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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20211B7881999-08-10010 August 1999 Transmits Summary of Two Meetings with Risk-Informed TS Task Force in Rockville,Md on 990514 & 0714 ML20209H6921999-07-15015 July 1999 Forwards Comments on Preliminary Accident Sequence Precursor Analysis Provided in NRC Re Operational Condition Reported in LER 269/1998-04 ML20195H1681999-06-10010 June 1999 Forwards Copy of Preliminary ASP Analysis of Operational Condition Discovered at Ons,Units 1,2 & 3 on 980212 & Reported in LER 269/98-004,for Review & Comment ML20207C0321999-05-18018 May 1999 Forwards Fifth Rept Which Covers Month of Apr 1999. Commission Approved Transfer of TMI-1 Operating License from Gpu to Amergen & Transfer of Operating License for Pilgrim Station from Beco to Entergy Nuclear Generating Co ML20206E4101999-04-26026 April 1999 Forwards Four Copies of Rev 9 Todpc Nuclear Security & Contingency Plan,Per 10CFR50.54(p)(2).Changes Do Not Decrease Safeguards Effectiveness of Plan.Encl Withheld,Per 10CFR73.21 ML20205T1301999-04-0909 April 1999 Informs That on 990317,C Efin & Ho Christensen Confirmed Initial Operator Licensing Exam Schedule for Y2K.Initial Exam Dates Scheduled for Wks of 000710 & 17 for Approx 13 Candidates ML20205B0571999-03-24024 March 1999 Informs That Author Determined That Partial Exemption from 10CFR170 Fee Requirements Appropriate for Footnote 4 of Review of License Renewal Application for Ons,Units 1,2 & 3, That Staff Determines Has Generic Value to Industry ML20207C0501999-02-25025 February 1999 Submits Annual Rept Specifying Quantity of Each of Principal Radionuclides Released to Environment in Liquid & Gaseous Effluents,Per 10CFR72.44(d)(3).Effluent Release from ISFSI for CY98 Was Zero ML20202H7621999-01-28028 January 1999 Discusses Guidance Re License Renewal for Operating Power Reactors Developed in Response to FY99 Energy & Water Development Appropriations Act Rept 105-581 ML20202J1901999-01-28028 January 1999 Discusses License Renewal for Operating Power Reactors.Two Applications Received for Renewing Operating Licenses. Commission Established Adjudicatory Schedule Aimed at Completing License Renewal Process in 30-36 Months ML20198S8721999-01-0707 January 1999 Responds to Message to Marks Re Info Request on Appeal Deadline & Desire to Serve Appeal Either by e-mail or by Alternative Regular Mail ML20198Q8871999-01-0707 January 1999 Responds to to Chairman SA Jackson Re Issues for Consideration for Commission During Oconee License Renewal Process.Commissioners Must Remain Impartial During Pendency of Case.Copy of Order LBP-98-33 Encl.Served on 990107 ML20198Q8971998-12-17017 December 1998 Expresses Concerns Re License Renewal of Duke Energy,Oconee Nuclear Station,Units 1,2 & 3.Commends NRC on Steps Agency Has Undertaken to Conclude Renewal Process.With Certificate of Svc.Served on 990107 05000269/LER-1998-012, Forwards LER 98-012-01,re RB Spray Pumps Being Declared Inoperable Due to Npsh.Rept Has Been Revised to Indicate Results of Testing & Corrective Actions Taken to Date1998-12-0303 December 1998 Forwards LER 98-012-01,re RB Spray Pumps Being Declared Inoperable Due to Npsh.Rept Has Been Revised to Indicate Results of Testing & Corrective Actions Taken to Date 05000269/LER-1998-013, Forwards LER 98-013-00 Re Condition Prohibited by Ts,Per 10CFR50.73(a)(1)(d).Circumstances & Causes for Event Have Not Been Fully Determined & Will Be Provided in Supplemental LER on or Before 9812021998-11-0202 November 1998 Forwards LER 98-013-00 Re Condition Prohibited by Ts,Per 10CFR50.73(a)(1)(d).Circumstances & Causes for Event Have Not Been Fully Determined & Will Be Provided in Supplemental LER on or Before 981202 ML20155D2651998-10-23023 October 1998 Expresses Appreciation for Supporting Commission Initiative in Issuing Recent Statement of Policy on Conduct of Adjudicatory Proceedings.Case-specific Orders Were Issued in Calvert Cliffs & Oconee License Renewal Proceedings ML20155B1481998-10-21021 October 1998 Informs That as Result of Discussion of Issues Re Recent Events in Ice Condenser Industry,Ice Condenser Mini-Group (Icmg),Decided to Focus Efforts on Review & Potential Rev of Ice condenser-related TS in Order to Clarify Issues ML20154B9421998-09-30030 September 1998 Amends Chattooga River Watershed Coalition Petition to Intervene in Proceedings Re Application of Duke Energy Corp to Renew OLs for Oconee Nuclear Station,Units 1,2 & 3 ML20154A8971998-09-30030 September 1998 Requests That Submitted Info Be Attached to Amends to Petition to Intervene in Proceedings Re Application of Duke Energy Corp to Renew Operating Licenses for Units 1,2 & 3 ML20153H6881998-09-27027 September 1998 Requests Consideration of Motion to Enlarge Time Required to Submit Amended Petition to Intervene in Proceeding Re Application of Duke Energy Corp to Renew OLs for Facilities ML20153E4721998-09-24024 September 1998 Forwards Notices of Appearances for Attorneys Representing Duke Energy Corp,Applicant in Proceeding for License Renewal of Oconee Units 1,2 & 3.With Certificate of Svc ML20153D1831998-09-17017 September 1998 Ack Receipt of of Duke Energy Co Inviting Reconsideration of Denial by NRC CFO of Duke Exemption Request from Annual Fee Requirements for General License Under 10CFR171.11(d) ML20151S7501998-08-31031 August 1998 Provides Update on Commitment Made by Licensee in Response to NOV & Imposition of Civil Penalty Re Valves in Ldst Instrument Lines That Were Incorrectly Translated Into Station Procedures ML20237B0871998-08-11011 August 1998 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 981007.Sample Registration Ltr Encl ML20236V9581998-07-27027 July 1998 Forwards Corrected Pages 3.5-30b of 961211 & 3.16-2 of 970205 TS Bases.Old Amend Numbers Were Left on Pages.Rev Changes Footer on Both Pages to Reflect Bases Changes ML20236P9451998-07-15015 July 1998 Forwards Emergency Response Data Sys Implementation Documents Including Data Point Library Updates for Oconee (Number 255),Dresden (Number 257) & Susquehanna (Number 258) ML20153D1961998-07-0909 July 1998 Requests NRC Reconsider & Grant Util Request for Exemption from Duplicative License Fee Under 10CFR171.11(d) for Storage of Spent Nuclear Fuel at Oconee Nuclear Station ML20236J9871998-06-24024 June 1998 First Final Response to FOIA Request for Documents.Documents Listed in App a Already Available in Pdr.Documents Listed in App B Being Released in Entirety ML20247G0881998-05-14014 May 1998 Provides Rev 2 to Section 3.3, Instrumentation, in Support of TS-362 Amend Request.Position on Testing of Analog Trip Type Instruments W/Regard to Transition from CTS to ITS, Restated.Summary Description of Its/Bases Changes,Encl 05000269/LER-1998-002, Forwards LER 98-002-01 Re non-isolable Weld Leak on Pressurizer Surge Line Drain Pipe Which Resulted in Unit Shutdown1998-04-30030 April 1998 Forwards LER 98-002-01 Re non-isolable Weld Leak on Pressurizer Surge Line Drain Pipe Which Resulted in Unit Shutdown ML20217G0351998-03-26026 March 1998 Submits Ltr to Update Commitment Made by Oconee in Response to Subject Violation.Update Assures That Details of Particular CA Are Appropriately Contained in Docketed Correspondence ML20203J9301998-02-26026 February 1998 Submits Response to NRC Bulletin 88-008, Thermal Stresses in Piping Connected to Rcs. Suppl 1 to Bulletin Attached & Contains Listed Commitments ML20199J7441998-02-0202 February 1998 Responds to NRC Bulletin 96-004 for NUHOMS-24P Sf Storage Sys Used at Plant Site.Nrc Reviewed Response & Found Response to Be Acceptable ML20198K9321998-01-13013 January 1998 Ack Receipt of Requesting Exemption from 10CFR171 for ISFSI License SNM-2503 & General License Provisions of 72.214 ML20198M9361998-01-12012 January 1998 Responds to Request That rept,BAW-2303P,rev 3 Be Considered Exempt from Mandatory Public Disclosure.Determined That Info Sought to Be Withheld Contains Proprietary Commercial Info & Will Be Withheld from Public Disclosure ML20203C8481997-12-10010 December 1997 Forwards Emergency Response Data Sys Implementation Documents for Plants.W/O Encl 05000269/LER-1997-003, Forwards LER 97-003-01 Re post-LOCA Boron Dilution Design Basis Not Being Met.Rept Includes Updated Info & Revised Corrective Action1997-11-12012 November 1997 Forwards LER 97-003-01 Re post-LOCA Boron Dilution Design Basis Not Being Met.Rept Includes Updated Info & Revised Corrective Action ML20198Q5741997-11-0303 November 1997 Provides Suppl to Initial 971020 Application for Amend to TS Re SG Tubing Surveillance Requirements,In Response to NRC 971030 Request for Addl Info.Proprietary Rev 3 to BAW-2303P, OTSG Repair Roll Qualification Rept Encl.Rept Withheld ML20211P1591997-10-17017 October 1997 Ack Receipt of & Check for $330,000 in Payment for Civil Penalty.Corrective Actions Will Be Examined During Future Insp ML20217D7261997-10-0101 October 1997 Informs That Staff Intends to Use Working Draft SRP-LR as Aid in Reviewing License Renewal Submittals Received from Dpc,Other Licensees & Owners Groups.Policy Issues Will Be Referred to Commission for Resolution ML20211F7981997-09-25025 September 1997 Submits Response to Violations Noted in Insp Repts 50-269/97-10,50-270/97-10 & 50-287/97-10 & Proposed Imposition of Civil Penalty in Amount of $330,000.Corrective Actions:Ldst Instrument Mods on All Three Units Completed ML20217D9341997-09-22022 September 1997 Informs That NRC Staff Has Accepted Deferral of Completion of Certain Actions Requested by Bulletin 96-03, Potential of Plugging of ECCS Strainers by Debris in Boiling Water Reactor ML20211C8021997-09-18018 September 1997 Forwards Revised TS Amend Re Reactor Bldg Structural Integrity.Previously Submitted TSs Contained Editorial Error ML20210T7121997-09-0404 September 1997 Informs That Representatives from Oconee Who Compose LERs Would Like to Meet W/Staff & AEOD at Convenient Place & Time to Facilitate Process.Concerns Addressed in Encl ML20216G5821997-09-0404 September 1997 Informs That 970730 Submittal Re Oconee Nuclear Station, Units 1,2 & 3 Will Be Marked Proprietary & Being Withheld Per 10CFR2.790(b)(5) & Section 103(b) of AEC Act of 1954 IR 05000269/19970071997-08-27027 August 1997 Discusses Insp Repts 50-269/97-07,50-270/97-07,50-287/97-07, 50-269/97-08,50-270/97-08 & 50-287/97-08 on 970606 & Forwards Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $330,000 ML20210N1531997-08-13013 August 1997 Confirms 970807 Telcon Between J Burchfield & R Carroll Re Management Meeting to Be Conducted at Oconee Nuclear Station on 970922.Purpose of Meeting to Discuss Oconee Emergency Power Project Initiatives ML20210M8381997-08-13013 August 1997 Confirms Conversation Between J Burchfield & R Carroll on 970807 Re Mgt Meeting to Be Conducted in Region II Ofc on 971113.Meeting to Discuss Status of Plant Performance Improvement Initiatives ML20210N1121997-08-12012 August 1997 Informs That NRC Plans to Administer Generic Fundamentals Exam Section of Written Operator Licensing Exam on 971008. Facililty Must Submit Either Ltr Indicating No Candidates Scheduled to Participate or Listing Names of Candidates ML20149J4841997-07-21021 July 1997 Forwards Addl Pages to Rev 5 to Duke Power Co Nuclear Security & Contingency Plan. Encl Withheld 1999-08-10
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20211B7881999-08-10010 August 1999 Transmits Summary of Two Meetings with Risk-Informed TS Task Force in Rockville,Md on 990514 & 0714 ML20195H1681999-06-10010 June 1999 Forwards Copy of Preliminary ASP Analysis of Operational Condition Discovered at Ons,Units 1,2 & 3 on 980212 & Reported in LER 269/98-004,for Review & Comment ML20207C0321999-05-18018 May 1999 Forwards Fifth Rept Which Covers Month of Apr 1999. Commission Approved Transfer of TMI-1 Operating License from Gpu to Amergen & Transfer of Operating License for Pilgrim Station from Beco to Entergy Nuclear Generating Co ML20205T1301999-04-0909 April 1999 Informs That on 990317,C Efin & Ho Christensen Confirmed Initial Operator Licensing Exam Schedule for Y2K.Initial Exam Dates Scheduled for Wks of 000710 & 17 for Approx 13 Candidates ML20205B0571999-03-24024 March 1999 Informs That Author Determined That Partial Exemption from 10CFR170 Fee Requirements Appropriate for Footnote 4 of Review of License Renewal Application for Ons,Units 1,2 & 3, That Staff Determines Has Generic Value to Industry ML20202H7621999-01-28028 January 1999 Discusses Guidance Re License Renewal for Operating Power Reactors Developed in Response to FY99 Energy & Water Development Appropriations Act Rept 105-581 ML20202J1901999-01-28028 January 1999 Discusses License Renewal for Operating Power Reactors.Two Applications Received for Renewing Operating Licenses. Commission Established Adjudicatory Schedule Aimed at Completing License Renewal Process in 30-36 Months ML20198Q8871999-01-0707 January 1999 Responds to to Chairman SA Jackson Re Issues for Consideration for Commission During Oconee License Renewal Process.Commissioners Must Remain Impartial During Pendency of Case.Copy of Order LBP-98-33 Encl.Served on 990107 ML20198S8721999-01-0707 January 1999 Responds to Message to Marks Re Info Request on Appeal Deadline & Desire to Serve Appeal Either by e-mail or by Alternative Regular Mail ML20155D2651998-10-23023 October 1998 Expresses Appreciation for Supporting Commission Initiative in Issuing Recent Statement of Policy on Conduct of Adjudicatory Proceedings.Case-specific Orders Were Issued in Calvert Cliffs & Oconee License Renewal Proceedings ML20153D1831998-09-17017 September 1998 Ack Receipt of of Duke Energy Co Inviting Reconsideration of Denial by NRC CFO of Duke Exemption Request from Annual Fee Requirements for General License Under 10CFR171.11(d) ML20237B0871998-08-11011 August 1998 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 981007.Sample Registration Ltr Encl ML20236P9451998-07-15015 July 1998 Forwards Emergency Response Data Sys Implementation Documents Including Data Point Library Updates for Oconee (Number 255),Dresden (Number 257) & Susquehanna (Number 258) ML20236J9871998-06-24024 June 1998 First Final Response to FOIA Request for Documents.Documents Listed in App a Already Available in Pdr.Documents Listed in App B Being Released in Entirety ML20199J7441998-02-0202 February 1998 Responds to NRC Bulletin 96-004 for NUHOMS-24P Sf Storage Sys Used at Plant Site.Nrc Reviewed Response & Found Response to Be Acceptable ML20198K9321998-01-13013 January 1998 Ack Receipt of Requesting Exemption from 10CFR171 for ISFSI License SNM-2503 & General License Provisions of 72.214 ML20198M9361998-01-12012 January 1998 Responds to Request That rept,BAW-2303P,rev 3 Be Considered Exempt from Mandatory Public Disclosure.Determined That Info Sought to Be Withheld Contains Proprietary Commercial Info & Will Be Withheld from Public Disclosure ML20203C8481997-12-10010 December 1997 Forwards Emergency Response Data Sys Implementation Documents for Plants.W/O Encl ML20211P1591997-10-17017 October 1997 Ack Receipt of & Check for $330,000 in Payment for Civil Penalty.Corrective Actions Will Be Examined During Future Insp ML20217D7261997-10-0101 October 1997 Informs That Staff Intends to Use Working Draft SRP-LR as Aid in Reviewing License Renewal Submittals Received from Dpc,Other Licensees & Owners Groups.Policy Issues Will Be Referred to Commission for Resolution ML20217D9341997-09-22022 September 1997 Informs That NRC Staff Has Accepted Deferral of Completion of Certain Actions Requested by Bulletin 96-03, Potential of Plugging of ECCS Strainers by Debris in Boiling Water Reactor ML20216G5821997-09-0404 September 1997 Informs That 970730 Submittal Re Oconee Nuclear Station, Units 1,2 & 3 Will Be Marked Proprietary & Being Withheld Per 10CFR2.790(b)(5) & Section 103(b) of AEC Act of 1954 IR 05000269/19970071997-08-27027 August 1997 Discusses Insp Repts 50-269/97-07,50-270/97-07,50-287/97-07, 50-269/97-08,50-270/97-08 & 50-287/97-08 on 970606 & Forwards Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $330,000 ML20210M8381997-08-13013 August 1997 Confirms Conversation Between J Burchfield & R Carroll on 970807 Re Mgt Meeting to Be Conducted in Region II Ofc on 971113.Meeting to Discuss Status of Plant Performance Improvement Initiatives ML20210N1531997-08-13013 August 1997 Confirms 970807 Telcon Between J Burchfield & R Carroll Re Management Meeting to Be Conducted at Oconee Nuclear Station on 970922.Purpose of Meeting to Discuss Oconee Emergency Power Project Initiatives ML20210N1121997-08-12012 August 1997 Informs That NRC Plans to Administer Generic Fundamentals Exam Section of Written Operator Licensing Exam on 971008. Facililty Must Submit Either Ltr Indicating No Candidates Scheduled to Participate or Listing Names of Candidates ML20148P5161997-06-30030 June 1997 Second Partial Response to FOIA Request for Documents.App B Records Being Made Available in PDR ML20141C6191997-06-23023 June 1997 Forwards RAI Re Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Related Gate Valves ML20148E0001997-05-29029 May 1997 Forwards SER Re 960724 Request Relief from Volumetric Exam Coverage Requirements of ASME Code,Section XI,1989 Edition, for Certain Welds in SG & in Letdown Cooler Heat Exchangers for Oconee Units 1,2 & 3.Request Granted ML20140A7241997-05-27027 May 1997 Requests That Interim Response Be Provided to Encl Amended Questions Re High Pressure Injection/Makeup Line Crack Found at Plant,Unit 2.Response Requested by 970529 ML20137Z5171997-04-22022 April 1997 Forwards RAI Re Plants Response to NRR Draft Rept on Plant Emergency Power Sys ML20137R1641997-04-0808 April 1997 Forwards RAI Re 960819 Response to NRC Bulletin 96-004, Chemical,Galvanic,Or Other Reactions in Spent Fuel Storage & Transportation Casks ML20147G4521997-03-0404 March 1997 Forwards Responses to Four Questions Raised During Region II 1996 USNRC Training Managers Conference ML20135D3171996-12-0606 December 1996 Forwards RAI Re Licensee Responses to Bulletin 96-02, Movement of Heavy Loads Over Spent Fuel,Over Fuel in Reactor Core,Or Over Safety-Related Equipment ML20134Q0761996-11-20020 November 1996 Conveys Results & Conclusions of Encl Operational Safeguards Response Evaluation,Conducted at Plant,Units 1,2 & 3 from 960520-23.W/o Encl ML20059F7201994-01-0606 January 1994 Forwards Insp Repts 50-269/93-32,50-270/93-32,50-287/93-32, 50-369/93-31,50-370/93-31,50-413/93-35 & 50-414,respectively on 931213-17.Violations Noted.Failure to Protect Safeguards Info IR 05000269/19930281993-12-23023 December 1993 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-269/93-28, 50-270/93-28 & 50-287/93-28 IR 05000269/19930291993-11-30030 November 1993 Discusses 931108 Enforcement Conference in Region II Ofc, Re Apparent Violation Noted in Insp Repts 50-269/93-29, 50-270/93-29 & 50-287/93-29 on 931019-27.List of Attendees, Meeting Summary & Licensee Presentation Encl IR 05000269/19930271993-11-18018 November 1993 Forwards Insp Repts 50-269/93-27,50-270/93-27 & 50-287/93-27.No Violations Identified ML20058B3811993-11-16016 November 1993 Forwards Safeguards Info Referenced in Preliminary Draft Guide to Facilitate Comments on Proposed Rule for Protection Against Malevolent Use of Vechicles at Nuclear Power Plants. W/O Encl IR 05000269/19930221993-11-0505 November 1993 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-269/93-22, 50-270/93-22 & 50-287/93-22.Understands That Revised Response Will Be Provided by 931203 ML20062J5471993-10-29029 October 1993 Forwards SE of Util 930128 & 0714 Supplemental Responses to IE Bulletin 79-27.Concerns Specified in Bulletin Have Been Adequately Addressed IR 05000269/19930241993-10-19019 October 1993 Forwards Insp Repts 50-269/93-24,50-270/93-24 & 50-287/93-24 on 930829-0925 & Notice of Violation ML20057G2661993-10-15015 October 1993 Responds to Licensee 870407 Request for Relief from Certain Section XI ASME Code Requirements Re Pressure Testing of Purification Demineralizers.Informs That SE Will Not Be Supplemented Due to Relief Being Granted IR 05000269/19930231993-09-24024 September 1993 Forwards Insp Repts 50-269/93-23,50-270/93-23,50-287/93-23 & 72-0004/93-23 on 930823-28 & Notice of Violation ML20057C3451993-09-17017 September 1993 Forwards Insp Repts 50-269/93-22,50-270/93-22 & 50-287/93-22 on 930725-0828 & Notice of Deviation ML20059B5861993-09-10010 September 1993 Ltr Contract,Providing Incremental Funds to Task Order 73, Mod 1, Electrical Distribution Sys Functional Insp - Oconee, Under Contract NRC-03-90-031 IR 05000269/19930201993-09-0303 September 1993 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-269/93-20, 50-270/93-20 & 50-287/93-20 IR 05000269/19930211993-08-18018 August 1993 Forwards Insp Repts 50-269/93-21,50-270/93-21 & 50-287/93-21 on 930627-0724 & Notice of Violation IR 05000269/19930171993-08-0909 August 1993 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-269/93-17, 50-270/93-17 & 50-287/93-17.Response Meets Requirements of 10CFR2.201 1999-08-10
[Table view] |
Text
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p < r. .
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" April 22,.1997
.4r. J. W. Hampton Vice President, Oconee Site:
Duke Power Company
)
P. O. Box 1439 ' '
-Seneca, SC 29679
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION RELATED TO DUKE POWER COMPANY'S RESPONSE TO THE NRR DRAFT REPORT ON THE OCONEE EMER6ENCY POWER SYSTEM (TAC NO. M93550)
Dear Mr. Hampton:
By letter dited October 31,19%, you responded to the NRR draft report
)
on the Oconee Emerg:ncy Power system. As a result of our review of this information, we have determined that additional information and clarificatier are needed to close out open issues and complete our report on the Oconee/Keowee emergency electrical distribution system. We request that you respond to the attached questions within 30 days.
Sincerely, ORIGINAL SIGNED BY:
David E. LaBarge, Senior Project Manager !
Project Directorate 11-2
. Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Docket Nos. 50-269, 50-270, and 50-287 i
Enclosure:
As stated l cc w/ enc 1: See next page DISTRIBUTION w/ attachment:
Docket File- J. Johnson, RII PUBLIC
R...Crlenjak, RII PD 11-2 Rdg. ACRS l S. Varga ' -
)
J. Zwolinski '
I r
D. LaBarge fMh N N f F. Ashe D. Nguyen Qy;O \ , g J. Lazevnick 40019 OGC To receive a copy of..this document, indicate in the box: "C" = Copy without attachment /enclosu(e- "E" = Copf with at,tachment/ enclosure "N" = No copy 0FFICE PM:POII-2 /#f] LA:PDIb2jp DfFhiV2 l 1 NAME DLABARGE:en LBliRRY N 4 HK40k DATE 4 /2 2. /97 (J/ NV /97 4 / s t/97 / /97 / /97 / /97 unurgau c.gur neanucn omcFICI AL RECORD COPY PDR ADOCK 0000269 P PDR
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UNITED STATES g
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NUCLEAR REEULATORY COMMISSION WASHINGTON, D.C. 30666 4 001
% ,,, April 22,1997 Mr. J. W. Hampton Vice President, Oconec Site Duke Power Company 1 P. O. Box 1439 Seneca, SC 29679 l
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION RELATED TO DUKE POWER COMPANY'S RESPONSE TO THE NRR DRAFT REPORl ON THE OCONEE EMERGENCY POWER SYSTEM (TAC NO. M93550)
Dear Mr. Hampton:
By letter dated October 31, 1996, yn9 responded to the NRR draft report on the Oconee Emergency Power Syste.9. As a result of our review of this information, we have determined the additional information and clarification are needed to close out open issues and complete our report on the i Oconee/Keowee emergene.y electrical distribution system. We request that you respond to the attached questions within 30 days.
Sincerely, avid E. LaBarge, Senior Project Manager Project Directorate II-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
~
Docket Nos. 50-269, 50-270, and 50-287
Enclosure:
As stated l cc w/ encl: See next page c
._. ___ . __ _ _ ._ _ _ _ . _ .~._ _ _ _ _ _ _ _ _ ____ _ ._. . _ . . _ _
( ,
i
! I Oconee Nuclear Station I Units 1, 2, and 3 l _
5 cc:
! Mr. Paul R. Newt 9n Mr. J. E. Burchfield i
- Legal Department (PB05E) . Compliance Manager Duke Power Company Duke Power Company l 422 South Church Street Oconee Nuclear Sitr.
- Charlotte, North Carolina 28242-0001 P. O. Box 1439
- Seneca, South Carolina 29679 I
! J. Michael McGarry, III, Esquire
! Winston and Strawn Ms. Karen E. Long
- 1400 L Street, NW. Assistant Attorney General
! Washington, DC 20005 North Carolina Department of !
i Justice l Mr. Robert B. Borsus P. O. Box 629 l j Framatome Technologies Raleigh, North Carolina 27602 i Suite 525 ;
i 1700 Rockville Pike Mr. G. A. Copp i i Rockville, Maryland 20852-1631 Licensing - EC050 l
. Duke Power Company I
- Manager, LIS 526 South Church Street
- NUS Corporation Charlotte, North Carolina 28242-0001 l l 2650 McCormick Drive, 3rd Floor l Clearwater, Florida 34619-1035
.l Senior Resident Inspector i U. S. Nuclear Regulatory Commission
!. Route 2, Box 610 l Seneca, South Carolina 29678 ;
i Regional Administrator, Regich II 4
U. S. Nuclear Regulatory Co'aission
- 101 Marietta Street, NW. FJite 2900 l
- Atlanta, Georgir. 30323 '
i
! Max Batavia, Chief
, Bureau of Radiological Health l South Carolina Department of Health
- and Environmental Control l 2600 Bull Street j Columbia, South Carolina 29201 l County Supervisor of Oconee County
- Walhalla, South Carolina 29621 i Mr. Dayne H. Brown, Director i Division of Radiation Protection i North Carolina Department of j Environment, Health and 4 Natural Resources I P. O. Box 27687
- i. Raleigh, North Carolina 27611-7687 i
- i i
REQUEST FOR ADDITIONAL INFORMATION I
DUKE POWER COMPANY i !
OCONEE NUCLEAR STATION ELECTRICAL DISTRIBUTION SYSTEM
- 1. The response to open issue No. 7 states that operating Oconee unit shutdoc loads (approximately 2 MW) are block loaded on the Lee combustion turbines, and additional loads are then manually started until approximately 5 MW is obtained. The shutdown loads, therefore, are ap)arently deenergized prior to initiation of the test in order to suasequently block load them on the Lee combustion turbine. This conflicts with the response to question A8 in Duke Power Company's ;
(DPC's) responses to staff questions dated January 31, 1996. That response states that during this test, the required startup equipment for the Oconee unit is not lost since the loads are transferred to the Lee
- CTG without a loss of power. Please clarify which of these responses is accurate.
If the shutdown loads are indeed briefly deenergized during the Lee (a) test, then readdress the staff's original question relative to your
,. January 31, 1996, response. The question was: "If this degree of loading can be obtained on the Lee combustion turbines during l startup, why can't the same test be performed on the Keowee units?"
- 2. The response provided to open issue No. 9 appears to contradict the information in calculation KC-UNIT 1-2-0098 (Keowee Governor fiechanical Single Failure Analysis) dated September 29,. 1993, and calculation KC UNIT l-2-0106, Rev. 1 (Keowee Power Operating festrictions for NSM-52966) dated May 4, 1995. The information in the referenced calculations indicates that, when the partial shutdown solenoid is deenergized, the )
wicket gates are limited to 25 percent open, and when the solenoid is
- energized there is no limit on the wicket gates. The calculations also indicate that on an emergency start from standby there is initially no limit on gate position, then Keowee speed switch 14/1 operates at 52 rpm to limit the gate position to 25 percent, and speed switch 13/1 operates
, at 122 rpm to remove the gate limit and return control to the governor.
The response to open issue No. 9, however, indicates that on an emergency start the partial shutdown solenoid energizes initially to allow the gates to open to 50 percent and the gate limit is set at 50 percent.
Please clarify.
(a) It also appears from this response that the monthly test performed to meet technical specifications is actually a modified normal start, since the auto synchronizer is turned off. Are there any other differences between that start and the normal start?
(b) Is the voltage and frequency the only acceptance criteria specified for the monthly test? What is the specified voltage and frequency acceptance criteria? Is the start time to specified voltage and frequency monitored, and what is its acceptance criteria?
L -
i' i
j l l
) (c) What are i.he reasons and difficulties associated with performing an ;
! emergency start test on a monthly basis instead of a modified normal l
', start? The modified normal start does not test emergency start gate !
- limit operation, immediate closure of the field circuit breaker, or !
emergency start relay contacts. '
(d; The response to open issue No. 9 indicates that the combination of i existing and proposed technical specifications results in three emergency start tests from a dead stop, and four from a running Keowee unit every 2 years. Are these numbers consistent with those j J
- provided in the response to open issue No. 447 That response ;
- indicates that the Keowee units are emergency started (both star.
1 and hot started) three times per 18 months and a total of 13 times
! over a 3-year period.
' (e) The response to issue No. 9 also indicates that under current technical specifications there is an 18-month emergency power switching logic (EPSL) functional test that is performed with a '
" start from dead stop on an ONS unit." What is the relationship of this test to the EPSL functional test provided to the staff in the January 31, 1996, DPC letter? The test provided to the staff was not a Keowee start from dead stop but rather an emergency start from <
generating to the grid. How many EPSL functional tests are from a '
dead stop and how many from generating to the grid? Are any of the
, Keowee starts from dead stop performed as a black start? !
- 3. Are any of the Oconee Technical Specification electrical tests referenced l in the most recent October 31, 1996, DPC letter going to be eliminated in the Technical Specification 3.7 rewrite? If so, which ones and why?
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- 4. In the response to open issue No. 28 it is indicated that analysis conducted to evaluate the past operability of the electrical system concluded that all required safety functions would have been accomplished ;
with the voltage at 11.9 kV. In the same response it is stated: 1 Due to different system loading, it is expected that the voltages required at the terminals of the Keowee generator to assure proper operation of safety loads will vary, depending on which failure scenario is being analyzed. The minimum generator voltage that bounds all cases and scenarios for the Keowee analysis is 13.5 kV.
It is not clear what the differences are that would lead to the conclusion that "all . required safety functions would have been accomplished" with the Keowee generator at 11.9 kV, and also conclude that "[t]he minimum generator voltage that bounds all cases and scenarios for the Keowee analysis is 13.5 kV." Please clarify. Also, please list l the full complement of failure scenarios that are referred to in the above quotation.
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- 5. It is not clear in the response to open issue No. 29 what DPC's final
- position is. The response states that procedure PT/0/A/0620/09, Keowee
[ Hydro Operation, does not put the Keowee unit through a load run; but it j doesn't indicate why it is not a load run. It references a one-time load i run test that was run in August 1996, and states that the test data l demonstrates that monthly load runs of Keowee are not necessary in light j of the fact that Keowee is frequently operated to the grid. However, the 4
final paragraph in the response states that normal operation of Keowee i verifies the first two surveillance requirements (synchronization and i load acceptance) in standard technical specifications, and Duke plans to
. trend data monthly on Keowee operation to the grid in order to verify :
1 proper heat exchanger operation. Please indicate why PT/0/A/0620/09 does i
not meet the criteria of a load run, and what combination of existing
- Keowee operation and additional verification will be used to demonstrate j the load run criteria is met by the Keowee hydro units.
- 6. The response to open issue No. 30 indicates that the LOCA signal is verified in step 12.35 of the EPSL functional test that was provided to
- the staff in a January 31, 1996, letter from DPC. It further states
- that subsequent steps 12.36, 12.37, 12.38, and 12.39 demonstrate that
! this LOCA signal is providing the emergency start to the Keowee units.
l In fact, it appears from the procedure that at step 12.35 both Keowee l units are already operating. Please verify that the LOCA signal of step 4 12.35 does not actually start the Keowee units but rather is used to
- verify logic actuation; contact closure, etc., necessary for the
- emergency start of the Keowee units. If this is not accurate, i specifically explain what steps 12.35 through 12.39 are verifying.
a l 7. The item 8 comment in attachment 2 notes that a single breaker failure
! will not cause the lockout of both Keowee units during periods of dual Keowee. unit grid generation and a simultaneous ground fault. It states that both ACB 1 and 2 would need to fail in order to lockout both Keowee units in the postulated scenario. These statements are made with regard to a statement made in the NRR report that "[a] subsequent single failure of a safety-related breaker to clear a fault on the overhead emergency power path could potentially cause the lockout of both Keowee units if '
they were generating to the grid." !
The circuit breaker that the staff was referring to in the NRR report is I not ACB 1 or 2, but rather an OCB in the switchyard. The failure i postulated was a failure of a Switchyard OCB to isolate a ground fault in I the switchyard or on a transmission line, outside the Keowee differential zone of protection. Such an uncleared ground fault would be seen by the ground fault protection scheme (59G relay) of both Keowee hydro units when they were generating to the grid and cause both units to trip.
Please respond whether this scenario is accurate.
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! 8. The item 13 comment in attachment 2 indicates that the diesel generator j hot restart test is not applicable for the Keowee units because the concern associated with the diesel generator's ability to start at high
- diesel temperatures does not exist at Keowee.
- We recognize that the Keowee hydro units do not necessarily have the same vulnerabilities as diesel units, but are there other vulnerabilities that
'. might be peculiar to the hydros relative to hot starting? We note that 3
in the response to open issue No. 30, DPC has indicated that a hot
] restart test was performed as part of a load run test on August 22-23, l 1996.
i 9. The item 15 cosmient in attachment 2 indicates that as a result of NSM ON-52966, the reclosure timers for the Keowee ACBs are set at 8.2 to 8.4 seconds, and the acceptance criterion is that they be greater than 4
4 seconds. What is the basis for the acceptance criterion? Why is there no upper bound on the acceptance criterion?
- 10. The item 16 comment in attachment 2 states that during the standby bus source undervoltage sensing test, each logic chain is actuated to ensure i
i that the resulting retransfer to startup signal is achieved. It indicates that the two-of-three verification is not necessary for the i standby bus undervoltage logic since a single failure is necessary in j order to require actuation of this logic.
I It is not clear what portion of the undervoltage sensing logic this test verifies and does not verify. How many logic chains are there, and is
! the two-of-three undervoltage signal provided to each logic chain? What
- types of failures would the test not capture and how is the test conducted?
- 11. Item 57 in attachment 2 of DPC's letter, indicates that item 18_in the i
NRR draft report (page 27) ir< correctly states that there is no similar 4
technical specification requirement at Oconee for the standard diesel ,
generator test of reaching rated voltage and frequency within a specified time. It comments that the annual emergency start test verifies that i Keowee can obtain the rated voltage and frequency within the test acceptance limits.
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- We note that the subject standard technical specification test referred i
to in the NRR draft report is a 10-year test of the simultaneous start l capability of both diesel generators. Is the annual emergency start test of the Keowee units referred to in the comment to item 57 a test of the
{ simultaneous start capability of both Keowee units? If both units are not emergency started simultaneously from a standby condition in that
{ test, it is not comparable to the subject 10-year test. Is a 4 simultaneous emergency start from standby periodically performed on both Keowee units?
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- 12. The final portion of the response to open issue No. I discusses the electrical loading that would occur if ECCS actuation signals were received during a three-unit Oconee LOOP. It indicates that if an l
ECCS actuation were to occur, only one additional HPI pump would be started in each unit, over and above the other HPI pumps and essential )
loads that were energized by other automatic features during the ;
- LOOP event. The response states that the load associated with these i additional HPI pumps is smaller than the Oconee LOOP or LOCA loads that !
' are currently analyzed to be block loaded onto an overhead or underground Keowee unit. It concludes, therefore, that the emergency power system would perform its intended function and is bounded by the current j analyses. '
! It is not clear why the fact that the load of the HPI pumps is leis than
- the entire LOOP or LOCA load, leads to the conclusion that the current .
. analyses bounds the subject scenario. Is this indicating that, because l
! .the loads are staggered during the event, the voltage transients seen are
! less than those analyzed? If so, how does the final steady-state load l during this scenario compare to the analyses in terms of voltage and CT4 i or CTS loading capability. Has a three-unit LOCA/ LOOP event been i analyzed, or does the conservatism used in the CYME analyses bound the j three-unit LOCA/ LOOP event?
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