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| ==Enclosures:== | | ==Enclosures:== |
| : 1. March 17, 1986, letter from Rahe to Berlinger transmittino (a) responses to NRC staff questions about UHI removal at McGurie and (b) revisions to Chapter 15 of the McGuire FSAR starting with page 15.6-7. | | : 1. {{letter dated|date=March 17, 1986|text=March 17, 1986, letter}} from Rahe to Berlinger transmittino (a) responses to NRC staff questions about UHI removal at McGurie and (b) revisions to Chapter 15 of the McGuire FSAR starting with page 15.6-7. |
| : 2. March 17, 1986, letter from H.B. Tucker to H.R. Denton, regarding UHI removal / isolation. | | : 2. {{letter dated|date=March 17, 1986|text=March 17, 1986, letter}} from H.B. Tucker to H.R. Denton, regarding UHI removal / isolation. |
| : 3. January 29, 1986, SNL letter Dobranich to Watt, TRAC-PFI/ MODI calculations 4 March 12, 1986, SNL transmittal Dobranich to Watt, UHI PWR with UHI removal. | | : 3. January 29, 1986, SNL letter Dobranich to Watt, TRAC-PFI/ MODI calculations 4 March 12, 1986, SNL transmittal Dobranich to Watt, UHI PWR with UHI removal. |
| : 5. November 20, 1985, memo Rowsome to Novak reliability assessment of USI auto-isolation capability. | | : 5. November 20, 1985, memo Rowsome to Novak reliability assessment of USI auto-isolation capability. |
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| ,24 $ l IO Ig (1 . jfgd I lNF M A W < 8 8603200300Bhh69 PDR ADOCK 0 PDR P | | ,24 $ l IO Ig (1 . jfgd I lNF M A W < 8 8603200300Bhh69 PDR ADOCK 0 PDR P |
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| . A SAFETY EVALUATION OF THE PROPOSED OPERATION OF MCGUIRE UNITS 1 & 2 WITHOUT UPPER HEAD INJECTION INTRODUCTION In a letter dated May 9, 1985, the Duke Power Company (licensee) proposed license amendments for McGuire Nuclear Station Units 1 and 2 to change the Technical Specifications in accordance with a program to delete Upper Head Injection (UHI) systems at McGuire. In the May letter, the licensee described the results of a feasibility study (for UHI removal) and outlined its program for obtaining NRC approval. | | . A SAFETY EVALUATION OF THE PROPOSED OPERATION OF MCGUIRE UNITS 1 & 2 WITHOUT UPPER HEAD INJECTION INTRODUCTION In a {{letter dated|date=May 9, 1985|text=letter dated May 9, 1985}}, the Duke Power Company (licensee) proposed license amendments for McGuire Nuclear Station Units 1 and 2 to change the Technical Specifications in accordance with a program to delete Upper Head Injection (UHI) systems at McGuire. In the May letter, the licensee described the results of a feasibility study (for UHI removal) and outlined its program for obtaining NRC approval. |
| The proposed Technical Specification changes were modified December 17, 1985 to provide for levels of modification achievable in successive fuel reloads. Options included: (1) operation with UHI available, (2) operation with UHI locked out, and (3) operation with UHI components external to the reactor vessel effectively removed. The licensee committed to support the proposed Technical Specification changes through confirmatory studies. | | The proposed Technical Specification changes were modified December 17, 1985 to provide for levels of modification achievable in successive fuel reloads. Options included: (1) operation with UHI available, (2) operation with UHI locked out, and (3) operation with UHI components external to the reactor vessel effectively removed. The licensee committed to support the proposed Technical Specification changes through confirmatory studies. |
| By letter of October 2,1985, the licensee submitted proposed revision to the McGuire Nuclear Station Safety Analysis for UHI _ Elimination. The FSAR reanalyses of the large break LOCA had utilized the computer code " BASH" which was then under review by the staff. The licensee noted that the reanalysis confirmed the proposed revisions to the technical specifications conservative but also that they may be relaxed to allow full operational flexibility. They intended to propose further changes following NRC approval of deletion of UHI, Problems were encountered by Westinghouse with BASH reflood heat transfer in February 1986. Accordingly, on March 17, 1986, the licensee submitted a reanalysis and update of the October 2,1985 safety analysis. This reanalysis utilized BART, a previously accepted Westinghouse evaluation model. It is the March 17, 1986 submittal which provides the principal basis for this Safety Evaluation. | | By letter of October 2,1985, the licensee submitted proposed revision to the McGuire Nuclear Station Safety Analysis for UHI _ Elimination. The FSAR reanalyses of the large break LOCA had utilized the computer code " BASH" which was then under review by the staff. The licensee noted that the reanalysis confirmed the proposed revisions to the technical specifications conservative but also that they may be relaxed to allow full operational flexibility. They intended to propose further changes following NRC approval of deletion of UHI, Problems were encountered by Westinghouse with BASH reflood heat transfer in February 1986. Accordingly, on March 17, 1986, the licensee submitted a reanalysis and update of the October 2,1985 safety analysis. This reanalysis utilized BART, a previously accepted Westinghouse evaluation model. It is the March 17, 1986 submittal which provides the principal basis for this Safety Evaluation. |
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217H5811999-10-15015 October 1999 Forwards 1999 Update to FSAR, for McGuire Nuclear Station.With Instructions,List of Effective Pages for Tables & List of Effective Pages for Figures ML20217G7861999-10-13013 October 1999 Forwards MOR for Sept 1999 & Revised MOR for Aug 1999 for McGuire Nuclear Station,Unit 1 & 2 ML20217F3591999-10-13013 October 1999 Forwards Info Copy of Cycle 14 COLR for McGuire Nuclear Station,Unit 1 ML20217F3261999-10-13013 October 1999 Submits Quantity of Tubes Insp from Either Side of SGs A-D & Lists Tubes with Imperfections,Locations & Size.No Tubes Removed from Svc by Plugging.Total of Eleven Tubing Wear Indications Identified at Secondary Side Supports in SGs ML20217F8011999-10-13013 October 1999 Informs That on 990930,NRC Completed mid-cycle PPR of McGuire Nuclear Station.Areas That Warranted More than Core Insp Program Over Next Five Months,Not Identified.Historical Listing of Plant Issues Encl ML20217J5091999-10-0606 October 1999 Forwards Revs to Section 16.15-4.8.1.1.2.g of McGuire Selected Licensee Commitments Manual.Section Has Been Revised to Allow Testing of Portions of DG Fuel Oil Sys Every 10 Yrs ML20217C8351999-10-0505 October 1999 Communicates Correction to Info Provided During 990917 Meeting with Duke Energy & NRC Region Ii.Occupational Radiation Safety Performance Indicator Values Should Have Been Presented as 1 Instead of 0 ML20217C4471999-10-0404 October 1999 Forwards Insp Repts 50-369/99-06 & 50-370/99-06 on 990801- 0911.Determined That One Violation Occurred & Being Treated as Non-Cited Violation ML20212J2191999-10-0404 October 1999 Informs That Util 980326 Response to GL 97-06, Degradation of SG Internals Provides Reasonable Assurance That Condition of Steam Generator Internals Are in Compliance with Current Licensing Bases for Facility ML20212J7801999-10-0404 October 1999 Discusses GL 98-01 Issued by NRC on 980511 & DPC Responses for McGuire NPP & 990615.Informs That NRC Reviewed Responses & Concluded That All Requested Info Re Y2K Readiness Provided.Subj GL Considers to Be Closed ML20212M1651999-09-23023 September 1999 Refers to 990917 Meeting at Region II Office Re Licensee Presentation of self-assessment of McGuire Nuclear Station Performance.List of Attendees & Licensee Presentation Handouts,Encl ML20212D1671999-09-20020 September 1999 Forwards Exemption & SER from Certain Requirements of 10CFR50,App A,General Design Criterion 57 Re Isolation of Main Steam Branch Lines Penetrating Containment.Exemption Related to Licensee Application ML20212B6491999-09-15015 September 1999 Informs That Encl Announcement Re 990913 Application for Amend to Licenses NPF-9 & NPF-7 Forwarded to C Observer in North Carolina,For Publication ML20212D5321999-09-15015 September 1999 Informs That Duke Energy Corp Agrees to Restrict Max Fuel Rod Average Burnup to 60,000 Mwd/Mtu,In Order to Support NRC Final Approval & Issuance of Requested Amend ML20212A4131999-09-14014 September 1999 Informs That TR DPC-NE-2009P Submitted in 990817 Affidavit, Marked Proprietary,Will Be Withheld from Public Disclosure, Pursuant to 10CFR2.709(b) & Section 103(b) of Atomic Energy Act of 1954,as Amended ML20216E8791999-09-14014 September 1999 Forwards Monthly Operating Repts for Aug 1999 & Revised Monthly Operating Rept for July 1999 for McGuire Nuclear Station ML20212A0501999-09-10010 September 1999 Informs That Postponing Implementation of New Conditions Improved by RG 1.147,rev 12,acceptable Since Evaluation on Relief Based on Implementing Code Case for Duration of Insp Interval ML20212A2631999-09-0909 September 1999 Forwards Rev 25 to McGuire Nuclear Station,Units 1 & 2 Pump & Valve Inservice Testing Program, IAW 10CFR50.55a. Section 8.0 Contains Summary of Changes & Detailed Description of Changes Associated with Rev 25 ML20212A5191999-09-0808 September 1999 Requests NRC Approval for Relief from Requirements of ASME Boiler & Pressure Vessel Code,Section XI,1989 Edition,App VI,VI-2430(c) & 2440(b).Approval of 99-GO-002 Is Requested by 000301 ML20211J3671999-08-31031 August 1999 Forwards Public Notice of Application for Amend to License NPF-9 Seeking one-time Extension of Surveillance Frequency for TS SR 3.1.4.2 Beyond 25% Extension Allowed by TS SR 3.0.2 ML20211M4451999-08-30030 August 1999 Forwards Summary of Util Conclusions Re Outstanding Compliance Issue Re Staff Interpretation of TS SR 3.0.1,per Insp Repts 50-369/99-03 & 50-370/99-03,as Discussed with NRC During 990618 Meeting ML20211H1741999-08-30030 August 1999 Forwards Comments on Catawba Nuclear Station Units 1 & 2 & McGuire Nuclear Station,Units 1 & 2 Specific Reactor Vessel Info Contained in Rvid.Ltr Dtd 990107,rept ATI-98-012-T005 & Partial marked-up Rept WCAP-14995 Encl ML20211K8831999-08-26026 August 1999 Forwards Insp Repts 50-369/99-05 & 50-370/99-05 on 990620-0731.Two Violations Occurred & Being Treated as NCVs ML20211G5181999-08-24024 August 1999 Forwards SE Re second-10-yr Interval Inservice Insp Program Plan Request for Relief 98-004 for Plant,Unit 1 ML20211F2971999-08-17017 August 1999 Forwards non-proprietary & Proprietary Updated Pages for DPC-NE-2009,submitted 980722.Pages Modify Fuel Design & thermal-hydraulic Analysis Sections of DPC-NE-2009. Proprietary Page 2-4 Withheld,Per 10CFR2.790 ML20211B1121999-08-16016 August 1999 Forwards Topical Rept DPC-NE-2012, Dynamic Rod Worth Measurement Using Casmo/Simulate, Describing Results of Six Drwm Benchmark Cycles at Catawba & McGuire & Discusses Qualification to Use Drwm at Catawba & McGuire ML20210V0171999-08-13013 August 1999 Confirms Conversation Between M Cash & M Franovich on 990806 Re Mgt Meeting,Scheduled for 990917 to Present self- Assessment of Plant Performance.Meeting Will Be Held in Atlanta,Ga ML20210S2231999-08-12012 August 1999 Forwards Monthly Operating Repts for July 1999 for McGuire Nuclear Station,Units 1 & 2.Revised Rept for June 1999,encl ML20210T4511999-08-10010 August 1999 Forwards Response to NRC RAI Re 981014 Standby Nuclear Svc Water Pond Dam Audit Conducted by FERC ML20210R4311999-08-10010 August 1999 Forwards Summary Rept of Mods,Minor Mods,Procedure Changes & Other Misc Changes Per 10CFR0.59 ML20210R0031999-08-10010 August 1999 Forwards Revised TS Bases Pages to NRC for Info & Use. Editorial Changes Were Made to Correct Incorrect UFSAR Ref Number Associated with Certain Reactor Coolant Sys Pressure Isolation Valves ML20210Q3701999-08-0505 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Authorized Representative of Facility Must Submit Ltr as Listed,Thirty Days Before Exam Date in Order to Register Individuals to Take Exam ML20210H7691999-07-21021 July 1999 Submits Summary of 990715 Meeting at Facility Re Presentation of Results of Most Recent Periodic Ppr.List of Meeting Attendees Encl ML20209H1551999-07-14014 July 1999 Forwards Monthly Operating Repts for June 1999 for McGuire Nuclear Station,Units 1 & 2.Revised Rept for May 1999 Also Encl ML20210E1931999-07-13013 July 1999 Forwards Insp Repts 50-369/99-04 & 50-370/99-04 on 990509-0619.Four Violations of NRC Requirements Occurred & Being Treated as Ncv,Consistent with App C of Enforcement Policy NUREG-1431, Forwards SER Agreeing with Util General Interpretation of TS LCO 3.0.6,but Finds No Technical Basis or Guidance That Snubbers Could Be Treated as Exception to General Interpretation1999-07-0909 July 1999 Forwards SER Agreeing with Util General Interpretation of TS LCO 3.0.6,but Finds No Technical Basis or Guidance That Snubbers Could Be Treated as Exception to General Interpretation ML20209G5151999-07-0808 July 1999 Forwards Amended Pages to Annual Radioactive Effluent Release Repts, for 1997 & 1998 for McGuire Nuclear Station. Portion of Rept Was Inadvertently Omitted Due to Administrative Error,Which Has Been Corrected ML20196J9001999-07-0606 July 1999 Informs That 990520 Submittal of Rept DPC-NE-3004-PA,Rev 1, Mass & Energy Release & Containment Response Methodology, Marked Proprietary Will Be Withheld Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954 ML20196J4381999-06-29029 June 1999 Informs That as Result of Staff Review of Util Responses to GL 92-01,rev 1,suppl 1,NRC Revised Info in Rvid & Releasing Rvid Version 2 ML20196G3721999-06-24024 June 1999 Documents Verbal Info Provided to NRR During Conference Call Re Relief Requests 98-002 & 98-003 ML20196G7461999-06-22022 June 1999 Requests Exemption from Requirements of 10CFR54.17(c) That Application for Renewed Operating License Not Be Submitted to NRC Earlier than 20 Yrs Before Expiration of Operating License Currently in Effect ML20195K3601999-06-14014 June 1999 Forwards MORs for May 1999 for McGuire Nuclear Station,Units 1 & 2 & Revised MORs for Apr 1999.Line 6 Max Dependable Capacity (Gross Mwe) on Operating Data Rept Should Be Revised to 1114 from Jan 1998 to Apr 1999 ML20195D5691999-06-0303 June 1999 Submits Ltr to Facilitate Closing of Inspector Follow Up Item 50-369,370/97-15-05,re Revising Site Drawings in UFSAR Into Summary one-line Flow Diagrams,Per NRC 990327 Telcon ML20195F1851999-06-0202 June 1999 Forwards Insp Repts 50-369/99-03 & 50-370/99-03 on 990328- 0508.Two Violations of NRC Requirements Identified & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy ML20195E8771999-06-0202 June 1999 Confirms Telcon with M Cash on 990524 Re Public Meeting for 990715.Purpose of Meeting to Discuss Results of NRC Most Recent PPR ML20207D0521999-05-21021 May 1999 Informs That in Telcon on 990519 Between a Orton & Rf Aiello Arrangements Made for Administration of Initial Written Exam for McGuire Nuclear Station on 990603.Exam Will Be Administered at Catawba Simultaneously with Written Exam ML20196L1791999-05-20020 May 1999 Communicates Util Licensing Position Re Inoperable Snubbers. Licensee Has Determined That Structure of ITS Has Resulted in Certain Confusion Re Treatment of Inoperable Snubbers ML20196L1851999-05-20020 May 1999 Forwards Proprietary & non-proprietary Version of Rev 1 to TR DPC-NE-3004, Mass & Energy Release & Containment Response Methodology, Consisting of Finer Nodalization of Ice Condenser Region.Proprietary Info Withheld ML20206T4481999-05-13013 May 1999 Forwards Rev 3 to Topical Rept DPC-NE-3002-A, UFSAR Chapter 15 Sys Transient Analysis Methodology, IAW Guidance Contained in NUREG-0390 ML20206R0791999-05-13013 May 1999 Forwards Monthly Operating Repts for Apr 1999 for McGuire Nuclear Station,Units 1 & 2 & Revised Monthly Operating Repts for Mar 1999 1999-09-09
[Table view] Category:INTERNAL OR EXTERNAL MEMORANDUM
MONTHYEARML20217L7171999-10-22022 October 1999 Informs That Encl Questions Were Transmitted by Email to PT Vu of Duke Energy Corp,In Preparation for Upcoming Telcon Re 990624 Amend Request ML20216J2171999-09-30030 September 1999 Informs That Encl Questions Were Transmitted by Email on 990930 to M Purser of Duke Energy Corp for Preparation of Upcoming Telcon.Questions Pertain to 990624 Amend Request ML20210L6601999-08-0505 August 1999 Forwards single-page Document Given to G Belisle of Region II by T Clements of Nuclear Control Institute Re Mixed Oxide Fuel ML20196K6231999-07-0101 July 1999 Forwards Draft Safety Evaluation on TR DPC-NE-2009, Duke Power Co Westinghouse Fuel Transition Rept. Rept Was Transmitted to Warren in Order to Prepare for Conference Call ML20195J1181999-06-14014 June 1999 Forwards Documents That Were Transmitted by Fax on 990614 to a Jones-Young Re Issues to Be Discussed in Upcoming Telcon Re DPC Response to GL 98-04 ML20207G3661999-06-0909 June 1999 Reissued Notification with Date Change of 990618 Meeting with DPC in Rockville,Maryland to Discuss Compensatory Actions (Allowed Outage Time) for McGuire Nuclear Station ML20207E7741999-06-0202 June 1999 Notification of 990617 Meeting with Util in Rockville,Md to Discuss Compensatory Actions (AOT) for McGuire Nuclear Station ML20206U4231999-05-18018 May 1999 Notification of 990602 Meeting with Duke Energy Corp,Vepco & Others in Rockville,Md to Discuss Technical,Regulatory & Licensing Issues Related to Proposed Future Use of Mixed Oxide Fuel at Catawba,Mcguire & North Anna Nuclear Stations ML20205H9131999-03-24024 March 1999 Forwards NRC Operator Licensing Exam Repts 50-369/99-301 & 50-370/99-301 (Including Completed & Graded Tests) for Tests Administered on 990125-0205 ML20199B0491999-01-11011 January 1999 Notification of 990127 Meeting with Duke Energy Corp in Rockville,Md to Discuss License Amend for Taking Credit for Soluble Boron & Boraflex ML20195H0421998-11-17017 November 1998 Informs That Encl Questions Were Transmitted by e-mail to Warren of Duke Energy Corp in Preparation for Upcoming Telephone Call.Memo & Enclosure Do Not Convey Formal Request for Info or Represent NRC Staff Position ML20154L0811998-09-23023 September 1998 Notification of 981016 Meeting with Util in Rockville,Md to Discuss Recent Site Performance Major Plant Equipment Upgrades & Operational,Licensing & Regulatory Issues.Meeting Has Been Cancelled ML20153E0781998-09-23023 September 1998 Revised Notification of 981016 Duke Energy Corp in Rockville,Md to Discuss Recent Site Performance,Major Plant Equipment Upgrades & Operational,Licensing & Regulatory Issues.Meeting Revised to Change Date & Room Number ML20151X1931998-09-14014 September 1998 Notification of 981006 Meeting W/Duke Energy Corp in Rockville,Md to Discuss Recent Site Performance,Major Plant Equipment Upgrades & Operational,Licensing & Regulatory Issues ML20249C6451998-06-25025 June 1998 Notification of 980709-10 Meeting W/Duke Energy Corp in Rockville,Md to Discuss Technical Issues Re Proposed Improved TSs for Catawba & McGuire Nuclear Stations ML20249B6241998-06-19019 June 1998 Forwards Draft SE Re Relocation of Meteorological Tower for Plant ML20248F1061998-06-0202 June 1998 Notification of 980617 & 18 Meeting W/Util in Rockville,Md to Discuss Technical Issues Re Proposed Improved TSs for Catawba & McGuire Nuclear Stations ML20217Q6151998-05-0707 May 1998 Notification of 980518 & 19 Meeting W/Util in Rockville,Md to Discuss Technical Issues Re Proposed Improved TSs for Catawba & McGuire Nuclear Stations ML20217M1831998-05-0101 May 1998 Notification of 980514 Meeting W/Util in Rockville,Md to Discuss Plans for Changes to TS Re Following Ice Condenser Issues:Ice Weight Redistribution,Reduction & Block Ice Utilization ML20199A4781998-01-22022 January 1998 Notification of 980204 Meeting W/Util in Rockville,Md to Discuss Staff Recent RAI Re Snubbers ML20198M8931998-01-12012 January 1998 Notification of 980127 Meeting W/Util in Rockville,Md to Discuss Technical Issues Covered by DEC TR in Support of Future Transition from Framatome to Westinghouse Fuel ML20198S8131997-10-30030 October 1997 Notification of 971118 Meeting W/Util to Discuss Specific Aspects of Dual Unit Trip & Licensee Corrective Actions ML20198K1961997-10-16016 October 1997 Notification of 971030 Meeting W/Util in Rockville,Md to Discuss Matters Re Proposed Improved TSs for Catawba & McGuire ML20210M8231997-08-22022 August 1997 Forwards Signed Original of Subject Order Attached for Transmittal to Ofc of Fr for Publication.W/O Encl ML20141B3041997-06-20020 June 1997 Notification of 970709 Meeting W/Util in Huntersville,Nc to Discuss Licensee Revs to 1996 Plant UFSAR & How 1996 Rev Complies w/10CFR50.71 ML20206L5711997-01-16016 January 1997 Discusses Grinell Snubbers for Use in Steam Generator Replacement Project.Snubbers Did Not Meet Purchase Specifications for Environ Conditions ML20129H7401996-08-29029 August 1996 Ack Receipt of 960801 Memo Re Reactor Trip Breaker Problems at Plants.Recommended That AEOD or Appropriate Group within NRR Advise OE Whether Technical Staff Considers That Violations Occurred,Per 10CFR50.73 or 10CFR21 ML20128Q2431996-08-0101 August 1996 Discusses Concerns Raised During 960722 AEOD Program Review Re Reportability of Reactor Trip Breaker Problems at Plants NUREG-1299, Forwards Continuation of Curtiss Papers to Be Filed Under Commission Correspondence in Pdr.Advanced Copy Sent to Pdr. List of Documents Included in Four Boxes Encl1994-06-29029 June 1994 Forwards Continuation of Curtiss Papers to Be Filed Under Commission Correspondence in Pdr.Advanced Copy Sent to Pdr. List of Documents Included in Four Boxes Encl ML20059E0261994-01-0404 January 1994 Notification of 940105 Meeting W/Util in Rockville,Md to Conduct AIT Meeting & Discuss Results of Licensee Investigation of Recent Loss of off-site Power Event at McGuire Plant ML20058J5061993-11-29029 November 1993 Notification of Significant Licensee Meeting W/Util on 931203 to Discuss Licensee Intended EAL Changes for All Three Plants Relative to NUMARC Issues & Implementation of EPA-400 ML20058J4911993-11-24024 November 1993 Notification of Significant Licensee Meeting W/Util on 931206 to Discuss self-assessment of Plant Performance Since 930802-1130 ML20058C9631993-11-19019 November 1993 Notification of 931201 Meeting W/Util in Rockville,Md to Update NRC on Mcguire,Units 1 & 2 & Catawba,Unit 1 Steam Generator Replacement Project ML20057D1651993-09-27027 September 1993 Notification of 930929 Meeting W/B&W in Rockville,Md to Discuss Installation Process Used for B&W Kinetic Sleeves at McGuire Nuclear Station ML20057C5441993-09-23023 September 1993 Notification of 930929 Meeting W/Util in Rockville,Md to Discuss Results of Util Investigation of Unit 1 SG Tube Leaks & Util Actions as a Result of Findings from Investigation ML20056H3141993-08-24024 August 1993 Forwards Safety Evaluation Accepting Critical Aspects of Proposed TS Changes Involving Increasing Min Rswt Boron Concentrations from 2,000 Ppm to 2,275 Ppm & Increasing Min Cla Boron Concentration from 1,900 Ppm to 2,000 Ppm ML20134B2531993-02-11011 February 1993 Responds to 930113 Request for Exceptions to N+1 Policy for Listed Plants.Approved Exceptions W/Stated Conditions Effective for Period of 2 Yrs ML20128G8201993-02-0101 February 1993 Notification of Significant Licensee Meeting W/Util on 930211 to Discuss Enforcment Conference on Safeguards Issues ML20126F2821992-12-24024 December 1992 Forwards Description of Valves Affected by Stroke Testing & Effect of Valves Being Opened or Closed During Testing,W/ Respect to Encl LER 369/90-022-1 Re RHR Sys Being Inoperable ML20128A0361992-11-30030 November 1992 Notification of 921215 Meeting W/Util in Rockville,Md to Discuss Status of Licensees Plans to Implement Pilot Program for Use of Seismic Stops in Lieu of Snubbers at Plant ML20059H7861990-09-10010 September 1990 Forwards Revised Resolution of Plant-Specific Differing Prof Opinion (DPO) Issues Concerning McGuire Tech Specs, in Support of Completion of Dpos,Per Author 891229 Memo.Actions Re Tech Specs Listed ML20055D9791990-07-0505 July 1990 Notification of 900719 Meeting W/Util in Rockville,Md to Discuss Cause,Morphology & Future Plans Re Cracking Tubes at Expansion Transition Zone & at Tube Support Locations in Steam Generators.Agenda Encl ML20246P6001989-09-0505 September 1989 Notification of 890907 Site Visit & Meeting W/Util to Observe Existing Corrosion of Unit 1 Steel Containment Vessel & Discuss Adequacy of Remaining Wall Thickness for Units 1 & 2 ML20246B8381989-08-22022 August 1989 Notification of 890831 Meeting W/Util in Rockville,Md to Discuss Util Findings from Steam Generator Tubes & Plugs Inspected During Present Refueling Outage of Unit 2 from Earlier Related Metallurgical Analyses of Unit 1 Specimens ML20245K3261989-04-26026 April 1989 Notification of 890505 Meeting W/Util in Rockville,Md to Discuss Cause of Unit 890307-08 Tube Rupture,Corrective Actions & Plans for Restart ML20247B7351989-03-24024 March 1989 Notification of 890503 Meeting W/B&W,Inel & Util in Rockville,Md to Discuss Licensing Submittals for Plants ML20236E2931989-03-15015 March 1989 Discusses Closure of Outstanding Tech Spec Concerns Deriving from R Licciardo Differing Prof Opinion Review of Plant Tech Specs.Requests That Priority Be Given to Final Closure Including Completion of Remaining 45 Specific Items ML20236E2971989-03-15015 March 1989 Discusses Incorporation of Items Into Westinghouse STS Deriving from NRC Confirmation of Generic & multi-plant Action Concerns from R Licciardo Review of Plant Tech Specs ML20206E5691988-11-15015 November 1988 Summarizes 881109 Telcon W/Util Re Control Area Ventilation Sys Mod & Associated Tech Spec Change.Addl Info Requested Stated ML20058N6761988-10-18018 October 1988 Discusses Action Item 5 Assigned in 880406 Memo Related to Diagnostic Evaluation Team Report for Plant on Pump Damage Due to Low Flow Cavitation 1999-09-30
[Table view] Category:MEMORANDUMS-CORRESPONDENCE
MONTHYEARML20217L7171999-10-22022 October 1999 Informs That Encl Questions Were Transmitted by Email to PT Vu of Duke Energy Corp,In Preparation for Upcoming Telcon Re 990624 Amend Request ML20216J2171999-09-30030 September 1999 Informs That Encl Questions Were Transmitted by Email on 990930 to M Purser of Duke Energy Corp for Preparation of Upcoming Telcon.Questions Pertain to 990624 Amend Request ML20210L6601999-08-0505 August 1999 Forwards single-page Document Given to G Belisle of Region II by T Clements of Nuclear Control Institute Re Mixed Oxide Fuel ML20196K6231999-07-0101 July 1999 Forwards Draft Safety Evaluation on TR DPC-NE-2009, Duke Power Co Westinghouse Fuel Transition Rept. Rept Was Transmitted to Warren in Order to Prepare for Conference Call ML20195J1181999-06-14014 June 1999 Forwards Documents That Were Transmitted by Fax on 990614 to a Jones-Young Re Issues to Be Discussed in Upcoming Telcon Re DPC Response to GL 98-04 ML20207G3661999-06-0909 June 1999 Reissued Notification with Date Change of 990618 Meeting with DPC in Rockville,Maryland to Discuss Compensatory Actions (Allowed Outage Time) for McGuire Nuclear Station ML20207E7741999-06-0202 June 1999 Notification of 990617 Meeting with Util in Rockville,Md to Discuss Compensatory Actions (AOT) for McGuire Nuclear Station ML20206U4231999-05-18018 May 1999 Notification of 990602 Meeting with Duke Energy Corp,Vepco & Others in Rockville,Md to Discuss Technical,Regulatory & Licensing Issues Related to Proposed Future Use of Mixed Oxide Fuel at Catawba,Mcguire & North Anna Nuclear Stations ML20205H9131999-03-24024 March 1999 Forwards NRC Operator Licensing Exam Repts 50-369/99-301 & 50-370/99-301 (Including Completed & Graded Tests) for Tests Administered on 990125-0205 ML20199B0491999-01-11011 January 1999 Notification of 990127 Meeting with Duke Energy Corp in Rockville,Md to Discuss License Amend for Taking Credit for Soluble Boron & Boraflex ML20195H0421998-11-17017 November 1998 Informs That Encl Questions Were Transmitted by e-mail to Warren of Duke Energy Corp in Preparation for Upcoming Telephone Call.Memo & Enclosure Do Not Convey Formal Request for Info or Represent NRC Staff Position ML20154L0811998-09-23023 September 1998 Notification of 981016 Meeting with Util in Rockville,Md to Discuss Recent Site Performance Major Plant Equipment Upgrades & Operational,Licensing & Regulatory Issues.Meeting Has Been Cancelled ML20153E0781998-09-23023 September 1998 Revised Notification of 981016 Duke Energy Corp in Rockville,Md to Discuss Recent Site Performance,Major Plant Equipment Upgrades & Operational,Licensing & Regulatory Issues.Meeting Revised to Change Date & Room Number ML20151X1931998-09-14014 September 1998 Notification of 981006 Meeting W/Duke Energy Corp in Rockville,Md to Discuss Recent Site Performance,Major Plant Equipment Upgrades & Operational,Licensing & Regulatory Issues ML20249C6451998-06-25025 June 1998 Notification of 980709-10 Meeting W/Duke Energy Corp in Rockville,Md to Discuss Technical Issues Re Proposed Improved TSs for Catawba & McGuire Nuclear Stations ML20249B6241998-06-19019 June 1998 Forwards Draft SE Re Relocation of Meteorological Tower for Plant ML20248F1061998-06-0202 June 1998 Notification of 980617 & 18 Meeting W/Util in Rockville,Md to Discuss Technical Issues Re Proposed Improved TSs for Catawba & McGuire Nuclear Stations ML20217Q6151998-05-0707 May 1998 Notification of 980518 & 19 Meeting W/Util in Rockville,Md to Discuss Technical Issues Re Proposed Improved TSs for Catawba & McGuire Nuclear Stations ML20217M1831998-05-0101 May 1998 Notification of 980514 Meeting W/Util in Rockville,Md to Discuss Plans for Changes to TS Re Following Ice Condenser Issues:Ice Weight Redistribution,Reduction & Block Ice Utilization ML20199A4781998-01-22022 January 1998 Notification of 980204 Meeting W/Util in Rockville,Md to Discuss Staff Recent RAI Re Snubbers ML20198M8931998-01-12012 January 1998 Notification of 980127 Meeting W/Util in Rockville,Md to Discuss Technical Issues Covered by DEC TR in Support of Future Transition from Framatome to Westinghouse Fuel ML20198S8131997-10-30030 October 1997 Notification of 971118 Meeting W/Util to Discuss Specific Aspects of Dual Unit Trip & Licensee Corrective Actions ML20198K1961997-10-16016 October 1997 Notification of 971030 Meeting W/Util in Rockville,Md to Discuss Matters Re Proposed Improved TSs for Catawba & McGuire ML20210M8231997-08-22022 August 1997 Forwards Signed Original of Subject Order Attached for Transmittal to Ofc of Fr for Publication.W/O Encl ML20141B3041997-06-20020 June 1997 Notification of 970709 Meeting W/Util in Huntersville,Nc to Discuss Licensee Revs to 1996 Plant UFSAR & How 1996 Rev Complies w/10CFR50.71 ML20206L5711997-01-16016 January 1997 Discusses Grinell Snubbers for Use in Steam Generator Replacement Project.Snubbers Did Not Meet Purchase Specifications for Environ Conditions ML20129H7401996-08-29029 August 1996 Ack Receipt of 960801 Memo Re Reactor Trip Breaker Problems at Plants.Recommended That AEOD or Appropriate Group within NRR Advise OE Whether Technical Staff Considers That Violations Occurred,Per 10CFR50.73 or 10CFR21 ML20128Q2431996-08-0101 August 1996 Discusses Concerns Raised During 960722 AEOD Program Review Re Reportability of Reactor Trip Breaker Problems at Plants NUREG-1299, Forwards Continuation of Curtiss Papers to Be Filed Under Commission Correspondence in Pdr.Advanced Copy Sent to Pdr. List of Documents Included in Four Boxes Encl1994-06-29029 June 1994 Forwards Continuation of Curtiss Papers to Be Filed Under Commission Correspondence in Pdr.Advanced Copy Sent to Pdr. List of Documents Included in Four Boxes Encl ML20059E0261994-01-0404 January 1994 Notification of 940105 Meeting W/Util in Rockville,Md to Conduct AIT Meeting & Discuss Results of Licensee Investigation of Recent Loss of off-site Power Event at McGuire Plant ML20058J5061993-11-29029 November 1993 Notification of Significant Licensee Meeting W/Util on 931203 to Discuss Licensee Intended EAL Changes for All Three Plants Relative to NUMARC Issues & Implementation of EPA-400 ML20058J4911993-11-24024 November 1993 Notification of Significant Licensee Meeting W/Util on 931206 to Discuss self-assessment of Plant Performance Since 930802-1130 ML20058C9631993-11-19019 November 1993 Notification of 931201 Meeting W/Util in Rockville,Md to Update NRC on Mcguire,Units 1 & 2 & Catawba,Unit 1 Steam Generator Replacement Project ML20057D1651993-09-27027 September 1993 Notification of 930929 Meeting W/B&W in Rockville,Md to Discuss Installation Process Used for B&W Kinetic Sleeves at McGuire Nuclear Station ML20057C5441993-09-23023 September 1993 Notification of 930929 Meeting W/Util in Rockville,Md to Discuss Results of Util Investigation of Unit 1 SG Tube Leaks & Util Actions as a Result of Findings from Investigation ML20056H3141993-08-24024 August 1993 Forwards Safety Evaluation Accepting Critical Aspects of Proposed TS Changes Involving Increasing Min Rswt Boron Concentrations from 2,000 Ppm to 2,275 Ppm & Increasing Min Cla Boron Concentration from 1,900 Ppm to 2,000 Ppm ML20134B2531993-02-11011 February 1993 Responds to 930113 Request for Exceptions to N+1 Policy for Listed Plants.Approved Exceptions W/Stated Conditions Effective for Period of 2 Yrs ML20128G8201993-02-0101 February 1993 Notification of Significant Licensee Meeting W/Util on 930211 to Discuss Enforcment Conference on Safeguards Issues ML20126F2821992-12-24024 December 1992 Forwards Description of Valves Affected by Stroke Testing & Effect of Valves Being Opened or Closed During Testing,W/ Respect to Encl LER 369/90-022-1 Re RHR Sys Being Inoperable ML20128A0361992-11-30030 November 1992 Notification of 921215 Meeting W/Util in Rockville,Md to Discuss Status of Licensees Plans to Implement Pilot Program for Use of Seismic Stops in Lieu of Snubbers at Plant ML20059H7861990-09-10010 September 1990 Forwards Revised Resolution of Plant-Specific Differing Prof Opinion (DPO) Issues Concerning McGuire Tech Specs, in Support of Completion of Dpos,Per Author 891229 Memo.Actions Re Tech Specs Listed ML20055D9791990-07-0505 July 1990 Notification of 900719 Meeting W/Util in Rockville,Md to Discuss Cause,Morphology & Future Plans Re Cracking Tubes at Expansion Transition Zone & at Tube Support Locations in Steam Generators.Agenda Encl ML20246P6001989-09-0505 September 1989 Notification of 890907 Site Visit & Meeting W/Util to Observe Existing Corrosion of Unit 1 Steel Containment Vessel & Discuss Adequacy of Remaining Wall Thickness for Units 1 & 2 ML20246B8381989-08-22022 August 1989 Notification of 890831 Meeting W/Util in Rockville,Md to Discuss Util Findings from Steam Generator Tubes & Plugs Inspected During Present Refueling Outage of Unit 2 from Earlier Related Metallurgical Analyses of Unit 1 Specimens ML20245K3261989-04-26026 April 1989 Notification of 890505 Meeting W/Util in Rockville,Md to Discuss Cause of Unit 890307-08 Tube Rupture,Corrective Actions & Plans for Restart ML20247B7351989-03-24024 March 1989 Notification of 890503 Meeting W/B&W,Inel & Util in Rockville,Md to Discuss Licensing Submittals for Plants ML20236E2931989-03-15015 March 1989 Discusses Closure of Outstanding Tech Spec Concerns Deriving from R Licciardo Differing Prof Opinion Review of Plant Tech Specs.Requests That Priority Be Given to Final Closure Including Completion of Remaining 45 Specific Items ML20236E2971989-03-15015 March 1989 Discusses Incorporation of Items Into Westinghouse STS Deriving from NRC Confirmation of Generic & multi-plant Action Concerns from R Licciardo Review of Plant Tech Specs ML20206E5691988-11-15015 November 1988 Summarizes 881109 Telcon W/Util Re Control Area Ventilation Sys Mod & Associated Tech Spec Change.Addl Info Requested Stated ML20058N6761988-10-18018 October 1988 Discusses Action Item 5 Assigned in 880406 Memo Related to Diagnostic Evaluation Team Report for Plant on Pump Damage Due to Low Flow Cavitation 1999-09-30
[Table view] Category:NRC TO ACRS
MONTHYEARML20140A5261986-03-18018 March 1986 Forwards Draft SER for Proposed Operation W/O upper-head Injection (Uhi) to Provide Basis for 860326 Meeting W/Eccs Subcommittee.Nrc Will Be Able to Conclude That Operation at 100% Power W/Uhi Isolated or Removed Acceptable 1986-03-18
[Table view] |
Text
, , f(ja%9 k UNITED STATES [ j -- 3 f f 4
3 NUCLEAR REGULATORY COMMISSION j
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..... M 16 g M4UB Mn MEMORANDUM FOR: Paul Boehnert Senior Staff Engineer, ACRS ,
FROM: Carl H. Berlinger, Chief Reactor Systems Branch, PWR-A
SUBJECT:
DRAFT SER FOR THE PROPOSED OPERATION OF MCGUIRE UNITS 1 AND 2 WITHOUT UPPER HEAD INJECTION Enclosed is a draft SER and its supporting documents for your consideration in anticipation of a March 26, 1986 meeting with the ECCS subcommittee.
As reflected in this draft SER we are in final stages of our technical review and are reasonably confident that upon completion, we will be able to conclude that operation of the McGuire units at 100% power with UHI isolated or removed is acceptable. However, prior to concluding this review, we wish to have the benefit of ACRS comments. We believe that the enclosed SER, although in draft form at this time, provides the basis for a meeting to this end, and is responsive to the request of the Committee during the February 21, 1985 meeting for further discussions prior to completion of the staff's review.
V r .
Carl H. Berlinger, Chief Reactor Systems Branch, PWR-A
Enclosures:
- 1. March 17, 1986, letter from Rahe to Berlinger transmittino (a) responses to NRC staff questions about UHI removal at McGurie and (b) revisions to Chapter 15 of the McGuire FSAR starting with page 15.6-7.
- 2. March 17, 1986, letter from H.B. Tucker to H.R. Denton, regarding UHI removal / isolation.
- 3. January 29, 1986, SNL letter Dobranich to Watt, TRAC-PFI/ MODI calculations 4 March 12, 1986, SNL transmittal Dobranich to Watt, UHI PWR with UHI removal.
- 5. November 20, 1985, memo Rowsome to Novak reliability assessment of USI auto-isolation capability.
- 6. March 5, 1986, memo Rossi to Hood, McGuire radiological safety evaluation report.
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. A SAFETY EVALUATION OF THE PROPOSED OPERATION OF MCGUIRE UNITS 1 & 2 WITHOUT UPPER HEAD INJECTION INTRODUCTION In a letter dated May 9, 1985, the Duke Power Company (licensee) proposed license amendments for McGuire Nuclear Station Units 1 and 2 to change the Technical Specifications in accordance with a program to delete Upper Head Injection (UHI) systems at McGuire. In the May letter, the licensee described the results of a feasibility study (for UHI removal) and outlined its program for obtaining NRC approval.
The proposed Technical Specification changes were modified December 17, 1985 to provide for levels of modification achievable in successive fuel reloads. Options included: (1) operation with UHI available, (2) operation with UHI locked out, and (3) operation with UHI components external to the reactor vessel effectively removed. The licensee committed to support the proposed Technical Specification changes through confirmatory studies.
By letter of October 2,1985, the licensee submitted proposed revision to the McGuire Nuclear Station Safety Analysis for UHI _ Elimination. The FSAR reanalyses of the large break LOCA had utilized the computer code " BASH" which was then under review by the staff. The licensee noted that the reanalysis confirmed the proposed revisions to the technical specifications conservative but also that they may be relaxed to allow full operational flexibility. They intended to propose further changes following NRC approval of deletion of UHI, Problems were encountered by Westinghouse with BASH reflood heat transfer in February 1986. Accordingly, on March 17, 1986, the licensee submitted a reanalysis and update of the October 2,1985 safety analysis. This reanalysis utilized BART, a previously accepted Westinghouse evaluation model. It is the March 17, 1986 submittal which provides the principal basis for this Safety Evaluation.
DRAFT EVALUATION s
A large break LOCA spectrum consisting of three double-ended cold-leg guillatine breaks with discharge coefficients (CD ) of .4, .6, and .8 were analyzed. An NRC-approved BART code was utilized. The UHI system had been disconnected externally leaving the components inside the reactor vessel unchanged. The cold leg accumulator system had been modified to more closely approximate other non-UHI plants. Accumulator pressure had been increased, water volume decreased slightly and the restriction between accumulator and primary system reduced to minimize the length of refill. For the limiting discharge coefficient, both minimum and maximum safety injection were considered. An Fg of 2.26 was assumed, coinciding with the current technical specification value.
We have reviewed the elements of these calculations and conclude that an appropriate methodology was used for analyzing ECCS performance under these conditions. The results of the analyses are within the performance limits of 10 CFR 50.46. The analyses took credit for rotention of UHI components internal to the reactor vessel.
A spectrum of three small breaks were analyzed using the NRC-approved NOTRUMP. The fuel performance was well within all acceptance criteria.
Two accidents were reanalyzed without UHI system actuation because it had previously been indicated that the system pressure could dip to below UHI initiation. DNBR limits were safely avoided for both events. (Inadvertent Opening of a Steam Generator Relief or Safety Valve,15.1.4 and Steam System Piping Failure, 15.1.5.)
Containment analysis for Large Break LOCA and Steamline Breaks were also adequately addressed.
We therefore conclude that the LOCA analysis for non-VMI operation is acceptable. Other Chapter 15 events potentially effected by UHI have been evaluated without exceeding limits.
1
JUSTIFICATION s
The action supported by this evaluation would permit removal of an element of the emergercy core cooling system (ECCS) as originally designed for the McGuire units. General Design Criterion 35 describes a system to provide abundant core cooling. The following discussion is intended to provide some insight into how removal is justified.
By design, the UHI could inject up to 1000 FT3 of water into the upper head of the reactor vessel during a postulated LOCA.. Vessel internals were provided to obtain uniform mixing with flow from the hot legs during blowdown. It was expected that UHI would enhance core cooling during blowdown and assure rewet or quench at the start of refill of the lower plenum.
In the process of developing an evaluation model for plants containing UHI, uncertainties were identified in modeling and in the supporting experiments.
Conservative or bounding or in some cases " alternate approh hes" were built into the evaluation model to compensate for the uncertainties and assure that the peak clad temperatures calculated were bounding, Reference NUREG-0297.
The limited credit for heat transfer allowed for in the UHI model has subsequently been exceeded by the enhanced cooling or reduced heatup derived from improved analytical models (as reflected in BART).
NRC consultants and Westinghouse have performed studies using both best estimate and NRC-approved evaluation model codes to characterize the difference between UHI and non-UHI response to the LOCA.
I l
Figure 1 compares evaluation model calculations. The plant transient shown as case 2 has been superseded by an analysis submitted on March 17, 1986 as a safety analysis revision. Unfortunately, the revised figure was not presently I available. The peak clad temperatures for Case 2 and the revised Case 2 during blowdown are essentially identical because they occur before UHI system injection. The hot rod is somewhat cooler at the end of blowdown with UHI.
UHI delays reflood and the hot rod reaches a higher temperature.
%i The best estimate calculations shown in Figure 2 produce about the same PCT during blowdown as with the evaluation model. The UHI case remains quenched, while the non-UHI case shows a reheat to 1430 F (some 600 F cooler than the EM results).
Table 1 lists some of the conservatisms'in the evaluation model. These are discussed further in the March 17 submittal from Westinghouse (Rahe to Berlinger) entitled " Responses to NRC Staff Questions about UHI Removal at McGuire".
The maximum safety injection case (without UHI and Cd of .6) provided the highest calculated peak clad temperature. Although this is within 10 CFR 50.46 limits, we are still evaluating the significance. ,
We believe the non-UHI peak clad temperature to be conservative and acceptable. We believe the UHI evaluation model to be excessively conservative, l
i
TABLE 1 SOME CONSERVATIVE ASPECTS OF THE EVALUATION MODEL The evaluation model conservatively prohibits quenching of the hot rod' independent of blowdown fluid conditions. Thus, the benefit of UHI l.
quench cooling is limited to the non-limiting _ fuel rods.
The quench line is not a best estimate line. It is biased
-conservatively by providing 90% confidence that 50% of the true data 4 population is above the line and also because the data'is from electrica'lly heated rods rather than fuel rods.
The evaluation model prohibits quench in the upflow direction.
A fictitious film boiling heat transfer coefficient is imposed. In a range of conditions the value is either 1.0 or 7 to 12 B/HR-FT 2 F.
Evaluation model usage requires that calculations be done for both perfect mixing and imperfect mixing in upper head to assure acceptably conservative results. This prohibits optimization of UHI systems.
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