Advises That Augmented Natural Circulation Training Should Be Performed.Descriptions of Natural Circulation Tests Should Be Included in Fsar.Detailed Test Procedures Must Be Submitted 60 Days Prior to Scheduled Test PerformanceML20126M431 |
Person / Time |
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Site: |
Cherokee ![Duke Energy icon.png](/w/images/7/75/Duke_Energy_icon.png) |
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Issue date: |
06/12/1981 |
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From: |
Tedesco R Office of Nuclear Reactor Regulation |
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To: |
Dail L DUKE POWER CO. |
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References |
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RTR-NUREG-0694, RTR-NUREG-0737, TASK-1.G.1, TASK-TM NUDOCS 8106180128 |
Download: ML20126M431 (4) |
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20195C5131999-05-28028 May 1999 Forwards Revs to Sections 3.9 & 5.6 of Its,Based on Resolution Telcons Held Between NRC Staff & Util on 990526 & 27 ML20138Q8301985-12-0303 December 1985 Further Response to FOIA Request for Records Re Voluntary or Required Redress of Sites Where Const Was Terminated, Including Crbr & Legal Analysis.Forwards App E Documents.App D & E Documents Available in Pdr.Photographs Also Available ML20132A8831985-09-12012 September 1985 Responds to 830921 Request That CPPR-167,CPPR-168 & CPPR-169 Be Deleted.Stabilization Plan Has No Significant Environ Impact.Dockets Changed to Canceled Status ML20098G6271984-09-27027 September 1984 Forwards Responses to 840617 Request for Addl Info in Order to Complete Review of Facility Site Stabilization Plan.W/Two Oversize Maps.Aperture Cards Available in PDR ML20095E3971984-08-16016 August 1984 Forwards Duke Power Co & North Carolina Municipal Power Agency 1 1983 Annual Repts LG-84-332, Forwards Most Recent Aerial Photographs of Site for Review of Stabilization Plan.W/O Encl1984-04-24024 April 1984 Forwards Most Recent Aerial Photographs of Site for Review of Stabilization Plan.W/O Encl ML20078C2031983-09-21021 September 1983 Requests Cancellation of CPPR-167,CPPR-168 & CPPR-169 Based on Current & Predicated Economic Conditions.Stabilization Plan Encl LG-83-314, Responds to NRC Requiring Detailed Analysis of TMI Action Item II.K.3.5, Automatic Trip of Reactor Coolant Pumps. Analysis Will Not Be Submitted,Due to Indefinite Delay in Const of Facility1983-04-0707 April 1983 Responds to NRC Requiring Detailed Analysis of TMI Action Item II.K.3.5, Automatic Trip of Reactor Coolant Pumps. Analysis Will Not Be Submitted,Due to Indefinite Delay in Const of Facility LG-83-163, Forwards Amend 19 to Duke Power Nuclear Guides.Amend 20 Will Be Forwarded in Apr 19831983-02-18018 February 1983 Forwards Amend 19 to Duke Power Nuclear Guides.Amend 20 Will Be Forwarded in Apr 1983 LG-83-049, Forwards Response to 821210 Request for Addl Info on IE Bulletin 81-03, Flow Blockage of Cooling Water to Safety Sys Components by Corbicula Sp (Asiatic Clam) & Mytilus Sp (Mussel). Monitoring Program for Clams to Be Established1983-01-17017 January 1983 Forwards Response to 821210 Request for Addl Info on IE Bulletin 81-03, Flow Blockage of Cooling Water to Safety Sys Components by Corbicula Sp (Asiatic Clam) & Mytilus Sp (Mussel). Monitoring Program for Clams to Be Established ML20063E6521982-08-24024 August 1982 Forwards Util & Nc Municipal Power Agency Annual Financial Repts for 1981 ML20062K3871982-05-20020 May 1982 Forwards First Quarter 1982 Yellow Book Updates Re Const Status ML20052F0901982-05-0404 May 1982 Informs That Addl Action Will Be Required in Order to Fully Comply W/Asme Code Requirements for Radiography of safe-end Welds.Discrepancy Will Be Resolved by re-radiographing Affected Welds ML20038D1361981-11-0303 November 1981 Responds to NRC 811014 Ltr Re Violations Noted in IE Insp Repts 50-491/81-03,50-492/81-03 & 50-493/81-03.Corrective Actions:Gas Cans Have Been Emptied & Placed in Motor Pool Storage Area ML20009D9001981-07-0808 July 1981 Responds to IE Bulletin 81-03 Re Blockage of Cooling Water to Safety Sys Components by Clams & Mussels.Provisions Will Be Made to Minimize Introduction of Clams Into Raw Water Sys.Fifteen Manhours Expended in Preparation of Bulletin NUREG-0694, Advises That Augmented Natural Circulation Training Should Be Performed.Descriptions of Natural Circulation Tests Should Be Included in Fsar.Detailed Test Procedures Must Be Submitted 60 Days Prior to Scheduled Test Performance1981-06-12012 June 1981 Advises That Augmented Natural Circulation Training Should Be Performed.Descriptions of Natural Circulation Tests Should Be Included in Fsar.Detailed Test Procedures Must Be Submitted 60 Days Prior to Scheduled Test Performance ML20004C2561981-05-28028 May 1981 Requests Authorization to Use ASME Code Cases 1481-2,1592-14 & 1644-8 in Fabrication of Primary Sys Components for Facilities ML19347D3491981-03-12012 March 1981 Responds to NRC 810223 Request for Addl Info Re Util Plans for Facilities.Completion of Cherokee 1 & 2 Has Been Indefinitely Delayed.Commercial Operating Dates for Cherokee 3 & Perkins 1,2 & 3 Have Not Been Determined ML19347D0311981-03-0404 March 1981 Forwards 810224 Press Release Re Delay of Facility Completion.Financial Situation Has Pushed Facility Completion Into Indefinite Future ML20008E7621981-02-24024 February 1981 Forwards PWR Const Milestones & Activities for McGuire 1 & 2,Catawba 1 & 2 & Cherokee 1.Key Event Dates Provided ML20003C2891981-02-11011 February 1981 Responds to IE Bulletin 80-23, Failures of Solenoid Valves Mfg by Valcor Engineering Corp. Bulletin Does Not Apply ML19345F3631981-02-0505 February 1981 Forwards Evacuation Time Estimates & Color Overlay Site Map, Per Discussions w/P81 Project Manager.W/O Site Map ML19345G0801981-01-27027 January 1981 Forwards Revision 1 to Response Re IE Bulletin 79-14 Revision 1,Suppl 2, Seismic Analysis for As-Built Safety-Related Piping Sys. Describes Program Which Will Give Assurance That Design Documents Reflect Sys Conditions ML19351F9851981-01-27027 January 1981 Responds to IE Bulletin 80-21, Valve Yokes Supplied by Malcolm Foundry Co,Inc. No safety-related Valves Using Specified Valve Yokes Are Used ML20002B9171980-11-11011 November 1980 Forwards Supplemental Responses to NRC 801016 Ltr Re Violations Noted in IE Insp Repts 50-369/80-08,50-370/80-05, 50-413/80-09,50-414/80-09,50-491/80-02,50-492/80-06 & 50-493/80-06.Final Rept to Be Submitted by 810131 ML19340B1411980-10-14014 October 1980 Requests Load Info Re Design Pressure,Loca & SSE Loads & Drawings for Five Containment Vessels Referred to in Statement of Work for FY81 ML19344E9781980-08-29029 August 1980 Responds to IE Bulletin 80-19,Revision 1.No mercury-wetted Matrix Relays Are Used or Planned for Use in Reactor Protection Sys ML19344F1871980-08-26026 August 1980 Responds to IE Bulletin 80-16.No Rosemount Models 1151 & 1152 Pressure Transmitters Are Used in safety-related Applications ML19336A6421980-08-15015 August 1980 Responds to NRC 800718 Ltr Re Violations Noted in IE Insp Repts 50-369/80-08,50-370/80-05,50-413/80-09,50-414/80-09, 50-491/80-07,50-492/80-06 & 50-493/80-06.Corrective Actions: Records Storage Facility Constructed ML19344E5061980-08-14014 August 1980 Responds to IE Bulletin 80-20, Failure of Westinghouse Type W-2 Spring Return to Neutral Control Switches. Review Showed No Westinghouse Type W-2 Switches Used in safety- Related Applications ML19331D3631980-08-0606 August 1980 Submits Response to IE Bulletin 79-03A.No SA-312 or A-312, Type 300 Series Fusion Welded Pipe in Use or Planned for Use Is Subj to Design Stresses Greater than 85% of ASME Code Allowable Stresses ML19338C3401980-08-0404 August 1980 Ack Receipt of IE Insp Repts 50-491/80-09,50-492/80-08 & 50-493/80-08 on 800611-13.No Proprietary Info ML19331B6111980-08-0404 August 1980 Submits Const Completion & Fuel Load Target Dates,In Response to NRC 800711 Ltr.For Unit 1,const Completion & Fuel Load Target Dates Are Jul 1980 & Jul 1991 for Unit 2.OL Application to Be Submitted by Sept 1986 ML19327A5411980-07-31031 July 1980 Responds to 800702 Request for Info Re Evacuation Times for Power Plants W/Current or Pending Cps.Cherokee & Perkins Stations Pose No Population Density Situation Which Would Cause Long Evacuation Times ML19331C2621980-07-28028 July 1980 Ack Receipt of IE Insp Repts 50-491/80-08,50-492/80-07 & 50-493/80-07 on 800624-25.No Proprietary Info ML19326E0641980-07-0707 July 1980 Forwards Response to IE Bulletin 80-08, Exam of Containment Liner Penetration Welds. Piping Penetrations Are Designed & Fabricated in Accordance w/1977 Edition of ASME Boiler & Pressure Vessel Code,Including Summer 1977 Addenda ML19327A0081980-06-25025 June 1980 Responds to NRC 790627 Ltr Re Violation Noted in IE Insp Repts 50-491/79-10,50-492/79-10 & 50-493/79-10.Corrective Actions:Corrected Procedure for Determining Bulk Density of Test Sand & Increased Testing of Filter Matl ML19318A8361980-06-0909 June 1980 Forwards Response to IE Bulletin 80-05 Re Vacuum Conditions Resulting in Damage to Holdup Tanks.Lists Vacuum Conditions in Low Pressure & Holdup Tanks by Tank Name,Sys,Quantity/ Unit,Design Pressure & Protective Measures ML19323G8791980-05-0808 May 1980 Ack Receipt of IE Insp Repts 50-491/80-05,50-492/80-05 & 50-493/80-05.No Proprietary Info ML19309G2151980-04-0303 April 1980 Ack Receipt of IE Insp Repts 50-491/80-04,50-492/80-04 & 50-493/80-04 on 800304-07.No Proprietary Info ML19309E8061980-03-28028 March 1980 Ack Receipt of IE Insp Repts 50-491/80-03,50-492/80-03 & 50-493/80-03 on 800303-05.No Proprietary Info ML19305D9951980-03-28028 March 1980 Ack Receipt of IE Insp Repts 50-491/80-02,50-492/80-02 & 50-493/80-02 on 800226-29. No Proprietary Info ML19305E1751980-03-19019 March 1980 Submits Response to IE Bulletin 80-03.Review Revealed That No Charcoal Adsorber Cells Have Been Received from Manufacturers ML19294B8521980-02-11011 February 1980 Ack Receipt of IE Insp Repts 50-491/80-01,50-492/80-01 & 50-493/80-01.No Proprietary Info ML19312D1301980-02-0505 February 1980 Responds to IE Bulletin 79-28.No Namco EA180 Limit Switches from Affected Production Period Are Used or Planned for Use ML19262C2231980-02-0404 February 1980 Informs of Change in Projected Commercial Operation Dates for Facilities.Units 1 & 2 Will Be Placed in Commercial Operation in Jan 1990 & Jan 1992,respectively.FSAR Will Be Filed in Jan 1987.Schedules Are Periodically Reviewed ML19312D5911980-01-22022 January 1980 Responds to NRC 791227 Ltr Re Violations Noted in IE Insp Repts 50-491/79-20,50-492/79-20,& 50-493/79-20.Corrective Actions:Samples Taken,Nonconforming Item Report Written & Computer Tickler Sys Implemented ML19305B9131980-01-15015 January 1980 Responds to NRC 791227 Ltr Re Violations Noted in IE Insp Repts 50-491/79-20,50-492/79-20 & 50-493/79-20.Corrective Actions:Concrete Aggregate Samples Taken,Nonconforming Item Rept Written & Computerized Tickler Sys Implemented ML19257D5661980-01-0707 January 1980 Forwards Revision to Response to IE Bulletin 79-02,Revision 2,re Pipe Support Base Plate Designs.Will Account for Base Plate Flexibility in Calculations of Bolt Loads by Using Conservative Hand Calculation Method ML19257D3801980-01-0404 January 1980 Responds to IE Bulletin 79-25, Failures of Westinghouse Bfd Relays in Safety-Related Sys. No Westinghouse Bfd/Nbfd Relays Are Used in safety-related Sys 1999-05-28
[Table view] Category:NRC TO UTILITY
MONTHYEARML20132A8831985-09-12012 September 1985 Responds to 830921 Request That CPPR-167,CPPR-168 & CPPR-169 Be Deleted.Stabilization Plan Has No Significant Environ Impact.Dockets Changed to Canceled Status NUREG-0694, Advises That Augmented Natural Circulation Training Should Be Performed.Descriptions of Natural Circulation Tests Should Be Included in Fsar.Detailed Test Procedures Must Be Submitted 60 Days Prior to Scheduled Test Performance1981-06-12012 June 1981 Advises That Augmented Natural Circulation Training Should Be Performed.Descriptions of Natural Circulation Tests Should Be Included in Fsar.Detailed Test Procedures Must Be Submitted 60 Days Prior to Scheduled Test Performance ML19351F9851981-01-27027 January 1981 Responds to IE Bulletin 80-21, Valve Yokes Supplied by Malcolm Foundry Co,Inc. No safety-related Valves Using Specified Valve Yokes Are Used ML20147J2401978-12-19019 December 1978 Forwards IE Bulletin 78-14 ML20204C7901978-11-24024 November 1978 Forwards IE Bulletin 78-12A,suppl to IE Bulletin 78-12. W/Encl ANO:7811300055 ML20062E9391978-11-24024 November 1978 Forwards IE Inspec Repts 50-491/78-08, 50-492/78-08 & 50-493/78-08 on 781030-1102 & Notice of Violation ML20148R4361978-11-16016 November 1978 Lists Staff Review Categories 2,3 & 4 for Consideration in Preparation of FSAR & Lic Review.W/Encl Descriptions of Categories 2,3 & 4 ML20148H9701978-11-0606 November 1978 Forwards IE Circular 78-18 ML20062C7171978-11-0202 November 1978 Finds Method for Modelling Piping Sys for Static & Dynamic Analysis Was Acceptable for Criteria Used in Analysis of Subj Facil.When Technique Is Used in Future It Must Meet Requirements Listed in Encl NRC Ltr ML20062C6921978-11-0202 November 1978 Requests Addl Info in Order That Review of Appl Can Continue:Az State Water Plan Phase II & III as Available, Mag Documents on Water Resources Mgt for Maricopa County & Phoenix Area Water Resources & Supply Planning ML20062C4101978-10-30030 October 1978 Provides Interim Eval of 780629 Util Class IE Equip Qualification Prog.Recommends Rev of Rept Per Info Requirements in Encl Question 1985-09-12
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20138Q8301985-12-0303 December 1985 Further Response to FOIA Request for Records Re Voluntary or Required Redress of Sites Where Const Was Terminated, Including Crbr & Legal Analysis.Forwards App E Documents.App D & E Documents Available in Pdr.Photographs Also Available ML20132A8831985-09-12012 September 1985 Responds to 830921 Request That CPPR-167,CPPR-168 & CPPR-169 Be Deleted.Stabilization Plan Has No Significant Environ Impact.Dockets Changed to Canceled Status NUREG-0694, Advises That Augmented Natural Circulation Training Should Be Performed.Descriptions of Natural Circulation Tests Should Be Included in Fsar.Detailed Test Procedures Must Be Submitted 60 Days Prior to Scheduled Test Performance1981-06-12012 June 1981 Advises That Augmented Natural Circulation Training Should Be Performed.Descriptions of Natural Circulation Tests Should Be Included in Fsar.Detailed Test Procedures Must Be Submitted 60 Days Prior to Scheduled Test Performance ML20147J2401978-12-19019 December 1978 Forwards IE Bulletin 78-14 ML20204C7901978-11-24024 November 1978 Forwards IE Bulletin 78-12A,suppl to IE Bulletin 78-12. W/Encl ANO:7811300055 ML20062E9391978-11-24024 November 1978 Forwards IE Inspec Repts 50-491/78-08, 50-492/78-08 & 50-493/78-08 on 781030-1102 & Notice of Violation ML20148R4361978-11-16016 November 1978 Lists Staff Review Categories 2,3 & 4 for Consideration in Preparation of FSAR & Lic Review.W/Encl Descriptions of Categories 2,3 & 4 ML20148H9701978-11-0606 November 1978 Forwards IE Circular 78-18 ML20062C7171978-11-0202 November 1978 Finds Method for Modelling Piping Sys for Static & Dynamic Analysis Was Acceptable for Criteria Used in Analysis of Subj Facil.When Technique Is Used in Future It Must Meet Requirements Listed in Encl NRC Ltr ML20062C6921978-11-0202 November 1978 Requests Addl Info in Order That Review of Appl Can Continue:Az State Water Plan Phase II & III as Available, Mag Documents on Water Resources Mgt for Maricopa County & Phoenix Area Water Resources & Supply Planning ML20062C4101978-10-30030 October 1978 Provides Interim Eval of 780629 Util Class IE Equip Qualification Prog.Recommends Rev of Rept Per Info Requirements in Encl Question 1985-09-12
[Table view] |
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-I i e < h WUCLEAR MGULATORY CC0"J:33:CN usm scros. o, c. 2csss
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% - e 'JUN 12 1981
'+ s Docket Nos.: 50-491/493 Mr. L. C. Dail, Vice President Design Engineering .
Duke Power Company P. O. Box 33189 Charlotte, North Carolina 28242
Dear Mr. Dail:
SUBJECT:
TMI-2 ACTION PLAN ITEM I.G.1 - SPECI AL LOW POW NUREG-0737 " Clarification of TMI Action Plan Requirerents" and NUREG-0694 "TMI- Related Requirements for New Operating Licenses", Item I.G.1, calls for the impleaentation of "a special low power testing program approved by NRC to be conducted.at cower levels no greater than 5 percent for the -
purposes of providing meaningful technical information beyond that obtained .
in the normal startup test program and to provide supplemantal training".
Some PWR applicants have committed to a series of natur3l circulation tasts.
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To date such tests have been performed at the Sequoyah 1, North Anna 2, and Salem 2 facilities. Based on the success of the programs at these plants, the staff has concluded that augmented natural circulation This istraining should to be implemen-be perforned for all future PWR operating licenses.
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ted by including descriptions of natural circulation tests in your FSAR (Chapter 14 - Initial Test Program). If they are not aircady included in your FSAR, tne natural circulation tests and associated training should be included either by modifying existing or adding new test descriptions in accordance -
with Regulatory Guide 1.70, Paragraph 14.2.12. The tests should fulfill the following objectives:
Training Each licensed reactor operator (R0 or SRO uho performs R0 or SR0 duties, respectively) should participate in the initiation, maintenance Operators andto should be able recovery from natural circulation mode.
recognize when natural circulation has stabilized, and should be able to control saturation margin, RCS pressure, and heat removal rate without
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exceeding specified operating limits.
Testing lengtn ine tests shculd demonstrate the following plant characteristics:
j o' fime required to stabilize natural circulation, core flow distribution, ability to establian and maintain natural circulation with and without THIS DOCUMENT CONTAINS 8106180/X M POOR QUAUTY PAGES
JU'l 12 19C?
onsite and offsite power, the ability to uniformly borate and cool dcwn to hot shutdown conditions using natural circulation, and subcooling monitor performance.
If these tests have been performed at a comparable prototype plant, they need be repeated only to the extent necessary to acccmplish the above training cbjectives.
Procedure Validation _
The tests should make maximum practical use of written plant procedures to validate the ccapleteness and accuracy of the procedures.
The natural circulation tests require a source of actual or simulated decay haat. The tests may be performed during initial startup using nuclear heat to situlate decay heat, or may be performed later in the initial fuel cycle when actual decay heat is adequate to permit meaningful testing. If the test objectives are not ccapromised, pump heat during forced circulaticn c:eration could provide an acceptable source of simulated decay heat (e.g., the Loss-cf-Onsite and Offsite A/C Test performed at Mcrth Anna 2).
Applicants who perforn a natural circulation boron-mixing and cooldcun test to demonstrate compliance with Branch Technical Position RSS 5TP 5-1 may use that test to acccmplish some or all of the above training and testing cbjectivas.
This guidance is provided for all PWR OL applicants. pen atory Gui de 1.68 and/or the Standard Review Plan will be revised at a future date to include natural circulation testing and the associated % ning. OL 3;plicants sh:uld subit test descriotions in accordance with Regul: tcry Guf Ge 1.70, Paragraph la.2.12, as part of their FSAR or an amendment t' ereto. Detailed test peccHures should be made available for NRC review 60 days ,.,rior to scheduled test cerfor,ance (see Regulatory Guide 1.68, Appendix B). When required by 10 CFR 60.59, a safety analysis must be prepared and distributed in accorcance with the requirements l
stated therein.
1 Sincerely, i
1, f m G($
Robert L.5/ . Assistant Director 6edesco, l
' Vf for Licensi nc
\ Division of Licensing cc: See next page 1
" . C. 2 ail, ,i.n % nen t
'J - . . ..
les ;a En;ineering
. . . . x. u. . t. .: 0 Ch -lo::e, North Carolina 25242
'alliam L. ?crter, Esq.
Associate General Counsel
.Y, r :X sv 2u esswao 3;ke Power Comoany Cnarlotte, North Carolina 28242
.'. Michael McGarry, III, Esq.
Debevoise & Lioerman 200 Seventeenth Street, N.W.
aasnington, D. C. 20035 William A. Raney, Jr. .
5:e:ial Duputy Attorney General
- P.G. Box 629 Ea eigh, North Carolina 27602 "ary A: erson Davis, Chairman YaMin River Cc=ittee R:ute 4, Scx 251
o:ksville, Nortn Carolina 27203
'illiam G. Pfefferkorn, Esq.
2124 Wachovia Building Winston-Salem, North Carolina 27101 4
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Docket File 50-491/492/493 LPDR PDR NSIC TERA '
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