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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217B3331999-10-0707 October 1999 Responds to 990825 Telephone Call Re Presense of Polychlorinated Biphenyl Wastes at Plant,Unit 1 ML20212F4481999-09-17017 September 1999 Forwards NRC Form 536 Containing Currently Proposed Site Specific Operator Licensing Exam Schedule & Estimates of Number of Applicants for Generic Fundamentals Exams Through Cy 2003 ML20212F7051999-09-14014 September 1999 Forwards Rev 19 to Ipn,Units 1 & 2 Physical Security Plan. Plan Withheld,Per 10CFR2.790(d) & 73.21 ML20211N0681999-09-0202 September 1999 Informs That Commission Requested Publication of Notice of Consideration of Issuance of Amend to Fol,Proposed NSHC Determination & Opportunity for Hearing. Amend Changes Senior Reactor License Requirement for Operations Manager ML20211H6291999-08-26026 August 1999 Forwards NPDES Discharge Monitoring Rept for July 1999 for Indian Point,Units 1,2 & 3. Rept of Noncompliance Is Attached for Noncompliance Which Occurred at Unit 3 ML20211E1531999-08-18018 August 1999 Forwards Semi Annual fitness-for-duty Program Performance Data for 990101-990630,IAW 10CFR26.71(d) ML20211H6051999-08-18018 August 1999 Forwards Rev 8 to Security Force Training & Qualification Plan, for Indian Point 3 Nuclear Power Plant.Rev Facilitates Transition of Duty Weapons Carried by Security Force Members from Revolvers to Semiautomatic Pistols ML20211A9241999-08-11011 August 1999 Informs That IPS Currently Estimates,That Approx Two Licensing Actions Will Be Submitted to NRC During Remainder of 1999 NRC Fiscal Yr & Approx Ten Will Be Submitted During 2000 NRC Fiscal Yr ML20210M7251999-07-26026 July 1999 Forwards Projection of Ability to Pay Retrospective Premium Adjustment for Period of Aug 1999 to 000731, Which Demonstrates That Ceny Will Have Sufficient Cash Flow &/Or Cash Reserve Available Throughout Period to Pay Premium ML20210G8911999-07-20020 July 1999 Forwards Application for Amend to License DPR-5 for Proposed New TS 3.2.1.i,revising Senior Reactor License Requirement for Operations Manager ML20209B6611999-06-29029 June 1999 Returns Recently Submitted Renewal Applications,Nrc Form 398,for Three Reactor Operators,As They Are Not Completed Properly.List of Docket Numbers & Block Numbers That Contain Incorrect Info & Block Numbers Not Completed.Without Encls ML20196A6371999-06-15015 June 1999 Forwards Rev 19 to Physical Security Plan.Rev Withheld,Per 10CFR2.790(d) & 73.21 ML20207D1861999-05-27027 May 1999 Informs That Effective 990328,NRC Office of NRR Underwent Reorganization.Mt Masnik Section Chief for Indian Point Station,Unit 1.JL Minns Remains Primary Contact for All Routine Licensing & Administrative Matters.Chart Encl ML20205R1981999-04-15015 April 1999 Requests That Dept of Environ Conservation Modify SPDES Permit for IPS IAW Proposed Rev Attached & Described as Listed ML20205R2961999-04-15015 April 1999 Forwards Copy of Proposed Change to Indian Point SPDES Permit NY0004472.Proposed Change Requests Permission to Add Permitted Outfall to Plant as Well as Change Character of Existing Outfall.Without Encl ML20196K8111999-03-31031 March 1999 Forwards Decommissioning Funding Status Rept for Indian Point,Units 1 & 2 Through 981231 ML20205F9711999-03-25025 March 1999 Informs That Under Separate Cover,Licensee Transmitted to Ofc of Nuclear Regulatory Research Annual Rept of Results of Individual Monitoring at Indian Point,Units 1 & 2,for CY98 ML20204F7931999-03-17017 March 1999 Forwards Table Outlining Nuclear Property Insurance Which Has Been Placed on Behalf of Consolidated Edison Co of Ny, Inc.Insurance Covers Indian Point,Units 1 & 2 ML20204J9971999-03-0909 March 1999 Forwards Insp Rept 50-003/98-19 on 981130-990222.No Violations Noted ML20203B9001999-02-0808 February 1999 First Partial Response to FOIA Request for Documents. Forwards Documents Listed in App a Already Available in PDR, Documents in App B Released in Entirety & Documents in App C Being Withheld in Part (Ref Exemption 6) ML20202J6171999-02-0505 February 1999 Forwards Transcript from 990120 Public Meeting Held in Peekskill,Ny Re Decommissioning ML20199H3731999-01-11011 January 1999 Informs That T Schmeiser,Con Ed Plant Manager for Plant Is Retiring,Effective 990111.AA Blind Will Assume Duties & Responsibilities of Plant Manager Until Replacement Named ML20198E9561998-12-21021 December 1998 Forwards Order Prohibiting Involvement in NRC Licensed Activities Re Deliberate Misconduct in Violation of Regulation When False Info Was Provided to Two NRC Licensees ML20198C2371998-12-15015 December 1998 Ltr Contract:Task Order 237, Review & Evaluation of Indian Point 3 Nuclear Power Plant Application for Conversion to Improved TS, Under Contract NRC-03-95-026 ML20198C4911998-12-11011 December 1998 Forwards Rev 18 to Physical Security Plan,Reflecting Organizational Changes & Incorporating Administrative Corrections & Clarifications.Encl Withheld ML20198C3251998-12-11011 December 1998 Responds to ,Responding to NRC Ltr Re Concerns Raised About Potential Chilling Effect from Temp Denial of Site Access to Employee Raising Safety Issues to Util Senior Mgt ML20155H2901998-11-0303 November 1998 Responds to to Lj Callan Expressing Concern About Continued Operation of Indian Point Nuclear Generating Station.Explanation Why NRC Do Not Think Revoking OLs for Indian Point Units 2 & 3 Justified,Provided ML20155F9181998-10-28028 October 1998 Forwards Changes to SPDES Permit,Removing Requirement to Monitor Svc Boiler Blowdown for Phosphates,Eliminate Redundant Sampling of Oil or Grease Entering Flow Tributary to Floor Drains,Per Ts,App B,Section 3.2 ML20155D2791998-10-23023 October 1998 Forwards Corrected Pages for Indian Point Annual Radiological Environ Operating Rept for 1997 ML20154Q1761998-10-21021 October 1998 Second Final Response to FOIA Request for Documents. Documents Listed in App C Being Withheld in Part (Ref FOIA Exemption 7) ML20154L8031998-10-16016 October 1998 Ack Receipt of & Payment in Amount of $55,000 in Electronic Funds for Civil Penalty Proposed by NRC in .Corrective Actions Will Be Examined During Future Insp ML20155H3021998-09-24024 September 1998 Urges NRC to Revoke Operating Licenses for Indian Point Nuclear Generating Station,Units 2 & 3 & Not Renew OL for Unit 1 ML20154A1391998-09-22022 September 1998 Informs That Effective 980724,AA Blind Assumed Position of Vice President,Nuclear Power & Ja Baumstark Assumed Position of Vice President,Nuclear Power Engineering,Effective 980813 ML20153F0661998-09-18018 September 1998 Provides Response to Violations Noted in Insp Rept 50-286/98-05 & Proposed Imposition of Civil Penalty Dtd 980819.Corrective Actions:Existing Drawings for Spare Switchgear Cubicles Have Been Revised ML20151W4871998-09-10010 September 1998 Informs That as Part of NRC Probabilistic Risk Assessment Implementation Plan,Commission Assigned Two Senior Reactor Analysts (Sras) to Each Regional Ofc.T Shedlosky & J Trapp Has Been Assigned as SRAs for Region I ML20151W9511998-09-10010 September 1998 Informs That as Part of NRC PRA Implementation Plan, Commission Has Assigned Two Senior Reactor Analysts (Sras) to Regional Ofc.T Shedlosky & J Trapp Has Been Assigned SRAs Duties for Region I ML20155F4391998-08-26026 August 1998 Forwards Demand for Info,Being Issued to Enable NRC to Fully Understand Recipient Views on Facts & Circumstances Surrounding Allegedly False Info Provided to Two NRC-licensed Activities ML20238F5151998-08-26026 August 1998 First Partial Response to FOIA Request for Documents. Documents Listed in App a Being Released in Entirety. Documents Listed in App B Being Withheld in Part (Ref FOIA Exemption 6) IR 05000286/19980051998-08-19019 August 1998 Discusses Insp Rept 50-286/98-05 on 980528-0612 & Forwards NOV & Proposed Imposition of Civil Penalty in Amount of $55,000.Most Significant Violation Involved Failure, Following Design Mod in Oct 1997 ML20237B1001998-08-0505 August 1998 Responds to NRC Re Violations Noted in Insp Repts 50-247/97-13,50-247/97-15,50-247/98-02 & Investigation Rept 1-97-038,respectively.Corrective Actions:Acted Promptly to Assure Conforming to Testing Requirements ML20236X8511998-07-31031 July 1998 Forwards Rept Re Projection of Ability to Pay Retrospective Premium Adjustment for Period 980801-990731,per 10CFR140.21 ML20236V4211998-07-13013 July 1998 Forwards SER Approving Topical Repts WCAP-14333P & WCAP-14334NP (Proprietary & non-propiretary, PRA of RPS & ESFAS Test Times & Completion Times ML20236Q1431998-07-0808 July 1998 Responds to Administrative Ltr 98-03 Re Operating Reactor Licensing Action Estimates IR 05000247/19970131998-07-0606 July 1998 Discusses Insp Repts 50-247/97-13,50-247/97-15 & 50-247/98-02 & Forwards Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $110,000 ML20238F5231998-06-29029 June 1998 FOIA Request for Documents Re NRC Office of Investigation Rept 1-97-038,meeting Minutes of Summary of Enforcement Conference on 980506 & Meeting Minutes or Summary of 980520 Predecisional Enforcement Conference ML20154Q1831998-06-29029 June 1998 FOIA Request for Documents Re NRC OI Rept 1-97-038,meeting Minutes of Summary of Enforcement Conference on 980506 & Meeting Minutes or Summary of 980520 Predecisional Enforcement Conference ML20236J9871998-06-24024 June 1998 First Final Response to FOIA Request for Documents.Documents Listed in App a Already Available in Pdr.Documents Listed in App B Being Released in Entirety ML20248F2891998-05-26026 May 1998 Ltr Contract:Task Order 8, Indian Point 2,A/E Follow-up Insp, Under Contract NRC-03-98-021 ML20248L9861998-05-21021 May 1998 Forwards Rev 7 to Security Force Training & Qualification Plan.Review to Verify Receipt of Revised Plan & Sign & Return Receipt Ack Form Provided ML20247M6951998-05-20020 May 1998 Forwards RAI Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions, for Plant,Unit 2 1999-09-02
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20212F4481999-09-17017 September 1999 Forwards NRC Form 536 Containing Currently Proposed Site Specific Operator Licensing Exam Schedule & Estimates of Number of Applicants for Generic Fundamentals Exams Through Cy 2003 ML20212F7051999-09-14014 September 1999 Forwards Rev 19 to Ipn,Units 1 & 2 Physical Security Plan. Plan Withheld,Per 10CFR2.790(d) & 73.21 ML20211H6051999-08-18018 August 1999 Forwards Rev 8 to Security Force Training & Qualification Plan, for Indian Point 3 Nuclear Power Plant.Rev Facilitates Transition of Duty Weapons Carried by Security Force Members from Revolvers to Semiautomatic Pistols ML20211E1531999-08-18018 August 1999 Forwards Semi Annual fitness-for-duty Program Performance Data for 990101-990630,IAW 10CFR26.71(d) ML20211A9241999-08-11011 August 1999 Informs That IPS Currently Estimates,That Approx Two Licensing Actions Will Be Submitted to NRC During Remainder of 1999 NRC Fiscal Yr & Approx Ten Will Be Submitted During 2000 NRC Fiscal Yr ML20210M7251999-07-26026 July 1999 Forwards Projection of Ability to Pay Retrospective Premium Adjustment for Period of Aug 1999 to 000731, Which Demonstrates That Ceny Will Have Sufficient Cash Flow &/Or Cash Reserve Available Throughout Period to Pay Premium ML20210G8911999-07-20020 July 1999 Forwards Application for Amend to License DPR-5 for Proposed New TS 3.2.1.i,revising Senior Reactor License Requirement for Operations Manager ML20196A6371999-06-15015 June 1999 Forwards Rev 19 to Physical Security Plan.Rev Withheld,Per 10CFR2.790(d) & 73.21 ML20205R2961999-04-15015 April 1999 Forwards Copy of Proposed Change to Indian Point SPDES Permit NY0004472.Proposed Change Requests Permission to Add Permitted Outfall to Plant as Well as Change Character of Existing Outfall.Without Encl ML20196K8111999-03-31031 March 1999 Forwards Decommissioning Funding Status Rept for Indian Point,Units 1 & 2 Through 981231 ML20205F9711999-03-25025 March 1999 Informs That Under Separate Cover,Licensee Transmitted to Ofc of Nuclear Regulatory Research Annual Rept of Results of Individual Monitoring at Indian Point,Units 1 & 2,for CY98 ML20204F7931999-03-17017 March 1999 Forwards Table Outlining Nuclear Property Insurance Which Has Been Placed on Behalf of Consolidated Edison Co of Ny, Inc.Insurance Covers Indian Point,Units 1 & 2 ML20199H3731999-01-11011 January 1999 Informs That T Schmeiser,Con Ed Plant Manager for Plant Is Retiring,Effective 990111.AA Blind Will Assume Duties & Responsibilities of Plant Manager Until Replacement Named ML20198C4911998-12-11011 December 1998 Forwards Rev 18 to Physical Security Plan,Reflecting Organizational Changes & Incorporating Administrative Corrections & Clarifications.Encl Withheld ML20155F9181998-10-28028 October 1998 Forwards Changes to SPDES Permit,Removing Requirement to Monitor Svc Boiler Blowdown for Phosphates,Eliminate Redundant Sampling of Oil or Grease Entering Flow Tributary to Floor Drains,Per Ts,App B,Section 3.2 ML20155D2791998-10-23023 October 1998 Forwards Corrected Pages for Indian Point Annual Radiological Environ Operating Rept for 1997 ML20155H3021998-09-24024 September 1998 Urges NRC to Revoke Operating Licenses for Indian Point Nuclear Generating Station,Units 2 & 3 & Not Renew OL for Unit 1 ML20154A1391998-09-22022 September 1998 Informs That Effective 980724,AA Blind Assumed Position of Vice President,Nuclear Power & Ja Baumstark Assumed Position of Vice President,Nuclear Power Engineering,Effective 980813 ML20153F0661998-09-18018 September 1998 Provides Response to Violations Noted in Insp Rept 50-286/98-05 & Proposed Imposition of Civil Penalty Dtd 980819.Corrective Actions:Existing Drawings for Spare Switchgear Cubicles Have Been Revised ML20237B1001998-08-0505 August 1998 Responds to NRC Re Violations Noted in Insp Repts 50-247/97-13,50-247/97-15,50-247/98-02 & Investigation Rept 1-97-038,respectively.Corrective Actions:Acted Promptly to Assure Conforming to Testing Requirements ML20236X8511998-07-31031 July 1998 Forwards Rept Re Projection of Ability to Pay Retrospective Premium Adjustment for Period 980801-990731,per 10CFR140.21 ML20236Q1431998-07-0808 July 1998 Responds to Administrative Ltr 98-03 Re Operating Reactor Licensing Action Estimates ML20238F5231998-06-29029 June 1998 FOIA Request for Documents Re NRC Office of Investigation Rept 1-97-038,meeting Minutes of Summary of Enforcement Conference on 980506 & Meeting Minutes or Summary of 980520 Predecisional Enforcement Conference ML20154Q1831998-06-29029 June 1998 FOIA Request for Documents Re NRC OI Rept 1-97-038,meeting Minutes of Summary of Enforcement Conference on 980506 & Meeting Minutes or Summary of 980520 Predecisional Enforcement Conference ML20248L9861998-05-21021 May 1998 Forwards Rev 7 to Security Force Training & Qualification Plan.Review to Verify Receipt of Revised Plan & Sign & Return Receipt Ack Form Provided ML20217F8501998-03-20020 March 1998 Forwards Table Which Outlines Nuclear Property Insurance That Has Been Placed on Behalf of Util,Per 10CFR50.54(w)(3) ML20199L9531998-01-26026 January 1998 Forwards Addl Info on Rev 6 to Security Force Training & Qualification Plan,Per 980113 Telcon Request of G Smith.Encl Withheld ML20199F7541998-01-21021 January 1998 Forwards Rev 17 to Physical Security Plan,Per Requirements of 10CFR50.54(p).Rev 17 Contains Summary of Changes, Detailing Changes Incorporated.Encl Withheld ML20198N1151998-01-20020 January 1998 Submits Status of Response to NRC Request for Addl Info, for Licenses TR-3 & R-93.Request for Commitment to Complete Decommissioning Activities by 2007 Has Been Persued Up Through Nasa Mgt ML20202F8281997-11-26026 November 1997 Reports Mod to Indian Point SPDES Permit as Required in Ts. Copy of New York State Dept of Environ Conservation Ltr That Modifies Permit Is Encl ML20198P7901997-10-31031 October 1997 Forwards Rev 6 to Physical Security Plan,Per 10CFR50.4(b)(4) to Meet Requirements of 10CFR50.54(p).Rev 16 Contains Summary of Changes, Detailing Changes Incorporated. Encl Withheld ML20198P3181997-10-30030 October 1997 Forwards Corrected Pages to Annual Radiological Environ Operating Rept for 1996 ML20211H7771997-10-0202 October 1997 Forwards Responses to RAIs 650.1 Through 650.8 Re Generic Issues & Generic Communications on Valve Testing & Valve Qualification.Westinghouse Status for Subject Issues Will Be Confirm W Pending Rev to Ssar & WCAP-13559 ML20211B4241997-09-19019 September 1997 Requests Withdrawal of Revs 16 & 18 to Physical Security Plan.Rev 16 re-submitted Per Provisions of 10CFR50.54(p)(2) & Deals W/Specific Operational Criteria of New Sys.Plan Withheld ML20211A9411997-09-18018 September 1997 Responds to NRC Re Violations Noted in Insp Rept 50-286/97-80.Corrective Actions:Revised Administrative Procedure AP-3 to Establish Responsibility for Engineering Review & Revised EOP ES-1.3 ML20149J2491997-07-16016 July 1997 Forwards Environ Ts/Nonroutine Event Rept for Units 1 & 2. Appropriate Ny State Agency Notified ML20148S5731997-06-26026 June 1997 Forwards Response to NRC Re Violations Noted in Insp Repts 50-247/96-80;96-07;96-08;97-03 & Imposition of Civil Penalties on 961027-970405.Corrective Actions:Unique Tag Numbers for Louvers Were Generated ML20148J1431997-06-0404 June 1997 Forwards Rev 15A to Ipn Units 1 & 2 Physical Security Plan, Per 10CFR50.54(p)(2).Plan Withheld ML20137M8371997-04-0101 April 1997 Provides Supplemental Response to RAI Re TS Change Request 96-01 on Conversion to Framatome Cogema Fuel.Tech Specs, Encl ML20137A8301997-03-13013 March 1997 Forwards Response to NRC Ltr Re Violations Noted in Insp Rept 50-286/96-80 on 961213.Corrective Actions:Expert Panel Has Agreed to Include Turbine Bldg & Power Conversion Equipment Bldg in Scope of IP3 Maint Rule Program JPN-97-008, Forwards Comments on Draft NUREG-1560, IPE Program: Persprctives on Reactor Safety & Plant Performance1997-03-0404 March 1997 Forwards Comments on Draft NUREG-1560, IPE Program: Persprctives on Reactor Safety & Plant Performance ML1004713451997-02-26026 February 1997 Forwards Proprietary & non-proprietary Versions of W Rept Entitled, Conditional Extension of Rod Misalignment TS for Indian Point 3. Authorization Ltr & Affidavit,Encl. Proprietary Encl Withheld Per 10CFR2.790 ML20135C7121997-02-21021 February 1997 Forwards Table That Outlines Nuclear Property Insurance on Behalf of Util Covering Units 1 & 2 ML1004713471997-02-18018 February 1997 Authorizes Utilization of Encl Affidavit by Util Re WCAP-14669,Rev 1, Conditional Extension of Rod Misalignment TS for Indian Point 3. Rept Should Be Withheld Per 10CFR2.790(b)(4) ML20134N6481996-12-24024 December 1996 Provides Further Details Re Corporate Reorganization of Consolidated Edison Co of Ny for Indian Point Units 1 & 2 ML20132C8071996-12-12012 December 1996 Forwards Check for $100 for Payment of NRC Invoice 7I0053 for Indemnity Fee on License DPR-5 for One Year Period 961204-971203.W/o Check ML20129D9611996-10-11011 October 1996 Forwards Controlled Copy of Plant Physical Security Plan,Rev 18,re Access Control Upgrade Which Adopts Biometric Hand Geometry.W/O Encl ML20117P6151996-09-11011 September 1996 Forwards Rev 9 to Security Training & Qualification Plan.W/O Encl ML20117E3891996-08-21021 August 1996 Forwards Four Copies of IP3 Security Contingency Plan,Rev 4. W/O Encl JPN-96-035, Informs NRC That Boraflex Not Used as Neutron Absorber in Either Util or Plant Spent Fuel Pool Storage Racks,Per GL 96-041996-08-0606 August 1996 Informs NRC That Boraflex Not Used as Neutron Absorber in Either Util or Plant Spent Fuel Pool Storage Racks,Per GL 96-04 1999-09-17
[Table view] Category:UTILITY TO NRC
MONTHYEARML0934410661990-09-0606 September 1990 Forwards Rev 20 to Vol I Emergency Plan Index,Rev 35 to Vol II, Emergency Response Activation, Rev 60 to Vol III EPIP Index & Rev 12 to IP-1011, Offsite Monitoring/Site Perimeter Surveys. ML1003314851990-08-0707 August 1990 Forwards Proprietary WCAP-12687 & Nonproprietary WCAP-12688, Indian Point Unit 2 Tube Fatigue Reevaluation, Rev 2,per NRC Request.Proprietary Rept Withheld (Ref 10CFR2.790) ML1003314901990-08-0101 August 1990 Forwards Proprietary WCAP-12670 & Nonproprietary WCAP-12671, Indian Point Unit 2 - Final Rept on Steam Generator Insp, Repair & Restoration Efforts During 1990 Midcycle Insp. Proprietary Rept Withheld (Ref 10CFR2.790(b)(4)) ML20058L4741990-07-31031 July 1990 Forwards 900713 Projection for Aug 1990 - Jul 1991 Guaranteeing Payment of Deferred Premiums ML20056A7181990-07-27027 July 1990 Forwards Corrected Page 3.10-9 Inadvertently Omitted from 900621 Application for Amend to License DPR-64 Re Removal of cycle-specific Parameter Limits Per Generic Ltr 88-16 ML20055G9971990-07-17017 July 1990 Forwards Decommissioning Financial Assurance Certification Rept for Facilities,Per 10CFR50.33(K)(2) ML0934410591990-07-16016 July 1990 Forwards Rev 34 to Vol II, Emergency Response Activation, & Revised Epips,Including Rev 11 to IP-1038,Rev 16 to IP-1050,Rev 6 to IP-1054 & Rev 12 to IP-1076 ML1003314461990-06-27027 June 1990 Forwards Proprietary & Nonproprietary WCAP-12625 & WCAP-12626, Status Rept Indian Point Unit 2 Mid-Cycle Steam Generator Insp Presentation to NRC & WCAP-12627 & WCAP-12628, Indian Point Unit 2 Steam Generator Insp.... ML20043H9981990-06-21021 June 1990 Forwards Application for Amend to License DPR-64,proposing Removal of cycle-specific Parameters from Tech Specs,Per Generic Ltr 88-16 ML20043G2971990-06-11011 June 1990 Submits Supplemental Info Re New Temp Sensors Installed in Primary Auxiliary Bldg & Revised Safety Evaluation,To Support 900412 Request for Tech Spec Changes.New Temp Sensors in Piping Penetration Have Setpoints of 140 F ML0934410501990-05-18018 May 1990 Forwards Rev 20 to Emergency Plan,Rev 33 to Emergency Response Activation & Revised Epips,Including IP-1011 ML1003312261990-05-16016 May 1990 Forwards Proprietary WCAP 12573 & Nonproprietary WCAP 12574, Indian Point Unit 2 Steam Generator Insp,Repair & Restoration Program Per NRC 900314 Request.Proprietary Rept Withheld ML20012F4791990-04-0303 April 1990 Informs That Current Revs to Emergency Plan Sent to NRC Document Control Desk ML1003312131990-03-0505 March 1990 Forwards Rev 5 to Fire Protection Program Plan. ML1003311891990-01-19019 January 1990 Forwards Nonproprietary WCAP-11812 & Proprietary WCAP-11811, Indian Point Unit 2 Evaluation for Tube Vibration Induced Fatigue, Per Request for Addl Info Re Implementation of NRC Bulletin 88-002.Proprietary Rept Withheld (Ref 10CFR2.790) ML1003311581989-11-20020 November 1989 Forwards Rev 2 to WCAP-12294 & Proprietary Rev 2 to WCAP-12293, Indian Point Unit 2 Steam Generator Girth Weld/ Feedwater Nozzles Rept,Spring,1989 Outage. Proprietary Rept Withheld (Ref 10CFR2.790) ML1003311711989-11-20020 November 1989 Forwards Public Version of Revised Emergency Procedures Document,Including Rev 4 to IAP-7,Revs 2 to IP-1008 to IP-1014,Rev 6 to IP-1016,Rev 4 to IP-1019,Rev 5 to IP-1029 & Revs 3 to IP-1033 & IP-1039 ML1003311541989-11-14014 November 1989 Forwards Nonproprietary WCAP-12443 & Proprietary WCAP-12442, Info Presented to NRC Re Indian Point Unit 2 Steam Generator Loose Objects, Per 891102 Meeting Concerning 1989 Inservice Insp.Proprietary Rept Withheld (Ref 10CFR2.790) ML1003311731989-11-13013 November 1989 Forwards Public Version of Revised EPIPs Including Rev 9 to IP-1002 & Rev 5 to IP-1007.W/DH Grimsley 891211 Release Memo ML1003311491989-10-24024 October 1989 Forwards Public Version of Books 1 & 2 of Emergency Procedures Document,Including Rev 4 to IP-1029, Emergency Closeout/Class Reduction Written Summary to Authorities. ML20248B2671989-09-25025 September 1989 Forwards Cycle 7 Startup Physics Test Rept,Indian Point Unit 3 ML20248B7601989-07-31031 July 1989 Forwards Licensee Guarantees of Payments of Deferred Premiums for Aug 1989 - Jul 1990 ML20245C9431989-06-20020 June 1989 Forwards Addl Info Re Security Illumination Project in Specific Areas of Plant.Security Lighting Upgrade Project Developed as Result of Security Illumination Project.Encl Withheld ML20246D8421989-04-28028 April 1989 Informs That Annual Fees for Operation of Plant Electronically Transferred on 890411 for Third Installment for FY89,per 10CFR170 ML20244D6091989-04-0707 April 1989 Forwards Payment of NRC Invoice H0771 Covering Review of Part 50 Applications,License Amends,Exemptions,Reliefs & Other Approvals for 871220 to 880618 ML20155F3801988-10-0404 October 1988 Responds to Generic Ltr 87-02 Re Resolution of USI A-46 Re Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors ML20245D9241988-09-30030 September 1988 Responds to NRC Concerns Noted in Insp Rept 50-247/88-20. Corrective Actions:Surveillance Procedure QA-713 Revised & QA Organization Will Independently Develop Listing & Perform Recommended Audit Prior to Oct 1989 ML20155A4841988-09-30030 September 1988 Forwards Correction to 880408 Rev 3 to Safeguards Contingency Plan.Encl Withheld (Reg 10CFR73.21 & 2.790) ML20154M5511988-09-15015 September 1988 Forwards Monthly Operating Rept for Aug 1988 for Indian Point Unit 2 & Revised Page to Monthly Operating Rept for Jul 1988 ML20207J2511988-08-19019 August 1988 Forwards Rev to Physical Security Plan for Plant.Rev Withheld (Ref 10CFR2.790(d) & 73.21) ST-HL-AE-2750, Discusses Summary of NRC Technical Audit of Us Tool & Die, Inc on 880720 & 21 Re Design of High Density Spent Fuel Rack.Audit Conducted to Support Util 880308 Amend Request Concerning Expanded Fuel Storage Capacity.Agenda Encl1988-08-0909 August 1988 Discusses Summary of NRC Technical Audit of Us Tool & Die, Inc on 880720 & 21 Re Design of High Density Spent Fuel Rack.Audit Conducted to Support Util 880308 Amend Request Concerning Expanded Fuel Storage Capacity.Agenda Encl ML20207C9411988-08-0101 August 1988 Forwards 880718 Projection for Period 880801-890731, Demonstrating That Util Will Have Sufficient Cash Flow &/Or Cash Reserves Available Throughout Period to Pay Restrospective Premium ML20195H5961988-06-15015 June 1988 Forwards Application for Amend to Licenses DPR-5 & DPR-21, Changing Tech Specs Re Organizational Charts ML20153F9031988-04-28028 April 1988 Forwards Changes,Tests & Experiments for 1986 ML20151P0901988-04-15015 April 1988 Forwards Application for Amend to Licenses DPR-5 & DPR-26, Incorporating Administrative Changes to Organization Charts. Fee Paid ML20151E4981988-04-0808 April 1988 Forwards Rev 3 to Safeguards Contingency Plan Indicating Organizational & Title Changes.Rev Withheld (Ref 10CFR2.790(d)(i)) ML20151C3361988-03-30030 March 1988 Forwards Revised Page to 871214 Proposed Amend to Security Plan.Page Withheld (Ref 10CFR2.790(d) & 73.21) ML20149H9581988-02-17017 February 1988 Forwards Response to Generic Ltr 88-02, Isap Ii. Seminar Suggested ML20238D1561987-12-23023 December 1987 Forwards Response to Facility Steam Generator Girth Weld Questions.Local Grindouts Permissible within Flat Portion of Uniform Zone & Meets ASME Code Requirements ML20237B6271987-12-14014 December 1987 Forwards Revised Pages to Rev 11 to Physical Security Plan to Incorporate Request Changes.Encl Withheld (Ref 10CFR73.21 & 10CFR2.790(d)(1)) ML20148K7681987-12-11011 December 1987 Forwards Exercise Objectives for Facility full-scale Emergency Preparedness Exercise Scheduled for Wk of 880320, Per Wj Lazarus .Util Intends to Fully Test Site Response to Simulated Emergency Condition ML20238C1201987-12-11011 December 1987 Forwards Public Version of Revised Emergency Procedures, Including Rev 6 to IP-1002, Emergency Notification & Communication & Rev 3 to IP-1007, Determination of Magnitude of Release & Exposure.... W/871224 Release Memo ML20236X4911987-11-18018 November 1987 Forwards Public Version of Revised Emergency Procedures Documents,Including Rev 1 to IP-1001, Mobilization of Onsite Emergency Organization. W/871208 Release Memo ML20196J0601987-11-0404 November 1987 Forwards Errata Sheet to 870928 Submittal Re NUREG-1150, Corrected Pages & Draft Version of Executive Summary ML20236C8401987-10-20020 October 1987 Responds to NRC Re Violations Noted in Insp Rept 50-247/87-20.Licensee Believes Repair of Svc Water Sys Not in Violation of ASME Section IX & Requests That Notice of Violation Be Rescinded ML20236G6701987-10-15015 October 1987 Forwards Public Version of Revised Pages to Book 2 of Emergency Procedures Document,Including App a, Emergency Roster & App B, Con Ed Medical Dept,Consultants & Agencies. W/871029 Release Memo ML20235P9141987-09-22022 September 1987 Forwards Public Version of Page Changes to Books 1 & 2 of Emergency Procedures document.W/871005 Release Memo ML20234B4401987-09-14014 September 1987 Forwards Best Estimate of Operator Licensing Schedules for FY88,FY89 & FY90,in Response to Generic Ltr 87-14.Dates for FY91 Exams Not Scheduled Yet ML20236G4691987-07-27027 July 1987 Forwards Addl Info Re 851219 Application for Amend to License DPR-5,revising Tech Specs to Delete Section 3.2.6 & Add Sections 4.1.7 & 4.1.8 Concerning Radiation Protection Requirements,Per Request ML20237G1891987-07-27027 July 1987 Forwards Public Version of Revised Pages to Book 2 to Emergency Procedures Document,Including App a, Emergency Roster & App B, Con Ed Medical Dept,Consultants & Agencies. W/870812 Release Memo 1990-09-06
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- .,'"~ indian Point 3 s Nuclear Power Plant P.O. Bor. 215
. Buchanan, NewYork 10511 914 739.8200
- > NewWrkPbwer 4# Authority January 9, 1987 BJR-87-003 Mr. Noel F. Dudley Lead Reactor Engineer U.S. N.R.C. Region 1 631 Park Avenue King of Prussia, PA 19406 Re: Simulator Examinations
Dear Mr. Dudley:
Notice of the results of our November 14, 1986 meeting has been received from Mr. Eselgroth. I appreciate the NRC's resolution of the Power Authority's concern for operating examinations at the Indian Point 2 Simulator.
Although the information regarding the simulator (changes, differences, and scenarios) has been forwarded to the NRC with the February, 1987 examination preparation material, I am forwarding an additional copy for your retention.
044-Bryan J. Ray l
v Training Coordinator BJR:ac cc: R. Tansky w/o attachments S. Bridges w/o attachments C C ,l~J -. , u ,; s y,.
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Attachments I: IP-3 CCR/IP-2 Simulator Differences
- Attachment II: Evaluations'for Which Simulator Can Be Used Effectively For Training IP-3 Operators Attachment III: Evaluations Where Differences Have An Impact-On The Use-of The IP-2 Simulator-For Training and For Evaluation Attachment IV: Analysis Of The Effect Of Simulator Differences On The Use Of The Emergency Operating Procedures Attachment V: Simulator Differences-Corrected 1
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ATTACHMENT I IP-3 CCR/IP-2 Simulator Differences and Corrective Measures This attachment will detail specific differences between the IP-3 CCR and the simulator and will denote those differences that can-be corrected or masked by instructor intervention.
The list is broken into two sections:
- Insignificant Differences ,
- Differences Transparent to the Operator Significant IP-3/ Simulator Differences Can Be Difference Corrected
- 1. Boron InjectionTank is located No on the suction of'the SI pumps as opposed to the discharge side.
- 2. Phase A containment Isolation No
, reset controls in the IP-3
-CCR are independent reset buttons while at the simulator the~ isolation valve switches i are used.
- 3. The Blackout Sensing Logic differs Yes between the simulator and IP-3
- 4. Motor Control Center 36C which is No h associated with 31 Diesel is not installed on the simulator.
- 5. IP-3 CCW system has two separable Yes headers while the simulator has one header.
- 6. The Rod Control In-Hold Out Switch No in the simulator operates the re-verse of the one in the IP-3 CCR.
- 7. High S/G level and SI are generator No trips on the simulator, but are turbine trips at IP-3.
-._,,,,,n &J - - a v ,,,,o 2 ATTACHMENT I IP-3 CCR/IP-2 Simulator Differences and Corrective Measures Significant IP-3/ Simulator Differences (continued)
Can Be Difference. Corrected
- 8. The plant computer has been- No removed from the simulator.
- 9. All safegaurds loads powered Yes from 2A also have have supply breakers from 3A.
- 10. Simulator does not have a No microprocessor controlled data logger for main gen-erator RTD's, but utilizes a multi point strip chart.
- 11. Simulator-does not have auto No transfer of instrument bus power for 31 and 32 inst.
busses.
- 12. Simulator has two speed No l
circulators the, IP-3 has variable speed circulators.
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- 13. Electrical power distribution No
! for station auxiliaries is i different.
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ATTACHMENT I IP-3 CCR/IP-2 Simulator Differences and Corrective Measures Insignificant IP-3/ Simulator Differences Can Be Difference Corrected
- 1. Simulator has only one cold No leg injection path per loop.
2.- The Boron Injection Tank is -Yes recirculated with the Boric Acid Transfer Pumps on IP-3 but not on the simulator.
3.- Recirculation ~ Switches operate Yes-equipment in a different sequence on the simulator.
- 4. . The feed pump' master controller No is on the flight panel in the simulator,- in the foxboro racks on IP-3
- 5. Turbine governor valves operate No simultaneously on the simulator, sequentially on-IP-3.
- 6. The CVCS makeup integrators are No electronic digital on the sim-ulator, mechanical digital on IP-3.
- 7. The RHR system valve alignment No different on the simulator.
- 8. The saturation meter on the sim- No ulator is in. degrees F vs psi.
- 9. The service water bypass gate No controls are located in the control room on the simulator, IP-3 controls are in the field.
! 10. RPI scales are in inches in the No i simulator, IP-3 indicator scales are in steps.
F l-ATTACHMENT I IP-3 CCR/IP-2 Simulator Differences and Corrective Measures Insignificant IP-3/ Simulator Differences (continued)
Can~Be Difference Corrected
- 11. Equipment controls and alarm No indicator locations may vary somewhat.
- 12. Plant controls are of modular No construction at IP-3 but not on the simulator.
- 13. Reactivity parameters on the No simulator are cycle 1.
- 14. UNI recorder has split scales on No the simulator but not on IP-3.
- 15. Protection channels are fed Yes from different inst. busses.
- 16. Post TMI incident design changes No are installed on a separate panel changing control room appearance.
(
l 17. An L&N bearing monitor is installed No
, in the simulator vs. a Fluke monitor on IP-3.
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- 18. FCU wier levels are digital on the No simulator and recorded, only analog on IP-3.
- 19. Diesel Gemerator numbering sequence No is different on the simulator.
i 20. Series containment isolation valves No are operated by one switch on the simulator, two switches on IP-3.
- 21. Simulator does not have a MSR vent No chamber modification.
- 22. Generator controls respond the reverse No l
of the IP-3 plant.
1 ATTACHMENT I -
IP-3 CCR/IP-2 Simulator Differences and Corrective Measures Insignificant IP-3/ Simulator Differences (continued)
Can Be Difference Corrected
- 23. Simulator does not have a fire display No and control panel.
- 24. Various trip setpoints are Yes slightly different.
- 25. Source Range loss of detector Yes voltage and high flux at shut down alarms are blocked by P-10 on the simulator.
- 26. Rad monitor recorders are located No within the operating area of-the simulator, IP-3 recorders are behind the flight panel.
- 27. S/G blowdown reset is via pushbutton No on the simulator switches on IP-3.
- 28. Turbo-graf recorder for turbine vib- No ration has been replaced with several mini-recorders on the simulator.
- 29. Low vacuum is indicated by white No j - lights adjacent to the vacuum re-corder on the simulator vs. an annunciator on IP-3.
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ATTACHMENT I IP-3 CCR/IP-2 Simulator Differences and Corrective Measures Differences Transparent to the Operator.
Can Be Difference Corrected
- 1. RTD's for RCS-hot and cold No legs are located in the RCS piping vs. bypass manifolds on IP-3
- 2. Simulator has no S/G tubes No plugged vs. 12% plugged on IP-3.
- 3. Simulator has no secondary Yes plant steam leakage. ,
- 4. Simulator has auto transfer Yes of;DC control power for 480V bus breaker control.
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E-3 8 SOo E-0 ct;p 37 ES-3.1 9 See ES-0.2 step 19 ES-3.2 7 See ES-0.2 step 19 I
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~ PROCEDURE STEP COMMENT.
.ES-3.3 7' Same as ES-3.2 step 7 ECA-0.0 9 Valves deenergized by a loss of ,
power cannot be manipulated by the instructor as a local operator action.
11 Cannot decrease generator H2 pressure on the simulator.
ECA-0.l' Attach. Simulator load distribution is 1 different.
7h. Valves 899A,B do not exist on the simulator..
ECA-1.1 9 Valves 1851A,B do not exist on the simulator.
ECA-1.2 4 Valves 1869A,B do not exist on the simulator.
Manual cold leg injection isolation valves in containment are not simulated.
ECA-2.1 6 Valves 1851A,B do not exist on the simulator.
ECA-3.1 1 Valves 1851A,B do not exist on the simulator.
ECA-3.2 No problem ECA-3.2 No problem
-ECA-3.3 No problem-1
! FR-S.1 1 DC distribution panels not simulated FR-S.2 NO PROBLEMS FR-C.1 1 SI valves different FR-C.2 1 SI valves different t FR-C.3 NO PROBLEMS FR-P.1 3 OPS arming setpoint is 297 F on simulator 6 Valves 1851A,B do not exist on the simulator.
In general, the emergency operating procedures can be effectively utilized by the operators using the IP-2 Simulator with only-minor exceptions. These have been pointed out above and do not reflect major problems with the use of the procedures nor has our experience. indicated any major problems.
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ATTACHMENT II EVOLUTIONS FOR WHICH SIMULATOR CAN BE USED EFFECTIVELY TO TRAIN IP-3 OPERATORS NORMAL OPERATION AND TRANSIENTS
- Rx and plant startup to full power ,
- Load changes throughout the source, intermediate and '
power range l
- Rx and plant shutdown to hot shutdown
- Plant cooldown on RHR to cold shutdown MINOR MALFUNCTIONS AND INSTRUMENT FAILURES
- All NIS operations and malfunctions
- All primary process instrument failures such as:
Tave PZR level and pressure SGWLC
- All Rod Control malfunctions including stuck and dropped rods
- All Reactivity control malfunctions
- All Rx protection malfunctions
- Primary, Secondary and support system pump trips
- Performance of routine surveillance tests
- Component inoperability requiring actions specified in the technical specifications
- Primary, Secondary and support system leaks that may or may not result in a unit trip but do not result in the actuation of the ESF systems
- Loss of an instrument bus i
- Loss of all AC power except that restoration is different (see differences) i
. . . - - . , - . - _ . _ _ , . - - - . _ _ - _ - - . _ - - - _ . . _ . - _ . , _ _ _ - , _ , _ . _ , . _ . _ . . , . . . , - . _ - _ _ , _ ~ - - _ , _ _ - , _ .
- .1 ATTACHMENT III EVOLUTIONS WHERE DIFFERENCES HAVE Mi IMPACT ON THE USE OF THE IP-2 SIMULATOR FOR TRAINING AND FOR EVALUATION MAJOR MALFUNCTIONS
- Primary, Secondary or support system failures that result in the actuation of SI, will require that operator to be aware of the differences specified in the differences list attachment I
'* Electrical malfunctions including loss of various busses, MCc's etc. are significantly different as noted in the differences list. While the general electrical bus arrangement is similar, the blackout logic, bus loads and diesel tie in are all different. This is what causes
- the most confusion. Certain aspects can be masked by the t instructor but this will continue to be a major difference.
- SI system valve incorrect alignment malfunctions l are difficult. While much of the SI system is the same, i IP-3'has 2 headers (BIT and Non-BIT) IP-2 only has 1.
This results in different valve designations'during'SI valve alignment checks.
- Problems with the BIT are difficult due to the design differences as noted in Attachment I.
- Phase A problems difficult only from the aspect of rosetting Phase 'A'. The isolation of the containment, the valves involved, and the system affects are virtually the i same.
1 p In several of the above, manual operator action is necessary i
to resolve the differences. This may serve as an exercise in re-enforcement of the need-to verify automatic actions. ;
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ATTACHMENT IV ANALYSIS OF THE EFFECT OF SIMULATOR DIFFERENCES ON THE USE OF THE EMERGENCY OPERATING PROCEDURES PROCEDURE STEP COMMENT E-0 9 Fan cooler ~ damper switches 12 Can't be done either unit not simulated 16 -Phase 'A' valve arrangement and logic very different 22 BIT valves can't be done 26 Subcooling check different but uses same indication 37 FCU valve control switches different but hasn't presented a major problem ES-0.1 NO PROBLEMS ES-0.2 19 SI valves different but can be simulated to accomplish the same effect without much problem 31 Same as step 19 ES-0.3 10 SI valve alignment E-1 6 See E-0 step 37 25c SI valve alignment ES-1.1 1 See E-0 step 37 15 BIT valves totally different 17 IVSW valves unit 2 only has 1410 and 1413 not 6200 and 6201. This doesn't present a major problem ES-1.2 NO PROBLEM ES-1.3 See differences list ATT I ES-1.4 See differences list ATT I
' Basically these procedures can be accomplished in their entirity provided the instructor place designators on the recirc swithces indicating the different numbering cchomo. All actions performed by the switches are virtually identical between the two units.
E-2 NO PROBLEM
ATTACMMENT V SIMULATOR DIFFERENCES CORRECTED The following items have been' deleted from the simulator
. differences list you have in your possession.
- 1) Full power on the simulator for the IP-3 load is now 100%, and corresponds to 1000MWe.
- 2) The Main Turbine and MBFP speed digital indicators have been changed to analog as in IP-3
- 3) The Turbine runback for the NIS dropped rod is now functioning on the simulator
- 4) The Tave program used at IP-3 has been incorporated onto the program disk for the simulator.
- 5) IP-3 specific setpoints for Rx Protection and Safeguards actuation have been incorporated i
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