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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:INCOMING CORRESPONDENCE
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 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 ML20217F3591999-10-13013 October 1999 Forwards Info Copy of Cycle 14 COLR for McGuire Nuclear Station,Unit 1 ML20217G7861999-10-13013 October 1999 Forwards MOR for Sept 1999 & Revised MOR for Aug 1999 for McGuire Nuclear Station,Unit 1 & 2 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 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 ML20216E8791999-09-14014 September 1999 Forwards Monthly Operating Repts for Aug 1999 & Revised Monthly Operating Rept for July 1999 for McGuire Nuclear Station 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 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 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 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 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 ML20210R4311999-08-10010 August 1999 Forwards Summary Rept of Mods,Minor Mods,Procedure Changes & Other Misc Changes Per 10CFR0.59 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 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 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 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 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 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 ML20206S9151999-05-11011 May 1999 Forwards Rev 29 to McGuire Nuclear Station Selected Licensee Commitments. Section 16.11-16.2 Has Been Revised to Apply Guidance of NUREG-0133 for Performing Gaseous Effluent Dose Pathway Calculations ML20206K1341999-05-0303 May 1999 Forwards 1999 Interim UFSAR for McGuire Nuclear Station. UFSAR Update Includes Items Relocated During Improved Tech Specs Implementation.Next Regular UFSAR Update as Required 10CFR50.71(e) Is Due in Oct 1999 ML20206F3321999-04-28028 April 1999 Forwards Annual Radioactive Effluent Release Rept for 1998 for McGuire Nuclear Station. Listed Attachments Are Contents of Rept.Revised ODCM Was Submitted to NRC on 990203 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 ML20206B4791999-04-20020 April 1999 Requests Exemption from GDC 57 Re Reactor Containment - Closed Sys Isolation Valves,As Described in 10CFR,App a for Containment Penetrations M393 & M261.Detailed Technical Evaluation & Justification for Exemption Request,Encl ML20205S9731999-04-19019 April 1999 Submits Info Re Quantity of SG Tubes Inspected,Tube Indications of Imperfections & Tubes Removed from Svc by Plugging,Per TS 5.6.8,part B 05000369/LER-1999-001, Forwards LER 99-01(S)-00 Re Contract Employee Submittal of False Info Resulting in Gaining Unescorted Access.No Licensee Planned Corrective Actions or Other Regulatory Commitments Were Identified as Result of Incidence1999-04-16016 April 1999 Forwards LER 99-01(S)-00 Re Contract Employee Submittal of False Info Resulting in Gaining Unescorted Access.No Licensee Planned Corrective Actions or Other Regulatory Commitments Were Identified as Result of Incidence ML20205P8891999-04-13013 April 1999 Forwards Monthly Operating Repts for Mar 1999 for McGuire Nuclear Station,Units 1 & 2.Revised Rept for Feb 1999 Encl ML20206K3561999-04-13013 April 1999 Forwards Revised McGuire Nuclear Station Selected Licensee Commitments (SLC) Manual. Significant Changes Are Marked by Vertical Bars on Right Margin ML20205K5131999-04-0707 April 1999 Forwards Complete Response to NRC 981209 & 990105 RAIs on Question 11 Re LARs for McGuire & Catawba Nuclear Stations. Addl Info Received from W & Contained in Encl W ML20205B6011999-03-23023 March 1999 Requests That NRC Place Technical Interface Agreement 97-02 Re URI 96-11-03,raising Operability & Design Criteria Conformance Issues Re Hydraulic Snubbers Installed at Plant & NRR Response on Dockets to Provide Record of Issue ML20205C4611999-03-23023 March 1999 Submits Correction to Violation Against 10CFR50 App B, Criterion VII, Control of Purchased Matl,Equipment & Svcs, Issued to McGuire Nuclear Station on 980807 ML20205B6161999-03-23023 March 1999 Provides Addl Info & Correction to Typo in Re License Bases Record Change Re License Amend Submittals ,approved as FOL NPF-9 & NPF-17,amends 184 & 166, respectively.Marked-up TS Pages,Encl ML20204J0051999-03-19019 March 1999 Forwards Response to 990127 & 28 RAIs Re GL 96-05 for Catawba & McGuire Nuclear Stations ML20204E1791999-03-18018 March 1999 Reflects 990318 Telcon Re License Bases Record Change for License Amend Submittals ,approved as Amends 184 & 166,respectively for Licenses NPF-9 & NPF-17.TS Pages Encl ML20204C8821999-03-15015 March 1999 Forwards Monthly Operating Repts for Feb 1999 for McGuire Nuclear Station,Units 1 & 2.Revised Rept for Jan 1999 Encl ML20207C2071999-02-25025 February 1999 Informs of Revised Expected Submittal Date of Proposed License Amend Presented at 990127 Meeting Re Soluble Boron & Boraflex.Util Plans to Submit Proposed License Amend in First Quarter of 1999 ML20207C7691999-02-22022 February 1999 Forwards Annual Occupational Radiation Exposure Rept for 1998. Rept Provides Tabulation of Number of Station,Utility & Other Personnel Receiving Exposure Greater than 100mRem/yr Followed by Total Dose for Each Respective Worker ML20207C6851999-02-22022 February 1999 Forwards Revised TS Bases Pages,Reflecting Removal of SI Signal on Low Steamline Pressure on Page B 3.3.2-16 & Adding Clarification for Increasing Hydrogen Recombiner Power During Testing on Page B 3.6.7-4 ML20206S3341999-01-28028 January 1999 Forwards Proprietary & non-proprietary Responses to NRC 981209 & 990105 RAIs Re Util Lars,Permitting Use of W Fuel at McGuire & Catawba Stations.Proprietary Info Withheld,Per 10CFR2.790 ML20199E0081999-01-12012 January 1999 Forwards MOR for Dec 1998 & Revised MOR for Nov 1998 for McGuire Nuclear Station,Units 1 & 2 ML20199C9861999-01-0707 January 1999 Forwards Annual Lake Norman Environ Summary Rept for 1997,as Required by NPDES Permit NC0024392,including Detailed Results & Data Comparable to That of Previous Years.With Corrected Pages 3 & 19 to 1994-95 Lake Norman Creel Rept 1999-09-09
[Table view] Category:UTILITY TO NRC
MONTHYEARML20059L0101990-09-19019 September 1990 Provides Addl Response to Violations Noted in Insp Repts 50-369/90-11 & 50-370/90-11,per .Corrective Action:Operations & Compliance Mgt Further Examined Event & Concluded That Trains Vc/Yc Inoperable Per Special Order ML20059L0091990-09-18018 September 1990 Informs of Delay in Response to Violations Noted in Insp Repts 50-369/90-14 & 50-370/90-14.Delay Due to Ongoing Review ML20059L5491990-09-14014 September 1990 Forwards Proprietary Response to Question Re Scope of Review of Topical Rept, Safety Analysis Physics Parameter & Multidimensional Reactor Transients Methodology, Per & 900723 Meeting.Response Withheld ML20059J7121990-09-14014 September 1990 Forwards Monthly Operating Rept for Aug 1990 for McGuire Nuclear Station Units 1 & 2 & Monthly Operating Status Rept for Jul 1990 ML20059L5521990-09-14014 September 1990 Forwards Response to 18 Questions Re Topical Rept DPC-NE-2004,per NRC 900802 Request for Addl Info.Encl Withheld (Ref 10CFR2.790) ML20065D4671990-09-11011 September 1990 Informs of Delay in Response to Violation Noted in Insp Repts 50-369/90-11 & 50-370/90-11,per Commitment in ML20064A8031990-09-10010 September 1990 Responds to NRC Ltr Re Violations Noted in Insp Repts 50-369/90-13 & 50-370/90-13.Corrective Actions:Procedures Dealing W/Fuel Handling Will Be Enhanced by Adding Sign Off to Sections Which Ref Fuel Handling in Tech Specs ML20059G3011990-09-0404 September 1990 Forwards Response to NRC 900327 Request for Addl Info Re BAW-10174, Mark-BW Reload LOCA Analysis for Catawba & Mcguire ML20064A5741990-09-0404 September 1990 Discusses Re Info to Support Util Position Relative to Resolving Issue of Main Steam Line Breaks Inside Ice Condenser Containments & Requests That Info Be Withheld (Ref 10CFR2.790) ML20064A5671990-09-0101 September 1990 Advises That Corrective Actions Re Violation of Insp Rept 50-369/89-01 & 50-370/89-01 Will Be Completed by 910101 ML20059D3461990-08-30030 August 1990 Forwards Semiannual Effluent Release Rept for First Half of CY90 & Revs to Process Control Program ML20059G9141990-08-22022 August 1990 Forwards Public Version of Revised Epips,Including Change 0 to RP/O/A/5700/01,Change 0 to RP/O/A/5700/02 & Change 0 to RP/O/A/5700/03 ML20059D1901990-08-22022 August 1990 Responds to Violations Noted in Insp Repts 50-369/90-11 & 50-370/90-11.Corrective Actions:Valves VC-1,VC-2,VC-3,VC-4, VC-9,VC-10,VC-11 & VC-12 Reopened Upon Discovery of VC-1 - VC-4 Being Closed & Procedure IP/0/13/3006/09 Revised ML16259A2391990-08-22022 August 1990 Forwards Public Version of Rev 27 to Company Crisis Mgt Implementing Procedure CMIP-2, News Group Plan. W/ Dh Grimsley 900906 Release Memo ML20059C1201990-08-20020 August 1990 Forwards Rept Summarizing Util Findings Re Three False Negative Blind Performance Urine Drug Screens Which Occurred During Jan & Feb 1990.Recommends That NRC Consider Generic Communication to Clearly State Reporting Requirement ML20059B4451990-08-20020 August 1990 Requests That NRC Approval of Original Relief Request 89-02 Be Extended to Include Changes to Mods MG-22233 & MG-22243 as Described.Hydrostatic Testing Impractical Due to Inadequacy of Test Boundaries ML20059C1591990-08-17017 August 1990 Suppls by Providing Addl Info to Support Util Position Re Anl Confirmatory Analysis of Main Steamline Breaks in Ice Condenser Plants.Encl Withheld ML20063Q0901990-08-15015 August 1990 Forwards Monthly Operating Repts for Jul 1990 for McGuire Nuclear Station Units 1 & 2 & Revised Rept for June 1990 ML20063Q2671990-08-14014 August 1990 Forwards Public Version of Revised Crisis Mgt Implementing Procedures,Including Rev 36 to CMIP-1,Rev 32 to CMIP-4,Rev 36 to CMIP-5,Rev 41 to CMIP-6,Rev 40 to CMIP-7,Rev 27 to CMIP-8 & Rev 35 to CMIP-9.W/DH Grimsley 900821 Release Memo ML20058N0181990-08-0808 August 1990 Forwards Response to Request for Addl Info Re BAW-10174, Mark-BW Reload LOCA Analysis for Catawba & Mcguire ML20063Q0181990-08-0707 August 1990 Confirms That Planned Corrective Actions Listed in Paragraph 3 of Insp Repts 50-369/90-10 & 50-370/90-10,appropriately Described ML20056A9541990-08-0101 August 1990 Provides Final Response to NUREG-0737,Item II.D.1, Performance Testing of Safety Relief Valves. Util Will Change Seal Configuration for Existing Valves to Seal on Steam Medium & Install Continuous Drain for Loop Piping ML20058L4061990-08-0101 August 1990 Forwards Rev 0 to Inservice Insp Rept Unit 1 McGuire 1990 Refueling Outage 6 ML20058L1811990-08-0101 August 1990 Forwards Safety Evaluation of Large Break LOCA Event Reanalysis Per 10CFR50.46 Re Peak Clad Temp Increases ML20059K0291990-08-0101 August 1990 Forwards Comments on Reactor Operator & Senior Reactor Operator Written Exams Administered on 900730 ML20056A1571990-07-23023 July 1990 Forwards Public Version of Change 0 to RP/0/A/5700/10 & Rev 25 to Section 18.2 of Radiation Protection Manual.W/ Dh Grimsley 900730 Release Memo NLS9000259, Responds to Violations Noted in Insp Repts 50-369/90-09 & 50-370/90-09.Corrective actions:in-house Training Will Be Provided on Correct Method for Determining Proper Response to Problem Investigation Processes1990-07-16016 July 1990 Responds to Violations Noted in Insp Repts 50-369/90-09 & 50-370/90-09.Corrective actions:in-house Training Will Be Provided on Correct Method for Determining Proper Response to Problem Investigation Processes ML20055F7721990-07-13013 July 1990 Forwards Monthly Operating Repts June 1990 for McGuire Nuclear Station Units 1 & 2 & Status Rept for May 1990 ML20044B0561990-07-0303 July 1990 Forwards Public Version of Epips,Consisting of RP/0/A/5700/02 & RP/0/A/5700/03 & RP/0/A/5700/04.W/ Dh Grimsley 900716 Release Memo ML20044A7941990-06-19019 June 1990 Forwards Public Version of Epips,Including HP/0/B/1009/06, HP/0/B/1009/10 & HP/0/B/1009/20 ML20043H5541990-06-18018 June 1990 Forwards Supplemental Info to Tech Spec Rev Request Re Auxiliary Bldg Filtered Ventilation Sys ML20043G1531990-06-15015 June 1990 Forwards Monthly Operating Repts for May 1990 & Corrected Unit Shutdowns & Power Reductions for Apr 1990 ML20043G1741990-06-0707 June 1990 Responds to Request for Addl Info Re BAW-10174, Mark-BW Reload LOCA Analysis for Catawba & Mcguire. Correct RCS Operating Pressure Would Be 2,250 Psia as Identified in Table 3-1 ML20043G3451990-06-0707 June 1990 Forwards Proprietary Response to Request for Addl Info Re Topical Rept BAW-10174, Mark-BW Reload Safety Analysis for Catawba & Mcguire. Response Withheld ML20043G7171990-06-0606 June 1990 Forwards Population Dose Analysis Summary for Plant Liquid Release Pathways Based on 1986 Release Estimates ML20043G6321990-06-0505 June 1990 Responds to Violations Noted in Insp Repts 50-369/90-01 & 50-370/90-01.Corrective Actions:Memo Issued Reemphasizing Importance of Frisking & Outlining Frisking Requirement & Personnel Counseled Re Completing Required Documentation ML20043G6281990-06-0404 June 1990 Advises That Corrective Actions Re Departmental Interface Issues to Resolve & Train on Revised Directive Will Be Completed by 900901,per Insp Repts 50-369/89-01 & 50-370/89-01 ML20043F4761990-05-30030 May 1990 Forwards Public Version of Revised Crisis Mgt Implementing Procedures,Consisting of Rev 20 to CMIP-13 & Deletion of CMIP-15 & CMIP-17.W/900612 Release Memo ML20043B5691990-05-23023 May 1990 Advises That Responses to Violations Noted in Insp Repts 50-369/90-01 & 50-370/90-01 Will Be Delayed Until 900601 ML20043C0781990-05-22022 May 1990 Responds to Violations Noted in Insp Repts 50-369/90-04 & 50-370/90-04.Corrective Actions:Correct Procedure Adherence Reemphasized to Job Supervisor & Engineering Group Involved in Authorization for Torque Change ML20043B9351990-05-16016 May 1990 Forwards Public Version of Epips,Including HP/1/B/1009/15 & HP/2/B/1009/15.W/DH Grimsley 900529 Release Memo ML20043A1041990-05-15015 May 1990 Forwards Monthly Operating Rept for Apr 1990 & Corrected Mar 1990 for McGuire Nuclear Station Units 1 & 2 ML20042G8221990-05-10010 May 1990 Forwards Addl Info Re Events Leading to 900509 Emergency Tech Spec (TS) Request Re TS 4.6.1.8,per Ds Hood 900510 Telcon & Requests That Changes Also Be Made to Unit 2 Ts. Proposed TS Encl ML20043A8621990-05-10010 May 1990 Forwards Info for Facility 1990 Refueling Outage Re Steam Generator F* Tubes & Tubes Removed from Svc or Repaired ML16152A9621990-05-0909 May 1990 Forwards Public Version of Revised Crisis Mgt Implementing Procedures,Including Rev 35 to CMIP-1,Rev 26 to CMIP-2,Rev 31 to CMIP-4,Rev 35 to CMIP-5,Rev 40 to CMIP-6,Rev 39 to CMIP-7 & Rev 26 to CMIP-8.W/DH Grimsley 900517 Release Memo ML20042G8331990-05-0808 May 1990 Forwards Info for Facility Tube Rupture Outage Re Steam Generator Inservice Insp,Per Tech Spec 4.4.5.5 & 6.9.2 ML16152A9531990-05-0202 May 1990 Forwards Proprietary DPC-NE-2000P-A & Nonproprietary DPC-NE-2000-A, DCHF-1 Correlation for Predicting Heat Flux in Mixing Vane Grid Fuel Assemblies. Proprietary Rept Withheld ML20042F2611990-04-30030 April 1990 Forwards Technical Evaluation That Concludes Fireproofing of Supports for safety-related HVAC Ducts Not Required & Amends Fire Protection Commitment Re HVAC Sys Support Fireproofing ML20042F8331990-04-26026 April 1990 Forwards Public Version of Revised Epips,Including Change 0 to RP/0/A/5700/01,RP/0/A/5700/02 & RP/0/A/5700/03 ML20042E0631990-04-13013 April 1990 Forwards Monthly Operating Repts for McGuire Nuclear Station for Mar 1990 & Feb 1990 Rept Re Personnel Exposure 1990-09-04
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,[. I. ENCLOSURE 3 s J DUKE POWER COMPANY MCGUIRE NUCLEAR STATION Po 1 sox 4sek CORNELIUS. N.C. 28o31 o488 TELEPHONE:470488751357 December 10, 1986 l Mr. John Munroe, Chief
- Operator Licensing Section U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, N. W.
, Suite 3100 Atlanta, Georgia 30303 l
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Subject:
McGuire Nuclear Station Review of Written Licensing Exams
Dear Sir:
Attached are our specific comments on the RO and SRO written examinations administered here on December 8, 1986. In addition, we also have these general concerns:
- 1. It appears that the learning objectives stated in our supplied training material were not used in selection of appropriate questions. Several questions appear to have been taken from the body of lesson plans and do not relate to the learning objectives for that lesson. This is inappropriate since our systematic approach to training is based on learning objectives. Lesson plans contain material that is beyond the expected learning objectives, and we strongly feel that questions on exams should be related to learning objectives.
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, 2. It appears that several questions require the verbatim memorization of Tech i Spec action statements that give the operator greater than one hour to take i the appropriate action. We feel that expecting memorization of this type information, which is available for reference in the control room, is ,
inappropriate.
i 8704280417 870403 PDR ADOCK 05000369 V PDR
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' > Raview of Written Licensing Exam Pag 2 2 December 10', 1986
, *- 6 If you need clarification on any of these items, please call Gary Gilbert at (704) 857-1357.
Very truly yours, len.2.175G,aff Tony . McConnell Manager McGuire Nuclear Station GDG/srt cc: Bill Griffin R. B. Travis W. O. Reeside P. F. 9.2 Attachment s
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. s MCGUIRE REACTOR OPERATOR LICENSE EXAMINATION 12/08/86 REVIEW GROUP COMMENTS SECTION 1 Question 1.02a Comment Test answer key reflects wrong answer.
Recommendation Change answer key to read DBW is more negative.
Justification Lesson Plan: OP-MC-RT-RCO, page 34 Lesson Plan reads "Overall effect of core age is that differential boron worth will get continually more negative from BOL to EOL. This is reflected by the DBW curve in the Data Book.
(Data Book Curve 6.2)
Question 1.05 Comment Test answer key reflects wrong answer.
Recommendation .
Change answer key to read: 1. Void coefficient
- 2. Doppler power coefficent
- 3. Moderator Temp. coefficient Justification Lesson Plan: OP-MC-RT-RCO, Handout MC-CP-RCO-7
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Pago 2 t L Question 1.06 Comment We feel that the explanations given in the answer key are incorrect.
Recommendation For all answers a, b, c, d explanations reference the Data Book Curve 6.5 that indicates the plant conditions that affect shutdown margin which is burnup, Tave, Boron concentration.
Rod height has no affect on shutdown margin.
Justification
- 1. Data Book curve 6.5
- 2. Lesson Plan OP-MC-RT-RB, page 14 through 18 Question 1.07 comment We feel that 1/2 of the required answer by the test answer key is not related to question asked. The question only asks "How" and not "Why".
Recommendation Delete the second part of the test answer given for this questicn and allow full credit for the first part which fully answers the question asked.
Justification he feel that, as indicated above, the first part of the test answer given fully answers the question asked.
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SECTION 2 Question 2.02c Comment We feel that the required answer by the test answer key is not related to question asked. The question did not ask for the individual NC Pump components. It only asks for additional actions that could occur upon Containment Phase B Isolation signal.
Recommendation We feel you should also accept "the Isolation of the KC System or RN System cooling to the NC pumps" for full credit.
Justification We feel that, as indicated above, the test answer given fully answers the question asked.
Question 2.03b comment Test answer key reflects wrong answer.
Recommendation Change answer to read:
High head injection (CCPs) System pressure Accumulators (CLAs) 600 + -50 psig Justification Lesson Plan: OP-MC-ECC-CLA, page 6, 1.3 A.l.d, page 9, 1.4.b.2 Lesson Plan: OP-MC-PS-NV, page 28 l
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Page 4 Question 2.04c Comment i
We feel that Part C to this question was not specific enough to require the answer indicated by the test key. The answer is only
- for pressurizer spray provided by the NC pumps.
Recommendation The actual answers provided by the students may include the pressure difference developed by the NV pumps and ND pumps which ,
is pressurizer Aux. spray supplies.
Justification Lesson Plan: OP-MC-SPS-SY-NC, page 15, 9.e and 9.f i
Question 2.07 j comment j
We feel this question is beyond the scope of required Reactor 1 Operator knowledge.
h l Recommendation l
We recommend this qu4stion be removed.
I i Justification l Lesson Plan: OP-MC-IC-IRE
! No Lesson Plan objectives and Lesson Plan does not provide a clear answer to this question. (Operator is required to know i
the cause of the Urgent Alarm, but is not required to know the i condition that cause the individual failures.)
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. t Question 2.08b comment The answer key does not reflect all the possible automatic actions that can occur if the tube leak continues, i
Recommendation We recommend that an acceptable answer should also be " EMF-46 Trip II alarm is received on high activity in the KC System, it i
will automatically close the KC surge tank vent".
Justification i Lesson Plan: OP-MC-SPS-SY-KC, page 10, 7.b i
j Question 2.14 I comment 1 The answer key does not rcflect the correct answer.
f Recommendation Change answer key to read: a. 12
- b. 12
- c. 33 l
' d. 57 i
The answer should be based on the answer the student indi-i cates in (a). The answer in (a) will dictate the NV System flow i balance values for b, c, and d.
i Justification i 1 The answer key has an incorrect assumption that seal leakoff flow decreases at the same proportion as seal injection flow
- decreases. This assumption is wrong because seal leakoff flow 4 is based on the #1 seal gap clearance which is dependent upon the #1 seal pressure difference.
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. i Question 2.15 Comment We feel it is beyond the required operator knowledge to memorize relief valve setpoints and the answer key does not reflect all the possible correct answers.
Recommendation Full credit should be received for five relief valves that discharge to the PRT without including the setpoints and the answer key should include the following relief valves:
- 1. NS pump suction relief
- 2. NI pump suction relief
- 3. NI, NV, NS relief valves Contact the McGuire Nuclear Station Training Organization for any answer in question (704)875-2961.
Justification I
Lesson Plan: OP-MC-SPS-SYS-NC No Lesson Plan objectives and Lesson Plan does not provide a clear answer to this question.
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Pag @ 7 SECTION 3 i
l Question 3.01a Comment The answer key may be misleading, since the student response may be that only NV-2 closes for Part 1 of answer a.
Recommendation l
We recommend that the student be given full credit if he states j that only NV-2 closes for Part 1 of answer a. t t
2 Justification i Lesson Plan: OP-MC-PS-ILE, Handout MC-ILE-4 i
Question 3.03 Comment The answer key is not complete.
Recommendation j The answer key should also include Incore ThermocoupPs Indica-
'l tions.
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j Justification Lesson Plan: OP-MC-CP-AD, Handout MC-SYS-SSF-2, 9-12-85 l
l Question 3.04b
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Comment The answer key does not reflect the answer the question asks for.
i i Recommendation The condition 2/4 Lo Lo Level in 2/4 SG's with Blackout I signal will result in the student including many answers associa-ted with a Blackout signal. Example of this would be the D/G '
sequencer actuation on a Blackout signal. This should be considered in the students' answers. l 1 Justification The question asks for all the initial automatic actions that I occur for each signal.
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Question 3.06 Comment The answer key does not include all possible correct answers.
Recommendation Include as a correct answer for full credit: No, containment spray will not occur because containment pressure is less than the CPCS setpoint of .35 psig."
Justification Lesson Plan: OP-MC-ECC-NS, page 11, 1.5.A.1 Question 3.08a and 3.08d Comment The answer key reflects the wrcng answer.
Recommendation Change the answer key to read:
- a. Rods will move out because Tref > Tave and the Temperature Error signal is the dominant signal between power mismatch and temperature error.
- d. Rods move in because Tref < Tave and Tref is decreasing due to turbine load decrease. This is the dominant signal and the power mismatch signal t
will also move rods in.
Justification Lesson Plan: OP-MC-IC-IRK, page 16, 1.4.B and page 14, Sect. G 1
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Paga 9 Question 3.13b Comment The student may answer the question between a possible range of 365 psig to 400 psig.
Recommendation Change answer key range to: "365 psig to 400 psig" Justification The test procedures at MNS accepts as a valid test lift pressure a value between 365 psig and 400 psig. The operators may answer the question with these values. There has been a recent incident at MNS in which a PORV operated at approximately 365 psig while in the low pressure. mode of operation. This incident is being incorporated into the Pzr Pressure Control Lesson Plan.
Question 3.16 Comment Answer key does not reflect all possible answers.
Recommendation Add to list of answers: P/A Converter Justification Lesson Plan: OP-MC-IC-IRE, page 23, Sect. 3.e i Question 3.17 Comment l l
The answer key does not reflect correct answer. The NV Lesson Plan reference has an incorrect value for VCT Lo Level auto swap.
Recommendation The correct value should be 1%. We recommend that you accept either 1% or 1.4%. This setpoint error will be corrected in the NV Lesson Plan.
Justification
! Annunciator Response Procedure: OP/1/A/6100/10H Panel AD7-D3
Paga 10 SECTION 4 Question 4.01 .
Comment Answer key is wrong.
Recommendation Change the answer key to read #2.
Justification Lesson Plan: OP-MC-SPS-IC-SPD, page 8 Question 4.02b comment The answer key does not reflect all the possible correct answers. The answer key only reflects case I of the NC Pump Malfunction Procedure.
Recommendation Include the following pump trip conditions in addition to the answers on the answer key for full credit:
Shaft vibration > 20 mils Frame vibration > 5 mils Motor Bearing Temp. > 195'F Stator Winding Temp. > 311*F Any three conditions acceptable for full credit. l l
Justification 1 AP/1/A/5500/08 Malfunction of NC Pump requires the operator to trip the NC pump if any of these conditions exist.
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Question 4.03b Comment We feel it is beyond the required knowledge of the operator to memorize specific steps of the subsequent action section of procedures.
Recommendation We recommend that you accept for full credit the following answer: 1. Start two boric acid transfer pumps
- 2. Open emergency boration control valve (NV-265)
Justification I The operator has all the Abnormal Procedures available for reference in the control Room for specific step sequence.
4 Question 4.10
, Comment The answer key is not complete.
Recommendation Include in the answer key: 4. If turbine will not trip, then close all S/G SM Isolation
! Valves.
Justification AP/1/A/5500/01 Reactor Trip, page 3 Question 4.12.b.2 l Comment 1
We feel this question is beyond the acope of required operator j knowledge.
Recommendation We recommend this question be removed.
Justification In accordance with Station Health Physics Manual and actual Station practice, this calculation will be performed by Health PhyL.vs. Refer to the MNS Health Physics Manual, Section 2.1.6.
, _ _ _ _ _ - . - _ _ , - _ _ - _ _,. __ - -.m__, - - . -
. .y Pcgn 12 Question 4.15 Comment We feel that the student should receive full credit if he states
" Manually exercise Reactor Trip Breakers".
Recommendation Accept " Manually exercise Reactor Trip Breakers" for full credit in answer #1 on the answer key.
l Justification
" Manually exercise Reactor Trip Breakers" fully answers the question asked.
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~ T Paga 1 MCGUIRE SENIOR REACTOR OPERATOR LICENSE EXAMINATION 12/08/86 REVIEW GROUP COMMENTS i
SECTION 5 l
Question 5.03 b comment Test answer key reflects wrong answer.
Recommendation Change answer key to read: Increase Justification QPTR by Tech. Spec. definition cannot be < 1; and the answer stated is for the Quadrant QPTR that had the divider barrier failure.
Question 5.04a Comment There are too many answers in the answer key. There are only four questions and there are five answers.
Recommendation We feel the correct answers are: 1. No effect
- 2. No effect
- 3. Higher
- 4. No effect - if change occurs and does not effect the total reacti-vity balance; or Higher - if the change l effects the total reacti-vity balance.
Justification Lesson Plan: OP-MC-SPS-RT-RB, page 11 through 13 ;
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Question 5.15 s
Comment
- Test answer key reflects wrong answer.
Recommendation Change answer key to read: 1. Void coefficient
- 2. Doppler power coefficent
- 3. Moderator Temp. coefficient Justification
! Lesson Plan: OP-MC-RT-RCO, Handout MC-CP-RCO-7 f
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SECTION 6 ,
Question 6.02 comment Part a: The answer key reflects a direct quote from the Lesson Plan body.
Part b: We feel this is beyond the required operator knowledge.
Recommendation Part a: We feel any reasonably worded answer should receive i full credit.
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Part b: We feel this question should be removed from the test.
1 Justification Part a: We feel that any reasonably worded answer will fully answer the question asked.
Part b: The power supplies are located on the Control Board for i operator reference.
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- Question 6.03a l comment i
The answer key does not reflect all possible answers, i
i Recommendation i
- We recommend that either NC System pressure or Charging Pump 1
Discharge Pressure be accepted as a full credit answer.
I Justification NV Pump discharge pressure will be slightly > NC System pressure at the pump seals.
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Recommendation i Full credit should be received for five relief valves that discharge to the PRT without including the setpoints and the answer key should include the following relief valves:
- 1. NS pump suction relief
- 2. NI pump suction relief
- 3. NI, NV, NS relief valves
- Contact the McGuire Nuclear Station Training Organization for any answer in question (704)875-2961.
l Justification Lesson Plan: OP-MC-SPS-SYS-NC No Lesson Plan objectives and Lesson Plan does not provide a
- clear answer to this question.
l Question 6.05c Comment i
The answer key does not reflect all the possible automatic
- actions that can occur if the tube leak continues.
! Recommendation
! We recommend that an acceptable answer should also be " EMF-46
'- Trip II alarm is received on high activity in the KC System, it i will automatically close the KC surge tank vent".
Justification Lesson Plan: OP-MC-SPS-SY-KC, page 10, 7.b i
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Pago 5 Question 6.06c Comment Answer key does not reflect all possible answers.
Recommendation Add to list of answers: P/A Converter Justification Lesson Plan: OP-MC-IC-IRE, page 23, rect. 3.c Question 6.07 comment The answer key is not complete.
Recommendation The answer key should also include Incore Thermocouple Indica-tions.
Justification Lesson Plan: OP-MC-CP-AD, Handout MC-SYS-SSF-2, 9-12-85
- Question 6.11 Comment
- 1. The answer key and test have incorrect point values.
- 2. We feel it is beyond the required operator knowledge to memorize alarm setpoints.
- 3. We feel the answer key does not reflect the question asked.
Recommendation
- 1. We recommend the correction of the point values.
- 2. We recommend the removal of the question.
- 3. If question is maintained on the test, the acceptable answer for the basis should be to prevent exceeding the Tech. Spec.
LCO limits.
Justification Lesson Plan OP-MC-ECC-CLA No Lesson Plan objectives and Lesson Plan does not provide a clear answer to this question.
Ptg3 6 Question 6.14 Comment Test answer key reflects wrong answer.
Recommendation
! Change answer to read:
High head injection (CCPs) System pressure Accumulators (CLAs) 600 + -50 psig Justification i
Lesson Plan: OP-MC-ECC-CLA, page 6, 1.3 A.1.d, page 9, 1.4.b.2 i Lesson Plan: OP-MC-PS-NV, page 28 ,
Question 6.15 Comment The answer key does not include all possible correct answers.
3 Recommendation
! Include as a correct answer for full credit: No, containment spray will not occur because containment pressure is less than j
the CPCS setpoint of .35 psig."
Justification Lesson Plant OP-MC-ECC-NS, page 11, 1.5.A.1 2
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.V Pagn 7 SECTION 7 Question 7.02 comment We feel it is beyond the required knowledge of the operator to memorize specific steps of operating procedures.
Recommendation We feel an acceptable answer to receive full credit is:
" Insert control rods and refer to Operating Procedure" Justification The operators will have the Operating Procedure in the Control Room while performing the Unit startup.
Question 7.04
! Comment We feel that the student should receive full credit if he states
" Manually exercise Reactor Trip Breakers".
Recommendation Accept " Manually exercise Reactor Trip Breakers" for full credit
- in answer #1 on.the answer key.
Justification
" Manually exercise Reactor Trip Breakers" fully answers the question asked.
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. '. Pcgo 8 Question 7.05 at comment The answer key does not address the condition if containment pressure is greater than 3 psig.
Recommendation Accept either the answer on the answer key or the following answer: "If containment pressure is > 3 psig and core exit thermocouples are increasing and pressurizer PORV's are open or if pressurizer pressure is > 2335 psig PORV setpoint".
Accept either answer for full credit.
I Justification EP/1/A/5000/09 Loss of All AC Power, RNO for > 3 psig 1
l j Question 7.06q comment The assumption stated in the answer key of 3000 R/Hr. was not
- j. found in the reference material.
i Recommendation We feel that any reasonable assumption should be accepted for I the dose rate and method of calculation.
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! There are numerous values for the dose rate of an uncovered Fuel Assembly existing throughout the industry such as 6 In addition, other effects such as scatter 10 R/Hr. at 1 ft.
i will affect the dose rate of some calculation from the source.
, The question is vague enough to allow at least two approaches to the calculation.
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-; .. 1 Page 9 Question 7.07a Comment The answer key specifies that the "A" CF control valve 4
be placed in manual.
i 1 Recommendation
- We recommend that the acceptable answer should be "All CF Control valves be placed in Manual".
Justification l AP/5500/16 specifies that all valves be placed in manual. .In
, addition, the "A" Channel (N-41) will input both "A" and "D" S/G level program.
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Question 7.15b Comment 4
l Written permission should not be a required response to this question, j Recommendation l We recommend that you remove " written permission received" from the answer key.
4 i Justification The context of the que'stion is such that the 10CFR20 requirements
! for exceeding the basic 1.25 Rem /qtr limit will be the response '
! rather than the administrative requirements for dose extension.
j 10CFR20 does not require written permission.
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- Question 7.16b Comment We feel it is beyond the required knowledge of the operator to memorize specific steps of the subsequent action section of
+ procedures.
Recommendation We recommend that you accept for full credit lhe followi~ng ^ '
1 answer: 1. Start two boric acid transfer pumps
- 2. Open emergency boration control valve (NV-265)
Justification The operator has all the Abnormal Procedures available,for i reference in the Control Room for specific step sequence.
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< -e - j SECTION 8 j I
Question 8.05b. i comment i L The answer key reflects an answer based on OMP 1-7. This is I misleading since the question context is referenced to Tech.
Specs.
Recommendation The acceptable answer should reference the Tech. Spec. minimum Shift crew statement for full credit'that reads:
- "The Fire Brigade shall not include"three members of the minimum shift crew necessary ... or the answer stated in the answer key.
i Justification
.s j. Tech. Spec. Section 6.2.2..e, page 6-1 4
i Question 8.10b
- Comment 1
We feel that this is beyond the required knowledge of the
- operator to recite a four hour Tech. Spec. action statement j
on a' written exam and assigning 1/2 of the. total point i value of the question to that answer.
Recommendation We recommend that this question be removed from the test.
Justification MNS expectation of the students is to be knowledgeable of one 4
hour or less action statements and the Tech. Specs. are available l l' to the operator in the Control Room at all times. '
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Question 8.11d Comment "RCP seal leakage" is a vague statement and could be mis-interpreted to mean leakage from the seals or seal injection supplied to the seals.
Recommendation 1 We recommend that you accept either " controlled leakage" or
" identified leakage" as a full credit answer.
Justification Tech. Spec. definition of control leakage is that seal injection supplied to the NC pumps and seal leakage (leakoff) is defined as identified leakage.
Question 8.15a Comment The answer key is not complete and incorrect.
Recommendation We recommend that is addition to the turnover sheet, you should also accept the R and R Log Book. Also, the Shift Supervisor Log Book is an unacceptable answer.
Justification OMP 2-2 and OMP 2-4 does not require specific logging of equipment that is out of service to be entered in the Shift Supervisor Log Book.
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Question 8.16b Comment We feel that this is beyond the required knowledge of.the operator to recite a two hour and a four hour Tech. Spec.
2 action statement on a written exam and assigning 2/3 of the total point value of the question to that answer, j
1 Recommendation
! We recommend that this question be removed from the test.
, Justification MNS expectation of the students is to be knowledgeable of one hour or less action statements and the Tech. Specs, are available
< to the operator in the Control Room at all times.
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! Question 8.17 1
Comment j We feel this question is beyond the required operator knowledge s and inappropriate for the following reasons:
- 1. Operation group is not responsible for determining or making Tech. Spec. reports.
- 2. There is no correct answer for part (a).
Recommendation (
} We recommend that this question be removed from the test.
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Justification '
- Tech. Spec. Section 6 and Station Directiv$ 2.8.1 (see i attachment of Station Directive 2.8.1)
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Question 8.21 Comment There is a typo in the answer key.
Recommendation Change the answer key to read: "c" Justification Station Directive 1.2.0 and Exam Bank Question reference (refer to Exam Bank question attachment) i i
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