-19019 February 1980
Responds to NRC 800204 Ltr Received 800213 Re NRC 800208 Meeting W/Snupps Representatives to Discuss Snupps QA Program.Requests NRC Reschedule Meeting & Provide State Public Svc Commission Sufficient Time to Participate
ML19294B8661980-02-14014 February 1980
Forwards Ny State Board on Electric Generation Siting & Environ 800211 Opinion & Order Vacating Previously Granted Certificate.Denies Application & Closes Proceeding
ML19260D5621980-02-0505 February 1980
Forwards Supplemental Deficiency Rept Re Qualification of Control Sys
ML19309B5491980-02-0505 February 1980
Forwards Supplemental Rept on Potential Deficiency Re Qualification of Control Sys Discussed in Util 790928 Ltr.No Unresolved Safety Concerns Re Pressure Controllers & Main Steam Line Atmospheric Relief Valve
ML19296D9961980-02-0101 February 1980
Responds to IE Bulletin 79-28.Investigation Re Planned Use of Namco EA180 Switches for Snupps Facilities Not Complete.Investigation Results & Corrective Actions Will Be Submitted in 3-4 Wks
ML19294B1891980-01-30030 January 1980
Notifies That Ny State Board on Electric Generation Siting & Environ Voted on 800123 to Rescind Approval of Plant Const & Operation.No Decision Can Be Made Re Continuation of NRC Proceedings Until Util Has Received Formal Opinion
ML19260E0561980-01-30030 January 1980
Notifies of Ny State Board on Electric Generation Siting & Environ 800123 Decision to Rescind Prior Approval of Const & Operation of Facility.No Date Set for Formal Opinion. Certificate of Svc Encl
ML19296B9801980-01-18018 January 1980
Forwards RO Pohl Testimony on Radon Emissions from U Mill Tailings Piles
ML19308C9981980-01-18018 January 1980
Responds to IE Bulletin 79-25.Westinghouse Bfd/Nbfd Relays Are Not Included in safety-related Portions of Design
ML19211D2751980-01-14014 January 1980
Discusses NRC Delay in Review of FSAR & OL Application. Review Schedule Should Be Established Promptly
ML19257B8871980-01-0404 January 1980
Responds to IE Bulletin 79-25, Failures of Westinghouse Bfd Relays in Safety-Related Sys. No Such Relays Have Been Identified.Will Advise Further in Two Wks
ML19291C3061980-01-0303 January 1980
Responds to IE Bulletin 79-02,Revision 2.Initial Response Satisfies Requirements of Revision 1.Facility Does Not Use Concrete Expansion Anchor Bolts to Support Seismic Category I Piping
ML19296D7051980-01-0303 January 1980
Responds to IE Bulletin 79-02,Revision 1.Initial 790705 Response Resolves NRC Concerns Re Use of Concrete Expansion Anchor Bolts for Pipe Support Base Plates.Util Does Not Use Expansion Anchors in Concrete or Structural Steel Members
ML19262C4241980-01-0303 January 1980
Responds to IE Bulletin 79-02,Revision 2, Pipe Support Base Plate Designs Using Concrete Expansion Anchor Bolts. Expansion Anchors in Concrete Block Walls Not Used.Util 790705 Response Need Not Be Modified or Amended
ML17249A4551980-01-0202 January 1980
Supplements 791212 Ltr Listing Six Suits Against Util. Seventh,Ew Garrett Vs Util,Received
ML19262B5671979-12-20020 December 1979
Responds to NRC 791018 Request for Addl Info Re Snupps Fire Protection Sys.Detailed Responses to Requests Will Be Included in FSAR Revision.Clarification of Sys Description Will Show Design in Compliance W/Nrc Requirements
ML19262B5831979-12-14014 December 1979
Discusses Potential Deficiency,Per 791116 Telcon to Nrc. Westinghouse Review Reveals That Dropped Rod Safety Analysis Deficiency May Affect Four Addl Loop Plants.Further Info Will Be Provided by FSAR Revision
ML19253C9361979-12-0606 December 1979
Notifies of Corrective Action for Potential Deficiency Re Engineered Safety Features Actuation Sys.Test Sequence to Detect Failure Will Be Incorporated Into Appropriate Procedures
ML19260C9481979-11-29029 November 1979
Forwards Final Deficiency Rept Re Gulf & Western Preassembly Formations
ML19305B9591979-11-0707 November 1979
Discusses Undetectable Failure in Engineered Safety Features Actuation Sys.Failure of P-4 Permissive Circuit in Both Redundant Protection Trains Could Result in Failure of Sys to Automatically Initiate Protective Function.Details Encl
ML19210C1331979-11-0707 November 1979
Confirms That Snupps FSAR Should Be Considered Tendered by Util.Snupps FSAR Will Be Incorporated by Formal Amend to License Application
ML19211A4241979-11-0101 November 1979
Submits Generic Response to IE Bulletin 79-14, Seismic Analysis for As-Built Safety-Related Piping Sys. Seismic Analysis Input Info Conforms to Actual as-built Configuration of safety-related Sys
ML19254F2061979-11-0101 November 1979
Requests NRC Concurrence on Usage of ASME Section III Code Case N-240, Hydrostatic Testing of Open-Ended Piping, Section Iii,Div 1.
ML19253C5961979-10-26026 October 1979
Responds to IE Bulletin 79-23 Re Potential Failure of Emergency Diesel Generator Field Exciter Transformer.Problem Not Applicable to Snupps Diesel Generators
ML20125B3041979-10-18018 October 1979
Forwards Request for Addl Info Re QA Aspects of Fire Protection Sys for Snupps Portion of Facilities
ML19253C7981979-10-15015 October 1979
Forwards Interim Deficiency Rept Re Qualification of Control Sys.Supplemental Rept in Approx Three Months
1998-02-12
[Table view]
Category:INCOMING CORRESPONDENCE
MONTHYEARML18037A3791982-05-27027 May 1982
Forwards Annual Financial Repts 1981 for Niagara Mohawk Power Corp,Ny State Electric & Gas Corp,Lilco,Rochester Gas & Electric Corp & Central Hudson Gas & Electric Corp
ML17258A1861981-09-22022 September 1981
Forwards Endorsements 73 & 74 to ANI Policy NF-170
ML20003G2671981-04-22022 April 1981
Forwards Second Draft Safety Evaluation of Snupps 10.1,10.2, 10.3,10.4.1 & 10.4.4, Steam & Power Conversion Sys.
ML17258A7951981-02-10010 February 1981
Forwards Summary of Actual Cash Flow for 1980,projected Cash Flow for 1981 & Financial Statement for 3 & 12 Months Ended 801231.Info Supports Util Guarantee to Pay Retrospective Premiums Required by Secondary Financial Protection Sys
ML17258A7371981-01-14014 January 1981
Forwards Public Version of Upgraded Evacuation Time Estimates for Facilities in Response to NRC 801209 Ltr
ML17250A7161980-10-29029 October 1980
Informs of Changes in Organizational Structure Per FE Drake Retirement as Board Chairman & Chief Executive Officer. Corporate Organization Chart,Effective 801001,encl
ML19338C4601980-08-11011 August 1980
Requests Info Re Basis for Denial of Certificate for Facility
ML19320A5831980-06-16016 June 1980
Responds to IE Bulletin 80-09, Hydramotor Actuator Deficiencies. Two safety-related Uses of Itt General Controls Models AH-90 & NH-90 Series Hydramotor Actuators Have Been Identified.Itt Is Testing Actuators
ML17250A3321980-06-12012 June 1980
Comments on 800506 Presentation to NRC Commissioners Re Status of SEP & Description of Difficulty as Lack of Aggression by Licensees.Nrc Has Not Provided Guidelines. Issues W/Higher Priorities Have Arisen
ML19323H2791980-06-0606 June 1980
Responds to IE Bulletin 80-05 Re Vacuum Condition Resulting in Damage to Chemical Vol Control Sys Holdup Tanks.Tank Damage Due to Vacuum Conditions Precluded by Design Provisions or Suitable Vent Connections
ML19318C1861980-06-0202 June 1980
Responds to IE Bulletin 79-28, Possible Malfunction of Namco Model EA180 Limit Switches at Elevated Temps. Top Cover Gaskets on Switches W/Applicable Date Codes Will Be Replaced on Valves Listed in Encl
ML17249A9111980-04-30030 April 1980
Forwards Response to IE Bulletin 80-04. Analysis of PWR Main Steam Line Break W/Continued Feedwater Addition. Auxiliary Feedwater Flow Becomes Dominant Factor in Determining Duration & Magnitude of Steam Flow Transient
ML20003H9601980-04-18018 April 1980
Advises That Licensee Considers 800320 Deficiency Rept Final.No Addl Action Planned Unless Required by New Info
ML19305D5111980-03-20020 March 1980
Discusses Undetectable Failure in Engineered Safety Features Actuation Sys.Utils Are Investigating Hardware Changes That May Preclude Further Testing,Provided That Changes Are Feasible.Otherwise,Tests Will Continue
ML19305C3751980-03-20020 March 1980
Informs That C-E 791026 Amend to Rept on IE Bulletin 78-12, Atypical Weld Matl in Reactor Pressure Vessel Welds, Should Be Considered Part of Util Bulletin Response
ML19305C3721980-03-20020 March 1980
Informs That Snupps Utils Are Investigating Hardware Changes to Preclude Need for Tests to Correct Deficiency in Engineered Safety Features Actuation Sys.Tests Will Be Made Part of Plant Procedures If Changes Are Not Feasible
ML19309G0821980-03-20020 March 1980
Responds to IE Bulletin 80-03 Re Charcoal Tray Adsorber Cells.Design & Manufacturer of Adsorber Cells Planned to Be Used Are Different than Type Described in Bulletin
ML19323D2451980-03-20020 March 1980
Responds to IE Bulletins 78-12,12A & 12B, Atypical Weld Matl in Reactor Pressure Vessel Welds. Util 790629 Ltr & C-E 791026 Ltr to NRC Constitutes Response to Bulletin
ML19309D3451980-03-0606 March 1980
Responds to IE Bulletin 79-28.Investigation Re Planned Use of Namco EA180 Switches,Identification in Snupps Design & Development of Plans for Corrective Action Requires More Time than Anticipated.Will Forward Response Later
ML19323C4271980-03-0606 March 1980
Responds to IE Bulletin 79-28, Possible Malfunction of Namco Model EA180 Limit Switches at Elevated Temps. Identification of Switches Has Required More Time than Anticipated.Util Will Respond as Soon as Possible
ML19294B1451980-02-22022 February 1980
Disagrees W/Nrc Plans Re ATWS Issue.New Plans May Not Serve Best Interests of Public Health & Safety.Nrc Should Not Impose Requirements Before Thorough Review of Mass of Technical Info Supplied Last Year
ML19296C5711980-02-19019 February 1980
Responds to NRC 800204 Ltr Received 800213 Re NRC 800208 Meeting W/Snupps Representatives to Discuss Snupps QA Program.Requests NRC Reschedule Meeting & Provide State Public Svc Commission Sufficient Time to Participate
ML19294B8661980-02-14014 February 1980
Forwards Ny State Board on Electric Generation Siting & Environ 800211 Opinion & Order Vacating Previously Granted Certificate.Denies Application & Closes Proceeding
ML19309B5491980-02-0505 February 1980
Forwards Supplemental Rept on Potential Deficiency Re Qualification of Control Sys Discussed in Util 790928 Ltr.No Unresolved Safety Concerns Re Pressure Controllers & Main Steam Line Atmospheric Relief Valve
ML19260D5621980-02-0505 February 1980
Forwards Supplemental Deficiency Rept Re Qualification of Control Sys
ML19296D9961980-02-0101 February 1980
Responds to IE Bulletin 79-28.Investigation Re Planned Use of Namco EA180 Switches for Snupps Facilities Not Complete.Investigation Results & Corrective Actions Will Be Submitted in 3-4 Wks
ML19294B1891980-01-30030 January 1980
Notifies That Ny State Board on Electric Generation Siting & Environ Voted on 800123 to Rescind Approval of Plant Const & Operation.No Decision Can Be Made Re Continuation of NRC Proceedings Until Util Has Received Formal Opinion
ML19260E0561980-01-30030 January 1980
Notifies of Ny State Board on Electric Generation Siting & Environ 800123 Decision to Rescind Prior Approval of Const & Operation of Facility.No Date Set for Formal Opinion. Certificate of Svc Encl
ML19296B9801980-01-18018 January 1980
Forwards RO Pohl Testimony on Radon Emissions from U Mill Tailings Piles
ML19308C9981980-01-18018 January 1980
Responds to IE Bulletin 79-25.Westinghouse Bfd/Nbfd Relays Are Not Included in safety-related Portions of Design
ML19211D2751980-01-14014 January 1980
Discusses NRC Delay in Review of FSAR & OL Application. Review Schedule Should Be Established Promptly
ML19257B8871980-01-0404 January 1980
Responds to IE Bulletin 79-25, Failures of Westinghouse Bfd Relays in Safety-Related Sys. No Such Relays Have Been Identified.Will Advise Further in Two Wks
ML19296D7051980-01-0303 January 1980
Responds to IE Bulletin 79-02,Revision 1.Initial 790705 Response Resolves NRC Concerns Re Use of Concrete Expansion Anchor Bolts for Pipe Support Base Plates.Util Does Not Use Expansion Anchors in Concrete or Structural Steel Members
ML19262C4241980-01-0303 January 1980
Responds to IE Bulletin 79-02,Revision 2, Pipe Support Base Plate Designs Using Concrete Expansion Anchor Bolts. Expansion Anchors in Concrete Block Walls Not Used.Util 790705 Response Need Not Be Modified or Amended
ML19291C3061980-01-0303 January 1980
Responds to IE Bulletin 79-02,Revision 2.Initial Response Satisfies Requirements of Revision 1.Facility Does Not Use Concrete Expansion Anchor Bolts to Support Seismic Category I Piping
ML17249A4551980-01-0202 January 1980
Supplements 791212 Ltr Listing Six Suits Against Util. Seventh,Ew Garrett Vs Util,Received
ML19262B5671979-12-20020 December 1979
Responds to NRC 791018 Request for Addl Info Re Snupps Fire Protection Sys.Detailed Responses to Requests Will Be Included in FSAR Revision.Clarification of Sys Description Will Show Design in Compliance W/Nrc Requirements
ML19262B5831979-12-14014 December 1979
Discusses Potential Deficiency,Per 791116 Telcon to Nrc. Westinghouse Review Reveals That Dropped Rod Safety Analysis Deficiency May Affect Four Addl Loop Plants.Further Info Will Be Provided by FSAR Revision
ML19253C9361979-12-0606 December 1979
Notifies of Corrective Action for Potential Deficiency Re Engineered Safety Features Actuation Sys.Test Sequence to Detect Failure Will Be Incorporated Into Appropriate Procedures
ML19260C9481979-11-29029 November 1979
Forwards Final Deficiency Rept Re Gulf & Western Preassembly Formations
ML19210C1331979-11-0707 November 1979
Confirms That Snupps FSAR Should Be Considered Tendered by Util.Snupps FSAR Will Be Incorporated by Formal Amend to License Application
ML19305B9591979-11-0707 November 1979
Discusses Undetectable Failure in Engineered Safety Features Actuation Sys.Failure of P-4 Permissive Circuit in Both Redundant Protection Trains Could Result in Failure of Sys to Automatically Initiate Protective Function.Details Encl
ML19254F2061979-11-0101 November 1979
Requests NRC Concurrence on Usage of ASME Section III Code Case N-240, Hydrostatic Testing of Open-Ended Piping, Section Iii,Div 1.
ML19211A4241979-11-0101 November 1979
Submits Generic Response to IE Bulletin 79-14, Seismic Analysis for As-Built Safety-Related Piping Sys. Seismic Analysis Input Info Conforms to Actual as-built Configuration of safety-related Sys
ML19253C5961979-10-26026 October 1979
Responds to IE Bulletin 79-23 Re Potential Failure of Emergency Diesel Generator Field Exciter Transformer.Problem Not Applicable to Snupps Diesel Generators
ML19253C7981979-10-15015 October 1979
Forwards Interim Deficiency Rept Re Qualification of Control Sys.Supplemental Rept in Approx Three Months
ML17249A1791979-10-0808 October 1979
Responds to 790808 Ltr Re Adequacy of Station Electric Distribution Sys Voltages.Submits Sys Model & Acceptance Criteria for Use W/Proprietary Code PTI-PSS/E to Verify Offsite Power Capability.Final Rept Submitted in 60 Days
ML19268C0321979-10-0505 October 1979
Responds to IE Bulletin 79-03 Followup Rept.Data Developed on Generic Basis & Considered Applicable to All Snupps Units.Fabrication & Installation of Youngstown Pipe Spools Will Proceed W/All Matl Analyzed Prior to Use
ML19209C2201979-10-0202 October 1979
Forwards Snupps FSAR to Be Incorporated Into Applications for OLs
ML19250A6451979-09-28028 September 1979
Notifies That Licensee Informed NRC on 790830 of Potential Deficiency Re Qualification of Control Sys Which Was Later Subj of IE Info Notice 79-22.Suppl Rept Will Be Issued in About 90 Days
1982-05-27
[Table view]
Category:UTILITY TO NRC
MONTHYEARML17258A7951981-02-10010 February 1981
Forwards Summary of Actual Cash Flow for 1980,projected Cash Flow for 1981 & Financial Statement for 3 & 12 Months Ended 801231.Info Supports Util Guarantee to Pay Retrospective Premiums Required by Secondary Financial Protection Sys
ML17258A7371981-01-14014 January 1981
Forwards Public Version of Upgraded Evacuation Time Estimates for Facilities in Response to NRC 801209 Ltr
ML17250A7161980-10-29029 October 1980
Informs of Changes in Organizational Structure Per FE Drake Retirement as Board Chairman & Chief Executive Officer. Corporate Organization Chart,Effective 801001,encl
ML19320A5831980-06-16016 June 1980
Responds to IE Bulletin 80-09, Hydramotor Actuator Deficiencies. Two safety-related Uses of Itt General Controls Models AH-90 & NH-90 Series Hydramotor Actuators Have Been Identified.Itt Is Testing Actuators
ML17250A3321980-06-12012 June 1980
Comments on 800506 Presentation to NRC Commissioners Re Status of SEP & Description of Difficulty as Lack of Aggression by Licensees.Nrc Has Not Provided Guidelines. Issues W/Higher Priorities Have Arisen
ML19323H2791980-06-0606 June 1980
Responds to IE Bulletin 80-05 Re Vacuum Condition Resulting in Damage to Chemical Vol Control Sys Holdup Tanks.Tank Damage Due to Vacuum Conditions Precluded by Design Provisions or Suitable Vent Connections
ML19318C1861980-06-0202 June 1980
Responds to IE Bulletin 79-28, Possible Malfunction of Namco Model EA180 Limit Switches at Elevated Temps. Top Cover Gaskets on Switches W/Applicable Date Codes Will Be Replaced on Valves Listed in Encl
ML17249A9111980-04-30030 April 1980
Forwards Response to IE Bulletin 80-04. Analysis of PWR Main Steam Line Break W/Continued Feedwater Addition. Auxiliary Feedwater Flow Becomes Dominant Factor in Determining Duration & Magnitude of Steam Flow Transient
ML20003H9601980-04-18018 April 1980
Advises That Licensee Considers 800320 Deficiency Rept Final.No Addl Action Planned Unless Required by New Info
ML19323D2451980-03-20020 March 1980
Responds to IE Bulletins 78-12,12A & 12B, Atypical Weld Matl in Reactor Pressure Vessel Welds. Util 790629 Ltr & C-E 791026 Ltr to NRC Constitutes Response to Bulletin
ML19305C3721980-03-20020 March 1980
Informs That Snupps Utils Are Investigating Hardware Changes to Preclude Need for Tests to Correct Deficiency in Engineered Safety Features Actuation Sys.Tests Will Be Made Part of Plant Procedures If Changes Are Not Feasible
ML19309G0821980-03-20020 March 1980
Responds to IE Bulletin 80-03 Re Charcoal Tray Adsorber Cells.Design & Manufacturer of Adsorber Cells Planned to Be Used Are Different than Type Described in Bulletin
ML19305C3751980-03-20020 March 1980
Informs That C-E 791026 Amend to Rept on IE Bulletin 78-12, Atypical Weld Matl in Reactor Pressure Vessel Welds, Should Be Considered Part of Util Bulletin Response
ML19305D5111980-03-20020 March 1980
Discusses Undetectable Failure in Engineered Safety Features Actuation Sys.Utils Are Investigating Hardware Changes That May Preclude Further Testing,Provided That Changes Are Feasible.Otherwise,Tests Will Continue
ML19309D3451980-03-0606 March 1980
Responds to IE Bulletin 79-28.Investigation Re Planned Use of Namco EA180 Switches,Identification in Snupps Design & Development of Plans for Corrective Action Requires More Time than Anticipated.Will Forward Response Later
ML19323C4271980-03-0606 March 1980
Responds to IE Bulletin 79-28, Possible Malfunction of Namco Model EA180 Limit Switches at Elevated Temps. Identification of Switches Has Required More Time than Anticipated.Util Will Respond as Soon as Possible
ML19294B1451980-02-22022 February 1980
Disagrees W/Nrc Plans Re ATWS Issue.New Plans May Not Serve Best Interests of Public Health & Safety.Nrc Should Not Impose Requirements Before Thorough Review of Mass of Technical Info Supplied Last Year
ML19309B5491980-02-0505 February 1980
Forwards Supplemental Rept on Potential Deficiency Re Qualification of Control Sys Discussed in Util 790928 Ltr.No Unresolved Safety Concerns Re Pressure Controllers & Main Steam Line Atmospheric Relief Valve
ML19260D5621980-02-0505 February 1980
Forwards Supplemental Deficiency Rept Re Qualification of Control Sys
ML19296D9961980-02-0101 February 1980
Responds to IE Bulletin 79-28.Investigation Re Planned Use of Namco EA180 Switches for Snupps Facilities Not Complete.Investigation Results & Corrective Actions Will Be Submitted in 3-4 Wks
ML19308C9981980-01-18018 January 1980
Responds to IE Bulletin 79-25.Westinghouse Bfd/Nbfd Relays Are Not Included in safety-related Portions of Design
ML19211D2751980-01-14014 January 1980
Discusses NRC Delay in Review of FSAR & OL Application. Review Schedule Should Be Established Promptly
ML19257B8871980-01-0404 January 1980
Responds to IE Bulletin 79-25, Failures of Westinghouse Bfd Relays in Safety-Related Sys. No Such Relays Have Been Identified.Will Advise Further in Two Wks
ML19291C3061980-01-0303 January 1980
Responds to IE Bulletin 79-02,Revision 2.Initial Response Satisfies Requirements of Revision 1.Facility Does Not Use Concrete Expansion Anchor Bolts to Support Seismic Category I Piping
ML19296D7051980-01-0303 January 1980
Responds to IE Bulletin 79-02,Revision 1.Initial 790705 Response Resolves NRC Concerns Re Use of Concrete Expansion Anchor Bolts for Pipe Support Base Plates.Util Does Not Use Expansion Anchors in Concrete or Structural Steel Members
ML19262C4241980-01-0303 January 1980
Responds to IE Bulletin 79-02,Revision 2, Pipe Support Base Plate Designs Using Concrete Expansion Anchor Bolts. Expansion Anchors in Concrete Block Walls Not Used.Util 790705 Response Need Not Be Modified or Amended
ML19262B5671979-12-20020 December 1979
Responds to NRC 791018 Request for Addl Info Re Snupps Fire Protection Sys.Detailed Responses to Requests Will Be Included in FSAR Revision.Clarification of Sys Description Will Show Design in Compliance W/Nrc Requirements
ML19262B5831979-12-14014 December 1979
Discusses Potential Deficiency,Per 791116 Telcon to Nrc. Westinghouse Review Reveals That Dropped Rod Safety Analysis Deficiency May Affect Four Addl Loop Plants.Further Info Will Be Provided by FSAR Revision
ML19253C9361979-12-0606 December 1979
Notifies of Corrective Action for Potential Deficiency Re Engineered Safety Features Actuation Sys.Test Sequence to Detect Failure Will Be Incorporated Into Appropriate Procedures
ML19260C9481979-11-29029 November 1979
Forwards Final Deficiency Rept Re Gulf & Western Preassembly Formations
ML19210C1331979-11-0707 November 1979
Confirms That Snupps FSAR Should Be Considered Tendered by Util.Snupps FSAR Will Be Incorporated by Formal Amend to License Application
ML19211A4241979-11-0101 November 1979
Submits Generic Response to IE Bulletin 79-14, Seismic Analysis for As-Built Safety-Related Piping Sys. Seismic Analysis Input Info Conforms to Actual as-built Configuration of safety-related Sys
ML19254F2061979-11-0101 November 1979
Requests NRC Concurrence on Usage of ASME Section III Code Case N-240, Hydrostatic Testing of Open-Ended Piping, Section Iii,Div 1.
ML19253C5961979-10-26026 October 1979
Responds to IE Bulletin 79-23 Re Potential Failure of Emergency Diesel Generator Field Exciter Transformer.Problem Not Applicable to Snupps Diesel Generators
ML19253C7981979-10-15015 October 1979
Forwards Interim Deficiency Rept Re Qualification of Control Sys.Supplemental Rept in Approx Three Months
ML17249A1791979-10-0808 October 1979
Responds to 790808 Ltr Re Adequacy of Station Electric Distribution Sys Voltages.Submits Sys Model & Acceptance Criteria for Use W/Proprietary Code PTI-PSS/E to Verify Offsite Power Capability.Final Rept Submitted in 60 Days
ML19268C0321979-10-0505 October 1979
Responds to IE Bulletin 79-03 Followup Rept.Data Developed on Generic Basis & Considered Applicable to All Snupps Units.Fabrication & Installation of Youngstown Pipe Spools Will Proceed W/All Matl Analyzed Prior to Use
ML19209C2201979-10-0202 October 1979
Forwards Snupps FSAR to Be Incorporated Into Applications for OLs
ML19209A5161979-09-28028 September 1979
Forwards First Deficiency Rept Re Qualification of Control Sys.Next Rept Will Be Submitted in Approx Three Months
ML19250A6451979-09-28028 September 1979
Notifies That Licensee Informed NRC on 790830 of Potential Deficiency Re Qualification of Control Sys Which Was Later Subj of IE Info Notice 79-22.Suppl Rept Will Be Issued in About 90 Days
ML19209A3941979-09-10010 September 1979
Responds to IE Bulletin 79-15, Deep Draft Pump Deficiencies, Re safety-related Application,Mfg & Overall Dimensions
ML19249A0651979-07-24024 July 1979
Responds to IE Bulletin 79-11.No Westinghouse Type DB-50 or 75 Circuit Breakers Included in Any safety-related Applications
ML19247B2961979-07-0505 July 1979
Forwards Rept on Pipe-Support Base Plate Designs Using Concrete Expansion Anchor Bolts, in Response to IE Bulletin 79-02.Response Is Result of Review Design & Installation Practices & Procedures for Anchor Bolts
ML19242B1141979-06-29029 June 1979
Responds to IE Bulletins 78-12,12A & 12B.C-E Submitted Rept Containing Info Requested Re Atypical Weld Matl in Reactor Pressure Vessel Welds.Westinghouse Will Inventory Archive Surveillance Weldment Matl to Be Used for Verification
ML17244A5691979-06-20020 June 1979
Requests Notification of Date for Meeting W/Nrc to Discuss Computer Models Which Reflect Upper Plenum Injection of ECCS
ML19247B0501979-06-15015 June 1979
Responds to IE Bulletin 79-09.GE Type AK-2 Circuit Breakers Not Used or Planned for Use in Design of safety-related Sys
ML19259C0491979-06-0101 June 1979
Requests NRC Concurrence Re Use of ASME Section III Code Case N-242,Matls Certification.
ML19273B6981979-05-30030 May 1979
Confirms Plan to Discuss & Resolve Matters Re Fuel Rod Bowing Effects in Snupps FSAR
ML19224C5241979-05-29029 May 1979
Responds to IE Bulletin 79-07 Re Seismic Stress Analysis of safety-related Piping.All Analyses Properly Performed & Methods Specified in Bulletin Not Used
ML19224D2931979-05-18018 May 1979
Responds to IE Bulletin 79-04.Component Cooling & Essential Svc Water Sys,Reactor Coolant,Auxiliary Feedwater,Feedwater, Compresed Air & Auxiliary Turbines Sys Will Use 3.4 or 6-inch Velan Swing Check Valves
1981-02-10
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ROCHESTER GAS AND ELECTRIC CORFCeATION 8'? EAST AVENUE, ROCHESTER, N.Y.146J9
.. , "l H.s > , a May 29, 1979 Mr. Boyce H. Grier, Director Office of Inspection and Enforcement, Region I U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406
SUBJECT:
IE Bulletin 79-07 RLNRC-0029 Docket No. 50-485
Dear Mr. Grier:
Your letter dated April 14, 1979 forwarded IE Bulletin 79-07 concerning seismic stress analysis of safety related piping. The following information is provided in response to your letter.
The items below are numbered to correspond to the Bulletin action items.
- 1. All of the seismic analyses for safety related piping were performed properly. None of the methods specified in the bulletin were used in the analyses.
- 2. This item is not applicable because proper analysis techniques were used. Computer program listings need not be provided.
- 3. All computer codes used in the seismic analysis of safety-related piping have verified as shown below:
(a) ME 632: Verified using PISOL (EDS Nuclear Inc.),
PIPESD (URS/ John A. Blum and Associates, Engineers), and TPIPE (PMB Systems Engineering Inc.).
(b) ME 101: Verified using ME 632, TPIPE and SUPERPIPE (EDS Nuclear Inc.).
(c) TPIPE: Verified using PISOL (EDS Nuclear Inc.) and ME 632.
(d) BSAP: Verified using ME 101. 27'L 158
( e) WESTDYN: Refer to WCAP 8252, Rev. 1, " Documentation of Selected Westinghouse Structural Analysis 79070204'67
/
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ROCHESTER GAS AtJO ELECTRIC CORP. SHEET No.
04TE May 29, 1979 To Mr. Boyce H. Grier 2 Computer Codes", May 1977, which is currently under NRC ceview.
- 4. Because all seismic stress analyses for safety related piping were performed using proper techniques no corrective action plan is necessary.
Sincerely yours, t r.
O n E. A thur.
ief Engineer xc: '. C. R. Anderson
. Lex K. Larson
. N. A. Petrick
. Gerald Charnoff
. J. L. Turdera
. U.S. Nuclear Regulatory Commission Office of Inspection and Enforcement Division of Reactor Construction Inspection Washington, DC 20555 272 159