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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217N3901999-10-25025 October 1999 Advises That Info Provided in & Affidavit Re Holtec Position Paper WS-115,rev 1,repts HI-87113, Rev 0,HI-87114,rev 0,HI-87102 Rev 0 & HI-87112,rev 0,marked Proprietary,Will Be Withheld from Public Disclosure ML20217L8591999-10-21021 October 1999 Discusses 990921 Request for Approval to Perform Alternative Testing as Part of Vermont Yankee Nuclear Power Station IST Program.Informs That Submittal Reviewed Against ASME Code Section XI Requirements & Forwards Safety Evaluation ML20217M1181999-10-19019 October 1999 Forwards NRC Rept Number 17, Requal Tracking Rept from Operator Licensing Tracking Sys.Rept Was Used by NRC to Schedule Requalification Exam for Operators & Record Requal Pass Dates ML20217D9711999-10-13013 October 1999 Responds to Request That Information Titled Addl Info Re Cycle Specific SLMCPR for Vermont Yankee Cycle 21 Be Withheld from Public Disclosure.Determined Info to Be Proprietary & Will Be Withheld from Public Disclosure ML20217F1261999-10-12012 October 1999 Forwards Update to Previously Submitted RELAP5 Analytical Assumptions for App R,Re RAI of 961104 BVY-99-130, Provides Clarification of Method for Determining MSIV Maximum & Minimum Pathway at Vermont Yankee Nuclear Power Station1999-10-0808 October 1999 Provides Clarification of Method for Determining MSIV Maximum & Minimum Pathway at Vermont Yankee Nuclear Power Station ML20217C1051999-10-0808 October 1999 Forwards Amend 153 to License DPR-3 & Safety Evaluation. Amend Revises TS Section 6.0,Administrative Controls,By Deleting TS Sections 6.2.2.f Which Contains Limits on Working Hours of Plant Staff ML20217C1501999-10-0707 October 1999 Forwards Insp Rept 50-271/99-11 on 990809-27.No Violations Noted.Insp Focused on Effectiveness of Engineering Functions in Providing for Safe Operation of Plant BVY-99-128, Submits Listed Addl Info in Support of 990414 Request for Clarification to SER Confirming Adequacy of Space Cooling for HPCI & RCIC Sys,Re Item II.K.3.24 of NUREG-0737.Copy of NEDE-24955,encl1999-10-0606 October 1999 Submits Listed Addl Info in Support of 990414 Request for Clarification to SER Confirming Adequacy of Space Cooling for HPCI & RCIC Sys,Re Item II.K.3.24 of NUREG-0737.Copy of NEDE-24955,encl ML20212J7891999-10-0404 October 1999 Informs That Licensee 980804,0628,29 & 990921 Responses to GL 98-01, Y2K Readiness of Computer Sys at NPPs Acceptable.Nrc Consider Subj GL to Be Closed for Plant ML20212J2231999-10-0101 October 1999 Forwards Copy of Environ Assessment & Fonsi Re 990317 Application for Amend to Revise TS Section 6.0 by Deleting TS Section 6.2.2.f Which Contains Limits on Working Hours of Plant Staff ML20212J6501999-09-30030 September 1999 Informs of Completion of mid-cycle PPR of VYNPS on 990913. No New Areas Identified in Which Licensee Performance Warranted Addl Insp Beyond Core Insp Program.Historical Listing of Plant Issues & Insp Plan Through Mar 2000 Encl ML20216J3531999-09-29029 September 1999 Responds to NRC Re Violations Noted in Insp Rept 50-271/99-12 on 990628-0811.Corrective Actions:Based on RFO 20 Maint Rule Outage Performance Review,Task Was Generated to Clarify & Enhance SD Monitoring Process BVY-99-122, Notifies of Intention to Reinstate Original Version of App F in FSAR & Correct Docket Re Assumption That Electrical Power Sys Are Designed IAW Requirements of GDC-171999-09-28028 September 1999 Notifies of Intention to Reinstate Original Version of App F in FSAR & Correct Docket Re Assumption That Electrical Power Sys Are Designed IAW Requirements of GDC-17 BVY-99-113, Requests Approval to Perform Alternative Testing to That Specified by ASME Boiler & Pressure Vessel Code,Section XI & Asme/Ansi OM, Operation & Maint of Nuclear Power Plants. Attachment 1 Provides Justification for Alternative Testing1999-09-21021 September 1999 Requests Approval to Perform Alternative Testing to That Specified by ASME Boiler & Pressure Vessel Code,Section XI & Asme/Ansi OM, Operation & Maint of Nuclear Power Plants. Attachment 1 Provides Justification for Alternative Testing BVY-99-116, Informs of Determination That Wh Schulze,License SOP-10528-1,will No Longer Maintain License at Facility. Termination of License Requested1999-09-21021 September 1999 Informs of Determination That Wh Schulze,License SOP-10528-1,will No Longer Maintain License at Facility. Termination of License Requested BVY-99-114, Provides Notification That Licensee Completed Y2K Remediation Efforts Described in Util 990608 Response to NRC GL 98-01,Suppl 11999-09-21021 September 1999 Provides Notification That Licensee Completed Y2K Remediation Efforts Described in Util 990608 Response to NRC GL 98-01,Suppl 1 BVY-99-121, Requests Extension Until 990929 to Respond to Violations Noted in Insp Rept 50-271/99-12,dtd 990819.Licensee Did Not Receive Rept Until 990830 & Addl Time Is Needed to Prepare & Allow for Adequate Review of Violation Response Submittal1999-09-20020 September 1999 Requests Extension Until 990929 to Respond to Violations Noted in Insp Rept 50-271/99-12,dtd 990819.Licensee Did Not Receive Rept Until 990830 & Addl Time Is Needed to Prepare & Allow for Adequate Review of Violation Response Submittal ML20212C1621999-09-17017 September 1999 Forwards Amend 175 to License DPR-28 & Safety Evaluation. Amend Revises TSs to Enhance Limiting Conditions for Operation & Surveillance Requirements Relating to Standby Liquid Control System BVY-99-115, Forwards non-proprietary & Proprietary Responses to 990714 RAI Re Civil & Mechanical Engineering Considerations for Proposed Change to TS to Increase Spent Fuel Storage Capacity from 2,870 to 3,355.Proprietary Encls Withheld1999-09-16016 September 1999 Forwards non-proprietary & Proprietary Responses to 990714 RAI Re Civil & Mechanical Engineering Considerations for Proposed Change to TS to Increase Spent Fuel Storage Capacity from 2,870 to 3,355.Proprietary Encls Withheld BVY-99-118, Responds to RAI Concerning GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions1999-09-16016 September 1999 Responds to RAI Concerning GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions ML20216F3171999-09-13013 September 1999 Forwards Insp Rept 50-271/99-06 on 990621-0801.One Violation Identified & Being Treated as Noncited Violation BVY-99-110, Informs of Util Intent to Replace Commitments Made in Licensee & Subsequently Ack in NRC with Containment Insp Criteria Defined in 10CFR50.55a(b)(2)(vi),per Drywell Coating Insp1999-08-31031 August 1999 Informs of Util Intent to Replace Commitments Made in Licensee & Subsequently Ack in NRC with Containment Insp Criteria Defined in 10CFR50.55a(b)(2)(vi),per Drywell Coating Insp BVY-99-111, Informs That Encl TS Bases Page 91 Has Been Revised to Allow Reactivity Anomaly BOC Steady State Core Reactivity to Be Normalized Between off-line Uncorrected Solution & on-line 3D-Monicore Exposure Corrected Solution1999-08-31031 August 1999 Informs That Encl TS Bases Page 91 Has Been Revised to Allow Reactivity Anomaly BOC Steady State Core Reactivity to Be Normalized Between off-line Uncorrected Solution & on-line 3D-Monicore Exposure Corrected Solution ML20211J5001999-08-31031 August 1999 Forwards Proposed Rev 29 to Yankee Decomissioning QA Program, for NRC Info & Approval.Yaec Requests That Rev 29, Dtd May 1999 & Originally Transmitted in Be Withdrawn from Further Consideration by NRC Staff ML20211J2711999-08-27027 August 1999 Forwards Amend 152 to License DPR-3 & Safety Evaluation. Amend in Response to Application Dated 990324,deletes License Condition 2.C (10) Which States: Licensee Shall Maintain FFD Program IAW Requirements of 10CFR26 ML20211G4791999-08-27027 August 1999 Forwards Notice of Withdrawal of 990420 Amend Request Re TS on Reloading & Unloading Sequence of Fuel in Reactor Core When All Fuel Removed from Core BVY-99-107, Submits Response to NRC RAI Re Proposed Change to TS to Increase Spent Fuel Storage Capacity from 2,870 to 3,355 Fuel Assemblies1999-08-26026 August 1999 Submits Response to NRC RAI Re Proposed Change to TS to Increase Spent Fuel Storage Capacity from 2,870 to 3,355 Fuel Assemblies ML20216F1891999-08-26026 August 1999 Forwards Copies of Maine Yankee & Yankee Rowe Refs Listed, Supporting Industry Position That Branch Technical Position Asb 9-2 Methodology over-estimates Spent Fuel Decay Heat ML20211E8841999-08-25025 August 1999 Requests That Licensee Provide bldg-specific Justification for Use of Method A.1 at Locations Where Amplification Significantly Exceeds 1.5 Limit Above 8 Hz ML20211E1371999-08-20020 August 1999 Forwards from J Bean to H Miller & FEMA Final Exercise Rept for 990427-29 Plume Exposure & Ingestion Pathway Exercise for Vermont Yankee Nuclear Power Station.No Deficiencies Noted.Areas Requiring C/A Identified ML20211H0851999-08-19019 August 1999 Forwards Insp Rept 50-271/99-12 on 990628-0711 & Nov. Violation Re Failure to Monitor Unavailability of Specific Sys,Structures & Components During Refueling Outage Did Not Allow Adequate Assessment of Maint Effectiveness BVY-99-108, Requests That Gv Bogue,Bj Croke,Vs Ferrizzi,Me French, Bk Mcnutt,Jf Meyer & DM Navarro Take BWR Gfes of OL Exam Administered on 991006.DA Daigler & ST Brown Will Have Access to Exams Before Tests Administered1999-08-19019 August 1999 Requests That Gv Bogue,Bj Croke,Vs Ferrizzi,Me French, Bk Mcnutt,Jf Meyer & DM Navarro Take BWR Gfes of OL Exam Administered on 991006.DA Daigler & ST Brown Will Have Access to Exams Before Tests Administered BVY-99-103, Informs That Util Expects to Submit Approx Twenty Licensing Actions in FY00 & FY01,in Response to Administrative Ltr 99-021999-08-18018 August 1999 Informs That Util Expects to Submit Approx Twenty Licensing Actions in FY00 & FY01,in Response to Administrative Ltr 99-02 ML20210S0621999-08-10010 August 1999 Forwards semi-annual fitness-for-duty Program Performance Data for six-month Period of 990101-990630,IAW 10CFR26.71(d) ML20210R1421999-08-0404 August 1999 Forwards Insp Rept 50-029/99-02 on 990411-0714.One Severity Level 4 Violation Occurred,Being Treated as NCV BVY-99-100, Forwards Revised Floor Response Spectra Diagrams,Originally Sent as Attachment 1 to Licensee to Nrc.Revised Diagrams Have More Legible Scale Markings1999-08-0202 August 1999 Forwards Revised Floor Response Spectra Diagrams,Originally Sent as Attachment 1 to Licensee to Nrc.Revised Diagrams Have More Legible Scale Markings ML20210M5791999-07-30030 July 1999 Responds to NRC 990726 Telcon Re Status of Resolution for USI A-46 Outliers.Written Summary,By Equipment Category, Listed ML20211E1701999-07-28028 July 1999 Forwards Copy of Final Exercise Rept for 990427-29,full- Participation Plume Exposure & Ingestion Pathway Exercise of Offsite Radiological Emergency Response Plans site-specific to VYNPS ML20210G4271999-07-27027 July 1999 Forwards Testing Data & Associated Results for Fitness for Duty Program at Plant for 990101-0630 ML20210G5041999-07-27027 July 1999 Responds to NRC 990301 RAI Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design- Basis Accident Conditions. Licensee Will Submit Info Re Proposed Sys Mod by 990916 ML20210J3031999-07-27027 July 1999 Submits Proposed Changes to Eals.Attachment 1 Provides Listing of Changes to EALs Along with Ref to Bases Documents Supporting Change ML20216D7321999-07-26026 July 1999 Forwards Insp Rept 50-271/99-05 on 990510-0620.Two Viiolations Being Treated as Noncited Violations ML20210F3691999-07-21021 July 1999 Submits Response to NRC Request for Clarification of Certain Details of Yaec Proposed Mods to Yankee Nuclear Power Station Defueled TS ML20209G2721999-07-14014 July 1999 Discusses Licensee Response to RAI Re GL 92-01,Rev 1,Suppl Suppl 1, Rv Structural Integrity, for Vermont Yankee Nuclear Power Station ML20209G6931999-07-14014 July 1999 Forwards Request for Addl Info Re Spent Fuel Storage Capacity Expansion ML20209J0601999-07-14014 July 1999 Forwards Rev 11 to Vols 1-10 of State of Nh Radiological Emergency Response Plan & Vols 11-50 to Town Radiological Emergency Response Plans,In Support of Vermont Yankee & Seabrook Station.Vols 17-19 of Were Not Included ML20209G1531999-07-12012 July 1999 Discusses Util Setpoint Control Program Implementation Schedule,As Committed to in Licensee 990514 Response to Notice of Violation,Insp Rept 50-271/97-10 ML20209D4881999-07-0909 July 1999 Forwards Rev 29 to Decommissioning QA Program, for Info & NRC Approval,Iaw 10CFR50.54(a)(3).Attachment a Provides Listing of Changes,But Does Not Discuss All Refomatting, Grammatical,Editorial or Typographical Changes ML20209C3271999-07-0101 July 1999 Forwards Rev 2 to Security Training & Qualification Plan.Rev Withheld 1999-09-30
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20217F1261999-10-12012 October 1999 Forwards Update to Previously Submitted RELAP5 Analytical Assumptions for App R,Re RAI of 961104 BVY-99-130, Provides Clarification of Method for Determining MSIV Maximum & Minimum Pathway at Vermont Yankee Nuclear Power Station1999-10-0808 October 1999 Provides Clarification of Method for Determining MSIV Maximum & Minimum Pathway at Vermont Yankee Nuclear Power Station BVY-99-128, Submits Listed Addl Info in Support of 990414 Request for Clarification to SER Confirming Adequacy of Space Cooling for HPCI & RCIC Sys,Re Item II.K.3.24 of NUREG-0737.Copy of NEDE-24955,encl1999-10-0606 October 1999 Submits Listed Addl Info in Support of 990414 Request for Clarification to SER Confirming Adequacy of Space Cooling for HPCI & RCIC Sys,Re Item II.K.3.24 of NUREG-0737.Copy of NEDE-24955,encl ML20216J3531999-09-29029 September 1999 Responds to NRC Re Violations Noted in Insp Rept 50-271/99-12 on 990628-0811.Corrective Actions:Based on RFO 20 Maint Rule Outage Performance Review,Task Was Generated to Clarify & Enhance SD Monitoring Process BVY-99-122, Notifies of Intention to Reinstate Original Version of App F in FSAR & Correct Docket Re Assumption That Electrical Power Sys Are Designed IAW Requirements of GDC-171999-09-28028 September 1999 Notifies of Intention to Reinstate Original Version of App F in FSAR & Correct Docket Re Assumption That Electrical Power Sys Are Designed IAW Requirements of GDC-17 BVY-99-113, Requests Approval to Perform Alternative Testing to That Specified by ASME Boiler & Pressure Vessel Code,Section XI & Asme/Ansi OM, Operation & Maint of Nuclear Power Plants. Attachment 1 Provides Justification for Alternative Testing1999-09-21021 September 1999 Requests Approval to Perform Alternative Testing to That Specified by ASME Boiler & Pressure Vessel Code,Section XI & Asme/Ansi OM, Operation & Maint of Nuclear Power Plants. Attachment 1 Provides Justification for Alternative Testing BVY-99-116, Informs of Determination That Wh Schulze,License SOP-10528-1,will No Longer Maintain License at Facility. Termination of License Requested1999-09-21021 September 1999 Informs of Determination That Wh Schulze,License SOP-10528-1,will No Longer Maintain License at Facility. Termination of License Requested BVY-99-114, Provides Notification That Licensee Completed Y2K Remediation Efforts Described in Util 990608 Response to NRC GL 98-01,Suppl 11999-09-21021 September 1999 Provides Notification That Licensee Completed Y2K Remediation Efforts Described in Util 990608 Response to NRC GL 98-01,Suppl 1 BVY-99-121, Requests Extension Until 990929 to Respond to Violations Noted in Insp Rept 50-271/99-12,dtd 990819.Licensee Did Not Receive Rept Until 990830 & Addl Time Is Needed to Prepare & Allow for Adequate Review of Violation Response Submittal1999-09-20020 September 1999 Requests Extension Until 990929 to Respond to Violations Noted in Insp Rept 50-271/99-12,dtd 990819.Licensee Did Not Receive Rept Until 990830 & Addl Time Is Needed to Prepare & Allow for Adequate Review of Violation Response Submittal BVY-99-115, Forwards non-proprietary & Proprietary Responses to 990714 RAI Re Civil & Mechanical Engineering Considerations for Proposed Change to TS to Increase Spent Fuel Storage Capacity from 2,870 to 3,355.Proprietary Encls Withheld1999-09-16016 September 1999 Forwards non-proprietary & Proprietary Responses to 990714 RAI Re Civil & Mechanical Engineering Considerations for Proposed Change to TS to Increase Spent Fuel Storage Capacity from 2,870 to 3,355.Proprietary Encls Withheld BVY-99-118, Responds to RAI Concerning GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions1999-09-16016 September 1999 Responds to RAI Concerning GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions BVY-99-110, Informs of Util Intent to Replace Commitments Made in Licensee & Subsequently Ack in NRC with Containment Insp Criteria Defined in 10CFR50.55a(b)(2)(vi),per Drywell Coating Insp1999-08-31031 August 1999 Informs of Util Intent to Replace Commitments Made in Licensee & Subsequently Ack in NRC with Containment Insp Criteria Defined in 10CFR50.55a(b)(2)(vi),per Drywell Coating Insp BVY-99-111, Informs That Encl TS Bases Page 91 Has Been Revised to Allow Reactivity Anomaly BOC Steady State Core Reactivity to Be Normalized Between off-line Uncorrected Solution & on-line 3D-Monicore Exposure Corrected Solution1999-08-31031 August 1999 Informs That Encl TS Bases Page 91 Has Been Revised to Allow Reactivity Anomaly BOC Steady State Core Reactivity to Be Normalized Between off-line Uncorrected Solution & on-line 3D-Monicore Exposure Corrected Solution ML20211J5001999-08-31031 August 1999 Forwards Proposed Rev 29 to Yankee Decomissioning QA Program, for NRC Info & Approval.Yaec Requests That Rev 29, Dtd May 1999 & Originally Transmitted in Be Withdrawn from Further Consideration by NRC Staff ML20216F1891999-08-26026 August 1999 Forwards Copies of Maine Yankee & Yankee Rowe Refs Listed, Supporting Industry Position That Branch Technical Position Asb 9-2 Methodology over-estimates Spent Fuel Decay Heat BVY-99-107, Submits Response to NRC RAI Re Proposed Change to TS to Increase Spent Fuel Storage Capacity from 2,870 to 3,355 Fuel Assemblies1999-08-26026 August 1999 Submits Response to NRC RAI Re Proposed Change to TS to Increase Spent Fuel Storage Capacity from 2,870 to 3,355 Fuel Assemblies BVY-99-108, Requests That Gv Bogue,Bj Croke,Vs Ferrizzi,Me French, Bk Mcnutt,Jf Meyer & DM Navarro Take BWR Gfes of OL Exam Administered on 991006.DA Daigler & ST Brown Will Have Access to Exams Before Tests Administered1999-08-19019 August 1999 Requests That Gv Bogue,Bj Croke,Vs Ferrizzi,Me French, Bk Mcnutt,Jf Meyer & DM Navarro Take BWR Gfes of OL Exam Administered on 991006.DA Daigler & ST Brown Will Have Access to Exams Before Tests Administered BVY-99-103, Informs That Util Expects to Submit Approx Twenty Licensing Actions in FY00 & FY01,in Response to Administrative Ltr 99-021999-08-18018 August 1999 Informs That Util Expects to Submit Approx Twenty Licensing Actions in FY00 & FY01,in Response to Administrative Ltr 99-02 ML20210S0621999-08-10010 August 1999 Forwards semi-annual fitness-for-duty Program Performance Data for six-month Period of 990101-990630,IAW 10CFR26.71(d) BVY-99-100, Forwards Revised Floor Response Spectra Diagrams,Originally Sent as Attachment 1 to Licensee to Nrc.Revised Diagrams Have More Legible Scale Markings1999-08-0202 August 1999 Forwards Revised Floor Response Spectra Diagrams,Originally Sent as Attachment 1 to Licensee to Nrc.Revised Diagrams Have More Legible Scale Markings ML20210M5791999-07-30030 July 1999 Responds to NRC 990726 Telcon Re Status of Resolution for USI A-46 Outliers.Written Summary,By Equipment Category, Listed ML20211E1701999-07-28028 July 1999 Forwards Copy of Final Exercise Rept for 990427-29,full- Participation Plume Exposure & Ingestion Pathway Exercise of Offsite Radiological Emergency Response Plans site-specific to VYNPS ML20210G4271999-07-27027 July 1999 Forwards Testing Data & Associated Results for Fitness for Duty Program at Plant for 990101-0630 ML20210G5041999-07-27027 July 1999 Responds to NRC 990301 RAI Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design- Basis Accident Conditions. Licensee Will Submit Info Re Proposed Sys Mod by 990916 ML20210J3031999-07-27027 July 1999 Submits Proposed Changes to Eals.Attachment 1 Provides Listing of Changes to EALs Along with Ref to Bases Documents Supporting Change ML20210F3691999-07-21021 July 1999 Submits Response to NRC Request for Clarification of Certain Details of Yaec Proposed Mods to Yankee Nuclear Power Station Defueled TS ML20209J0601999-07-14014 July 1999 Forwards Rev 11 to Vols 1-10 of State of Nh Radiological Emergency Response Plan & Vols 11-50 to Town Radiological Emergency Response Plans,In Support of Vermont Yankee & Seabrook Station.Vols 17-19 of Were Not Included ML20209G1531999-07-12012 July 1999 Discusses Util Setpoint Control Program Implementation Schedule,As Committed to in Licensee 990514 Response to Notice of Violation,Insp Rept 50-271/97-10 ML20209D4881999-07-0909 July 1999 Forwards Rev 29 to Decommissioning QA Program, for Info & NRC Approval,Iaw 10CFR50.54(a)(3).Attachment a Provides Listing of Changes,But Does Not Discuss All Refomatting, Grammatical,Editorial or Typographical Changes ML20209C3151999-07-0101 July 1999 Forwards Rev 9 to Security Plan,Reflecting Plant Decommissioning Activities & Continues to Provide Protection Against Radiological Sabotage.Rev Withheld ML20209C3271999-07-0101 July 1999 Forwards Rev 2 to Security Training & Qualification Plan.Rev Withheld ML20196J2321999-06-30030 June 1999 Submits Input from Util Technical Staff Re Soil Disposal on-site Under 10CFR20.2002 & Expresses Interest in Pursuing Approval to Use Same Methodology (Implemented Through Util ODCM & Reported as Noted) If Possible ML20196J7421999-06-29029 June 1999 Informs NRC That Vygs Has Implemented Severe Accident Management,As Committed to in Licensee to NRC ML20209B6111999-06-29029 June 1999 Resubmits Summary of Vynp Commitments Page to Replace Original Page Submitted with Responding to GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants ML20209B5861999-06-28028 June 1999 Provides Alternative Y2K Readiness Status Described in Supplement 1 to GL 98-01, Y2K Readiness of Computer Sys at Npps. Y2K Readiness Disclosure Rept Encl ML20209C3751999-06-28028 June 1999 Forwards non-proprietary Rev 16 to EPIP OP 3524, Emergency Actions to Ensure Initial Accountability & Security Response & Proprietary Rev 12 to EPIP OP 3531, Emergency Call-In Method. Proprietary Encl Withheld ML20209D1611999-06-28028 June 1999 Forwards UFSAR for Ynps.Updated Ynps FSAR Is Being Submitted Biennially,Iaw Commitment in Ltr Dtd 950614.Document Reflects Changes Made to Ynps as of 981231,unless Otherwise Noted BVY-99-084, Forwards Proprietary Application & Medical Certificate for Mod of Listed SRO License,For Gj Leclair.Gj Leclair Will Be Trained & Evaluated in Accordance with Util Lsro Training Description.Proprietary Info Withheld,Per 10CFR2.7901999-06-18018 June 1999 Forwards Proprietary Application & Medical Certificate for Mod of Listed SRO License,For Gj Leclair.Gj Leclair Will Be Trained & Evaluated in Accordance with Util Lsro Training Description.Proprietary Info Withheld,Per 10CFR2.790 ML20195H1741999-06-15015 June 1999 Forwards Original & Copy of Request for Approval of Certain Indirect & Direct Transfer of License & Ownership Interests of Montaup Electric Co (Montaup) with Respect to Nuclear Facilities Described as Listed ML20195D6781999-06-0707 June 1999 Forwards Original & Two Copies of New England Coalition on Nuclear Pollution & Consolidated Intervenor Opposition to Yankee Atomic Electric Co Motion to Terminate,As Required by Rule for Filing ML20207E6301999-06-0101 June 1999 Informs of Relocation of Yaec Corporate Ofcs,Effective 990501.New Address Submitted.All Formal NRC Correspondence to Util Should Be Directed to Duke Engineering & Svcs, Marlborough,Ma ML20207D7991999-05-29029 May 1999 Forwards Original & Two Copies of Ltr to ASLB Chairman in Matter of Yankee Nuclear Power Station Proceeding.With Certificate of Svc ML20207D8181999-05-29029 May 1999 Requests That Board Convey to Panel That within Period of Time Authorized by NRC Regulations Author Intends to File, on Behalf of Intervenors,Responsive Pleading to Yaec Pending Motion to Withdraw in Ref Matter.With Certificate of Svc ML20195D5341999-05-27027 May 1999 Forwards Description of Vermont Yankees Plans for Insp of & Mods to Certain Reactor Vessel Internals ML20195C5891999-05-27027 May 1999 Forwards Response to NRC 990301 RAI Re GL 96-05 Program at Vermont Yankee Nuclear Power Station BVY-99-074, Forwards Application & Medical Certificate Required for Renewal of Jd Livingston,License OP-10049,RO License.Medical Certificate Withheld1999-05-26026 May 1999 Forwards Application & Medical Certificate Required for Renewal of Jd Livingston,License OP-10049,RO License.Medical Certificate Withheld ML20195B3491999-05-25025 May 1999 Submits Withdrawal of Proposed License Amend to Approve Plant Termination Plan.New Application Will Be Submitted in Future ML20195B4081999-05-24024 May 1999 Withdraws Licensee Commitment,Contained in ,To Reinitiate ITS Project Following Completion of FSAR Accuracy Verification Project.Util Will Continue to Modify Current TS with Number of Improvements BVY-99-067, Informs That Bw Metcalf,License SOP-1761-9,has Retired from VYNPS & Will No Longer Require License.Nrc Is Requested to Terminate License1999-05-21021 May 1999 Informs That Bw Metcalf,License SOP-1761-9,has Retired from VYNPS & Will No Longer Require License.Nrc Is Requested to Terminate License ML20196L1801999-05-18018 May 1999 Withdraws Licensee & Attachment,Containing Rev 2 to Vermont Yankee Operational QA Manual, from Further Consideration by Nrc.Summary of Commitments Encl 1999-09-29
[Table view] |
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YANKEE ATOMICELECTRIC COMPANY "'C"*lo".g*g)l,'[*g'"
. l 580 Main Street, Bolton, Massachusetts 01740-1398
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. June 23,1997 BYR-97-027 BVY-97-73 4
- United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Reference (s): (a) License No. DPR-3 (Docket 50-29) Yankee Rowe (b) License No. DPR-28 (Docket 50-271) Vermont Yankee
Subject:
Yankee Atomic Electric Company Operational Quality Assurance Program (YOQAP-I-A), Rev. 28 Enclosed for your information is Revision 28 of YOQAP-I-A. This revision addresses clarifications and updates to our Quality Assurance Program for Yankee (Reference (a)) and Vennont Yankee (Reference (b)).
An evaluation has been performed on these changes to determine if any requirements in the previously NRC-approved QA Program were deleted or made less efTective, and thereby constitute a reduction of commitments. This evaluation also evaluated the revised program against the criteria contained within 10CFR50, Appendix B.
The clarifications and organizational changes do not constitute a reduction in commitments and continue to satisfy the criteria of 10CFR, Part 50, Appendix B. (See Attachment A for a description of all changes.)
The exception toVermont Yankee's alternative to Regulatory Guide 1.26 is not considered a reduction in safety and is intended to improve the overall documentation of the program.
9707010064 970623 I ED.R ADOCK 05000029 L W PM I
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l United States Nuclear Regulatory Commission Document Control Desk June 23,1997 Page 2 If you have any questions in regard to this revision, please contact Mr. Walter K. Peterson of this office.
Sincerelr g C. Ikussell Clark
!fn i
! Executive Director, Quality Assurance l I
CRC /ja I
Enclosure .
c: USNRC Region I USNRC Chief of Performance Program Section !
USNRC Project Manager, YNPS )
USNRC Resident Inspector, VYNPS .
USNRC Project Manager, VYNPS j J. M. Oddo W. K. Peterson R. J. Wanczyk, Vermont Yankee
' J. J. Duffy
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ATTACHMENT A Y00AP-I-A\ Summary of Changes - Revision 28 Item No. Y00AP i-A ' Change Description Reason for Section Change 1 -
All pages Update Added Vermont Yankee Nuclear Power Corporation to title. All applicable pages changed VY VP, Operations to VY Sr. VP, Operations.
2 -
Page 1 Update Added approvals by Vermont Yankee Director of Safety and Regulatory Affairs, and YAEC President.
Deleted approvals by YAEC Vice Presidents.
3 -
Page VII Update Revision 28 added to address organizational changes.
4 Policy Page 1 Clarification Statement Ultimate responsibility for quality l changed from "each individual" to j "the line organization." '
5 Policy Page 1 Update Statement " Director of Quality Assurance" title changed to " Executive Director of Quality Assurance."
6 Policy Page 2 Update Statement Signature line deleted.
7 I Page 1 of 43 Update Changed "VY VP, Operations" to "VY Director of Safety and Regulatory Affairs."
8 I Page 2 of 43 Update Change reflects the title change in 5 above.
9 I Page 2 of 43 Update Deleted the President's responsibility to appoint NSAR Committee members and the Chairman for Yankee. Also addded review and approval on all 0A Program changes.
10 I Page 5 of 43 Update Changed "VY VP, Operations" to "VY Director of Safety and Regulatory Affairs."
I, (
a Item No. Y00AP-I-A Change Description Reason inr i
Section Chano
= m. _
11 I Page 6 of 43 Update
{ Deleted "and Manager of Operations"
- from Decommissioning Manager's title.
1 12 I Page 6 of 43 Update {
- Deleted the Decommissioning
- Manager's responsibility for
" independent review and/or approval for all changes."
l 13 I Page 6 of 43 Update i~ j Deleted the Decommissioning Manager's responsibility for " review )
j and approval of vendor-provided training programs for site staff: ;
4 the procedures and purchase 1
- requests."
I 14 1- Page 6 of 43 Update i
Deleted the Decommissioning
- Manager's responsibility to evaluate i "the site's position of specified
- in-plant audit discrepancies" and to 1 prepare Implementation Directives.
4 15 I Page 7 of 43 Update
. Added the performance of l surveillances at the Corporate
! Engineering office.
16 I Page 9 of 43 Update Changed " Director M ' ngi nee ri ng Services ' to "Eng'.neering Services Manager."
17 I Page 9 of 43 Update Engineering Services Manager reports to a Vice President.
18 I Page 13 of 43 Update Deleted "and Manager of Operations,"
to reflect title change in 11 above.
19 I Page 14 of 43 Update Deleted section for Cost Control and Planning Manger.
20 I Page 14 of 43 Update Added " Manager of Operations" to the Site Manager's title.
Item No. Y00AP-I-A Change Description Reason for Section Change 21 I Page 14 of 43 Update The Site Manager / Manager of Operations now reports to the Decommissioning Manager.
l 22 I Page 15 of 43 Update l The Site Manager's responsibility to act as Chairman of the Plant Operations Review Committee has been deleted.
23 I Page 15 of 43 Update The Site Manager is no longer "directly" responsible for the safe, orderly, and efficient operation of the site. . ."
24 I Page 15 of 43 Update The Site Manager is no longer responsible for the Security Program and Fire Protection Program.
25 I Page 15 of 43 Update The Site Manger is no longer l responsible for Site maintenance and repair.
26 I Page 15 of 43 Update The Site Manager no longer provides information and reports to the Nuclear Safety Audit and Review Committee.
27 I Page 15 of 43 Update The Site Manager now evaluates the site's position on specified in-plant audit discrepancies and prepares " Implementation Directives"
- for the Site.
28 I Page 15 of 43 Update Changed the title " Operations Manager" to " Plant Superintendent."
l 29 I Page 15 of 43 Update l
Plant Superintendent reports to the Site Manager / Manager of Operations.
30 I Page 15 of 43 Update The Plant Superintendent is "Directiv responsible for the safe, orderly, and efficient operation of the Site. . ."
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9 Item No. Y00AP-I-A Change Description Reason for Section Chenge 31 I Page 16 of 43 Update l The Plant Superintendent is !
responsible for security, maintenance, operations, technical services, including the security and fire protection programs.
i 32 1 Page 16 of 43 Update !
The Plant Superintendent acts as Chairman of the Plant Operations Review Committee. I
]
d 33 I Page 16 of 43 Update l l The Plant Superintendent is I responsible for site maintenance and repair.
34 I Page 17 of 43 Update The Plant Superintendent directs 1.tivities of Mechanical and Electrical Maintenance.
Instrumentation and Control and Maintenance Engineering.
35 I Page 16 of 13 Update Shift Supervisors report to the Operations Supervisor who reports to the Plant Superintendent.
36 I Page 18 of 43 Update I
" Maintenance and Construction Manager" title changed to
" Construction Manager." l 37 I Page 18 of 43 Update Deleted the Construction Manager's responsibility to direct the activities of Mechanical and Electrical Maintenance, Instrumentation and Control, and l Maintenance Engineering.
l 38 I Page 18 of 43 Update Deleted the Construction Manager's responsibility to direct plant l maintenance repairs and to assure I compliance of maintenance activities to applicable State, Federal, and license requirements.
39 I Page 18 of 43 Update Change reflects the title change in 20 above.
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Item No. Y00AP-I-A Change Description Reason for Section Change 40 I Page 19 of 43 Update Deleted the Training Manager's responsibility to maintain lines of communication with the Site Manager on Plant Training Programs.
41 I Page 19 of 43 Update Change reflects the title change in 20 above.
42 1 Page 20 of 43 Update
" Plant Radiation Protection and Chemistry Manager" title changed to
" Radiation Protection and Chemistry Manager."
43 I Page 20 of 43 Update Added that Radiation Protection and Chemistry Manager has direct access to the Plant Superintendent for matters relating to radiological health and safety of employees and the public.
I 44 I Page 21 of 43 Update
" Health and Safety Supervisor" title ;
changed to " Health and Safety Manager." l 45 I Page 21 of 43 Update .
Change reflects the title change in 1 20 above. l 46 1 Page 22 of 43 Update Senior Vice President, Operations, dispositions In-Plant Audits and issues concurrence directive to the plant.
47 I Page 22 of 43 Update l Added position of Director of Safety and Regulatory Affairs 48 I Page 23 of 43 Update
! Added position of Director of l Procurement 49 I Page 23 of 43 Update Director of Engineering has overall responsibility for the design and plant engineering.
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Item No. Y00AP-I-A Change Description Reason for Section Change 50 I Page 25 of 43 Update Added position of System Engineering Manager.
51 I Page 27 of 43 Update
" Operations Superintendent" title i
changed to " Maintenance Superintendent."
52 I Page 27 of 43 Update Deleted the words " operation" and l
" Operations" from Maintenance Superintendent's responsibilities.
53 I Page 27 of 43 Update Changed " operation of the facility" l to " maintenance of the facility."
)
1 54 I Page 27 of 43 Update Changed "for operating a nuclear power plant" to "for maintenance of a nuclear power plant." .
l 55 I Page 29 of 43 Update l Moved Operations Manager from page i 31 (of Rev. 27).
56 I Page 29 of 43 Update Operations Manager reports to the Plant Manager. !
57 I Page 29 of 43 Update Deleted Operations Manager's responsibility to fulfill duties and responsibilities similar to and/or as described in the FSAR.
58 I Page 29 of 43 Update Deleted Operations Manager's responsibility to be directly in charge of the Operations Department.
59 I Page 31 of 43 Update Deleted Performance Engineering Manager 60 I Page 31 of 43 Update For Nuclear Services Manger, changed
" Oversees and manages programs associated with nuclear services. .
. " to " Design authority for programs l associated with nuclear services. .
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Item No. Y00AP-I-A Change Description Reason for l Section Change l 61 I Page 32 of 43 V,odate For Design Engineering Managers, l changed " Oversee and manage the electrical /I&C/ mechanical / fluid l systems. . ." to " Design authority I for the electrical /I&C/ mechanical / fluid systems. . ."
62 I Page 33 of 43 Update Changed " Instrument & Control Manager" title to " Electrical and Controls Manager."
63 I Page 33 of 43 Update For Electrical and Controls Manager, deleted responsibility to fulfill duties and responsibilities similar to and/or as described in the FSAR.
64 I Page 33 of 43 Update For Electrical and Controls Manager, delete responsibility to be directly in charge of the Instrument and Control Department.
65 I Page 33 of 43 Update Changed " instrumentation" to
" electrical."
66 I Page 33 of 43 Update Added " equipment" after " electrical and controls."
67 I Page 34 of 43 Update Changed
" elect rical ."
68 I Page 34 of 43 Update Changed " Maintenance Manager" title to " Mechanical Facilities Maintenance Manager."
69 I Page 34 of 43 Update The Mechanical Facilities Maintenance Manager reports to the l Maintenance Superirtendent.
70 I Page 34 of 43 Update Deleted Mechanical Facilities Maintenance Manager's responsibility to fulfill duties and responsibilities similar to and/or l as described in the FSAR.
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Item No. Y00AP-I-A Change Description Reason for Section Change J
l 71 I Page 34 of 43 Update Deleted ' Mechanical Facilities Maintenance Manager's responsibility to be directly in charge of the Maintenance Department.
72 I Page 34 of 43 Update Deleted references to electrical activities.
73 I Page 34 of 43 Update Deleted the phrase "with the exception of Instrumentation and control maintenance activities."
74 I Page 34 of 43 Update Changed department name from
" Maintenance Department" to
" Mechanical Facilities Maintenance Department."
75 I Page 35 of 43 Update Deleted " preventive maintenance, material procurement" from department commitments.
76 I Page 35 of 43 Update Change reflects department name change in 74 above.
77 I Page 35 of 43 Update Deleted Mechanical Facilities Maintenance Manager's responsibility to establish and maintain equipment history records.
78 I Page 35 of 43 Update Deleted Mechanical Facilities Maintenance Manager's responsibility to procure materials and spare parts.
79 I Page 35 of 43 Update Added position of Work Control Manager.
80 I Page 36 of 43 Update Deleted Chemistry Manager's responsibility to fulfill duties and responsibilities similar to and/or as described in the FSAR.
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l l Item No. YOOAP-I-A Change Description Reason for Section Change 81 I Page 37 of 43 Update Deleted Chemistry Manager's responsibility to be directly in l charge of the Chemistry Department.
82 I Page 37 of 43 Update Deleted Radiation Protection Manager's responsibility to fulfill l
duties and responsibilities similar to and/or as described in the FSAR.
83 I Page 37 of 43 Update l Deleted Radiation Protection Manager's responsibility to be directly in charge of the Radiation i Protection Department.
84 I Page 38 of 43 Update Deleted Reictor Engineering Manager's r esponsibility to fulfill l duties and responsibilities similar to and/or as described in the FSAR.
I 84 I Page 38 of 43 Update Deleted Reactor Engineering Manager's responsibility to be directly in charge of the Reactor l Engineering Department. '
85 I Page 40 of 43 l'~ date Under " Plant Operations Review Committee," changed " Technical Specifications to the Operating i License DPR-3" to "Defueled Technical Specification to the Possession Only License DPR-3." l 86 I Page 41 of 43 Update For the Yankee Plant, changed reference to read, "See Section 6.5.2 NSARC, of the Yankee Defueled Technical Specifications to the Possession Only License No. DPR-3."
87 I Figure 1 Update Page 42 of 43 l Organizational chart revised to l l delete the positions of Director of l
Engineering Services and Assistant '
Site Manager.,
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Reason for Change Description Change Item No. Y00AP-I-A 4 Section Update
,=aw .=
I Fi gu r.: 1 88 Page 42 of 43 Organizational chart revised to i f
delete Manager of Operations from the Decommissioning Manager's title and to add it to the Site Manager's ti tl e .
Up$ ate I Figure 1 89 Page 42 of 43 Organizational enart revised to change the repo; ting lines for the NSAR Committee and PORC.
Update I Figure 1 90 Page 42 of 43 O rganizational cnart revised to c hange the following titles: i O perations Manager's title to Plant S uperintendent. Health & Safety Supervisor to Mealth & Safety Manager, and Maintenance &
Construction Manager to Construction Manager.
Clarification 1
Figure 1 91 Page 42 of 43 Organizational chart revised to add the functional areas reporting to the Plant Superintendent.
Update I Figure 2 92 Page 43 of 43 Organizational chart revised to add the positions of Director of Safety
& Regulatory Affairs. the Director h of Procurement, and the Work Control Manager. 4 Update I Figure 2 93 Page 43 of 43 Organizational chart revised to delete the following: YAEC President, YAEC Vice Presidents, YAEC Engineering Department Managers, and QA Surveillance Group.
Update I Figure 2 [
94 Page 43 of 43 Organizational chart revised to change the reporting lines for the Executive Director of Quality Assurance and the Operations Manager.
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Item No. Y00A?-I-A Change Description Reason for Section Change 95 Appendix B Page 17 of 27 Clarification Added ANS 52.1, 1983, and Regulatory Guide 1.26, Section 2.d. as alternates to the present exception to Regulatory Guide 1.26, Rev. 3 for Vermont Yankee.
96 Appendix B Page 20 of 27 Update Changed "The Vermont Yankee ;
Operating Plant" to "The Yankee and I the Vermont Yankee Plants."
97 Appendix B Page 21 of 27 Update I Changed " Vermont Yankee" to " Yankee j and Vermont Yankee." l 98 Appendix B Page 26 of 27 Update Deleted "(Vermont Yankee Plant only)."
99 Appendix B Page 26 of 27 Update Changed "The Vermont Yankee Operating PlLnt" to "The Yankee and the Vermont Yankee Plants."
100 Appendix B Page 27 of 27 Update Changed " Vermont Yankee" to " Yankee and Vermont Yankee."
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