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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217L7971999-10-20020 October 1999 Submits Results of Review of 990521 & 0709 Ltrs Which Provided Core Shroud Insp Results & Tie Rod Stabilizer Assemblies ML20217G1291999-10-15015 October 1999 Forwards Errata to Safety Evaluation for Amend 168 Issued to FOL DPR-63 on 990921.Description of Flow Control Trip Ref Cards to Be Consistent with Application for Amend ML20217K2831999-10-14014 October 1999 Submits Response to NRC Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates, for Fiscal Yrs 2000 & 2001 ML20217H3211999-10-0808 October 1999 Forwards Changed Pages for Issue 5,rev 1 of Nine Mile Point Station Physical Security & Safeguards Contingency Plan,Iaw 10CFR50.54(p).Without Encls ML20212K8601999-10-0606 October 1999 Responds to Concern in 990405 Petition Re Residual Heat Removal Alternate Shutdown Cooling Modes of Operation at Nine Mile Point Nuclear Station,Unit 2 ML20216J9311999-09-30030 September 1999 Forwards Response to NRC 981119 Suppl RAI Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions ML20212J4651999-09-30030 September 1999 Informs of Completion of mid-cyle PPR of Nine Mile Point Nuclear Station on 990916.Determined That Problems in Areas of Human Performance & Work Control Required Continued Mgt Attention.Historical Listing of Plant Issues Encl ML18040A3701999-09-30030 September 1999 Provides Changes to Application for Amend Re Volumes 1-11 of 981016 Submittal & Discard & Insertion Instructions Re Integration of Proposed Changes,In Response to NRC RAIs ML20212K8641999-09-30030 September 1999 Informs That During 990927 Telcon Between J Williams & J Bobka,Arrangements Were Made for Administration of Exams at Plant During Wk of Feb 14,2000.Preliminary RO & SRO License Applications Should Be Submitted 30 Days Prior Exam ML20212J8831999-09-30030 September 1999 Informs That Util 980810 & 990630 Responses to GL 98-01 & Suppl 1, Y2K Readiness of Computer Sys at NPPs Acceptable. NRC Considers Subj GL to Be Closed for Plant ML20212E9801999-09-23023 September 1999 Submits Info in Response to Request for Estimated Initial Operator Licensing Exam Needs,Per Administrative Ltr 99-03 ML20216F7101999-09-17017 September 1999 Forwards Response to NRC 990806 RAI Re USI A-46,verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors.Nrc Is Informed That Actions Required for Resolution of USI A-46 Have Been Completed ML20212B2821999-09-14014 September 1999 Responds to 990712 Correspondence Which Responded to NRC Ltr Re High Failure Rate for Generic Fundamentals Exam of 990407 for Nine Mile Point.Considers Corrective Actions Taken to Be Acceptable ML20212D8981999-09-14014 September 1999 Forwards ISI Summary Rept for Refueling Outage 15 & Flaw Indication Repts.Supporting Info Repts & Calculations, Encl ML20212B2581999-09-10010 September 1999 Requests That Name of Bm Bordenick Be Removed from Nine Mile Point,Units 1 & 2 Service List ML20211P5771999-09-10010 September 1999 Forwards Application for Amends to Licenses DPR-63 & NPF-69, to Transfer Licenses to Amergen Energy Co,Llc.Ts Pages & Proprietary Addendum,Included.Proprietary Encl Withheld ML20212A1341999-09-0707 September 1999 Forwards Summary Rept Secondary Containment Leakage Testing, Dtd June 1999 for Nine Mile Point,Unit 1,IAW TS 6.9.3.f ML20211K8141999-09-0101 September 1999 Forwards Reactor Containment Bldg Ilrt,Iaw Plant TS 6.9.3.e.Testing Confirmed That TS 3.3.3/4.3.3 & 6.16 Primary Containment Leakage Requirements Were Satisfactorily Met ML20211L9221999-09-0101 September 1999 Confirms That Licensee Will Retain Weld 32-WD-050 as IGSCC Category F Until Completion of Reinspection Program,In Response to NRC ML20211J6461999-08-30030 August 1999 Forwards Response to NRC 990625 RAI Re NMPC Responses to GL 92-01,rev 1,supplement 1, Reactor Vessel Structural Integrity ML20211K3001999-08-30030 August 1999 Forwards Semi-Annual Radioactive Effluent Release Rept for 990101-990630 & Revised ODCM, for Nine Mile Point,Unit 1. Format Used for Effluent Data Is Outlined in App B of Regulatory Guide 1.21,rev 1 ML20211K5031999-08-30030 August 1999 Responds to Ltr Addressed to Chairman Dicus, Expressing Concerns Involving 990624 Automatic Reactor Shutdown.Insp Findings & Conclusions Will Be Documented in Insp Repts 50-220/99-06 & 50-410/99-06 by mid-Sept 1999 ML20211H1921999-08-26026 August 1999 Forwards Application for Amend to License DPR-63,supporting Implementation of Noble Metal Chemical Addition by Raising Reactor Water Conductivity Limits in TSs 3.2.3.a,3.2.3.c.1 & 3.2.3.b ML20211P5161999-08-26026 August 1999 Discusses Submitted on Behalf of Niagara Mohawk Power Corp Written Comments Addressing 10CFR2.206 Petition & Request That Ltr & Attached Response Be Withheld from Public Disclosure.Request Denied ML20211G4921999-08-26026 August 1999 Advises That Info Re Comments Addressing 10CFR2.206,dtd 990405 Will Be Withheld from Public Disclosure,In Response to ML20211D7731999-08-20020 August 1999 Forwards Semiannual FFD Program Performance Data Rept Covering Period 990101 Through 990630 ML20211B9371999-08-18018 August 1999 Provides Addl Info Re Application of Method a at Nmp,Unit 1 as Described in Generic Implementation Procedure,Rev 2 (GIP-2),NRC Supplemental SER 2 & Documents Ref in GIP-2 Upon Which GIP-2 Is Based ML18040A3691999-08-16016 August 1999 Forwards Response to NRC 990510 RAI Pertaining to NMP Application for Amend Re Conversion of NMPNS Unit 2 Current TS to Its.Nrc Requested Info Re Several Sections,Including Section 3.6, Containment Sys. ML20210Q0031999-08-11011 August 1999 Informs That Due to Printing Malfunction,Some Copies of Author Ltr Dtd 990726,may Not Have Included Second Page of Encl 2 of Ltr ML20210R6661999-08-10010 August 1999 Confirms Conversation on 990721 Re Concerns of Syracuse Anti-Nuclear Effort on Status of 2.206 Petition (Filed 990524) & Upcoming NRC Performance Review Meeting on Nine Mile Point Units 1 & 2 ML20210R8101999-08-10010 August 1999 Forwards 1998 Annual Repts for NMP & co-tenants,including Rg&E,Energy East Corp/Nyse&G,Chg&E & Long Island Power Authority,Per 10CFR50.71(b) ML20210L5321999-08-0606 August 1999 Forwards List of Subjects Discussed During 990714 Telcon with Representatives of Niagara Mohawk Power Corp on Unit 1 Re USI A-46 Issue ML18041A0711999-07-30030 July 1999 Forwards Rev 1 to NMP2-ISI-006, Second Ten Year Interval ISI Program Plan for Nine Mile Point Nuclear Power Station Unit 2. Significant Changes from Rev 0 Listed ML20210J9351999-07-29029 July 1999 Informs That NMP Is Changing Completion Date for Replacement of Valves Having O Rings with Installed Life Greater than Eight Years.Replacement to Be Completed by 991031, During Hydrogen Monitoring Sys Maintenance Outage ML20216E1491999-07-26026 July 1999 Forwards Two Ltrs Received from NMPC Re Nine Mile Point Unit 1 Core Shroud Related to 10CFR2.206 ML20210E9151999-07-23023 July 1999 Discusses Evaluation of Recirculation Line Weld 32-WD-050 Indication Found During 1997 Refueling Outage (RFO14) at NMPNS Unit 1.Requests Notification of Decision to Retain Category F Classification Until Listed Conditions Satisfied ML20209G7911999-07-12012 July 1999 Provides Info Requested in NRC Re 990407 Generic Fundamentals Exam Failure Causes & Corrective Actions ML20209G3711999-07-12012 July 1999 Provides Final Root Cause Evaluation Re GL 94-03, Intergranular Stress Corrosion Cracking of Core Shrouds in Bwrs, for Unit 1 ML20209G2001999-07-0909 July 1999 Forwards RFO-15 Core Shroud Insp Summary Rept, as Required by GL 94-03, Intergranular Stress Corrosion Cracking of Core Shrouds in BWRs & BWRVIP Rept BWR Core Shroud Insp & Flaw Evaluation Guideline (BWRVIP-01) ML20209F8561999-07-0606 July 1999 Forwards Rev 1 to Nmp,Unit 1 COLR for Cycle 14. Rept Is Being Submitted to Commission in Compliance with TS 6.9.1.f.4 ML20211K5071999-07-0606 July 1999 Submits Concerns Re 990624 Event Involving Automatic Reactor Shutdown.More than 5 Failures Were Identified in Event Number 35857 ML20196J6421999-06-30030 June 1999 Discusses Completion of Licensing Action for GL 96-01, Testing of Safety-Related Logic Circuits, Issued on 960110 ML20209B7071999-06-30030 June 1999 Responds to NRC Request for Info Re Y2K Readiness at Nuclear Facilities,As Contained in GL 98-01,Supp 1, Y2K Readiness of Computer Sys at Nuclear Power Plants. Y2K Readiness Disclosure,Encl ML20211P5271999-06-29029 June 1999 Submits Written Comments Addressing Petition Dtd 990405, Submitted by R Norway as It Relates to Expressed Concerns That Involve NMPC Activities.None of Relief Requested in Petition Warranted ML20196K6461999-06-29029 June 1999 Discusses Ofc of Investigations Rept 1-98-33 Re Unqualified Senior Reactor Operator Assuming Position of Assistant Station Shift Supervisor at Unit 1 on 980616.One Violation Being Cited as Described in Encl NOV ML20209B3501999-06-25025 June 1999 Submits Torus Shell & Coupon Corrosion Rate Determination for Nmpns,Unit 1.Torus Meets ASME Code Requirements,Iaw NRC 920825 & 940811 SERs ML20212J4431999-06-25025 June 1999 Discusses Responses to RAI Re GL 92-01,rev 1,suppl 1, Reactor Vessel Structural Integrity ML20209B3531999-06-25025 June 1999 Informs NRC That All Actions Associated with NRC Bulletin 96-003, Potential Plugging of ECC Suction Strainers by Debris in Bwrs, Has Been Completed.Summary of Actions Completed & Other Pertinent Info Is Provided in Attachment ML20196F5721999-06-23023 June 1999 Forwards Rev 3 to NMP1-IST-003, Third Ten Year Inservice Testing Program Plan, Which Will Begin on 991226.Program Plan Conforms to Requirements of 1989 Edition of ASME Boiler & Pressure Vessel Code.Three Relief Requests,Encl ML20196G1461999-06-23023 June 1999 Informs That Actions Requested in GL 96-01, Testing of Safety-Related Logic Circuits Completed 1999-09-07
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20217K2831999-10-14014 October 1999 Submits Response to NRC Administrative Ltr 99-02, Operating Reactor Licensing Action Estimates, for Fiscal Yrs 2000 & 2001 ML20217H3211999-10-0808 October 1999 Forwards Changed Pages for Issue 5,rev 1 of Nine Mile Point Station Physical Security & Safeguards Contingency Plan,Iaw 10CFR50.54(p).Without Encls ML18040A3701999-09-30030 September 1999 Provides Changes to Application for Amend Re Volumes 1-11 of 981016 Submittal & Discard & Insertion Instructions Re Integration of Proposed Changes,In Response to NRC RAIs ML20216J9311999-09-30030 September 1999 Forwards Response to NRC 981119 Suppl RAI Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions ML20212E9801999-09-23023 September 1999 Submits Info in Response to Request for Estimated Initial Operator Licensing Exam Needs,Per Administrative Ltr 99-03 ML20216F7101999-09-17017 September 1999 Forwards Response to NRC 990806 RAI Re USI A-46,verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors.Nrc Is Informed That Actions Required for Resolution of USI A-46 Have Been Completed ML20212D8981999-09-14014 September 1999 Forwards ISI Summary Rept for Refueling Outage 15 & Flaw Indication Repts.Supporting Info Repts & Calculations, Encl ML20212B2581999-09-10010 September 1999 Requests That Name of Bm Bordenick Be Removed from Nine Mile Point,Units 1 & 2 Service List ML20211P5771999-09-10010 September 1999 Forwards Application for Amends to Licenses DPR-63 & NPF-69, to Transfer Licenses to Amergen Energy Co,Llc.Ts Pages & Proprietary Addendum,Included.Proprietary Encl Withheld ML20212A1341999-09-0707 September 1999 Forwards Summary Rept Secondary Containment Leakage Testing, Dtd June 1999 for Nine Mile Point,Unit 1,IAW TS 6.9.3.f ML20211K8141999-09-0101 September 1999 Forwards Reactor Containment Bldg Ilrt,Iaw Plant TS 6.9.3.e.Testing Confirmed That TS 3.3.3/4.3.3 & 6.16 Primary Containment Leakage Requirements Were Satisfactorily Met ML20211L9221999-09-0101 September 1999 Confirms That Licensee Will Retain Weld 32-WD-050 as IGSCC Category F Until Completion of Reinspection Program,In Response to NRC ML20211K3001999-08-30030 August 1999 Forwards Semi-Annual Radioactive Effluent Release Rept for 990101-990630 & Revised ODCM, for Nine Mile Point,Unit 1. Format Used for Effluent Data Is Outlined in App B of Regulatory Guide 1.21,rev 1 ML20211J6461999-08-30030 August 1999 Forwards Response to NRC 990625 RAI Re NMPC Responses to GL 92-01,rev 1,supplement 1, Reactor Vessel Structural Integrity ML20211H1921999-08-26026 August 1999 Forwards Application for Amend to License DPR-63,supporting Implementation of Noble Metal Chemical Addition by Raising Reactor Water Conductivity Limits in TSs 3.2.3.a,3.2.3.c.1 & 3.2.3.b ML20211D7731999-08-20020 August 1999 Forwards Semiannual FFD Program Performance Data Rept Covering Period 990101 Through 990630 ML20211B9371999-08-18018 August 1999 Provides Addl Info Re Application of Method a at Nmp,Unit 1 as Described in Generic Implementation Procedure,Rev 2 (GIP-2),NRC Supplemental SER 2 & Documents Ref in GIP-2 Upon Which GIP-2 Is Based ML18040A3691999-08-16016 August 1999 Forwards Response to NRC 990510 RAI Pertaining to NMP Application for Amend Re Conversion of NMPNS Unit 2 Current TS to Its.Nrc Requested Info Re Several Sections,Including Section 3.6, Containment Sys. ML20210R6661999-08-10010 August 1999 Confirms Conversation on 990721 Re Concerns of Syracuse Anti-Nuclear Effort on Status of 2.206 Petition (Filed 990524) & Upcoming NRC Performance Review Meeting on Nine Mile Point Units 1 & 2 ML20210R8101999-08-10010 August 1999 Forwards 1998 Annual Repts for NMP & co-tenants,including Rg&E,Energy East Corp/Nyse&G,Chg&E & Long Island Power Authority,Per 10CFR50.71(b) ML18041A0711999-07-30030 July 1999 Forwards Rev 1 to NMP2-ISI-006, Second Ten Year Interval ISI Program Plan for Nine Mile Point Nuclear Power Station Unit 2. Significant Changes from Rev 0 Listed ML20210J9351999-07-29029 July 1999 Informs That NMP Is Changing Completion Date for Replacement of Valves Having O Rings with Installed Life Greater than Eight Years.Replacement to Be Completed by 991031, During Hydrogen Monitoring Sys Maintenance Outage ML20209G3711999-07-12012 July 1999 Provides Final Root Cause Evaluation Re GL 94-03, Intergranular Stress Corrosion Cracking of Core Shrouds in Bwrs, for Unit 1 ML20209G7911999-07-12012 July 1999 Provides Info Requested in NRC Re 990407 Generic Fundamentals Exam Failure Causes & Corrective Actions ML20209G2001999-07-0909 July 1999 Forwards RFO-15 Core Shroud Insp Summary Rept, as Required by GL 94-03, Intergranular Stress Corrosion Cracking of Core Shrouds in BWRs & BWRVIP Rept BWR Core Shroud Insp & Flaw Evaluation Guideline (BWRVIP-01) ML20209F8561999-07-0606 July 1999 Forwards Rev 1 to Nmp,Unit 1 COLR for Cycle 14. Rept Is Being Submitted to Commission in Compliance with TS 6.9.1.f.4 ML20211K5071999-07-0606 July 1999 Submits Concerns Re 990624 Event Involving Automatic Reactor Shutdown.More than 5 Failures Were Identified in Event Number 35857 ML20209B7071999-06-30030 June 1999 Responds to NRC Request for Info Re Y2K Readiness at Nuclear Facilities,As Contained in GL 98-01,Supp 1, Y2K Readiness of Computer Sys at Nuclear Power Plants. Y2K Readiness Disclosure,Encl ML20211P5271999-06-29029 June 1999 Submits Written Comments Addressing Petition Dtd 990405, Submitted by R Norway as It Relates to Expressed Concerns That Involve NMPC Activities.None of Relief Requested in Petition Warranted ML20209B3501999-06-25025 June 1999 Submits Torus Shell & Coupon Corrosion Rate Determination for Nmpns,Unit 1.Torus Meets ASME Code Requirements,Iaw NRC 920825 & 940811 SERs ML20209B3531999-06-25025 June 1999 Informs NRC That All Actions Associated with NRC Bulletin 96-003, Potential Plugging of ECC Suction Strainers by Debris in Bwrs, Has Been Completed.Summary of Actions Completed & Other Pertinent Info Is Provided in Attachment ML20196G1461999-06-23023 June 1999 Informs That Actions Requested in GL 96-01, Testing of Safety-Related Logic Circuits Completed ML20196F5721999-06-23023 June 1999 Forwards Rev 3 to NMP1-IST-003, Third Ten Year Inservice Testing Program Plan, Which Will Begin on 991226.Program Plan Conforms to Requirements of 1989 Edition of ASME Boiler & Pressure Vessel Code.Three Relief Requests,Encl ML20209B2951999-06-22022 June 1999 Informs That Training Re Pressure Relief Panels Was Completed for Remainder of Target Population on 990226 ML20196E9231999-06-21021 June 1999 Forwards Response to NRC 990510 RAI Re NMP 981116 Application Proposing Changes to TSs to Provide Reasonable Assurance That Coupled neutronic/thermal-hydraulic Instabilities Were Detected & Suppressed in NMPN-1 Reactor ML18040A3651999-06-0707 June 1999 Forwards for Filing Original Application of Central Hudson & Gas & Electric Corp Seeking Extension of Expiration Date of Order,Dtd 980719,issued by Commission ML18040A3661999-06-0404 June 1999 Informs That Entire Attachment to Ltr NMP2L 1862 Dtd 990421, Should Be Replaced with Entire Attachment Being Sent with Present Ltr ML20195C9751999-06-0101 June 1999 Informs That Weld 32-WD-050 Will Be Reclassified Back to GL 88-01 Category a Weld & ASME Code Section XI Insps Will Be Conducted in Next Three Insp Periods ML20195C9601999-05-28028 May 1999 Provides Final Extent of Condition Evaluation Re Failed Cap Screw Beyond Upper Spring.Nmpc Continues to Conclude as Stated in That No Addl Mods Are Needed Other than Those Indicated in Ltr ML20207F1811999-05-24024 May 1999 Petitions NRC to Suspend Operating License of NMP for NMPNS Unit 1 Until Such Time as NMPC Releases Most Recent Insp Data on Plant Core Shroud & Adequate Public Review of Plant Safety Accomplished Because of Listed Concerns ML20195B1861999-05-21021 May 1999 Requests Staff Approval of Proposed Mod to Each of Four Tie Rods Per 10CFR50.55a(a)(3)(i).Summary of Tie Rod Insp Findings,Summary of Root Cause Evaluation of Failure of Cap Screw,Calculation B-13-01739-23 & Summary of Se,Encl ML20207D1541999-05-21021 May 1999 Forwards Issue 5,rev 0 of Physical Security & Safeguards Contingency Plan for Nmpns.Summary of Changes Included to Facilitate Review.Encls Withheld ML20207D5331999-05-21021 May 1999 Forwards Issue 3,Rev 1 of NMP Nuclear Security Training & Qualification Plan.Summary of Changes Is Included with Plan to Provide Basis for Individual Changes & to Facilitate NRC Review.Plan Withheld Per 10CFR2.790 ML20206S2621999-05-16016 May 1999 Expresses Concerns About Safety of Nmp,Unit 1 Nuclear Reactor.Nrc Should Conduct Insp of Reactor Including Area Besides Core Shroud Welds & Publicly Disclose Results at Least Wk Before Restart Date ML20195D5911999-05-13013 May 1999 Submits Final Copy of Open Ltr to Central Ny,With Proposals Re Nine Mile One Core Shroud Insp During Refueling Outage Which Began on 990411 ML20206P1981999-05-11011 May 1999 Forwards Response to NRC RAI Re NMP Previous Responses to GL 96-05, Periodic Verification of Design-Basis of SR Movs, for NMP Units 1 & 2 ML20206R6941999-05-10010 May 1999 Responds to 990413 & 0430 Ltrs Re Apparent Violation Noted in Investigation Rept 1-98-033.Util Agrees with Violation, But Disagrees with Characterization That Violation Was Willful or Deliberate ML20206N0291999-05-0707 May 1999 Forwards Rev 39 to NMP Site Emergency Plan & Revised Epips,Including Rev 1 to EPMP-EPP-03,rev 5 to EPIP-EPP-25 & Rev 5 to EPIP-EPP-28 ML20206G8121999-04-30030 April 1999 Forwards Comments on Draft Reg Guide DG-1083, Content of UFSAR IAW 10CFR50.71(e), Dtd Mar 1999.Util Generally Supports DG-1083 ML20206F7731999-04-22022 April 1999 Forwards Renewal Application for SPDES Permit Number NY-000-1015 for Nmpns,Units 1 & 2 1999-09-07
[Table view] Category:UTILITY TO NRC
MONTHYEARML17056A9771990-08-30030 August 1990 Forwards Semiannual Radioactive Effluent Release Rept for Jan-June 1990 & Revs 4 & 5 to Odcm. ML18038A3231990-08-30030 August 1990 Forwards Semiannual Radioactive Effluent Release Rept Jan- June 1990 & Revs 6-8 to Odcm. Radioactive Effluent Release Rept Includes Summary of Liquid,Gaseous & Solid Effluents & Justification for Revs to ODCM ML18038A3221990-08-24024 August 1990 Forwards NRC Form 474, Simulation Facility Certification & Supporting Documentation ML18038A3201990-08-21021 August 1990 Discusses Status of Completion of Generic Safety Issue 75, Item 2.2.2 Re Vendor Interface for safety-related Components ML18038A3251990-08-20020 August 1990 Forwards Rev 3 to Nine Mile Point Requalification Program Action Plan, Certifying That All short-term Corrective Actions Completed ML20058Q1151990-08-15015 August 1990 Forwards Response to Regulatory Effectiveness Review on 900604-08.Response Withheld (Ref 10CFR73.21) ML20055G5261990-07-18018 July 1990 Forwards Decommissioning Rept Indicating Reasonable Assurance That Funds Available to Decommission Facility. Financial Assurance of Cotenants Also Encl ML17058A5841990-06-27027 June 1990 Forwards Rev 8 to Updated FSAR for Nine Mile Point Unit 1. Changes Re Findings Noted in Insp Rept 50-220/88-201 Included in Rev.Rev Does Not Reflect Changes Re Reg Guide 1.97,Rev 2 ML18038A3051990-06-26026 June 1990 Responds to Generic Ltr 90-04 Re Status of Implementation of Generic Safety Issue Requirements.Tabulated Info Re Generic Safety Issue Title,Applicability,Status & Remarks Encl ML20042E3741990-04-11011 April 1990 Lists Info Re Unit Containment Vent & Purge Valves,Per NRC 900315 Request ML20012F6131990-03-30030 March 1990 Forwards Changes to Security Training & Qualification Plan. Plan Rewritten & Revised to Incorporate performance-oriented Training Program.Plan Withheld (Ref 10CFR2.790(d)) ML17056A6721990-03-0202 March 1990 Forwards Semiannual Radioactive Effluent Release Rept for Jul-Dec 1989 & Rev 3 to Administrative Procedure AP-3.7.1, Unit 2 Radwaste Process Control Program. ML18038A7071990-02-0505 February 1990 Forwards Rev 5 to NMPC-QATR-1, QA Topical Rept for Nine Mile Point Nuclear Station Operations. ML18038A7061990-01-10010 January 1990 Forwards Rev 21 to Emergency Plan,Revised Emergency Action Procedures,Including Rev 7 to S-EAP-1,Rev 11 to S-EAP-2,Rev 8 to S-EAP-3 & Epips,Including Rev 13 to S-EPP-4 & Rev 13 to S-EPP-20 ML20042D1981989-12-28028 December 1989 Informs of Delay in Response to Generic Ltr 89-10, Safety-Related Motor-Operated Valve Testing & Surveillance, Until BWR Owner Group Generic Program Completed & NRC Appraisal of Program Reviewed by Util ML18038A7021989-11-28028 November 1989 Responds to Generic Ltr 89-21 Re Status of Implementation of USI Requirements.Usi A-5,A-6 & A-7 Inapplicable to Facility ML18038A7711989-11-28028 November 1989 Responds to Generic Ltr 89-21 Re Status of Implementation of USI Requirements.Requirements for NUREG-0612 Re Control of Heavy Loads Near Spent Fuel Completed.Usi A-40 Re Seismic Design Criteria Being Resolved as Part of USI A-46 ML18038A7701989-10-25025 October 1989 Forwards Rev 1 to Updated SAR for Nine Mile Point Unit 2. All Errata Items Identified in Attachment 1 to Previous Updated SAR Transmittal Ltr of 890428 Resolved.Programs to Resolve Setpoint Issues Will Be Established by 891130 ML18038A7611989-09-29029 September 1989 Forwards Addl Info Re Simulator Certification for Facility, Per 890803 Request.Schedule Extension Verbally Granted Until 890930 ML18038A6641989-09-0808 September 1989 Forwards Restart Readiness Rept. Rept Submitted in Fulfillment of Util Third Action Required by Confirmatory Action Ltr CAL-88-17,dtd 880724 ML17056A2701989-08-30030 August 1989 Forwards Nine Mile Point Nuclear Station - Unit 2 Semiannual Radioactive Effluent Release Rept Jan-June 1989 & Rev 1 to Administrative Procedure AP-3.7.1 Process Control Program. ML20245E8451989-08-0707 August 1989 Forwards Rev 6 to Training & Qualification Plan.Rev Withheld (Ref 10CFR73.21 & 10CFR2.790(d)) ML20247M2771989-07-25025 July 1989 Forwards Issue 2,Rev 0 to Physical Security Plan.Specific Changes Set Forth in Attachment A.Supporting Info Set Forth in Attachment B.Master Acronym & Abbreviation List Also Encl.Encls Withheld (Ref 10CFR73.21) ML20246N9041989-07-13013 July 1989 Forwards Vital Area Evaluation for Plant Screenhouse.Encl Withheld (Ref 10CFR73.21(b)) ML18038A6611989-07-11011 July 1989 Provides Response to Generic Ltr 89-06, Task Action Plan Item I.D.2 - Spds. Certification Stating Plant Unit 1 SPDS Sys Meets Requirements of NUREG-0737,Suppl 1 & Plant Unit 2 SPDS Sys Will Be Modified to Meet NUREG-0737,Suppl 1 Encl ML18038A6591989-06-23023 June 1989 Forwards Util Response to 890522 Salp.Util Agrees W/Need to Improve Surveillance Testing Data & Upgrading Design Basis for Core Spray & HPCI Sys ML20244E3631989-06-15015 June 1989 Forwards Revised Application for Amend to License DPR-63, Incorporating Request to Limit Reactor Power Level at Which Blocking Valve in Feedwater May Be Closed ML18038A4731989-05-31031 May 1989 Forwards Emergency Preparedness Exercise/Drill Scenario 12 1989 Annual Exercise, Vols 1 & 2 ML18038A4581989-04-28028 April 1989 Forwards Rev 0 to Updated SAR for Nine Mile Point Unit 2. Emergency Plan,Formerly Included in Fsar,Not Included in Updated Sar.Portions of Util Responses to NRC FSAR Questions Incorporated Into Body of Initial Updated SAR ML20246Q0071989-04-28028 April 1989 Forwards Proprietary Section 6A of Updated FSAR for Nine Mile Point Unit 2.Section 6A Withheld (Ref 10CFR2.790) ML20246B5451989-04-28028 April 1989 Advises That Util Will Submit Rev to Restart Action Plan After Receipt of Repts from NRC Special Team Insp & INPO Reassessment of Facility ML18038A4561989-03-23023 March 1989 Forwards Addl Info Supporting Application to Use Alternative to 10CFR50.55a Requirements.W/Two Oversize Drawings ML18038A4551989-03-21021 March 1989 Provides Util Plans for Future Exam & Evaluation of Four Feedwater Nozzles Per NUREG-0619.Indications Conservatively Evaluated as Cracks Not Scratch Marks.During 1993 Refueling Outage,Sparger from Nozzle a Will Be Removed 05000410/LER-1989-003, Forwards Corrected Copy of LER 89-003-00 Submitted on 890320.Typo Identified on Page 5 of 7 Corrected1989-03-21021 March 1989 Forwards Corrected Copy of LER 89-003-00 Submitted on 890320.Typo Identified on Page 5 of 7 Corrected ML18038A4521989-03-0202 March 1989 Forwards Responses to NRC Questions Re Licensee Restart Action Plan & Nuclear Improvement Program.Replacement Pages for Action Plan Encl ML20245J5521989-03-0202 March 1989 Forwards Rept of Physical Security Event,Reported Via Emergency Notification Sys on 890203 ML18038A4511989-02-22022 February 1989 Forwards Rev 4 to NMPC-QATR-1, QA Program Topical Rept for Nine Mile Point Nuclear Station Operations. Revs Include Corporate Reporting & Responsibility Changes as Well as Descriptions for Organizations Not Previously Identified ML18038A4501989-02-14014 February 1989 Forwards Rev 1 to TR-6801-2, Mark I Torus Shell & Vent Sys Thickness Requirements Nine Mile Point Unit 1 Nuclear Station. Requests Approval to Use Certified Matl Test Repts for Most of Torus Matls ML18038A4341989-01-18018 January 1989 Forwards Revised,Second 10-yr Interval Inservice Testing Program Plan for Plant & Supporting Documentation,Per 881220 Commitment.Interim Approval of Program as Submitted to Spent Fuel Loading Scheduled for Apr 1989 Requested ML18038A4201988-09-29029 September 1988 Advises That No Unresolved Safety Issues Re Flow Fluctuations & Neutron Flux Noise Exist,Per NRC 880527 Ltr Requesting Summary of Plans to Mitigate Oscillations in APRM Signals & Total Core Flow ML20154C4221988-09-0909 September 1988 Informs That Contracted Vendor to Present Courses Will Not Be Able to Commence Training Until Later in Month of Oct or Early Nov 1988.Schedule Revised to Have Instrumentation & Control Initial Training Implemented by Nov 1988 ML20154B4301988-09-0808 September 1988 Forwards Security & Safeguards Contingency Plan.Definition of Security Force Member Discussed.Plan Withheld ML17055E2471988-08-30030 August 1988 Forwards Semiannual Radioactive Effluent Release Rept, Jan-Jun 1988, & Revs 4 & 6 to Offsite Dose Calculation Manual. ML18038A4121988-07-28028 July 1988 Forwards Info Re Implementation of NUREG-0131,Rev 2, Technical Rept on Matl Selection & Process Guidelines for BWR Coolant Pressure Boundary Piping. ML18038A4101988-07-28028 July 1988 Forwards Comments,Clarifications & Agreements Re Implementation Re 880506 SER Concerning 10CFR50,App J.Info Submitted Per Commitment Resulting from 880609 Meeting W/ NRC.W/15 Oversize Drawings ML18038A4111988-07-28028 July 1988 Forwards Licensee Response to Generic Ltr 88-01 Re Austenitic Stainless Steel Piping at Facility.Application for Amend to Incorporate Requirements of Generic Ltr Will Be Submitted Later ML20151A2971988-07-15015 July 1988 Forwards Changes to Physical Security Plan.Supporting Info Also Encl.Encls Withheld (Ref 10CFR73.21) ML20151A2751988-07-15015 July 1988 Forwards Changes to Security Training & Qualification Plan. Changes Withheld (Ref 10CFR2.790) ML18038A4081988-07-0707 July 1988 Submits Listed Changes to Util 880609 Comments on SALP, Including Advisal That Review of Nonradiological Chemistry Program Revised to More Accurately Describe How Review Performed ML18038A4061988-07-0606 July 1988 Responds to Request for Addl Info on ATWS Review Re Alternate Rod Injection & Recirculation Pump Trip Sys.W/ Seven Oversize Drawings 1990-08-30
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REQUL45gRY INFORNATIQN -DISTRIBUT~ SYSTEl'f. (R IDS>
'I ACCESSION NBR: 8606110212 DOC. DATE: 86/06/05 NOTARIZED: YES DOCKET ¹ FACIL: 50-410 Nine Nile Point Nuclear Station~ Unit 2~ Niagara Noha 05000410 AUTH. NAIVE AUTHOR AFFILIATION MANQAN, Q. V. Niagara Nohatok Poeer Corp.
RECIP. MANE RECIPIENT AFFILIATION ADENSANp E". Q. BAR Prospect DirectoY ate 3
SUBJECT:
Forwards Rev 1 to oFFsite dose calculation manual>'per 860502 request. Sections containing equations 5 methodology signiFicantlg expanded to clariFg source oF equations.
Franklin Research Ctr comments also encl.
DISTRIBUTION CEDE: *GCBD CDPIEB RECEIVED: LTR TITLE: OR/Licensing Submittal: Appendix I l ENCL g SIZE:
NOTES:
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0 UM'QHAWK NIAGARA MOHAWK POWER CORPORATION/300 ERIE BOULEVARD WEST, SYRACUSE, N.Y. 13202/TELEPHONE (315) 474-1511 June 5, 1986 (NMP2L 0733)
Ms. Elinor G. Adensam, Director BWR Project Directorate No. 3 U.S. Nuclear Regulatory Commission 7920 Norfolk Avenue Washington, DC 20555
Dear Ms. Adensam:
Re: Nine Mile Point Unit 2 Docket No; 50-410 I
The enclosed Revision 1 to the Nine Mile Point Nuclear Station Unit 2 Offsite Dose Calculation Manual (ODCM) is submitted in response to your request of May 2, 1986. The general requirements of the Request for Additional Information as well as the specific comments provided by Franklin Research Center have been addressed in revision 1 of the Offsite Dose Calculation Manual, as summarized below and in the attachment to this letter.
The seventeen specific references to the Technical Specifications listed in paragraph 2 of the Request for Additional Information have been included as a cross-reference in the Table of Contents. Specific references to the Technical Specifications are also included within each section. The sections containing equations and methodology have been significantly expanded to clarify the source of the equations, and examples are given for many of them.
The referenced tables, Table 2.1 for liquid effluent monitors and Table 3.1 for offgas, have been provided as representative values. Sections 2.1.3, for liquid monitors and 3.1.3, for gaseous monitors, have been provided to discuss periodic calibration to confirm these values.
Section 6 has been added to provide the discussion of several table notations which resulted from the development of the Environmental Monitoring Program specifications.
Figure 5.1.3-1 of the Technical specifications has been provided in addition to the maps showing envrionmental sampling locations.
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Ms. Elinor G. Adensam Page 2 Attachment 1 of this letter is an item-by-item response to the comments provided by Franklin Research Center.
Additional information and further clarification has been provided to produce a complete and comprehensive Offsite Dose Calculation Manual. Your further suggestions for improvements will receive our immediate attention.
Very truly yours, C. V. Mangan Senior Vice President NLR:saa Enclosure 1684G xc: R. A. Gramm, NRC Resident Inspector Project File (2)
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UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION In the Matter of Niagara Mohawk Power Corporation ) Docket No. 50-410 (Nine Mile Point Unit 2) )
AFFIDAVIT C. V. Man an , being duly sworn, states that he is Senior Vice President of Niagara Mohawk Power Corporation; that he is authorized on the part of said Corporation to sign and file with the Nuclear Regulatory Commission the documents attached hereto; and that all such documents are true and correct to the best of his knowledge, information and belief.
Subscribed and sworn to before me, a Notary ublic in and for the State of New York and County of' thi s day of 1986.
Notary Public in and for linen 'ounty, New York My Commission expires:
CHRISTINE AUSTIN Notary Public in the Qate of Neo Yorit uaiihed in Onondaga Co. No. 478768g Ex <<ea March 30, lou
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ATTACHMENT 1 Franklin Research Center ODCM Comments (Unit 2)
Rev. 0 Rev. 0 Rev. 1 Rev. 1
~Sub'ect Pa e Number Comments ~Res onse ~PII b Table of Contents 'he Licensee should provide a A table of contents table of contents for the ODCM. has been provided.
Liquid Radwaste The Licensee should specify the The units (cpm) are Effluent Monitor units for the alarm setpoints. given in Section 2.1.2.1.
Alarm Setpoint (Sec. 2.1.2.1) 'nthe factor the equation for k
the setpoint, is not clearly The factor has been set at 0.8 in Section 2.1.2.1 defined. The Licensee may apply the laboratory experience to introduce an appropriate safety factor for the setpoint calculation: the factor should be a specific number.
1, 2 'he Licensee should provide The nominal flow rates are 7 nominal flow rates for the provided in Section 2.1.3.1.
effluent line (f) and the dilution flow (F). Also, the sources of dilution water should be identified.
Service Water A and B 'ame as above, specify the The units (cpm) are given 5 and Cooling Tower units for alarm setpoint. in Section 2.1.2.3.
Blowdown Radiation Detector Alarm Setpoint (Sec. 2.1.2.2)
0 Rev. 0 Rev. 0 Rev. 1 Rev. 1
~Sub'ect Pa e Number Comments ~Res ense Pa e Number
'ame as above, specify the The factor hs been set at 5 factor k. 0.8 in Section 2.1.2.3.
Service Hater A and 8 Specify the nominal flow rates The nominal flow rates are 10 and Cooling Tower for service water A and 8, and provided in Section 2.1.3.2.
Blowdown Radiation the cooling tower blowdown.
Detector Alarm Setpoint (Sec. 2.1.2.2) 'he Licensee has not considered Provision for setting the simultaneous releases from Radwaste Monitor set point more than one effluent line in concurrent with the setpoint calculation. contamination of a dilution stream are provided in Liquid Effluent Detectors Responses
't is not clear to what types of radiation (gamma, beta, or both)
Section 2.1.2.2.
Liquid Effluent Detector discussion provides this 6
(Table 2-1) the detector responses provided info. in Section 2.1.3.1 in Table 2-1 are related.
'hat is the justification for Response of the detector 6 considering only the isotopes to liquid samples from listed in the tables? Are other appropriate waste streams isotopes ignored? is described in Section 2.1.3.1.
Liquid Concentration 'o demonstrate that the Licensee's Technical Liquid Effluent 12 Concentration will be Specification 3.11.1.1 is met, calculated and compared to the surveillance requirements MPC in accordance with the specify that the sampling and equation of Section 2.2 for analysis program be implemented all effluent streams for all according to Table 4.11-1 of the periods of release. This RETS. According to the NRC Branch summation will therefore Technical Position, the Licensee account for combined should: discharges to the same release point.
Rev. 0 Rev. 0 Rev. 1 Rev. 1
~Sub ect Pa e Number Comments ~Res ouse ~PN b "Provide the equations and methodology to be used at the station or unit for each liquid release point according to the Specification 3.11.1.1. For systems with continuous or batch releases, and for systems designed to monitor and control both continuous and batch releases, provide the assumptions and parameters to be used to compare the output of the monitor with the liquid concentration specified. State the limitations for combined discharges to the same release point.
In addition, provide the Section 2.5 addresses 15 method and assumptions for sample representativeness.
obtaining representative The results of sampling samples from each batch and and analysis in accordance describe the previous with Table 4.11-1 provide post-release analyses or the concentration data composite sample analyses used in Section 2.2.
used to meet the specification."
Liquid Effluent Dose Liquid pathways are not clearly All efflluents are 28, 13 Dose Calculation identified for the dose calculation. discharged via the same Methodology (Sec. 2.2) pathway. See figure 2-9 and Section 2.3 for discussion of the dose pathways to be included in dose calculation.
Rev. 0 Rev. 0 Rev. 1 Rev. 1
~Sub ect Pa e Number Comments ~Res ouse ~PII I
'quations for the dose factor Section 2.4 provides the 14 A;t should be provided in the ODCM. equation from NUREG 0133 Section 4.3.1 which was referenced in Rev. 0.
Table 2-2 The Licensee should explain why Section 2.4 explains why 15 the table provides data only only the isotopes listed for the isotopes listed. were provided and describes the action to be taken if nuclides are encountered in addition to those provided in Table 2-2.
Stack Noble Gas Detector Alarm Setpoint
'nits for the alarm setpoint not The units (uCi/sec) are 30 specified. given in Section 3.1.2.1.
(Sec. 3.1.2.1)
'he factor k used for the The factor has been set at 31 setpoint equation is not defined 0.8 in Section 3.1.2.1.
or specified.
Hhat is the height of the stack The elevated releases 33 and the level of effluent releases discharged from the stack (elevated vs. ground level)? (8 131 meters) are discussed in Section 3.1.3.
Vent Nobel Gas 'ame comments as stated for stack The units (uCi/sec) are 31 Detector Setpoint monitor above. given in Section 3.1.2.2.
(Sec. 3.1.2.2)
The factor has been set 31 at 0.8 in Section 3.1.2.2.
Rev. 0 Rev. 0 Rev. 1 Rev. 1
~sub'ecc Pa e Number Comments ~Res onse ~PN N The vent is considered a 33, 58, ground level or combined 59 elevated/ground level release, as discussed in Sections 3.1.3, 3.4.5 and 3.4.6.
'imultaneous releases not Section 3.1.3 includes a 33 considered in the setpoint discussion of simultaneous calculation. release.
Vent Noble Gas 'he resulting unit for the The equation given in 31 Detector Setpoint setpoint equation is not Section 3.1.2.2 yields (Sec. 3.1.2.2) consistent with what it is uCi/sec, as required.
intended for: the end result will read "(m3/cc) (cpm)"
rather than just "(cpm)".
Offgas Pretreatment 'he Licensee has not been The units of Sections 31, 32 Noble Gas Detector consistent in choosing the 3.1 2.2 and 3.1.2.3 are
~
Setpoint (Sec. 3.1.2.3) units for the flow rates: now given in ml/sec and (m3/sec) was used in CFM, corresponding to the Sec. 3.1.2.2 and (cc/min) was two separate systems. It used in Sec. 3.1.2.3. is not desirable to make these the same.
Nobel Gas Detector 'pecify the types of radiation The off-gas monitor 36 Response (Table 3-1) (gamma or beta) for the detector detector is described in responses. Section 3.1.3.3
'rovide justifications for having Section 3.1.3.3 describes 36 only a few isotopes for the table. OG Monitor calibration and addresses Table revision based on isotopic analysis of offgas samples during operation.
Rev. 0 Rev. 0 Rev. 1 Rev.
~Sub 'ct Pa e Number Comments ~Res ense 1
Pa e Number Dose Rate Calculation 10 'he Licensee has not referenced Section 3.2 identifies the 37 Methodology (Sec. 3.2) the dose limits with which Dose Rate limits which compliance is to be demonstrated apply.
for the dose calculations.
12 'he Licensee uses 1.7E-06 (sec/m3) Changed X/Q to 2.0E-6 in 38, 39, for the highest calculated annual Sections 3.2.1 and 3.2.2 to 31 (X/Q), which is lower than 2.0E-06 be consistent with value (sec/m3) provided by the Licensee used for setting alarm in Section 3.1.2.2 (p. 7). Explain point (Section 3.1.2.2) the discrepancy. which is also based on: dose rate at the Site Boundary.
Plume Shine Parameters 13 'he Licensee has not provided a The methodology of 45 (Table 3-2) methodology to calculate the plume calculation is provided shine factors Bi and Vi. in Section 3.4.1.
'he Licensee did not provide any The values have been 62 data for Table 3-2. (The Licensee provided in Table 3-2.
stated that "The values in this table will be provided at a later time".)
Tables 3-4 to 3-21 15 to 32 Provide equations in the ODCM for The equations for 47-58 the parameters calculated in the calculating the parameters tables. for Tables 3-4 to 3-6 are in Section 3.4.3 and those for Tables 3-7 to 3.21 are in Section 3.4.4.
Uranium Fuel Cycle 35 'he Licensee stated that fish The drinking water pathway 90, 91 consumption and shoreline sediment is not significant.
are the pathways used for liquid Methodology for calculating dose calculation. However, the doses from shoreline drinking water pathway is not sediment is provided in considered. Also, the methodology Section 4.1.
to calculate doses from shoreline sediment is not provided in the ODCM.
~Sub'ect Rev. 0 Pa e Number 35 Rev. 0 Comments No methodology is provided to Rev. 1
~Res ouse The methodology using
~b Rev.
92 1
estimate the direct radiation. environmental TLD's is given in Section 4.3.
36 'he equation given for factor R The differences in the 94 is incorrect: some typographic equation given and the errors may have been committed. equations of Sections C-3 and C-4 of Reg. Guide 1.109 are identified in Section 4.4. (X/Q is in units of sec/m3). The equation is correct.
Environmental Honi toring Program 41-43 'nthe nature Table 5.1 for sampling locations, of the locations (such No on-si te moni tori ng locations are required.98-100 as on-site, control, or indicator) Control locations are is not clearly specified for each those located at map location. Since Nine Mile Point locations 30, 31, 38, 43, Units 1 and 2 and the Fitzpatrick 47, 54, 55; all easily plant are located at the same site, distinguished by distance the envrionmental sample locations, and direction. Unit 1 and by agreement between the respective Unit 2 ODCH's now indicate licensees, are supposed to be identical locations; the identical. However, numerous JAF recent revision differences are found between should be the same.
the sample locations of Nine Mile Point Unit 2 and the locations provided in the FitzPatrick ODCM (Rev. 2 dated June 25, 1985). It appears that Nine Mile Point Unit 2 has a complete list of the most up-to-date information on sample locations. However, the differences may reflect lack of coordination between the respective licensees on environmental sample programs.
Rev. 0 Rev. 0 Rev. 1 Rev. 1
~Sub'ect Pa e Number Comments ~Res ense Pa e Number Monthly Liquid Oose 'he Licensee did not provide a Section 2.6 was provided 16 Projection (RETS 4.11.1.3.1) section to describe the methodology to address TS 3.11.1.3.
for monthly liquid dose Note that it is expected projection per the Licensee's the liquid radwaste system RETS 3.11.1.3. will be fully utilized at all times, thus negating the need to make such a projection, except in unusual circumstances.
Liquid and Gaseous 'he NRC Branch Technical Position Figures 2-1, 2-2 and 2-3 20, 21, 22 Effluent Flow Oiagrams as issued in 1979 specifies needs define the Low Conduc-for the licensees to provide tivity Liquid Waste effluent flow diagrams to clarify System. Figures 2-4, and explain the operability of the 2-5 and 2-6 define the 23, 24, 25 radwaste treatment systems. The High Conductivity Branch Technical Position states: Liquid Waste System.
"Provide a flow diagram(s) defining the treatment paths and the com- Figures 2-7 and 2-& 26, 27 ponents of the radioactive liquid, define the Regenerant gaseous and solid waste manage- Waste System.
ment systems that are to be main-tained and used, pursuant to f Sol i di i cati on of 10CFR50.36a, to meet Technical waste is addressed Specifications 3.11.1.3, 3.11.2.4 in the Process Control and 3.11.3.1. Subcomponents of Program, separately packaged equipment can be identi- submitted (see TS fied by a list. For operating 3.11.3). The figures reactors whose construction permit provided are from the applications were filed prior to FSAR, Chapter 11.
January 2, 1971, the flow diagram(s) shall be consistent with the information provided in confor-mance with Section V.B.1 of Appendix I to 10CFR50. For OL applications whose construction permits were filed after January 2, 1971, the flow diagram(s) shall be consistent with the information provided in Chapter ll of the Final Safety Analysis Report (FSAR) or amendments thereto."
I Rev. 0 Rev. 0 Rev. 1 Rev. 1
~Sob ect Pa e Number Comments ~Res oose Pa e Number Liquid and Gaseous The flow diagrams should also tifiessFigure 2-9 iden-ODCM 28 Effluent Flow Diagram contain information on the the Service (Cont.) effluent monitoring instrumentation Water monitors (RE regarding the setpoint calculation. 146A and RE 146B),
Thus, the information as required by the Cooling Tower the Branch Technical Position Blowdown monitor includes: (RE157), and the Liquid Radwaste "The instrumentation for each alarm Effluent monitor and trip setpoint, including radiation (RE 206).
monitoring and sampling systems and effluent control features, should Figure 3-5 iden- 87 be identified by reference to the tifies the Gaseous FSAR (or Final Hazard Summary). Effluent pathways.
This information should be consis-tent with the recommendations of Figure 3-6 provides 88 Section I of Standard Review Plan a block diagram of 11.5, NUREG-75/087 (Revision 1)." the stack monitor (RE 170). The vent monitor (RE 180) is essentially identical.
Estimation of I-133 The licensee did not provide a Section 3.5 was 59 method to estimate the release of provided to indicate I-133. On estimating the radio- the methods of activity of I-133, the NRC staff estimating I-133 has specific guidance as follows: release.
"Under appropriate conditions, the See Section 3.5 59 l-133 contribution could be impor-tant to the Part 20 dose rates and to the Appendix I doses.
Therefore, Specifications 3/4.11.2.1 and 3/4.11.2.3 should be written as shown in the enclosures.
0 C' Rev. 0 Rev. 0 Rev. 1 Rev. 1
~Sub'ect Pa e Number Comments ~Res ouse Pa e Number Estimation of I-133 These speci fi cati ons wi 1 1 not (Cont.) explicitly require sampling and analysis to determine the I-133 releases. Therefore, Table 4.11-2 need not specify I-133.
Conversely, the Specifications will require accounting for I-133 and the method for so doing must be detailed in the ODCM. Acceptable methods will be addressed in NUREG-0133, Rev. l.
Acceptable approaches to estimating I-133 releases are as follows:
- 1. Convert the samples for I-133 (as well as I-131) and assume a constant release rate so buildup is proportional to
[1 exp(- At)]/A .
- 2. Periodically take short-period samples to determine the ratio of I-131 to I-133 activity. Then, use this ratio to estimate I-133 re-leases based on measurements of I-131 releases.
- 3. In special cases, where a Method 2 or Method 3 59 plant lacks capability for will be used depending measuring I-133, assume that on analytical results the I-133 activity release obtained. Method 1 is is 4 times the I-131 ambiguous; we do not acti vi ty." plan to use it.
t Rev. 0 Rev. 0 Rev. 1
~Seb ect Pa e.Number Comments ~Res onse Estimation of I-133 This requirement is applicable to (Cont.) a BHR such as Nine Mile Point Unit 2, especially since I-133 is not included in the sampling analysis program described in their RETS Table 4.11-2.
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