Similar Documents at Salem |
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217M2101999-10-19019 October 1999 Forwards NRC Rept Number 17, Requal Tracking Rept from Operator Licensing Tracking Sys.Rept Was Used by NRC to Schedule Requalification Exam for Operators & Record Requal Pass Dates ML18107A5601999-10-18018 October 1999 Submits 30-day Fuel Clad Temp Rept,Iaw 10CFR50.46.Rept Describes Changes to Calculated Peak Clad Temp (PCT) for Salem Generating Station Large & Small Break LOCA Analyses ML18107A5531999-10-0808 October 1999 Forwards Summary Rept of Plant Startup & Power Ascension Testing for Sgs,Unit 2 Cycle 11,per Requirements of TS 6.9.1.1 ML18107A5561999-10-0707 October 1999 Requests Relief Associated with Containment Examinations at Hope Creek & Salem Generating Stations.Attachment 1 Includes Proposed Alternatives & Supporting Justification for Relief Requests ML18107A5591999-10-0505 October 1999 Informs That Nj Dept of Environ Protection Has No Comments on License Change Request S99-07 for Sgs,Units 1 & 2 ML18107A5501999-10-0505 October 1999 Provides Current Status of Pse&G Actions Re GL 98-01, Y2K Readiness of Computer Sys at Npps, for Salem Nuclear Generating Station,Units 1 & 2 & Hope Creek Nuclear Generating Station ML18107A5521999-10-0505 October 1999 Encourages NRC to Support Abb Combustion Engineering Nuclear Power Request for Priority Review of Generic TR Re Crossflow Ultrasonic Flow Measurement Sys IR 05000272/19990071999-09-28028 September 1999 Forwards Insp Repts 50-272/99-07 & 50-306/99-07 on 990721- 0831.One Potentially Safety Significant Issue Identified Dealing with Control Room Special Ventilation System.Four Addl Issues of Low Safety Significance Identified ML18107A5341999-09-22022 September 1999 Provides Data Re Operator Licensing Exam for Salem & Hope Creek Station,In Response to NRC Form 536 (7-1999) ML18107A5421999-09-22022 September 1999 Forwards Discharge Monitoring Rept for Salem Generating Station for Aug 1999.Rept Is Required by & Prepared Specifically for EPA & Nj Dept of Environ Protection ML20212B3631999-09-14014 September 1999 Forwards Rev 13 to Salem - Hope Creek Security Plan,Iaw 10CFR50.54(p).Summary of Proposed Changes to Plan,Encl. Encl Withheld ML18107A5321999-09-13013 September 1999 Forwards Revised 10CFR50.92 Evaluation to Clarify Util Response to Question Number 1 Re Amend to Modify TS 3/4 8.1, AC Power Sources. ML18107A5351999-09-13013 September 1999 Informs That NRC Has Reviewed Pse&G Request Proposing to Modify TS Which Allow EDG to Be Operated for 24 Surveillance Test During Any Mode,Iaw 10CFR50.91(b) & Has No Comments ML18107A5331999-09-13013 September 1999 Provides Notification That PSEG Intends to Utilize ASME Code Case N-481 During Second ISI Interval at Sgs Units 1 & 2 ML18107A5221999-09-0808 September 1999 Requests Approval to Use ASME Code Case N546,which Provides Alternative Qualification Requirements That Allow Personnel Most Familiar with Walkdown of Plant Sys,Like License Operators to Perform VT-2 Examinations ML18107A5231999-09-0808 September 1999 Forwards Salem Generating Station Semiannual Radioactive Effluent Release Rept for Jan-June 1999. Rept Summarizes Liquid & Gaseous Releases & Solid Waste Shipments from Salem Generating Station for Period of Jan-June 1999 ML18107A4981999-08-26026 August 1999 Forwards Response to NOV That Resulted from Predecisional Enforcement Conference Conducted on 990624.Corrective Actions:Communications to Supervisors Reinforced Employee Right & Duty to Raise Nuclear Safety Issues ML18107A5181999-08-26026 August 1999 Forwards Ninety Day Rept for ISI Activities Conducted at Sgs,Unit 2 During Ninth Extended Outage & Tenth Refueling Outage.List of Encl,Provided ML18107A5061999-08-26026 August 1999 Provides First Feedback from Observation of NRC Insp Under Pilot Nuclear Power Plant Insp Program.Attached Are Completed Insp Feedback Forms for Procedure 71111, Attachment 21 & Procedure 71151 ML18107A5051999-08-24024 August 1999 Informs That Nj Dept of Environ Protection Bureau of Nuclear Engineering Has Reviewed Request IAW Requirements of 10CFR50.91(b) & Has No Comments Re Amend to FOL Change Request S99-02 to Modify TS Re Penetration Valves ML18107A4921999-08-23023 August 1999 Provides Suppl Info Re 971024 Amend Request to Modify TS 3/4 7.7, Auxiliary Bldg Exhaust Air Filtration Sys. Util Withdraws from Request All Proposed Changes Associated with Filter Testing,Per Issuance of GL 99-02 ML18107A4911999-08-20020 August 1999 Forwards Revised Plant Attribute Libraries for Salem & Hope Creek Generating Stations,Iaw 10CFR50,App E,Vi, Emergency Response Data Sys, 3.b.Changes Are Identified by Rev Bars ML18107A4861999-08-19019 August 1999 Forwards NPDES Discharge Monitoring Rept, for Salem Generating Station for Month of Jul 1999.Rept Required by & Prepared Specifically for EPA & Nj Dept of Environ Protection ML18107A4831999-08-18018 August 1999 Submits Licensee Comments on NRC 990730 Ltr Which Provided Notification of Close Out of TAC Numbers MA0567 & MA0568 Re GL 92-01,Rev 1,Suppl 1 ML18107A4801999-08-13013 August 1999 Requests That Pse&Gs Contact in NUREG-0383, Directory of Compliance for Radioactive Matl Packages, Be Changed ML18107A4751999-08-0505 August 1999 Forwards Fitness for Duty Performance Data Rept for Six Month Period Ending 990630 ML20210M7571999-08-0404 August 1999 Forwards Response to Requesting Addl Info Re Status of Decommissioning Funding for Lgs,Pbaps & Sngs. Attachment Provides Restatement of Questions Followed by Response ML18107A4531999-07-20020 July 1999 Forwards Discharge Monitoring Rept for Salem Generating Station, for June 1999.Rept Is Required by & Prepared for EPA & Nj Dept of Environ Protection ML18107A4431999-07-0606 July 1999 Informs That Nj Dept of Environ Protection Bureau of Nuclear Engineering Has Reviewed Pse&G License Change Request S98-17 Re Permissible Enrichment Values for New Fuel Storage & Has No Comments ML20196J6301999-07-0101 July 1999 Requests Addl Info Re Status of Decommissioning Funding for Limerick Generating Station,Units 1 & 2,Peach Bottom Atomic Power Station,Units 1,2 & 3 & Salem Nuclear Generating Station,Units 1 & 2 ML18107A4181999-06-30030 June 1999 Submits Response to NRC Request for Info Re Y2K Readiness at Npps,Per GL 98-01,suppl 1.Disclosure Encl ML20209B6751999-06-29029 June 1999 Ack Receipt of from Dr Powell in Response to NRC Re Fitness for Duty.Attachment 2 of Will Be Withheld from Public Disclosure,Per 10CFR2.790 ML18107A4131999-06-25025 June 1999 Provides Further Clarification of Licensing & Design Basis for 125 Vdc Battery Margins for Sgs & HCGS for Meeting Station SBO & Loca/Loop Loading Requirements,Per Util 990426 Ltr & Discussion with NRC ML18107A4091999-06-22022 June 1999 Forwards Discharge Monitoring Rept for May 1999,containing Info as Required by Permit NJ0005622.Rept Prepared Specifically for EPA & Nj Dept of Environ Protection ML18107A4061999-06-21021 June 1999 Provides Supplemental Info to Proposed License Amend, Modifying TS 3/4 7.7, Auxiliary Bldg Exhaust Air Filtration Sys. Info Re Acceptance Criterion Discussed ML18107A3691999-06-11011 June 1999 Forwards Corrected Monthly Operating Rept for Apr 1999 for Salem Generating Station,Unit 1.Original Submittal Contained Typo for year-to-date Value for Numbers of Hours Generator Was on Line (Service Hours) ML18107A3641999-06-0404 June 1999 Requests Enforcement Discretion for TS 3/4.6.2.3 Re Containment Cooling Sys for Salem Generating Station,Unit 1 ML18107A3561999-06-0303 June 1999 Informs That Nj Dept of Environ Protection Bureau of Nuclear Engineering Has Reviewed Pse&G License Change Request S99-05 & Has No Comments ML18107A3611999-05-27027 May 1999 Forwards Responses to NRC 990301 & 990323 RAIs for Salem & Hope Creek Generating Stations Relating to GL 96-05 ML18107A3301999-05-24024 May 1999 Forwards Suppl Info Re GL 95-07, Pressure Locking & Thermal Binding of Safety Related Power Operated Gate Valves. Encl Contains Methodology Used in Determination of Pressure Locking Susceptibility of PORVs Block Valves ML18107A3371999-05-21021 May 1999 Forwards NPDES Discharge Monitoring for Salem Generating Station for Apr 1999, Containing Info as Required by Permit NJ0005622 ML18107A3291999-05-20020 May 1999 Forwards Redacted Response to NRC 990322 RAI Re Notification of Licensed Operator That Tested Positive for Alcohol. Attachment 2 Withheld,Per 10CFR2.790(a)(6) ML18107A3031999-05-18018 May 1999 Provides Summary of Changes to NRC Commitments That Have Been Made But Not Reported by Other Means,Iaw with NEI Process for Managing NRC Commitments ML18107A2891999-05-13013 May 1999 Forwards Rev 36 to Pse&G Nuclear Business Unit Emergency Plan. Rev 36 Incorporates Changes to Section 1-3,6 & 7 & 9-17.Attached Copy Includes All Sections of EP for Completeness ML18107A2951999-05-12012 May 1999 Submits SG Tube Plugging Rept,Per Plant TS 4.4.6.5.a.Total of 47 Tubes Were Plugged During SG Tube Insps,Which Were Completed During Plant Tenth RFO ML18107A2861999-05-11011 May 1999 Forwards Rev 0 to NFS-0174, COLR for Salem Unit 2 Cycle 11. COLR Rept Was Received by Util as Part of Reload SE ML18107A2481999-04-29029 April 1999 Forwards 1998 Annual Radiological Environ Operating Rept for Salem & Hope Creek Generating Stations. Rept Summarizes Results of Radiological Environ Surveillance Program for 1998 ML18107A2511999-04-27027 April 1999 Submits 30-day Fuel Clad Temp Rept for Salem Generating Station,Units 1 & 2.Rept Describes Changes to Calculated Peak Clad Temp (PCT) for Plant Large & Small LOCA & Small Break LOCA Analyses ML18107A2631999-04-26026 April 1999 Provides Clarification on Licensing & Design Basis for 125 Vdc Battery Margins for Sgs & HCGS for Meeting SBO & Loca/ LOOP Loading Requirements ML18107A2371999-04-26026 April 1999 Forwards Corrected Response to NRC RAI Re Licensee Request for Change to TS Permissible Enrichment Values for New Fuel Storage.Incorrect Attachment Was Provided with Util 990412 Ltr to Nrc.Encl Supersedes 990412 Submittal 1999-09-08
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML18107A5601999-10-18018 October 1999 Submits 30-day Fuel Clad Temp Rept,Iaw 10CFR50.46.Rept Describes Changes to Calculated Peak Clad Temp (PCT) for Salem Generating Station Large & Small Break LOCA Analyses ML18107A5531999-10-0808 October 1999 Forwards Summary Rept of Plant Startup & Power Ascension Testing for Sgs,Unit 2 Cycle 11,per Requirements of TS 6.9.1.1 ML18107A5561999-10-0707 October 1999 Requests Relief Associated with Containment Examinations at Hope Creek & Salem Generating Stations.Attachment 1 Includes Proposed Alternatives & Supporting Justification for Relief Requests ML18107A5501999-10-0505 October 1999 Provides Current Status of Pse&G Actions Re GL 98-01, Y2K Readiness of Computer Sys at Npps, for Salem Nuclear Generating Station,Units 1 & 2 & Hope Creek Nuclear Generating Station ML18107A5521999-10-0505 October 1999 Encourages NRC to Support Abb Combustion Engineering Nuclear Power Request for Priority Review of Generic TR Re Crossflow Ultrasonic Flow Measurement Sys ML18107A5591999-10-0505 October 1999 Informs That Nj Dept of Environ Protection Has No Comments on License Change Request S99-07 for Sgs,Units 1 & 2 ML18107A5341999-09-22022 September 1999 Provides Data Re Operator Licensing Exam for Salem & Hope Creek Station,In Response to NRC Form 536 (7-1999) ML20212B3631999-09-14014 September 1999 Forwards Rev 13 to Salem - Hope Creek Security Plan,Iaw 10CFR50.54(p).Summary of Proposed Changes to Plan,Encl. Encl Withheld ML18107A5321999-09-13013 September 1999 Forwards Revised 10CFR50.92 Evaluation to Clarify Util Response to Question Number 1 Re Amend to Modify TS 3/4 8.1, AC Power Sources. ML18107A5331999-09-13013 September 1999 Provides Notification That PSEG Intends to Utilize ASME Code Case N-481 During Second ISI Interval at Sgs Units 1 & 2 ML18107A5351999-09-13013 September 1999 Informs That NRC Has Reviewed Pse&G Request Proposing to Modify TS Which Allow EDG to Be Operated for 24 Surveillance Test During Any Mode,Iaw 10CFR50.91(b) & Has No Comments ML18107A5231999-09-0808 September 1999 Forwards Salem Generating Station Semiannual Radioactive Effluent Release Rept for Jan-June 1999. Rept Summarizes Liquid & Gaseous Releases & Solid Waste Shipments from Salem Generating Station for Period of Jan-June 1999 ML18107A5221999-09-0808 September 1999 Requests Approval to Use ASME Code Case N546,which Provides Alternative Qualification Requirements That Allow Personnel Most Familiar with Walkdown of Plant Sys,Like License Operators to Perform VT-2 Examinations ML18107A5061999-08-26026 August 1999 Provides First Feedback from Observation of NRC Insp Under Pilot Nuclear Power Plant Insp Program.Attached Are Completed Insp Feedback Forms for Procedure 71111, Attachment 21 & Procedure 71151 ML18107A5181999-08-26026 August 1999 Forwards Ninety Day Rept for ISI Activities Conducted at Sgs,Unit 2 During Ninth Extended Outage & Tenth Refueling Outage.List of Encl,Provided ML18107A4981999-08-26026 August 1999 Forwards Response to NOV That Resulted from Predecisional Enforcement Conference Conducted on 990624.Corrective Actions:Communications to Supervisors Reinforced Employee Right & Duty to Raise Nuclear Safety Issues ML18107A5051999-08-24024 August 1999 Informs That Nj Dept of Environ Protection Bureau of Nuclear Engineering Has Reviewed Request IAW Requirements of 10CFR50.91(b) & Has No Comments Re Amend to FOL Change Request S99-02 to Modify TS Re Penetration Valves ML18107A4921999-08-23023 August 1999 Provides Suppl Info Re 971024 Amend Request to Modify TS 3/4 7.7, Auxiliary Bldg Exhaust Air Filtration Sys. Util Withdraws from Request All Proposed Changes Associated with Filter Testing,Per Issuance of GL 99-02 ML18107A4911999-08-20020 August 1999 Forwards Revised Plant Attribute Libraries for Salem & Hope Creek Generating Stations,Iaw 10CFR50,App E,Vi, Emergency Response Data Sys, 3.b.Changes Are Identified by Rev Bars ML18107A4831999-08-18018 August 1999 Submits Licensee Comments on NRC 990730 Ltr Which Provided Notification of Close Out of TAC Numbers MA0567 & MA0568 Re GL 92-01,Rev 1,Suppl 1 ML18107A4801999-08-13013 August 1999 Requests That Pse&Gs Contact in NUREG-0383, Directory of Compliance for Radioactive Matl Packages, Be Changed ML18107A4751999-08-0505 August 1999 Forwards Fitness for Duty Performance Data Rept for Six Month Period Ending 990630 ML20210M7571999-08-0404 August 1999 Forwards Response to Requesting Addl Info Re Status of Decommissioning Funding for Lgs,Pbaps & Sngs. Attachment Provides Restatement of Questions Followed by Response ML18107A4431999-07-0606 July 1999 Informs That Nj Dept of Environ Protection Bureau of Nuclear Engineering Has Reviewed Pse&G License Change Request S98-17 Re Permissible Enrichment Values for New Fuel Storage & Has No Comments ML18107A4181999-06-30030 June 1999 Submits Response to NRC Request for Info Re Y2K Readiness at Npps,Per GL 98-01,suppl 1.Disclosure Encl ML18107A4131999-06-25025 June 1999 Provides Further Clarification of Licensing & Design Basis for 125 Vdc Battery Margins for Sgs & HCGS for Meeting Station SBO & Loca/Loop Loading Requirements,Per Util 990426 Ltr & Discussion with NRC ML18107A4061999-06-21021 June 1999 Provides Supplemental Info to Proposed License Amend, Modifying TS 3/4 7.7, Auxiliary Bldg Exhaust Air Filtration Sys. Info Re Acceptance Criterion Discussed ML18107A3691999-06-11011 June 1999 Forwards Corrected Monthly Operating Rept for Apr 1999 for Salem Generating Station,Unit 1.Original Submittal Contained Typo for year-to-date Value for Numbers of Hours Generator Was on Line (Service Hours) ML18107A3641999-06-0404 June 1999 Requests Enforcement Discretion for TS 3/4.6.2.3 Re Containment Cooling Sys for Salem Generating Station,Unit 1 ML18107A3561999-06-0303 June 1999 Informs That Nj Dept of Environ Protection Bureau of Nuclear Engineering Has Reviewed Pse&G License Change Request S99-05 & Has No Comments ML18107A3611999-05-27027 May 1999 Forwards Responses to NRC 990301 & 990323 RAIs for Salem & Hope Creek Generating Stations Relating to GL 96-05 ML18107A3301999-05-24024 May 1999 Forwards Suppl Info Re GL 95-07, Pressure Locking & Thermal Binding of Safety Related Power Operated Gate Valves. Encl Contains Methodology Used in Determination of Pressure Locking Susceptibility of PORVs Block Valves ML18107A3291999-05-20020 May 1999 Forwards Redacted Response to NRC 990322 RAI Re Notification of Licensed Operator That Tested Positive for Alcohol. Attachment 2 Withheld,Per 10CFR2.790(a)(6) ML18107A3031999-05-18018 May 1999 Provides Summary of Changes to NRC Commitments That Have Been Made But Not Reported by Other Means,Iaw with NEI Process for Managing NRC Commitments ML18107A2891999-05-13013 May 1999 Forwards Rev 36 to Pse&G Nuclear Business Unit Emergency Plan. Rev 36 Incorporates Changes to Section 1-3,6 & 7 & 9-17.Attached Copy Includes All Sections of EP for Completeness ML18107A2951999-05-12012 May 1999 Submits SG Tube Plugging Rept,Per Plant TS 4.4.6.5.a.Total of 47 Tubes Were Plugged During SG Tube Insps,Which Were Completed During Plant Tenth RFO ML18107A2861999-05-11011 May 1999 Forwards Rev 0 to NFS-0174, COLR for Salem Unit 2 Cycle 11. COLR Rept Was Received by Util as Part of Reload SE ML18107A2481999-04-29029 April 1999 Forwards 1998 Annual Radiological Environ Operating Rept for Salem & Hope Creek Generating Stations. Rept Summarizes Results of Radiological Environ Surveillance Program for 1998 ML18107A2511999-04-27027 April 1999 Submits 30-day Fuel Clad Temp Rept for Salem Generating Station,Units 1 & 2.Rept Describes Changes to Calculated Peak Clad Temp (PCT) for Plant Large & Small LOCA & Small Break LOCA Analyses ML18107A2371999-04-26026 April 1999 Forwards Corrected Response to NRC RAI Re Licensee Request for Change to TS Permissible Enrichment Values for New Fuel Storage.Incorrect Attachment Was Provided with Util 990412 Ltr to Nrc.Encl Supersedes 990412 Submittal ML18107A2631999-04-26026 April 1999 Provides Clarification on Licensing & Design Basis for 125 Vdc Battery Margins for Sgs & HCGS for Meeting SBO & Loca/ LOOP Loading Requirements ML18107A2411999-04-22022 April 1999 Forwards Draft Revised Pages 4.1 & 4.2 of Nuclear Business Unit Emergency Plan for Hope Creek & Salem Generating Stations.Changes Are Noted in Italics ML18107A1841999-04-14014 April 1999 Forwards PSEG Annual Rept for 1998, & PECO Annual Rept for 1998. Stockholders Annual Rept of Each Owner & Cash Flow Statements Showing 1998 Actual & 1999 Projected Cash Flow with Explanation Encl ML18107A1981999-04-12012 April 1999 Responds to 990312 RAI Re Request for Change to TSs Permissible Enrichment Values for New Fuel Storage,Which Was Submitted on 990202 ML18107A1691999-04-12012 April 1999 Forwards Proprietary & non-proprietary Epips,Including Rev 17 to EPIP 807,rev 1 to NC.EP-EP.ZZ-0801(Q) & Rev 2 to NC.EP-EP.ZZ-0806(Q) & Revised EPIPs Table of Contents. Proprietary Info Withheld ML20205K4541999-04-0808 April 1999 Forwards Revised Info Re 990330 NRC Nuclear Power Reactor Licensee Financial Qualifications & Decommissioning Funding Assurance Status Rept ML18106B1491999-04-0505 April 1999 Forwards Drafts of Proposed Changes to Pages 4.1 & 4.2 of Emergency Plan,Which Are Contained on Page 4.2 & Noted in Italics & Underlined ML20205F8981999-03-31031 March 1999 Provides Info Re Status of Decommissioning Funding for LGS, Units 1 & 2,PBAPS,Units 1,2 & 3 & Sgs,Units 1 & 2,per Requirements of 10CFR50.75(f)(1) ML18106B1431999-03-31031 March 1999 Forwards Pse&G Rept on Financial Min Assurance for Period Ending 981231 for Hope Creek,Salem,Units 1 & 2 & Pbaps,Units 2 & 3,IAW 10CFR50.75 ML18107A2201999-03-30030 March 1999 Forwards Final Exercise Rept for 980303,full-participation Plume Exposure Pathway Exercise & 980505-07, full-participation Ingestion Pathway Exercise of Offsite Radiological Emergency Response for Salem & Hope Creek 1999-09-08
[Table view] Category:UTILITY TO NRC
MONTHYEARML18095A4881990-09-17017 September 1990 Requests Regional Waiver of Compliance from Tech Spec 3.6.2.3, Containment Cooling Sys. Waiver Requested in Order to Allow Replacement of Containment Fan Cooler Unit Motor #22 W/O Requiring Plant Shutdown ML18095A4901990-09-13013 September 1990 Provides Supplemental Info Applicable to Clarification of 10CFR50,App R Exemption Request Re Fire Suppression Sys for Panel 335,per NRC Request ML20059E6821990-09-0404 September 1990 Forwards Info Re Temporary Mod to Security Plan Concerning Protected Area.Info Withheld ML18095A4641990-08-31031 August 1990 Forwards Revised Response to NRC Bulletin 88-004 Re Potential pump-to-pump Interaction.Util Pursuing Permanent Solution to Issue & Will Implement Appropriate Permanent Field Change by End of Unit 1 10th Refueling Outage ML18095A4621990-08-31031 August 1990 Provides Revised Response to Generic Ltr 89-13, Svc Water Problems Affecting Safety-Related Equipment. Only HXs Exhibiting Unsatisfactory Test Results Will Be Inspected & Possibly Cleaned ML18095A4431990-08-30030 August 1990 Forwards Salem Generating Station Semiannual Radioactive Effluent Release Rept,Jan-June 1990 & Rev 6 to Odcm. ML18095A4531990-08-30030 August 1990 Forwards RERR-28, Salem Generating Station Semiannual Radioactive Effluent Release Rept for Jan-June 1990 & Revised Odcm.W/O Revised ODCM ML18095A4391990-08-29029 August 1990 Forwards Semiannual Rept Re fitness-for-duty Performance Data for 6-month Period Ending 900630,per 10CFR26.71(d).Rept Includes Testing Results,Random Testing Program Results & Confirmed Positive Tests for Specific Substances ML18095A4421990-08-28028 August 1990 Clarifies 900710 Request for Amends to Licenses DPR-70 & DPR-75,changing Sections I & M.Under Proposed Change,Section I Should Be Changed to Read Section 2.J for License DPR-70 & Section M Changed to Read Section 2.N for License DPR-75 ML20059B6611990-08-22022 August 1990 Confirms That 10 Anchor/Darling Model S350W Swing Check Valves Installed at Plant,Per NRC Bulletin 89-002.All 18 Valves Inspected & Retaining Block Studs Replaced W/Upgraded Matl.No Crack Noted on Any Studs Which Were Replaced ML20059C2861990-08-21021 August 1990 Provides Correction to 900810 Response to Request for Addl Info Re Util Request for Restatement of OL Expiration Dates ML18095A4151990-08-10010 August 1990 Forwards Response to Request for Addl Info Re Reinstatement of OL Expiration Dates Based on Original Issuance of Ols. Advises That Correct Expiration Date for OL Proposed to Be 200418 ML18095A4091990-08-0909 August 1990 Forwards Responses to NRC Comments Re Plant Simulator Certification for 10CFR55.45(b)(2),per 891228 Ltr ML18095A4061990-08-0808 August 1990 Forwards Corrected marked-up Pages for Tech Spec Table 3.3-11 Re Subcooling Margin Monitor & Reactor Vessel Level Instrumentation Sys,Per 900223 Ltr.Administrative Changes Made as Indicated ML18095A3861990-07-30030 July 1990 Forwards Listing of Station Blackout Major Audit Items Resolution Scope,Per Station Blackout Schedule Commitment ML18095A3661990-07-26026 July 1990 Forwards Decommissioning Repts for Hope Creek,Peach Bottom & Salem Nuclear Generating Stations ML18095A3761990-07-26026 July 1990 Forwards Decommissioning Repts & Certification of Financial Assurance for Plants ML18095A3721990-07-24024 July 1990 Forwards Rept & Certification of Financial Assurance for Decommissioning for Plants,Per 10CFR50.75 ML18095A3751990-07-18018 July 1990 Provides Status of Commitments Made to NRC by Util in 900109 Ltr Re NUREG-0737,Item II.D.1,per 900628 Telcon ML18095A3741990-07-18018 July 1990 Provides Supplemental Info Re Facility sub-cooling Margin Monitor ML18095A3611990-07-18018 July 1990 Responds to NRC Bulletin 90-001, Loss of Fill-Oil in Transmitters Mfg by Rosemount. ML18095A3621990-07-18018 July 1990 Forwards Corrected Tech Spec Page 3/4 3-5 for License Change Request 89-12 Submitted on 891227 & 900521 ML18095A3591990-07-13013 July 1990 Corrects Typo in 900702 Response to Generic Ltr 90-04 Re Schedule for Completion of Remaining Open Items ML18095A3471990-07-11011 July 1990 Responds to NRC 900611 Ltr Re Violations Noted in Insp Repts 50-272/90-14 & 50-311/90-14.Corrective Actions:Directive from Radiation Protection Mgt to All Radiation Protection Personnel Issued Re Control of Compliance Agreement Sheets ML18095A3451990-07-10010 July 1990 Forwards Addl Info Re License Change Request 89-03 Re Reactor Trip Sys Instrumentation ML18095A3461990-07-10010 July 1990 Responds to NRC 900608 Ltr Re Violations Noted in Insp Repts 50-272/90-12 & 50-311/90-12.Corrective Actions:Assessment of ECCS & Component Performance Undertaken & ECCS Flow Testing Procedure Upgraded to Address Human Factors ML18095A3491990-07-10010 July 1990 Forwards Jn Steinmetz of Westinghouse 900614 Ltr Re Reassessment of Util Response to Bulletin 88-002 ML18095A3481990-07-10010 July 1990 Submits Supplemental Rept Identifying Root Cause of Missed Commitment & Corrective Actions to Assure Future Compliance Re Implementation of Mods to Facility PASS ML18095A3441990-07-0909 July 1990 Provides Written Notification Re Change in Calculated Peak Clad Temp,Per 900606 Verbal Notification ML18095A3281990-07-0202 July 1990 Responds to NRC 900530 Ltr Re Violations Noted in Insp Repts 50-272/90-09 & 50-311/90-09.Corrective Actions:Util Intends to Use Nuclear Shift Supervisor as Procedure Reader & EOP, Rev 2 Under Development ML18095A3301990-07-0202 July 1990 Responds to Generic Ltr 90-04 Re Status of Licensee Implementation of Generic Safety Issues.Table Describing Status of Generic Safety Issue Implementation Encl ML18095A3391990-06-29029 June 1990 Forwards Correction to 890913 License Change Request 88-09, Consisting of Tech Spec Page 3/4 4-13 ML18095A3221990-06-28028 June 1990 Provides Supplemental Info Re 900223 Proposed Revs to Tech Specs for Reactor Vessel Level Instrumentation Sys.Tables 3.3-11a & 3.3-11b Should Be Combined Into Single Table ML18095A3231990-06-28028 June 1990 Responds to NRC 900518 Ltr Re Violations Noted in Insp Repts 50-272/90-10,50-311/90-10 & 50-354/90-07.Two Noncited Violations Disputed.Util fitness-for-duty Program Exceeds Part 26 Requirements for Positive Blood Alcohol Limits ML18095A3241990-06-28028 June 1990 Forwards Retyped Pages to 871224 License Change Request 87-15 & Modified,Per 900620 Ltr ML18095A3211990-06-26026 June 1990 Requests 30-day Extension Until 900730 to Provide Completion Schedule to Resolve Audit Findings Re Station Blackout ML18095A3161990-06-25025 June 1990 Forwards Supplemental Info Re Response to Generic Ltr 88-14. All Committed Actions Complete as of 900613 ML18095A3141990-06-25025 June 1990 Provides Schedule Change for Implementation of Control Room Mods.Schedule Modified to Address Overhead Annunciator Human Engineering Discrepancies During Phase III ML18095A3201990-06-25025 June 1990 Responds to NRC 900524 Ltr Re Violations Noted in Insp Repts 50-272/90-11 & 50-311/90-11.Corrective Actions:All Overdue Operations & Maint Procedure Files Reviewed for Outstanding Rev Requests & Procedure Upgrade Program Initiated ML18095A3001990-06-20020 June 1990 Provides Addl Info Re Application for Amend to Licenses DPR-70 & DPR-75 Concerning Turbine Valve Surveillance Interval,Per 900320 Request.Util Adding Direction to Personnel If Unnacceptable Flaws Found ML20043H6221990-06-20020 June 1990 Provides Supplemental Info Re NRC Bulletin 88-008 for Fifth Refueling Outage.Detailed Test Rept Being Prepared to Document Results of Each Individual Insp Re Insulation, Hangers & High Energy Break Areas ML18095A2991990-06-20020 June 1990 Forwards Westinghouse Affidavit Supporting 900412 Request for Withholding Proprietary Info from Public Disclosure Per 10CFR2.790 ML18095A2721990-06-0808 June 1990 Responds to NRC 900329 Ltr Re Weaknesses Noted in Insp Repts 50-272/90-80 & 50-311/90-80.Corrective Actions:Fire Doors Placed on Blanket Preventive Maint Work Order & Damaged Fire Doors Will Be Repaired Immediately ML18095A2711990-06-0606 June 1990 Submits Info in Support of 900522 Verbal Request for Relief from Requirements of ASME Section XI ML18095A2611990-06-0101 June 1990 Forwards Corrected Operating Data Rept, Page for Apr 1990 Monthly Operating Rept ML18095A2521990-06-0101 June 1990 Forwards Application in Support of Request for Renewal of NJPDES Permit NJ0005622,per Requirements of Subsection 3.2 of Plant Environ Protection Plan,Nonradiological ML18095A2591990-06-0101 June 1990 Forwards Corrected Unit Shutdown & Power Reductions, Page for Apr 1990 Monthly Operating Rept ML18095A2411990-05-30030 May 1990 Submits Special Rept 90-4 Addressing Steam Generator Tube Plugged During Fifth Refueling Outage.Plugging Completed on 900516.Cause of Tube Degradation Attributed to Normal Wear Due to Erosion/Corrosion Factors ML18095A2431990-05-30030 May 1990 Informs of Util Plans Re Facility Cycle 6 Reload Core, Expected to Achieve Burnup of 16600 Mwd/Mtu.All Postulated Events within Allowable Limits Based on Review of Basis of Cycle 6 Reload Analysis & Westinghouse SER ML18095A2531990-05-29029 May 1990 Provides Addl Info Re End of Life Moderator Temp Coefficient.Feedback Used in Steam Line Break Has No Relationship to Full Power Moderator Density Coefficient 1990-09-04
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Public Service Electric and Gas Company Steven E. Miltenberger Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-4199 Vice President and Chief Nuclear Officer United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:
RESPONSE TO NRC ACCEPTANCE OF THE OFFSITE DOSE CALCULATION MANUAL, REV. 3 SALEM GENERATING STATION DOCKET NOS. 50-272 AND 50-311 Public Service Electric and Gas Company (PSE&G) hereby submits a revision to the ODCM in response to your letter dated June 24, 1988. Paragraph 2 of your cover letter requested a response to each point raised in the conclusion section of the Technical Specification Report (TER). Enclosed as Attachment 1 is the response you requested.
Should you have any questions regarding this submittal, please contact Mr. David Mohler at (609) 339-4546.
Sincerely, Attachment e901040013* aaf221-- -~-----
PDR ADOC~ 05000272. .
p PNU
- Document Control Desk 2 DEC 2 7 1988 w/o Attachment c Mr. J. c. Stone Licensing Project Manager Ms. K. Halvey Gibson, Acting Senior Resident Inspector Mr. w. T. Russell, Administrator Region I Ms. J. Moon, Interim Chief New Jersey Department of Environmental Protection Division of Environmental Quality Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625
' TER PART 4 - MAJOR DISCREPANCIES ITEM 1.
It was requested that the 'SFp' seasonal correction factor (0.5) used in Equation 2.11 of the ODCM be "adjusted to agree with that fraction of a quarter when the 0.5 factor is applicable."
The purpose of the SFp factor is to adjust for that half of the year when milch animals are provided feed from stored vegetation.
During this half of a year (November thru April) the milch animals do not graze. So as not to grossly overestimate the dose from the possible release of radioiodines and particulates during this non-grazing time period, the average dose is calculated.
The SFp factor provides the means for an average dose for the grass-cow-milk and vegetation pathways throughout the year.
This correction factor was considered adequate in discussions with the Nuclear Regulatory Commission. This average dose was considered to be within the errors of the dose calculation methods provided in NUREG-0133 and Reg. Guide 1.109.
We feel the SFp correction factor is adequate and that no adjustment is necessary to Equations 2.11 and 2.12 of the Salem ODCM.
ITEM 2.
It was requested that the calculated organ dose equation in Section 2.5.1 (Equation 2.11) be clarified to mean the dose due to all pathways not just the controlling pathway.
In Revision 5 of the Salem ODCM the definition of Dao in Equation 2.11 was changed from "dose or dose commitmeRt via controlling pathway p and age group a (as identified in Table 2-4) .. "to "dose or dose commitment via all pathways p and controlling age group a (as identified in Table 2-4) .* ".
ITEM 3.
The definition of the term CW in Equation 1.5 was requested to be changed from " .. release period" to " .. reporting period".
NUREG-0133 describes the equivalent (dilution flow) as "the near field average dilution factor during any liquid effluent release." Reg. Guide 1.21 reporting requirements define the term as the "Average stream flow during periods of release .. " (NOTE: stream (dilution) flow is considered to be the circulating water system, no credit is taken for additional Delaware River dilution). It is our interpretation the dilution flow during a liquid release's release period is .reported, not 1
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ITEM 3 (cont'd).
the' dilution flow over the entire reporting period. The term
'reporting period' is interpreted to mean over an entire quarter.
Changing to this requested definition could be interpreted to mean liquid releases are being made continuously at Salem sta-tion. As well, the dose calculations under this definition would be grossly underestimated and the volume of dilution water reported grossly overestimated.
Based on our interpretation of NUREG-0133 and Reg. Guide 1.21 the definition of cw is appropriate as currently written.
TER PART 4 - ADDITIONAL DISCREPANCIES ITEM 1.
The reference to the tables was corrected from Table 2-1 and Table 2-2 to Table 2-2 and Table 2-3 respectively in section 2.2.2.
ITEM 2.
It was questioned as to why Table 2-4 does- not identify the child-vegetation pathway as discussed in section 2.5.1, last paragraph.
The last paragraph of section 2.5.1 states; "For evaluating the maximum exposed individual, the infant age group is controlling for the milk pathway and the child age group is controlling for the vegetation pathway. "Only the controlling age group and pathway as identified in Table 2-4 need be evaluated for compli-ance with Technical Specification 3.11.2.3."
In Table 2-4 the pathways listed for radioiodines and particulates are the infant-milk and ground pathway for an unrestricted area (residence/dairy) and the child-inhalation pathway at the site boundary. These locations and pathways are taken from the Safety Evaluation Report, Supplement No. 3 for the Salem Generating Station, Unit 2 NUREG-0517, December 1978, pages 11-6 to 11-8 and Table 11.6. NUREG-0517 considered the maximum exposed individual for the unrestricted area to be the infant-milk pathway from a cow grazing location 4.8 miles NNE of the vent. Since there is no edible vegetation and no dairy farm located at or near the site boundary NUREG-0517 listed the child-inhalation pathway to be the controlling pathway of the site boundary, not the child-vegetation.
In summary, the child-vegetation pathway is not included in 2
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ITEM 2 (cont'd).
Tabie 2-4 because it is not the limiting dose pathway for Salem's site boundary or unrestricted area. The limiting pathways are the child-inhalation at the site boundary and infant-milk for the unrestricted area per NUREG-0517. There are no vegetation nor milk pathways at the site boundary. The statement; "** and the child age group is controlling for the vegetation pathway." has been removed from Section 2.5.1 in Revision 4 of the Salem ODCM.
ITEM 3.
It was requested that the units of the term W in section 2.5.2 be corrected.
The units of the term W in section 2.5.2 were corrected from 1/m to 1/m2 .
ITEM 4.
It was requested that some additions be made to definitions in Equation 2.16.
The following additions were made to Equation 2*16 on page 27 of the ODCM; the definition of 0.13 was added and the subscript i was added for the term PF.
Since the equation, as defined by the term Qi*, is the release rate of a single pathway j then no su~script j need be added to the summation sign in the equation.
ITEM 5.
It was noted that a simplified diagram illustrating the solid waste treatment system was not included.
Figure 1-3, which may have inadvertently been omitted from the distribution to the NRC, is included in this revision.
ITEM 6.
It was noted that some dose conversion factors within Table 2-5 of the ODCM needed to be checked for correctness.
These values were recalculated using NuReg-0133 and Reg Guide 1.109 and compiled below. There were some discrepancies between the ODCM and the correct values. The latest revision of the ODCM reflects the corrections to these discrepancies.
The results of the comparison is below:
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ITEM 6 (cont'd)
- Equation 1 for inhalation pathway dose conversion factors P = K(BR) DFA = 1E6
p = dose rate conversion factor K = unit conversion = 1E6 pCi/uCi BR = breathing (m 3 /yr) rate of group from R.G. 1.109 Table E-5 DFA = dose factor from Reg. Guide 1.109 Table E-7 to E-10 PATHWAY: Inhalation Path Isotope BR DFA p ODCM #
Teen-lung Ag-llOm 8000 8.44E-04 6.75E5 6.75E5 Teen-lung Te-125m 8000 6.70E-05 5.36ES 5.36ES Child-liver Rb-86 3700 5.36E-05 1.98ES 1.98ES Infant-lung Fe-59 1400 7.25E-04 1.01E6 1.02E6 Based on our calculations the numbers in the ODCM are correct and do not need to be changed.
Equation 2 for cow-milk (food) dose conversion factors:
Q (U)
P = K r --------- (ref. NuReg-0133, p. 26) where:
p = dose rate conversion factor K = unit conversion = 1E6 pCi/uCi Q = cow's consumption rate from R.G. 1.109 Table E-3 =SO u = food consumption rate from R.G. 1.109 Table E-5 y = agricultural productivity from R.G. i.109 Table E-15
= 0.7 for grass-cow-milk-man pathway F = stable element coefficients from R.G. 1.109 Table E-1 r = fraction of deposited activity retained on crops
= 1 for iodines, 0.2 for others from R.G. 1.109 Table E-15 DFL = maximum organ ingestion dose factor from Table E-11 to E-14 Ai = decay constant for radionuclide of concern (sec-1)
""'Aw = decay constant for removal of activity from leak and plant surfaces by weathering= 5.73E-7 sec-1 t = transport time from pasture to cow, milk, person from Table E-15 = 1.73ES secs 4
salem odcm
ITEM 6 (cont'd).
With all the constants multiplied the above equation for isotopes other than radio-iodines reduces to:
1.43E7 * (U)
- 1.73E5) p = -----------------------------------------
(ft_+ 5.73E-7)
The above equations were then utilized to calculate the dose factors for the isotopes, pathways and organs listed in the NRC review:
PATHWAY: Grass-Cow-milk organ Isotope ---=-F__ _y_ DFL p ODCM #
Adult-Liver Rb-86 4.30E-7 3.0E-2 310 2.llE-5 2.59E9 1. 35E5 Adult-T.Body Rb-86 4.30E-7 3.0E-2 310 9.83E-6 1. 21E9 5.90E4 Adult-GI-LL! Rb-86 4.30E-7 3.0E-2 310 4.16E-6 5.11E8 l.66E4 The conversion factors in the ODCM have been corrected in this revision.
Adult-Bone Zr-95 1. 22E-7 5.0E-6 310 3.04E-8 9.46E2 1. 07E5 Adult-Liver Zr-95. 1.22E-7 5.0E-6 310 9.75E-9 3.03E2 3.44E4 Adult-T.Body Zr-95 1.22E-7 5.0E-6 310 6.60E-9 2.05E2 2.33E4 Adult-Kidney zr-95 1. 22E-7 5.0E-6 310 1.53E-8 4.76E2 5.24E4 Adult-GI-LL! Zr-95 1. 22E-7 5.0E-6 310 3.09E-5 9.62E5 1.50E5 The conversion factors in the ODCM have been corrected in this revision.
Adult-Bone Nb-95 2.29E-7 2.5E-6 310 6.22E-9 8.25E4 1. 41E4 Adult-Liver Nb-95 2.29E-7 2.5E-6 310 3.46E-9 4.59E4 7.82E3 Adult-T.Body Nb-95 2.29E-7 2.5E-6 310 1.86E-9 *2.47E4 4.21E3 Adult-Kidney Nb-95 2.29E-7 2.5E-6 310 3.42E-9 4.54E4 7.74E3 Adult-GI-LL! Nb-9 2.29E-7 2.5E-6 310 2.lOE-5 2.79E8 1.04E5 The conversion factors in the ODCM have been corrected in this revision.
Teen-Bone Ce-141 2.47E-7 1. OE-4 400 1.33E-8 8.87E3 1. 99E4 Teen-Liver Ce-141 2.47E-7 1. OE-4 400 8.88E-9 5.92E3 1.35E4 Teen-T.Body Ce-141 2.47E-7 1. OE-4 400 1.02E-9 6.81E2 1.53E3 Teen-Kidney Ce-141 2.47E-7 1. OE-4 400 4.18E-9 2.79E3 6.26E3 Teen-GI-LL! Ce-141 2.47E-7 1. OE-4 400 2.54E-5 1.69E7 1. 20E5 The conversion factors in the ODCM have been corrected in this revision.
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ITEM 6 (cont'd)~
PATHWAY: Grass-Cow-milk (cont'd)
Organ Isotope Ai ---=-F- _!L DFL P ODCM #
Teen-Liver Ba-140 6.27E-7 4.0E-4 400 3.48E-8 5.95E4 5.95E4 Based on our calculations the numbers in the ODCM are correct and do not need to be changed.
For radio-iodines the factor 1.43E7 in Equation 3 above becomes 7.14E7 because the factor r = 1.
PATHWAY: Grass-Cow-milk (cont'd)
Organ Isotope "i F _!L DFL p ODCM #
Teen-Bone I-131 9.97E-7 6.0E-3 400 5.85E-6 5.38E8 5.38E8 Teen-Liver I-131 9.97E-7 6.0E-3 400 8.19E-6 7.53E8 7.53E8 Teen-T.Body I-131 9.97E-7 6.0E-3 400 4.40E-6 4.04E8 4.04E8 Teen-Thyroid I-131 9.97E-7 6.0E-3 400 2.39E-3 2.20Ell 2.20Ell Teen-Kidney I-131 9.97E-7 6.0E-3 400 1.41E-5 1. 30E9 1. 30E9 Teen-GI-LL! I-131 9.97E-7 6.0E-3 400 1.62E-6 1. 49E8 1. 49E8 Based on our calculations the numbers in the ODCM are correct and do not need to be changed.
Child-Bone Y-91 1. 36E-7 l.OE-5 330 6.02E-7 3.91E4 9.14E5 Child-T.Body Y-91 l.36E-7 1.0E-5 330 1.61E-8 1.04E3 2.44E4 Child-GI-LL! Y-91 1. 36E-7 1. OE-5 330 8.02E-5 5.21E6 l . 84E5 The conversion factors in the ODCM have been corrected in this revision.
PATHWAY: Vegetation Organ Isotope ~i B _!L DFL p ODCM #
Child-Bone Ce-141 2.47E-7 l.OE-4 520 2.0SE-6 1. 27E8 1.27E8 Child-Liver Ce-141 2.47E-7 1.0E-4 520 6.52E-7 3.98E7 3.98E7 Child-T.Body Ce-141 2.47E-7 1.0E-4 520 1.llE-7 6.78E6 6.78E6 Child-Kidney Ce-141 2.47E-7 l.OE-4 520 3.61E-7 2.21E7 2.21E7 Child-GI-LL! Ce-141 2.47E-7 l.OE-4 520 1.74E-4 1.04E10 1.04E10 Based on our calculations the numbers in the ODCM are correct and do not need to be changed.
The dose conversion factors listed in the ODCM are used in the RETSCode computer program at Salem. The RETSCode program 6
salem odcm
ITEM 6 (cont'd) is used for effluent release permits and generating the semi-annual report. A comparison was also done between the correct values calculated below and the RETSCode values. No discrepancies were found. In other words, the computer program used to determine dose per the ODCM has had the correct dose conversion factors while the Salem ODCM did not.
None of the isotopes with incorrect dose conversion factors below has been released from Salem Units 1 and 2.
ITEM 7.
It was requested that the term 'D' in Equations C.5 thru C.8 in the ODCM be properly subscripted.
These terms have been properly subscripted in this revision of the ODCM (Appendix c, page C-4).
ITEM 8.
It was requested that the dose rate conversion factor for
.I-131 to the thyroid of the infant on page D-2 of Appendix D be corrected from 1.675E12 to 1.05E12.
This dose rate conversion factor has been corrected from 1.675E12 to 1.05E12 in this revision of the ODCM (page D-3).
ITEM 9.
There was a request for clarity on the words "particulate radio-iodines" on page D-3 of Appendix D.
This term has been corrected from "particulate radio-iodines" to "particulates" in this revision of the ODCM.
ITEM 10.
It was questioned as to whether Table E-1 in the ODCM indicated three air sample locations near the site.
Salem Technical Specification Table 3.12-1 requires 3 airborne samples close to the site location.
Artificial Island, which is the site location of Salem Units 1 and 2, is surrounded by United States Wetlands and abuts the Delaware River. There is only one access road to the site and the nearest resident is 3.4 miles away. Due to the isolation of the site it is difficult to locate many air sample stations near the site because of little access to power supplies. As well, considering the use of the nearby wetlands, the cost for placing an air sampling station 7
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ITEM 10 (cont'd) in these wet lands is not justified. Thus, it is our opinion that the locations of 5Sl, 5Dl and 16El fulfill the requirements of Technical Specification Table 3.12-1. The latest revision of the ODCM indicates all the air sample sites as:
5Sl - 1.0 miles E of vent 5Dl - 3.5 miles E of vent 16El - 4.1 miles NNW of vent lFl - 5.8 miles N of vent 2F2 - 8.7 miles NNE of vent (control location)
ITEM 11.
It was noted that Table E-1 does not include any drinking water locations, food product sample stations for crops grown with water affected by the liquid effluents, a surface water sampling location at the outfall, or a sediment sampling location at the outfall as required by Technical Specification Table 3.12-1.
The nearest public water supply is more than 30 miles upstream of the site. We believe the intent of the Technical Specification was to sample drinking water supplies that could be directly effected by a nuclear generating stations liquid effluents.
The Delaware River, at our discharge point, is brackish water. There are no direct effects on drinking water supplies. The water supply in and around the site of Salem Units 1 and 2 is well water. In the radiological environmental moni-toring program there are 2 well water sample locations - 5Dl, 3.5 miles E of vent, and 3El, 4.1 miles NE of vent. Thus, the well water sample locations fulfill the requirements of Technical Specification, Table 3.12-1.
Due to the brackish water there is no irrgation dowstream of Salem Station. There are no crop samples available which use the Delaware River for irrigation.
There are five surface water samples taken from the Delaware River:
llAl - 0.2 miles W of vent (outfall area) 12Cl - 2.5 miles WSW of vent (cross-stream) 7El - 4.5 miles SE of vent 1F2 - 7.1 miles N of vent 16Fl - 6.9 miles NNW of vent Location llAl takes the samples from the outfall area of liquid effluents. Location 12Cl takes samples across the river from the outfall area. Since the Delaware River is a 8
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ITEM 11 (cont'd) tidal river the rest of the sample locations satisfy both of the required up-stream and down-stream locations.
At the location llAl there is a sediment sample obtained.
All of these locations are indicated in the enclosed revision 5 of the Salem ODCM on Table E-1. The last revisions (Revision 3 and 4) also lists these same sample locations on Table E-1.
ITEM 12.
It was noted that Figures 1-1, 1-2, 1-3, 2-1, 2-2, and E-1 were illegible.
In the last revision of the Salem ODCM (Rev. 4) Figures 1-1, 1-2, and E-1 were improved upon and are included in this revision. Figures 1-3, 2-1 and 2-2 are currently being improved upon and should be included in Revision 6 of the Salem ODCM. These were not included in Revision 5 due to current design changes being implemented.
TER PART 4 - SUGGESTIONS ITEM 1.
It was recommended that the use of the term Ci be limited to the accepted use as the unit for curies and that another symbol be used for concentrations throughout the document.
It was also recommended the use of the terms c and C should be reviewed to determine if better terms could be used to avoid confusion in some equations.
We agree that the terms 'Ci' (used in all equations section 1 of the ODCM), 'c' and 'C' (Equation 1.1) should be changed to eliminate any confusion. As well, the terms* 'f' and 'F' (Equation 1.1) should also be changed. However, the terms
'c','C','f' and 'F' were all adapted directly from the first equation in the addendum of NuReg-0133.
To reduce some of the confusion in the terms used in the equation from NuReg-0133 we redefined the terms c,f and F in the Salem ODCM. We feel, however the term Ci was adequate enough for defining the number of uCi/ml (concentration). To change this term in the ODCM would also require revisions to many procedures which utilize the same terms. It is our opinion that there is need to change the term Ci.
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ITEM 2.
It was suggested that the term Ci include the definition of undiluted concentration instead of just concentration.
We have included this suggestion in Section 1.2.1 of Revision 5 of the Salem ODCM.
ITEM 3.
It was recommended that a low level alarm setpoint be considered for the liquid effluent monitors.
All the liquid effluent monitors for Salem station have a "warning" alarm setpoint which is administratively set at 50%
of the alarm setpoint. Where as this is not a required feature for effluent monitors and there is no documented guidelines for a "low level alarm" setpoint the "low level alarm" or warning setpoints are not included in the Salem ODCM.
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