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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217F8231999-10-13013 October 1999 Informs That on 990930,NRC Completed mid-cycle PPR of Catawba Nuclear Station.Based on Review,Nrc Did Not Identify Any New Areas That Warranted More than Core Insp Program Over Next Five Months.Historical Listing of Issues,Encl ML20217H0041999-10-13013 October 1999 Forwards MOR for Sept 1999 & Revised MOR for Aug 1999 for Catawba Nuclear Station,Units 1 & 2 ML20217F1301999-10-0707 October 1999 Forwards Rev 1 to Request for Relief 99-03 from Requirements of ASME B&PV Code,In Order to Seek Relief from Performing Individual Valve Testing for Certain Valves in DG Starting (Vg) Sys ML20212J3011999-10-0101 October 1999 Forwards Exemption from Certain Requirements of 10CFR54.17(c) Re Schedule for Submitting Application for Operating License Renewal.Se Also Encl ML20217K2651999-10-0101 October 1999 Forwards Retake Exams Repts 50-413/99-302 & 50-414/99-302 on 990921-23.Two of Three ROs & One SRO Who Received Administrative Section of Exam Passed Retake Exam, Representing 75 Percent Pass Rate 05000414/LER-1999-004, Forwards LER 99-004-01,providing Correction to Info Previously Provided in Rev 0 of Rept.Planned Corrective Actions Contain Commitments1999-09-27027 September 1999 Forwards LER 99-004-01,providing Correction to Info Previously Provided in Rev 0 of Rept.Planned Corrective Actions Contain Commitments 05000413/LER-1999-015, Forwards LER 99-015-00 Re Inoperability of Auxiliary Bldg Ventilation Sys That Exceeded TS Limits Due to Improperly Positioned Vortex Damper.Commitments Are Contained in Corrective Actions Section of Encl Rept1999-09-27027 September 1999 Forwards LER 99-015-00 Re Inoperability of Auxiliary Bldg Ventilation Sys That Exceeded TS Limits Due to Improperly Positioned Vortex Damper.Commitments Are Contained in Corrective Actions Section of Encl Rept ML20217A7911999-09-24024 September 1999 Forwards Insp Repts 50-413/99-05 & 50-414/99-05 on 990718- 0828 at Catawba Facility.Nine NCVs Identified Involving Inadequate Corrective Actions Associated with Degraded Svc Water Supply Piping to Auxiliary Feedwater Sys ML20212E6471999-09-24024 September 1999 Discusses GL 98-01 Issued by NRC on 980511 & DPC Responses for Catawba NPP & 990615.Informs That NRC Reviewed Response for Catawba & Concluded That All Requested Info Provided.Considers GL 98-01 to Be Closed for Catawba ML20212F0941999-09-21021 September 1999 Discusses Closeout of GL 97-06, Degradation of Steam Generator Internals for Cns,Units 1 & 2 ML20212M2001999-09-20020 September 1999 Confirms 990913 Telcon Between M Purser & R Carroll Re Management Meeting to Be Conducted on 991026 in Atlanta,Ga to Discuss Operator Licensing Issues 05000414/LER-1999-005, Forwards LER 99-005-00 Re Missed EDG TS Surveillance Concerning Verification of Availability of Offsite Power Sources Resulted from Defective Procedure.Planned Corrective Actions Stated in Rept Represent Regulatory Commitments1999-09-20020 September 1999 Forwards LER 99-005-00 Re Missed EDG TS Surveillance Concerning Verification of Availability of Offsite Power Sources Resulted from Defective Procedure.Planned Corrective Actions Stated in Rept Represent Regulatory Commitments ML20212D5321999-09-15015 September 1999 Informs That Duke Energy Corp Agrees to Restrict Max Fuel Rod Average Burnup to 60,000 Mwd/Mtu,In Order to Support NRC Final Approval & Issuance of Requested Amend ML20212B4641999-09-14014 September 1999 Forwards Monthly Operating Repts for Aug 1999 & Revised Monthly Operating Rept for Catawba Nuclear Station,Units 1 & 2 ML20212A4131999-09-14014 September 1999 Informs That TR DPC-NE-2009P Submitted in 990817 Affidavit, Marked Proprietary,Will Be Withheld from Public Disclosure, Pursuant to 10CFR2.709(b) & Section 103(b) of Atomic Energy Act of 1954,as Amended ML20212M1931999-09-13013 September 1999 Refers to 990909 Meeting Conducted at Region II Office Re Presentation of Licensee self-assessment of Catawba Nuclear Station Performance.List of Attendees & Licensee Presentation Handout Encl ML20212A3751999-09-10010 September 1999 Informs That Postponing Implementation of New Conditions Improved by RG 1.147,rev 12,acceptable Since Evaluation on Relief Based on Implementation Code Case for Duration of Insp Interval ML20212A5191999-09-0808 September 1999 Requests NRC Approval for Relief from Requirements of ASME Boiler & Pressure Vessel Code,Section XI,1989 Edition,App VI,VI-2430(c) & 2440(b).Approval of 99-GO-002 Is Requested by 000301 05000413/LER-1999-014, Forwards LER 99-014-00, Missed Surveillance & Operation Prohibited by TS Occurred as Result of Defective Procedures or Program & Inappropriate TS Requirements. Planned Corrective Action Stated in Rept Represents Commitment1999-09-0101 September 1999 Forwards LER 99-014-00, Missed Surveillance & Operation Prohibited by TS Occurred as Result of Defective Procedures or Program & Inappropriate TS Requirements. Planned Corrective Action Stated in Rept Represents Commitment 05000414/LER-1999-003, Forwards LER 99-003-01, Unplanned Actuation of ESFAS Due to a SG High Level Caused by Inadequate Procedural Guidance. Suppl Rept Provides Info Re Root Cause & Corrective Actions Associated with Event Developed Subsequent to Rev1999-08-31031 August 1999 Forwards LER 99-003-01, Unplanned Actuation of ESFAS Due to a SG High Level Caused by Inadequate Procedural Guidance. Suppl Rept Provides Info Re Root Cause & Corrective Actions Associated with Event Developed Subsequent to Rev 0 of LER ML20211H1741999-08-30030 August 1999 Forwards Comments on Catawba Nuclear Station Units 1 & 2 & McGuire Nuclear Station,Units 1 & 2 Specific Reactor Vessel Info Contained in Rvid.Ltr Dtd 990107,rept ATI-98-012-T005 & Partial marked-up Rept WCAP-14995 Encl ML20211M4451999-08-30030 August 1999 Forwards Summary of Util Conclusions Re Outstanding Compliance Issue Re Staff Interpretation of TS SR 3.0.1,per Insp Repts 50-369/99-03 & 50-370/99-03,as Discussed with NRC During 990618 Meeting 05000413/LER-1999-013, Forwards LER 99-013-00,re RHR Heat Exchanger Bypass Valves Not Verified Per TS Surveillance.Surveillance Procedures Have Been Revised & There Are No Further Planned Corrective Actions or Commitments in LER1999-08-25025 August 1999 Forwards LER 99-013-00,re RHR Heat Exchanger Bypass Valves Not Verified Per TS Surveillance.Surveillance Procedures Have Been Revised & There Are No Further Planned Corrective Actions or Commitments in LER ML20211M8191999-08-25025 August 1999 Confirms 990825 Telcon Between G Gilbert & R Carroll Re Mgt Meeting to Be Held on 990909 in Atlanta,Ga,To Allow Licensee to Present self-assessment of Catawba Nuclear Station Performance ML20211A9641999-08-20020 August 1999 Forwards SE Authorizing Licensee 990118 Request for Approval of Proposed Relief from Volumetric Exam Requirements of ASME B&PV Code,Section XI for Plant,Units 2 ML20211C1191999-08-18018 August 1999 Forwards ISI Rept Unit 1 Catawba 1999 RFO 11, Providing Results of ISI Effort Associated with End of Cycle 11 ML20211B9471999-08-18018 August 1999 Forwards Request for Relief 99-02,associated with Limited Exam Results for Welds Which Were Inspected During Unit 1 End of Cycle 11 RFO ML20211C3651999-08-17017 August 1999 Forwards Rev 25 to Catawba Nuclear Station Units 1 & 2 Pump & Valve Inservice Testing Program, Which Includes Reformatting of Manual & Addl Changes as Noted in Attached Summary of Changes ML20211F2971999-08-17017 August 1999 Forwards non-proprietary & Proprietary Updated Pages for DPC-NE-2009,submitted 980722.Pages Modify Fuel Design & thermal-hydraulic Analysis Sections of DPC-NE-2009. Proprietary Page 2-4 Withheld,Per 10CFR2.790 05000413/LER-1999-011, Forwards LER 99-011-00,re Missed Surveillance on Both Trains of CR Area Ventilation Sys Resulting in TS Violation.Planned Corrective Actions Stated in LER Represent Regulatory Commitment1999-08-16016 August 1999 Forwards LER 99-011-00,re Missed Surveillance on Both Trains of CR Area Ventilation Sys Resulting in TS Violation.Planned Corrective Actions Stated in LER Represent Regulatory Commitment ML20211B1121999-08-16016 August 1999 Forwards Topical Rept DPC-NE-2012, Dynamic Rod Worth Measurement Using Casmo/Simulate, Describing Results of Six Drwm Benchmark Cycles at Catawba & McGuire & Discusses Qualification to Use Drwm at Catawba & McGuire ML20210V0321999-08-13013 August 1999 Forwards Insp Repts 50-413/99-04 & 50-414/99-04 on 990606- 0717.Six Violations of NRC Requirements Identified & Being Treated as non-cited Violations,Consistent with App C of Enforcement Policy ML20210S2751999-08-12012 August 1999 Forwards Monthly Operating Repts for July 1999 for Catawba Nuclear Station,Units 1 & 2.Revised Rept for June 1999,encl ML20210Q3751999-08-0505 August 1999 Informs That NRC Plans to Administer Gfes of Written Operator Licensing Exam on 991006.Authorized Representative of Facility Must Submit Ltr as Listed,Thirty Days Before Exam Date,In Order to Register Individuals for Exam ML20210N9521999-08-0404 August 1999 Forwards Changes to Catawba Nuclear Station Selected Licensee Commitments Manual.Documents Constitutes Chapter 16 of Ufsar.With List of Effective Pages IR 05000413/19980131999-08-0202 August 1999 Discusses Integrated Insp Repts 50-413/98-13,50-414/98-13, 50-413/98-16,50-414/98-16 & NRC Special Repts 50/413/99-11 & 50-414/99-11 Conducted Between Aug 1998 & May 1999.Six Violations Occurred,Based on OI Investigation & Insp ML20210M6411999-07-29029 July 1999 Forwards Request for Relief 99-03 from Requirements of ASME Boiler & Pressure Vessel Code,In Order to Seek Relief from Performing Individual Valve Testing for Certain Valves in DG Starting Air (Vg) Sys 05000413/LER-1999-010, Forwards LER 99-010-01 Which Replaces LER 99-002.Rept Number Has Been Changed in Order to Conform to Numbering Convention Specified in NUREG-1022,since Primary Event Involved Both Units1999-07-22022 July 1999 Forwards LER 99-010-01 Which Replaces LER 99-002.Rept Number Has Been Changed in Order to Conform to Numbering Convention Specified in NUREG-1022,since Primary Event Involved Both Units IR 05000413/19990101999-07-22022 July 1999 Discusses Insp Rept 50-413/99-10 & 50-414/99-10 on 990314- 0424 & Forwards Notice of Violation Re Failure to Comply with TS 3.7.13,when Misalignment of Two Electrical Breakers Rendered SSS Inoperable from 981216-29 ML20217G5241999-07-20020 July 1999 Forwards Exam Repts 50-413/99-301 & 50-414/99-301 on 990524- 27,0603,07-10 & 16.Of Fourteen SRO & RO Applicants Who Received Written Exams & Operating Tests,Eight Applicants Passed & Six Failed Exam 05000413/LER-1999-009, Forwards LER 99-009-00,re Inoperability of Containment Valve Injection Water Sys Valve in Excess of TS Limits.Root Cause & Corrective Actions Associated with Event Are Being Finalized & Will Be Provided in Supplement to Rept1999-07-19019 July 1999 Forwards LER 99-009-00,re Inoperability of Containment Valve Injection Water Sys Valve in Excess of TS Limits.Root Cause & Corrective Actions Associated with Event Are Being Finalized & Will Be Provided in Supplement to Rept 05000414/LER-1999-001, Forwards LER 99-001-01 Re Unanalyzed Condition Associated with Relay Failure in Auxiliary Feedwater Sys,Due to Inadequate Single Failure Analysis.Rev Is Being Submitted to Include Results of Failure Analysis Which Was Performed1999-07-15015 July 1999 Forwards LER 99-001-01 Re Unanalyzed Condition Associated with Relay Failure in Auxiliary Feedwater Sys,Due to Inadequate Single Failure Analysis.Rev Is Being Submitted to Include Results of Failure Analysis Which Was Performed ML20209H4431999-07-14014 July 1999 Forwards Monthly Operating Repts for June 1999 for Catawba Nuclear Station,Units 1 & 2.Revised Rept for May 1999 on Unit Shutdowns Also Encl ML20210A5771999-07-14014 July 1999 Forwards Revsied Catawba Nuclear Station Selected Licensee Commitments Manual, Per 10CFR50.71(e),changing Sections 16.7-5,16.8-5,16.9-1,16.9-3,16.9-5 & 16.11-7.Manual Constitute Chapter 16 of UFSAR ML20216D3941999-07-14014 July 1999 Forwards Revs to Catawba Nuclear Station Selected Licensee Commitments Manual NUREG-1431, Forwards SER Agreeing with Util General Interpretation of TS LCO 3.0.6,but Finds No Technical Basis or Guidance That Snubbers Could Be Treated as Exception to General Interpretation1999-07-0909 July 1999 Forwards SER Agreeing with Util General Interpretation of TS LCO 3.0.6,but Finds No Technical Basis or Guidance That Snubbers Could Be Treated as Exception to General Interpretation ML20196L0371999-07-0808 July 1999 Approves Requested Schedule Change of Current two-year Requalification Examinations to non-outage dates.Two-year Cycle Will Start on 991001 & Will End on 020930 05000413/LER-1999-008, Forwards LER 99-008-00,re Operation Prohibited by TS 3.5.2. Rev to LER Will Be Submitted by 990812 Which Will Include All Required Info About Ventilation Sys Pressure Boundry Breach1999-07-0808 July 1999 Forwards LER 99-008-00,re Operation Prohibited by TS 3.5.2. Rev to LER Will Be Submitted by 990812 Which Will Include All Required Info About Ventilation Sys Pressure Boundry Breach ML20196J9001999-07-0606 July 1999 Informs That 990520 Submittal of Rept DPC-NE-3004-PA,Rev 1, Mass & Energy Release & Containment Response Methodology, Marked Proprietary Will Be Withheld Per 10CFR2.790(b)(5) & Section 103(b) of AEA of 1954 IR 05000413/19990031999-07-0101 July 1999 Discusses Insp Repts 50-413/99-03 & 50-414/99-03 Completed on 990605 & Transmitted by Ltr .Results of Delibrations for Violation Re Discovery of Potentially More Limiting Single Failure Affecting SGTS Analysis Provided 1999-09-08
[Table view] Category:EXTERNAL CORRESPONDENCE
MONTHYEARML20205G8191999-03-30030 March 1999 Provides Comments on Revised Draft Rfa for Duke Power ML20108B1181996-04-23023 April 1996 Forwards Groundwater Monitoring Rept for Catawba Nuclear Station Conventional Wastewater Treatment Ponds from Samples Collected on 960304 ML20100C0651996-01-25025 January 1996 Informs That DPC Would Like to Raise Level of Standby Nuclear SW Pond from 572 Feet to 574 Feet to Provide Addl Cw Due to Operational Concerns ML20095D5321995-12-0101 December 1995 Approves Facility 950920 Request to Use Dimethylamine in Feedwater Sys to Reduce & Prevent Corrosion Fouling ML20094R9311995-11-30030 November 1995 Requests Approval to Begin Using Polyacrylate Dispersant for Siltation Control.Product Will Be Used in Plants Nuclear Svc Water & Low Pressure Svc Water Sys & Discharged at non- Toxic Concentrations to Lake Wylie from Outfall 001 ML20094R6721995-11-29029 November 1995 Forwards Groundwater Monitoring Rept for CNS Conventional Wastewater Treatment Ponds.Samples Collected on 950905,in Accordance W/Sampling & Analysis Plan ML20094F7841995-11-0303 November 1995 Provides Copy of Record Sheet for Tracking Communications Diesel Run Hs at Plant.W/O Encl ML20093E4321995-10-0505 October 1995 Confirms 950918 Telcon Re Response to Sc Dept of Health & Environ Control Air Permit Insp ML20092K2341995-09-20020 September 1995 Revises 941014 Request for Mods of Thermal Limitations for Outfall 001,changing Daily Average Temp Limitation of 95 F to Weekly Average Temp ML20092K2431995-09-20020 September 1995 Requests Approval to Begin Using Dimethylamine Which Will Be Discharged in non-toxic Concentrations.Product Will Be Used in Plant FW Sys in Order to Reduce & Prevent Corrosion Fouling.Chronic Toxicity Study on Pre-Tect 9002 Encl ML20092G8211995-09-12012 September 1995 Provides Toxicity Test Results for Outfall 002 ML20087J6461995-08-14014 August 1995 Requests 6-month Extension to Continue Use of Na Br in Cooling Towers at Facility,Per NRC ML20086M9641995-07-19019 July 1995 Forwards NPDES Supplemental Info Update to NPDES Permit Application,Proposed Rewrite of NPDES Permit & Supplemental Info,Description of Requested Permit Changes & Marked Up of Existing Permit Showing Changes ML20083N5641995-05-17017 May 1995 Imforms That Since mid-March,continuous Flow Observed Coming from Stormwater Outfall 17/18.Util Concluded That Source of Effluent at Stormwater Outfall 17/18,leakage from Conventional Waste Treatment Basins ML20083P9891995-05-16016 May 1995 Forwards Groundwater Monitoring Data for CNS Conventional Wastewater Treatment Ponds.Samples Collected on 950313,in Accordance W/Protocol Outlined in Sampling Analysis Plan ML20083M1901995-05-10010 May 1995 Requests That 950315 Approval Ltr from Sc Dept of Health & Environ Control,Approving Use of Listed Treatment Chemicals, Be Modified & Reissued for Listed Reasons ML20082N4311995-04-19019 April 1995 Describes Discovery & Corrective Actions Concerning Discharge of Cooling Tower Water Through Stormwater Outfall, Reported to Ft Lawn Ofc on 950321 ML20080P7371995-02-28028 February 1995 Submits Follow Up Rept on Authorized Discharge of Cooling Water to Lake Wylie That Occurred on 950222-23 at Plant & Informs of No Observed Environ Impact During Discharge. Underground Pipe Repaired & Cause Being Investigated ML20080K1601995-02-15015 February 1995 Requests Approval to Use Listed Addl Treatment Chemicals. Informs That Request Needed by 950324 in Order to Meet Schedule ML20078J0361995-01-31031 January 1995 Forwards Revised Ltr from York County Stating Willingness to Serve CNS - Cooling Tower Yard,Project Ws 4610001 Along W/ Revised Flow Test Data ML20077K2611995-01-0404 January 1995 Requests That Sodium Bromide Be Approved as Permanent Treatment Compound for Control of Algae in Cooling Towers at Catawba Nuclear Station ML20073E4351994-09-15015 September 1994 Responds to Requesting Approval to Extend Timeframe for Sodium Bromide Trial Test for Use in Cooling Towers ML20072H6001994-08-16016 August 1994 Forwards Updated CNS Conventional Treatment Ponds Groundwater Monitoring Program ML20071L5811994-07-28028 July 1994 Informs That Floating Aerator Test Canceled & Will Not Be Performed for Sanitary Treatment Sys,Per Request Made to & Approved by Industrial & Agriculture Wastewater Div of Sc Dept of Health & Environ Control in June 1993 ML20069G9531994-06-0202 June 1994 Forwards Approval Ltr from DHEC Authorizing Use of Sodium Bromide in Cooling Towers.Internal DHEC Memo from V Beaty Giving Rept on Review of Toxicity Data Util Supplied to Sc on Sodium Bromide Also Encl ML20070M5851994-04-22022 April 1994 Submits Written follow-up Notification for Release of Ethylene Glycol on 940413.Caused by Technician Error.Pond Routinely Monitored for Adverse Environ Consequences & None Observed ML20070M1761994-04-15015 April 1994 Updates State of Sc on Status of SG Chemical Metal Cleaning Project Previously Scheduled to Occur This Summer.Decision Made Not to Perform Chemical Cleaning on Catawba Unit 2 SGs During Upcoming Outage ML20063K5961994-02-17017 February 1994 Forwards Approval from South Carolina Dept of Health & Environ Control to Use Treatment Chemicals for Steam Generator Chemical Metal Cleaning to Occur Later This Yr ML20062N4121993-12-28028 December 1993 Requests Approval to Use Ethylenediamine (EDA) & Ammonium Carbonate for Use in Cleaning Sgs.Info on EDA & Ammonium Carbonate Required by Permit (Part Iii,Item 9) Encl ML20059B1431993-12-21021 December 1993 Forwards 931213 Memo from South Carolina Dept of Health & Environ Control Approving Months of Mar,June,Sept & Dec as Months to Perform Toxicity Monitoring for Outfalls 001 & 002 ML20059C6391993-12-13013 December 1993 Ack Receipt of Re Biomonitoring at Outfalls 001 & 002 Required by NPDES Permit SC0004278.Agrees W/Request to Conduct Quarterly Biomonitoring Sampling During Third Month of Each Quarter Based on Review of Ltr ML20057D6341993-09-30030 September 1993 Requests Reduction in Toxicity Monitoring Requirements for Outfalls 001 & 002.Summary of Toxicity Monitoring History for Outfalls Listed ML20056H1461993-08-31031 August 1993 Discusses Plans to Change Util to Molybdate Based Corrosion Inhibitor Program Per Part III Item A.9 ML20056H1431993-08-31031 August 1993 Requests Trial Alternate Method Be Approved by State for Drainage of Cooling Towers at Util ML20044H1141993-05-27027 May 1993 Requests Permission to Use Sodium Bromide,On Trial Basis,To Control Biological Growth During Summer Months.Sodium Bromide Effective in High Ph Water & Need for Sulphuric Acid Should Almost Completely Be Eliminated ML20073E6061991-04-26026 April 1991 Forwards NPDES Discharge Monitoring Rept for Catawba Nuclear Station for Mar 1991. on 910321,overflow from Manway Discharged Into Standby Nuclear Svc Water Pond. Repairs Made to Clogged Line ML20077E0631991-04-18018 April 1991 Advises That on 910415,small Amount of Diesel Fuel Contamination Found While Drilling Cathodic Protection Well. Groundwater Monitoring Well Will Be Installed Where Well Drilled for Cathodic Protection Well ML20043B5701990-05-22022 May 1990 Forwards Description of Several Items Associated W/Facility Wastewater Treatment Sys Previously Not Mentioned in NPDES Permit Application ML19354E8791990-01-25025 January 1990 Forwards Application for NPDES Permit for Storm Water Discharge at Plant ML19324C2881989-11-0707 November 1989 Forwards Addl Info to Draft Renewal of NPDES Permit SC0004278 within 60 Days,Per 890707 Request.Info Should Be Considered as Supplemental to 881108 Application for Renewal of Permit ML20248F2951989-09-29029 September 1989 Notifies That on 890901,18.6 Lb of Hydrazine Released to Atmosphere.Caused by Blade of Handtruck Piercing Bottom of Drum While Transporting Hydrazine from Warehouse to Usage Point.Employees Evacuated ML20206C1521988-11-0808 November 1988 Forwards Application for Renewal of NPDES Permit SC0004278, Per 40CFR122.21 ML20153F4381988-08-30030 August 1988 Comments on Draft NPDES Permit Mod for Plant.Components of Draft Mod Acceptable W/Listed Exceptions ML20198B7371985-10-31031 October 1985 Advises That Documents Filed W/Nrc,Except for Legal Documents,Will No Longer Be Provided Since ALAB-813 Became Final Agency Action on 851025.Related Correspondence ML20133K4051985-10-0808 October 1985 Advises That Radiological Emergency Response Plan in Support of Fixed Nuclear Facilities Approved.W/O Ltr to NRC Indicating Approval of State & Local Plans & Preparedness ML20133K4091985-10-0808 October 1985 Advises That Emergency Response Plan Approved,Conditional Upon Verification of Alert & Notification Sys.W/O Ltr to NRC Indicating Approval of State & Local Plans & Preparedness ML20107L7211984-11-0808 November 1984 Confirms 841106 Telcon Re Answers to Applicant Interrogatories on EPJ-3 for Which Conservation Council Lead Intervenor.Interrogatories Filed on 841005 & Responses Due on 841029.Related Correspondence ML20088A6901984-04-0909 April 1984 Forwards Planning Research Corp Rept, Assumptions Underlying Departure Times for Evacuation of Emergency Planning Zone. W/O Encl.Related Correspondence ML20087N6541984-03-29029 March 1984 Forwards Applicant Supplemental Answers to Carolina Environ Study Group & Palmetto Alliance 840329 First Set of Interrogatories,Consisting of Answers from Agencies Included in Emergency Planning.Related Correspondence ML20087C4581984-03-11011 March 1984 Forwards Applicant Interrogatories & Request to Produce Documents Re Diesel Generator Contention,Per 840223 Order. Related Correspondence 1999-03-30
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' DukeIbwer Company
. Generation Smsces Department 1.U33Itagers Ferry Road lianterset!!e, NC28078 7929
- DUKEPOWER August 31, 1993 Mr. Timothy M. Eleazer Industrial and Agricultural Wastewater Division South Carolina Department of Health and Environmental Ccntrol 2600 Bull Street Columbia, SC 29201
Subject:
Catawba Nuclear Station NPDES Permit No. SC0004278 Notification of Maintenance Chemical File: CN-702.13
Dear Mr. Eleazer:
Pursuant to Part III item A. 9. Catawba Nuclear Station is planning to change to a molybdate based corrosion inhibitor program. If this program is successful it will be implemented in several closed cooling water systems that currently use sodium nitrite as their main corrosion inhibitor. Once implemented this program would significantly reduce the amount of sodium nitrite that is used at Catawba Nuclear Station.
l The product will be utilized in closed cooling water systems and will only be discharged on an intermittent frequency during system maintenance or possibly by leaks. It potentially could be ;
discharged via Outfalls 001 and 002 to Lake Wylie. )
The product will primarily be discharge through butfall 002- the !
conventional waste treatment system (WC). When cooling system j maintenance is required the product would be drained to the WC system and discharged via outfall 002. The product could also be l discharged through outfall 001 due to system leaks or system drainage via the liquid radwaste system. l n ") 1 1 'l . ;
9309080295 930831 7 PDR ADOCK 05000413 -
P PDR I L
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Attachment #1 provides the information that is required by Part III {
A item 9 of the subject permit. Attachment #2 provides toxicity ;
information on a typical molybdate based corrosion inhibitor product to be used - Performax 330. ,
Attachment #3 provides toxicity test results on nitrite. A comparison of this toxicity data indicates that nitrite is the most
- restrictive compound. With reference to the subject NPDES permit j Part III A. item 8. the NOEC for nitrite is 4.3 mg/l ( 6.- mg/l as sodium nitrite).
i Attachment #4 is a copy of the Material Safety Data Sheet (MSDS) ;
for Performax 330. Performax 330 is a typical product that is planned on being used. Different proprietary names for the same i compound may be selected for use. The attached MSDS identifies the ;
various ingredients along with their CAS numbers. ;
Summary t
Based on the information provided, it is requested that the use of t a molybdate based corrosion inhibitor be approved and that a limit ,
of 4.3 mg/l (6.'4 mg/l as-sodium nitrite) for nitrite for Outfalls -
001 and 002 be established. If approval is granted Catawba would like to begin use of this product by October 20, 1993. Please note i i
that 4.3 mg/l of nitrite is equivalent to 1.3 mg/l NO 2 -N/l or l nitrite as nitrogen . !
If you need additional information please give John Estridge a call ;
at (704) 875-5965. '
Sincerely, l
h Y
Q, w llk i Jo n S. Carter, Technical System Manager Environmental Division, Water Protection ,
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bc:- J.T. Harris-CN01EM ;
A.P. Jackson-CNO3CH J.S. Velte-MG03A3 ~
M.A. Lascara .;
S.D. Davenport-EC07D C.L. Peed W.J. Davis-CN01CH '
R.R. Wylie G.W. Sain-EC07D i
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ATTACHMENT 1 CATAWBA NUCLEAR STATION PROPOSED MAINTENANCE CHEMICAL LIMIT .
i AUGUST 26, 1993 NPDES PERMIT SC0004278 PART III ITEM 9 REQUIREMENTS ,
- 1) NAME AND GENERAL COMPOSITION OF THE MAINTENANCE CHEMICAL "
a) Sodium Nitrite ;
b) Sodium Molybdate c) Sodium Metasilicate Anhydrous _
For the general composition of the maintenance chemical please i refer to the attached Material Safety Data Sheet.
- 2) QUANTITIES TO BE USED Approximately 1000 pounds / year of this product are to be added to closed cooling systems.
- 3) FREQUENCY OF USE i Product will be added to plant systems as needed to maintain concentration levels of between 1000 and 3000 mg/1. q
- 4) PROPOSED DISCHARGE CONCENTRATION Based on toxicity information as referenced in Part III A.
Item 8, the NOEC for nitrite is 4.3 mg/1.(6.4 mg/l as sodium nitrite) Therefore a daily maximum limit of 4.3 mg/l Nitrite per an occurrence is requested for Outfalls 001 and 002.
Sampling to confirm compliance with this limit would be required whenever maintenance activities or leaks occur that have the potential to exceed the value of 3.5 mg/1. !
- 5) EPA REGISTRATION NUMBER unknown
- 6) AQUATIC TOXICITY INFORMATION See Attachments #2 and #3.
l-5
ij A&kt 2
~
2 i
PERFORMAX" 330 Conn 0SION INHIBITOR e
l I
i AQUATIC TOXIf,12DC i 96 HOUR LC 50 RAINBOW TROUT:
1,581.1 mg/l (CONFIDENCE LIrgTS 95%:
1,000 - 2,500 mg/1) '
.1,000 mg/l 96 IIOUR LC50_ FATHEAD MINNOW:
812.3 mg/l (CONFIDENCE LIMITS 95%:
682 - 968 mg/1)
NOEC FATHEAD MINNOW:
500 mg/l 48 HOUR LC50 DAPHNIA MAGNA: !
526.8 mg/l (CONFIDENCE LIMITS 95%:
381 - 738 mg/1)
NOEC DAPHNIA MAGNA:
125 mg/l '
2 i
- i f
- No observed ef fect concentration.
i I
i I
A+%%nf3 =
. Memo to: Mitch C. Griggs '
Date: 24 January 1990 t
Subject:
Acute and Chronic Toxicity of Nitrite (as NANO2 ) to ,
Ceriodaphnia dubia {
Data C. reported previously regarding chronic dubia (memo from J.S. Velte to M.C.
toxicity of nitrite to Griggs dated 10 January 1990) is in error and should not be used. I was notified by our i chemists this morning that the results of prior nitrite analyses had been reported erroneously to me as "mg NO 2
/L" when, in fact they were "mg NO 3-N/L". In other words, the concentrations that I had been provided represented only the mass of the nitrogen component of the nitrite ion, not the entire ion. This problem i is easily by 3.28. corrected by multiplying the values reported previously A revised analysis of the chronic toxicity test is reported here, as are the results of a recently completed and }
" properly" analyzed acute toxicity test with Cb, dubia.~~ Please accept my apologies for any confusion this has caused you. On the bright side, we no longer need be concerned about the mysterious disappearance of nitrite in lake water (we've !
recovered essentially 100% of what was added). And, nitrite has }
proven thought!even less toxic to C6,dubia than we had originally i Here are the revised chronic test results, based on measured NO concentrations (see Table 1) . The raw data are attached. 2 NOEC =,4.3 mg NO /L 2
LOEC = 8.5 mg NO2 /L f Chronic Value (CV) =
m/4.3 X 8.5 = 6.0 mg NO /L 2 $
t A Moving Average-Angle (MAA) analysis of the 48-hour static acute test data gave the following LC50 and associated 95% confidence limits (again, the raw data sheet, and a graph of the nominal vs.
measured exposure concentrations -- Figure 2, are attached).
LC50 = 28 mg NO,/L ,
Lower and Upper 95% Confidence Limits = 21 and 39 mg NO /b 2
If you have questions, concerns, or need additional information, !
please call me.at 875-5237. Again, I'm sorry for the confusion.
i Jb S. Velte i Scientist i cc w/a ttachments: R. Biswas K. Finley G. Vaughan l
i'
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FIGURE 2 Nominal and Measured Concentrations of NO2 in Lake Wylie Water.
(from: acute toxicity of nitrite to L dubia test)
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EXPOSURE TREATMENT NUMBER i
l
' - ;gg ,;;g ,, c.m2rpacy
"* MATEAL SAE On:a Orsw Plaza. Soont:n. N1w J:rs:y 07005 Telcph:ns DATA SHt:tg Phona (2011263-7600/Telax 136444 1(800) 274-5263 e 1(800) ASHLAND DEFINmONS c nw k This defimtion page is intended for use with Material Safety Cata Sheets supplied by the Orew Chemical Corocration.
Recioients of these cata sheets snould consult tne CSHA Safety ano Heatth Stancards (29 CFR 19102. parucutariy suocar G - Occucational Heastn and Environmental Control, and subcart - Personai Protective Ecutornent, for generai guiaance on controi of potential Occupationai Heaith ano Saf ety Hazaros.
SECTION I SECTION IV 4.ont)
PRODUCT IDENTIFICATION EXTINGUISHING MEDIA: Followng National Fire GENERAL OR GENERIC ID: Chemical f am>Iv or product Protection Association criteriau cescription.
FIREFIGHTING PROCEDURES: Minimum equipment to DOT HAZARD CLASSIFICATION: Proouct meets DOT protect firefighters trom toxic procuets of vaoonzation.
criteria for hazaros listed. comoustion or decomoosition in fire situations. Other firefighting hazards may atso be inoicated.
SECTION -11 COMPONFNTS SPECIAL FIRE AND EXPLOSION HAZARDS: States hazarcs not covered tav other sections.
Comconents are listed in this section if thev present a NFPA CODES: Hazard ratings assigned by the National physical or health hazaro and ere present at or aoove Fire Protection Association 1% en tne mixture. If a component is identified as a CARCINOGEN by NTP. IARC. or OSHA as of the~ oate SECYIOh-on the MSDS. it wdl be hsted and f ootnoted in' this HEALTH HAZARD UATA section wnen present at or wcve 0.1*. in the procuct.
Negauve conNsions concerning carcinogemcity are not PERMISSIBLE EXPOSURE LIMIT: For product.
a:.m; m Acditionat hearth inf ormanon may be found in THRESHOLD LIMIT VALUE: For- product. i Section V. Components suolect to the reporting recuir ements of Section 313 of SARA Title lit are EFFEC 3 OF ACUTE OVEREXPOSURE: Potential local t identified in the f ootnotes in tnis section. along with ano x. W ects due - singte or snort term typical cercentages. Other comoonents mav be listeo if overex osure to the eyes ano ein or through innatation deemeo accropriate. :: a a :.cn.
E3cosure recommendations are for comoonents. OSHA EFFECTS OF CHRONIC OVEREXPOSURE: Potential local
- ermissible Exposur e Limits (PELS) and American and systemic ef f ects due to repeated or long term Conference of Governmental Inoustrial Hygienists overexposure to the eyes anc skin or through inhalation or ingestion.
(ACGiH) Threshold Limit Values (TLVs) apcear on tne hne with the component identification. Other recommendations appear as footnotes. FIRST AID: Procedures to be followed when deshng
. with accidental overexposure.
SECTION til PRIMARY ROUTE OF ENTRY: Based on properties and PHYSTCAL DATA expected use.
DOfLING POINT: Of product if knowrt The lowest EUN W vaaue of the components is listeo f or mixtures. REACTIVITY DATA VAPOR PRESSURE: Of proouct of knowrt The hignest HAZARDOUS POLYMERIZATION: Conditions to avoid to value of the components is listea for mixtures. prevent hazardous polymerization resulting in a large reiease of energy.
SPECIFIC VAPOR DENSITY: Comeared to AIR = 1. I f STABttMY: Conditions to avoid to prevent hazardous or tna Specific Vapor Oensity of a proouct is not known. violent decomposition.
the value es expressed as hgnter or greater than air.
SPECIFIC GRAVITY: Compared to WATER = 1. If INCOMPATIBILITY: Materials and conditions to avoid to Specific Gravity of product is not known the value is prevent hazardous reactions.
expressed as less than or greater than water.
SECTION Vil pH: If applicable.
SPILL OR LEAK PROCEDURES PERCENT VOLATILES: Percentage of material with initial boding point below A25 degrees Fahrennert and Reasonaole precautions to be taken and methods of vccor pressure above fl.1mm Hg at S8 F. containment, clean up and disposal Consult federal EVAPORATION RATE: Indicated as faster or stower a am m h es W
. than ITr% ETHE~t unless etnuwise stated. any moorting r n tificauen requirements.
, y SECTION Vill r1RE AND EXPLOSION DATA FLASH PO!NT: Method identified. Protective equipment which may be needed when handting the product.
EXPLOSION LIMITS: For proouct if known. The towest value of the components ss insted for mixtures. SECTION IX HAZARDOUS DECOMPOSITION PRODUCTS: Known or expected hazarcous procucts r esuiting from heating.
burning or otner reactions. Covers any relevant points not previously menuoned.
ADDITIONA1. COMMENTS Comainers snould be eitner reconoitionea by CERTIFIED firms or properiv discosed of by APPROVED firms. Discosat of container s snould te .n accorcance wem aopiscacie ta vvs and r eculatinns. "EMP TY" arums snould not be given to
.ncividuais.
'V ano u Senous accidents save resuited from tne rmsuw of ' EMPTIED' containers (drums.caits.etel Ref er to Sections
. . - . . . . . . . . - . . = A setisy
- MATERIAL SAFETY arwe omeAA car- Telephone
~
Ons Drew Plaza. Boonton. Naw Jrrsey 07005 DATA SHE Phone (2011263-7600/Telax 136444 1(800) 274-5263 or w 1(800) ASHLAND od2874 PERFORMAX(TM) 330 COOLING WATER TREATMNT Page:
THIS MSDS CCMPLIES WITH 29 CFR i910.1200 (THE HAZARD CCM41N! CATION STANDARD
..............................................................................................)..........
Proouct Names
_ PERFORMAK(TM) 330 COOLING kATER ~REATMiT CD 10 922 - Data Sheet No: 023118s-004 Preparea:
DREW INDUSTRIAL O! VISION 05/29/91 500 ARO OALE ORIVE Superseces : 0A/24/94 SUITE 115 PRODUCT:
01ARLOT~E 4918001 NC INVOICE:
28210 INVOICE OATE:
70: DREW INDUSTRI AL O! VISION O!$TRICT MANAGER 500 AROCALE ORIVE OiARLOTTE t
.. . . . _ W ? NO 1 ag e s* r, m m.m.s.n e t*Iy 4 minela a r m a m*r.n u m'!,
General or Generic ID: COOLING WATTR TREATMENT DOT Hazarc Classificatient OrN-E IF PRESENT. I ARC. NTP AND OSHA CARCINOGENS AND OEMICALS SUEUECT 'O THE REPORT-ING REQUIREMENTS SEEOF SARA TITLE DEFINITION.P. AGE FOR!!! SECTION CLARIFICATION 313 ARE IDENTIFIED IN THIS SECTION.
INGREDIENT % (t:y WT) PEL TLV Note 500!UM NITWITE .
CAS s: 7632-00-0 10-25
( 1) t i
500!UM M)LYBOATE CAS s: 7631-95-0 1-10 S NG/M3 C. 4 -
SOCIUM NITRATE USs 7631-99-4 1-10
( 2)
SODIUM METASILICATE ApeWCROUS CAS s: 6834-92-0 1-10 15 pC/M3 10 MS/M3 ( 3)
F Hotes:
( 1) PEL/TLV NOT ESTABLISHED FOR THIS MATERIAL
( 2) PEL/TLV NOT ESTABLISHED FOR THIS MATERIAL
( 3) PEL AND TLV ARE FOR TOTAL NUISANCE FARTICULATES. '
Botling Point for COMPONENT ( 55-70%) 212.00 Deg F
( 100.00 Deg C)
Vapor Pressure
@ 760.00 m Hg f cr C04PONENT( 55-70%) '
17.50 m Hg e 68.00 Deg F
( 20.00 Deg C)
Soscif1c Vaocr Censity KAVIER THAN AIR Specific Gravity t.250 e 77.00 Ceg F t
( 25.00 Des C)
Percent Volatiles .
t 55-70%
Evaporation Rate SLOWER THAN ET}ER get Appearance 12.9 .
r CLEAR. YELLOW State l LIOJID FLASH POINT NOT APPLICABLE EXPLOSIVE LIMIT NCT APPLICAOLE EYTINGUISHING MEDI A: WATER FOG HAZARDOUS DECOMPOSITION PRODUCTS: MAY FORM T0XIC MATERI ALS:. N!*ROGEN COMPOUNOS l FIRLFIGHTING rRESSURE DEMAND PROCEDURES:
M10E AND FULL WEAR BODY PROTEC* SELF-CONTAINED ION W4LN FIG M NG BREATHING FIRES. APPARATUS WIN A FULL FACEPI!
4 COPYRIGHT 1991 CONTINUED ON PAGE: 2 I
.-