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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217M7571999-10-22022 October 1999 Advises That Attachment 1 to ,Marked as Proprietary,Re Safety Limit MCPR & Fuel Vendor Change Will Be Withheld from Public Disclosure Per 10CFR2.790(b)(5) ML20217M2101999-10-19019 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 ML20217H8471999-10-18018 October 1999 Discusses Completion of Licensing Action for GL 98-01 & Suppl 1, Yr 2000 Readiness of Computer Sys at Npps, to All Holders of Operating Licenses for NPPs 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 ML20217K8441999-10-15015 October 1999 Submits Revised Commitment to NRC Bulletin 90-01,Suppl 1 for Hope Creek Generating Station ML20217H9771999-10-13013 October 1999 Forwards SRO & RO Initial Exam Rept 50-354/98-302,suppl Rept on 990125-29,mtg Meeting on 990322,990429-30 & 0617-18 in-office Review & 990720 Telcon on Appeal Results.Overall, 11 of 16 Applicants Received NRC Licenses 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 ML20217C4391999-10-0606 October 1999 Informs That Util Authorized to Administer Initial NRC Retake Written Exam to Applicant Listed,During Week of 991011 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 ML20217A9601999-10-0404 October 1999 Forwards Errata Redressing Deficiencies & Correcting Two Typos to Ufsar,Rev 10.Incorporate Attached Pages/Figures Into Controlled Copies of UFSAR ML20217A6861999-10-0101 October 1999 Forwards Insp Rept 50-354/99-05 on 990711-0829.Four Violations Occurred Re Areas of Fire Protection,Operation at Reduced Feedwater Inlet Temp & safety-related Battery Charging Operation & Being Treated as NCVs LR-N990430, Forwards Rev 10 to Hope Creek Generating Station Ufsar,Iaw 10CFR50.71(e).Details Re Each Change Also Attached to Facilitate NRC Review1999-09-28028 September 1999 Forwards Rev 10 to Hope Creek Generating Station Ufsar,Iaw 10CFR50.71(e).Details Re Each Change Also Attached to Facilitate NRC Review 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 05000354/LER-1999-009, Forwards LER 99-009-00, License Condition Violation - Min FW Temp Limits. Commitments Made by Util Encl1999-09-20020 September 1999 Forwards LER 99-009-00, License Condition Violation - Min FW Temp Limits. Commitments Made by Util Encl ML20217K7781999-09-16016 September 1999 Forwards Discharge Monitoring Rept for Hope Creek Generating Station for Month of 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 ML20212B4021999-09-13013 September 1999 Submits Supplemental Info Related to Hope Creek License Change Request (LCR) H98-08,submitted to NRC on 981230, Re Flood Protection TS Changes 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 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 ML20211N5421999-09-0808 September 1999 Forwards Amend 121 to License NPF-57 & Safety Evaluation. Amend Revises TSs by Relocating Procedural Details of RETS to Offsite Dose Calculation Manual LR-N990395, Provides Comments on NRC Ltr Dtd 990714, Closure of TAC Number MA1194 - Response to RAIs to GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity, for Hope Creek Generating Sation. Revised GE Report Encl Also1999-09-0101 September 1999 Provides Comments on NRC Ltr Dtd 990714, Closure of TAC Number MA1194 - Response to RAIs to GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity, for Hope Creek Generating Sation. Revised GE Report Encl Also 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 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 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 ML20211B5341999-08-20020 August 1999 Forwards RAI Re 2nd 10-yr ISI Interval Relief Requests Re Plant.Info Requested to Be Provided within 60 Days of Receipt of Ltr 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 ML20210R4911999-08-11011 August 1999 Forwards Insp Rept 50-354/99-04 on 990530-0711.No Violations Noted.Inspectors Reviewed Performance Indicators Submitted as Part of Pilot Program for New Regulatory Oversight Process & Verified Data 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 ML20210H9241999-07-26026 July 1999 Informs That State of Nj Dept of Environ Protection Has No Comments on Licensee 990517 Request for Amend to TS by Adding TS 3.3.10, Instrumentation of OPRM Sys ML20210F3271999-07-22022 July 1999 Forwards SE Granting Relief Requests RR-B1,RR-C1,RR-D1 & RR-B3 Re First 10-year Interval for ISI Program at Hope Creek 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 ML20210D3971999-07-16016 July 1999 Forwards Discharge Monitoring Rept for Hope Creek Generating Station, for June 1999.Rept Is Required by & Prepared for EPA & Nj Dept of Environ Protection 05000354/LER-1999-007, Forwards LER 99-007-00,re License Condition Violation - Class-1E Battery Charging Operation.Commitments Made by Util Encl1999-07-14014 July 1999 Forwards LER 99-007-00,re License Condition Violation - Class-1E Battery Charging Operation.Commitments Made by Util Encl ML20209G2831999-07-14014 July 1999 Disclosure Closure of TAC MA1194 Re Licensee Response to RAI to GL 92-01,Rev 1,Suppl 1, Rc Structural Integrity, for Plant LR-N990250, Provides Proposed Alternative & Supporting Justification for Relief from Augmented Inservice Requirements of 10CFR50.55a(g) for Volumetric Exam of RPV Circumferential Welds1999-07-0909 July 1999 Provides Proposed Alternative & Supporting Justification for Relief from Augmented Inservice Requirements of 10CFR50.55a(g) for Volumetric Exam of RPV Circumferential Welds 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 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 ML20217K8441999-10-15015 October 1999 Submits Revised Commitment to NRC Bulletin 90-01,Suppl 1 for Hope Creek Generating Station 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 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 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 ML20217A9601999-10-0404 October 1999 Forwards Errata Redressing Deficiencies & Correcting Two Typos to Ufsar,Rev 10.Incorporate Attached Pages/Figures Into Controlled Copies of UFSAR LR-N990430, Forwards Rev 10 to Hope Creek Generating Station Ufsar,Iaw 10CFR50.71(e).Details Re Each Change Also Attached to Facilitate NRC Review1999-09-28028 September 1999 Forwards Rev 10 to Hope Creek Generating Station Ufsar,Iaw 10CFR50.71(e).Details Re Each Change Also Attached to Facilitate NRC Review ML18107A5341999-09-22022 September 1999 Provides Data Re Operator Licensing Exam for Salem & Hope Creek Station,In Response to NRC Form 536 (7-1999) 05000354/LER-1999-009, Forwards LER 99-009-00, License Condition Violation - Min FW Temp Limits. Commitments Made by Util Encl1999-09-20020 September 1999 Forwards LER 99-009-00, License Condition Violation - Min FW Temp Limits. Commitments Made by Util Encl 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 ML20212B4021999-09-13013 September 1999 Submits Supplemental Info Related to Hope Creek License Change Request (LCR) H98-08,submitted to NRC on 981230, Re Flood Protection TS Changes 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 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 LR-N990395, Provides Comments on NRC Ltr Dtd 990714, Closure of TAC Number MA1194 - Response to RAIs to GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity, for Hope Creek Generating Sation. Revised GE Report Encl Also1999-09-0101 September 1999 Provides Comments on NRC Ltr Dtd 990714, Closure of TAC Number MA1194 - Response to RAIs to GL 92-01,Rev 1,Suppl 1, Reactor Vessel Structural Integrity, for Hope Creek Generating Sation. Revised GE Report Encl Also 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 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 ML20210H9241999-07-26026 July 1999 Informs That State of Nj Dept of Environ Protection Has No Comments on Licensee 990517 Request for Amend to TS by Adding TS 3.3.10, Instrumentation of OPRM Sys 05000354/LER-1999-007, Forwards LER 99-007-00,re License Condition Violation - Class-1E Battery Charging Operation.Commitments Made by Util Encl1999-07-14014 July 1999 Forwards LER 99-007-00,re License Condition Violation - Class-1E Battery Charging Operation.Commitments Made by Util Encl LR-N990250, Provides Proposed Alternative & Supporting Justification for Relief from Augmented Inservice Requirements of 10CFR50.55a(g) for Volumetric Exam of RPV Circumferential Welds1999-07-0909 July 1999 Provides Proposed Alternative & Supporting Justification for Relief from Augmented Inservice Requirements of 10CFR50.55a(g) for Volumetric Exam of RPV Circumferential Welds 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 LR-N990316, Responds to NRC Request for Info Re Y2K Readiness at Npps, Per GL 98-01,suppl 1.Disclosure Encl1999-06-30030 June 1999 Responds 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 ML20209B6441999-06-21021 June 1999 Offers No Comments on Licensee 990529 Request for Revs to Plant Radiological Effluent Ts,Per GL 89-01 ML20196E6471999-06-21021 June 1999 Forwards Revised marked-up TS Page for HCGS License Change Requests H99-02 & H99-05,dtd 990329 & 0524,respectively. Revised Pages Do Not Alter Conclusions Reached in 10CFR50.92 No Significant Hazards Analysis Previously Submitted ML20196E9631999-06-17017 June 1999 Informs That Util Has Made Change to Commitment Stated in NRC Ser,Suppl 5.Commitment That Has Been Changed Is Item Number 1 of First Paragraph on Page 9-3 of Ser,Suppl 5 LR-N990295, Submits Change 1 to Relief Request RR-A4,which Clarifies Requirements Re Snubber Visual Insps.Request Was Submitted as Part of Plant Second Interval ISI Program on 9905111999-06-16016 June 1999 Submits Change 1 to Relief Request RR-A4,which Clarifies Requirements Re Snubber Visual Insps.Request Was Submitted as Part of Plant Second Interval ISI Program on 990511 05000354/LER-1999-006, Forwards LER 99-006-00 Re Esfa B Channel Primary Containment Isolation Signal Actuation.Attachment a Lists Commitments Util Making to NRC Re LER1999-06-15015 June 1999 Forwards LER 99-006-00 Re Esfa B Channel Primary Containment Isolation Signal Actuation.Attachment a Lists Commitments Util Making to NRC Re LER 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 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 ML20059H5391990-09-10010 September 1990 Forwards Data Re Bailey Solid State Logic Modules (Sslm) Reliability Program for Period Ending June 1990.Quarterly Summaries of Sslm Data Will Be Provided to End of June 1991 ML20059E6821990-09-0404 September 1990 Forwards Info Re Temporary Mod to Security Plan Concerning Protected Area.Info Withheld ML20059E6791990-09-0404 September 1990 Forwards Security Upgrade Project Status Rept,Per Regulatory Effectiveness Review.Rept Withheld (Ref 10CFR73.21) 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 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 ML20059D2531990-08-30030 August 1990 Forwards Hope Creek Generating Station Semiannual Radioactive Effluent Release Rept RERR-9 for Jan-June 1990 & Rev 11 to ODCM for Hope Creek Generating Station ML20059E7021990-08-30030 August 1990 Forwards RERR-9, Hope Creek Generating Station Semiannual Radioactive Effluent Release Rept for Jan-June 1990 & Rev 11 to Odcm.Summary of Change to ODCM & Rationale Provided in Part G of RERR-9.W/o Rev 11 to ODCM 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 ML20059D2191990-08-27027 August 1990 Provides Change to Schedule for Implementing Generic Ltr 88-11.Revised pressure-temp Curves Will Be Submitted Prior to Completion of Second Refueling Outage.Existing pressure- Temp Curves Conservative to 32 EFPY ML20059C3051990-08-24024 August 1990 Notifies of Minor Structural Enhancements to Spent Fuel Racks Issued by Util 891101 Proposed Change to Tech Spec 5.6.3 ML20059D2491990-08-24024 August 1990 Requests Regional Waiver of Compliance from Tech Specs 4.0.3 & 4.8.1.1.2.f.2.Waiver Allows Sufficient Time to Perform Surveillance Requirement W/O Requiring Unit Shutdown.Request Involves No Irreversible Environ Consequencies 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 ML18095A3761990-07-26026 July 1990 Forwards Decommissioning Repts & Certification of Financial Assurance for Plants ML18095A3661990-07-26026 July 1990 Forwards Decommissioning Repts for Hope Creek,Peach Bottom & Salem Nuclear Generating Stations ML18095A3721990-07-24024 July 1990 Forwards Rept & Certification of Financial Assurance for Decommissioning for Plants,Per 10CFR50.75 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 ML18095A3741990-07-18018 July 1990 Provides Supplemental Info Re Facility sub-cooling Margin Monitor 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 ML20055G1571990-07-17017 July 1990 Requests Waiver of Compliance from Tech Spec 6.3.1 Re Requirement That Facility General Manager (Gm) Hold Senior Operator License.Waiver Will Temporarily Allow Individual to Fill Position While Gm Attends off-site Mgt Program 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 ML20055G4721990-07-11011 July 1990 Requests Extension Until Sept 1990 to Submit Level 1 Analysis,Per Generic Ltr 88-20 Re Individual Plant Exam Completion 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 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 ML18095A3491990-07-10010 July 1990 Forwards Jn Steinmetz of Westinghouse 900614 Ltr Re Reassessment of Util Response to Bulletin 88-002 ML18095A3451990-07-10010 July 1990 Forwards Addl Info Re License Change Request 89-03 Re Reactor Trip Sys Instrumentation ML18095A3441990-07-0909 July 1990 Provides Written Notification Re Change in Calculated Peak Clad Temp,Per 900606 Verbal Notification ML20055E5181990-07-0303 July 1990 Suppls Request for Noncode Temporary Repair of Svc Water Sys.Ultrasonic Exam of Area Surrounding Patch Will Include Samples,In Accessible Areas,Out to Diameter of 14 Inches 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 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 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 ML20055D0351990-06-26026 June 1990 Forwards Addl Info Re Svc Water Sys Noncode Temporary Repair,Per 900621 Application.Util Will Perform Ultrasonic Testing of Pipe Wall Adjacent to Fillet Weld Repair & on Patch.Insps Will Be Performed at 90-day Intervals ML18095A3211990-06-26026 June 1990 Requests 30-day Extension Until 900730 to Provide Completion Schedule to Resolve Audit Findings Re Station Blackout 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 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 1990-09-04
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Public Service Electric and Gas Company Thomas M. Crimmins, Jr. Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-4700 Vice President - Nuclear Engineering JUL 1 8 1990 NLR-N90149 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:
RESPONSE TO BULLETIN 90-01 SALEM AND HOPE CREEK GENERATING STATIONS DOCKET NOS. 50-272, 50-311 AND 50-354 Public Service Electric and Gas Company (PSE&G) hereby forwards ~
requested information in response to Bulletin 90-01 "Loss of Fill-Oil in Transmitters Manufactured by Rosemount." Enclosure 1 details the actions taken by PSE&G to* address the subject bulletin, and Attachments 1 and 2 provide the requested data. If you have any questions regarding this.response, please do not hesitate to call.
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Attachments 9007240013 900718 PDR ADOCK 05000272 Ci PDC
Document Control Desk 2 -
NLR-N90149 JUL 1 8 .1990 C Mr. J. C. Stone Licensing Project Manager - Salem Mr. c. Y. Shiraki Licensing Project Manager - Hope Creek Mr. T. Johnson Senior Resident Inspector Mr. T. Martin, Administrator Region I Mr. Kent Tosch, Chief New Jersey Department of Environmental Protection Division of Environmental Quality Bureau of Nuclear Engineering CN 415 .
Trenton, NJ 08625
ENCLOSURE I. Bulletin 90-01 requests that power reactor licensees provide/implement the following actions within 120 days of receipt:
A. CONFIRM THAT THE FOLLOWING ACTIONS HAVE BEEN COMPLETED:
- 1. Identify Model 1153 Series B, 1153 Series D, and Model 1154 pressure or differential pressure transmitters, excluding Model 1153 Series B, 1153 Series D, and Model 1154 transmitters manufactured by Rosemount subsequent to July 11, 1989, that are currently utilized in either safety-related systems* or systems installed in accordance with 10CFR50.62 (the ATWS rule).
RESPONSE
All Rosemount Model 1153 Series B, D and Model 1154 pressure or differential pressure transmitters installed at, Salem and Hope Creek Generating Stations have been identified and documented in a computerized database maintained at each station. There are 266 of these transmitters in service at Hope Creek, 117 at Salem Unit 1, and 120 at Salem Unit 2.
- 2. Determine whether any transmitters identified in Item 1 are from the manufacturing lots that have been identified by Rosemount as having a high failure fraction due to loss of fill-oil. Addressees are requested not to utilize transmitters from these suspect lots in the reactor protection or engineered safety features actuation systems; therefore, addressees are requested to develop and implement a program to replace, at the earliest appropriate opportunity, transmitters from these suspect lots in use in the reactor protection or engineered safety features actuation systems.
RESPONSE
Prior to the issuance of Bulletin 90-01 there were 63 transmitters installed at Hope Creek, 2 at Salem Unit 2 and none at Salem Unit 1 from the manufacturing lots identified by Rosemount as having a high failure rate due to loss of fill-oil.
One of the Salem 2 transmitters was replaced as scheduled in May 1990. Three of the Hope Creek transmitters were replaced in March 1990 to initiate the replacement program. One other transmitter at Hope Creek was later identified as showing unacceptable symptoms of oil loss and replaced. There remain 59 transmitters from the suspect lots at Hope Creek and one at Salem 2.
NLR-N90149
The breakdown of these transmitters is as follows:
Hope Creek Transmitters in control circuits for RPS, ESF, or ATWS systems:
28 units in "Pressurized Service" - (transmitters which are normally or intermittently operated above atmospheric pressure) 14 units in "Atmospheric Pressure Service" - (transmitters which are operated at or below atmospheric pressure except for a possibility of a brief exposure to 60 psi during a Design Basis Accident)
Transmitters associated with Reactor Protection, ESF or ATWS systems but with indication or alarm only functions:
9 units in "Pressurized Service" J.units in "Atmospheric Pressure Service" Five (5) transmitters are not associated with Reactor Protection, ESF, or ATWS systems A replacement program has been initiated at Hope Creek to replace all 37 transmitters associated with the Reactor, ESF, or ATWS systems in "pressurized service," including those with alarm or indication only function. This replacement program will be completed by the end of the third refueling outage which is scheduled to begin in January of 1991.
There are no plans to replace the 17 units in "Atmospheric Pressure.Service." The manufacturer's investigation of this issue has determined that these units are at no significant risk of suffering from loss of fill-oil. The performance of these units in the enhanced surveillance program has been* exemplary.
The five units not associated with RPS, ESF or ATWS will be monitored through the enhanced surveillance program and scheduled for replacement if inoperability occurs. One of these has been identified as exhibiting symptoms of potential oil loss (Attachment 1) and has been scheduled for replacement during the January 1991 refueling outage.
Salem 2 Transmitter associated with ESF system but with indication or alarm only function
- 1 unit in "Pressurized Service" NLR-N90149
The single transmitter installed at Salem unit 2 has an indication only function. It is currently scheduled for replacement by October 1991.
- 3. Review plant records (for example, the three most recent calibration records) associated.with the transmitters identified in Item 1 above to determine whether any of these transmitters may have already exhibited symptoms indicative of loss of fill-oil. Appropriate operability acceptance criteria should be developed and applied to transmitters identified as having exhibited symptoms indicative of loss of fill-oil from this plant record review. Transmitters identified as having exhibited symptoms indicative of loss of fill-oil that do not conform to the operability acceptance criteria should be addressed in accordance with
- the applicable technical specification. Transmitters identified as having exhibited symptoms indicative of loss of fill-oil that do not conform to the operability acceptance criteria and are not addressed in the technical specifications should be replaced at the earliest appropriate opportunity. *
RESPONSE
A review of plant records is being conducted to determine whether any of the installed transmitters have exhibited symptoms of oil loss. The result of this review are documented in Engineering Evaluation A-O-VAR-CEE-0296, Rev. 1. All suspect lot transmitter reviews have been completed and of all transmitters identified in_
Item 1, 90% are complete for Hope Creek; 92% are complete for Salem 1 and 89% are complete for Salem 2. The remaining units' reviews will be completed by August 31, 1990. Appropriate operability criteria has been developed and utilized.
Transmitters required to be operable and subsequently declared inoperable will be addressed in accordance with the applicable technical specification action statement. Inoperable non-technical specification transmitters will be addressed by updating the basis for continued operation, if appropriate, and scheduled for replacement.
- 4. Develop and implement an enhanced surveillance program to monitor transmitters in Item 1 for symptoms of loss of fill-oil. This enhanced surveillance program should consider the following or equally effective actions:
- a. Ensuring appropriate licensee personnel are aware of the symptoms that a transmitter, both during operation and during calibration activities, may exhibit if i t is experiencing of loss of fill-oil and the need for prompt identification of transmitters that may exhibit these symptoms; NLR-N90149
- b. Enhanced- transmi~ter monitoring to identify sustained transmitter drift;
- c. Review of transmitter performance following planned_or unplanned plant transients or tests to identify sluggish transmitter response; -
- d. Enhanced awareness of sluggish transmitter response to either increasing or decreasing test pressures during calibration activities;
- e. Development and implementation of a program to detect changes in process noise; and
- f. Development and application to transmitters identified as having exhibited symptoms indicative of loss of fill-oil of an appropriate operability acceptance criteria. Transmitters identified as having exhibited symptoms indicative of loss of fill-oil that do not conform to the operability acceptance criteria should be addressed in accordance with the applicabie '
technical specification. Transmitters identified as having exhibited symptoms indicative of loss of.
fill-oil that do not conform to the operability acceptance criteria and are not addressed in the technical specifications should be replaced at the earliest appropriate opportunity.
RESPONSE
The enhanced surveillance program at Salem and Hope Creek for Rosemount model 1153 and 1154 transmitters consists of the following:
Drift Analysis - Transmitter drift will continue to be trended in the same manner as.performed for Engineering Evaluation A-O-VAR-CEE-0296, Rev. 1. Station procedures are presently being revised t~ ensure the flow of data to the program coordinator.
Sluggish Response Monitoring - All calibration procedures are being revised to include directions to check for sluggish response during normal calibrations. In addition, transmitters which are identified as potential oil leakers -
may be subjected to a full upper range limit calibration to confirm oil loss.
Process Noise Analysis - A program to record and analyze transmitter response to process noise was developed and -
implemented at Hope Creek as a result of the February 1989 10CFR Part 21 notification issued by Rosemount. This program covers transmitters in processes which provide sufficient noise to generate adequate data and which have not been in service a sufficient time to verify their fully reliable operation. The program is run quarterly as an NLR-N90149
independent monitor of transmitter degradation. It also can be used as a verification method for transmitters which show signs of oil loss by the drift analysis method. A similar program is being initiated at Salem Generating Station. The program will continue for as long as it is judged to be of benefit. *
- 5. Document and maintain in accordance with existing plant procedures a basis for continued plant operation covering the time period from the present until such time that the Model 1153 Series B, 1153 Series D, and Model 1154 transmitters from the manufacturing lots that have been identified by Rosemount as having a high failure fraction due to loss of fill-oil in use in the reactor protection or engineering safety features actuation systems can be replaced. In addition, while performing the actions requested above, addressees may identify transmitters exhibiting symptoms indicative of loss of fill-oil that do not conform to the established operability acceptance criteria and are not addressed in the technical specifications. As these transmitters are identified, this basis for continued plant operation should be updated to address these transmitters covering the time period from the time these transmitters are identified until such time that these transmitters can be replaced. When developing and updating this basis for continued plant operation, addressees may wish to consider transmitter diversity and redundancy, diverse trip functions (a separate trip function that may also provide a corresponding trip signal), special system and/or component tests, or (if necessary) immediate replacement of certain suspect transmitters.
RESPONSE
The basis for continued operation (JCO) has been completed and documented in Engineering Evaluation (A-O-VAR-CEE-0296, Rev. 1.
This JCO will be updated/revised to include new.transmitter information as necessary.
B. Identify the indicated manufacturer; the model number; the system the transmitter was utilized in; the approximate amount of time at pressure; the corrective actions taken; and the disposition (e.g., returned to vendor for analysis) of Rosemount Model 1153 Series B, Model 1153 Series D, and Model 1154 transmitters that are believed to have exhibited symptoms indicative of loss of fill-oil or have been confirmed to have experienced a loss of fill-oil. This should include Model 1153 Series B, Model 1153 Series D and Model 1154 transmitters manufactured after July 11, 1989.
NLR-N90149
RESPONSE
The list of transmitters at Salem and Hope Creek which have exhibited symptoms of oil loss is included as Attachment _1 ..
- c. Identify the system in which the Model 1153 Series B, 1153 Series D, and Model 1154 transmitters from the manufacturing lots that have been identified by Rosemount as having a high failure fraction due to loss of fill-oil are utilized and provide a schedule for replacement of these transmitters which are in use in the reactor protection Qr engineered safety features actuation systems.
RESPONSE
The list of transmitters installed at Hoi:;>e Creek. from the *
- manufacturing *.lots identified by Rosemount. as having high failure rates is included as Attachment 2. Suspect lot trans~itters in
."pressurized service" are scheduled for replacement during the next refueling outages - scheduled to begin in January 1991.
"Atmospheric pressure service" transmitters will continue to be monitored through the enhanced surveillance program, there are no plans to replace these 17 units. The manufacturer's investigation of this issue has determined that these units are at no significant risk of suffering loss of fill-oil. These units do not exhibit any symptoms of pending failure.
Salem Unit 2 has one transmitter from the identified lot, 2PT-919. It monitors safety injection discharge pressure but has no control or trip function. It will be replaced prior to the end of the Fall 1991 refueling outage.
II. Model 1153 Series B, Model 1153 Series D and Model 1154 transmitters that, subsequent to providing the response required by Item 1 above, exhibit symptoms of loss of fill-oil or are confirmed to have experienced a loss of fill-oil should be reviewed for reportability under existing NRC regulations. If determined not to be reportable, addressees are requested to document and maintain, in accordance with existing plant procedures, information
. consistent with that requested in Item I B) above for each transmitter identified.
RESPONSE
Rosemount transmitters that exhibit symptoms of loss of fill-oil or are confirmed to have experienced a loss of fill-oil will continue to be reviewed for reportability. PSE&G intends to maintain the existing data bases for Rosemount transmitters at Artificfal Island.
NLR-N90149
Attachment 1 TRANSMITTERS EXHIBITING SIGNS OF POTENTIAL OIL LOSS SINCE ISSUE OF BULLETIN 90-01 Static Net Time Suspect Tag No. Model System Press at Press List Disposition Hope Creek 1BBLT-N080D 1153DB4 RPS/Isol 1000 PSI 36 mos. y To be replaced-Sched. by 8/15/90 Bi-weekly noise analysis until replacement Post Accident 1BBLT-3683B 1153DB4 Monitoring lOOOPSI 21 mos. N To be replaced during (Indication only) 1991 outage 1BCFT-N015B 1153DB5 RHR 167PSI 35 mos. y Replaced 5/90 to be (Indication only) 350PSI 11 mos. returned to Rosemount 1BCFT-N052C 1153DB4 RHR 167PSI 46 mos. N To be replaced upon receipt of replacement unit.
1BGFT-N012A 1153DB5 RWCU 1102PSI 36 mos. N Monthly zero output check.
Confirmation Test to be performed during next system outage.
1EGFT-2549B3 1153DB5 SACS 135PSI 51 mos. y To be replaced upon receipt (Indication only) of substitute -No later than 1991 Outage.
Salem lPT-457 1153GD9 Pressurizer 2200PSI 65 mos. N Daily channel checks Control against 3 redundant units
- to verify operating at drift until replacement.
Replacement by 7/31/90.
1LT-935C 1153HD4 Safety Inject 650PSI 60 mos. N To be replaced during fall (Indication/Alarm) 1990 Outage Only
J>:iq" No.
01/09/90 8.2 ATTACHMENT 2 HOPE CREEK SUSPECT TRANSMITTER DATABASE SUS.
INSTRUMENT ID DESCRIPTION CLASS R CODE STATIC PR. SERIAL # INSTALL DATE .LOT TRIP
~PDT*N086B*B21 STEAM LINE A FLO\J ESF 7 980.0 419038 03/01/88 y y 1ABPDT*N086D*B21 STEAM LINE A FLO\J ESF 7 980.0 419157 03/01/88 y y 1ABPDT*N088D*B21 STEAM LINE C FLO\J ESF 7 980.0 419158 03/01/88 y y 1ABPDT*N089B*B21 STEAM LINE D FLO\J ESF 7 980.0 419040 03/01/88 y y 1BBFT *N014B
- 831 LOOP A RECIRC FLO\l 'RPS 5 1025.0 412235 08/01/86 y y 1BBFT*N014D*B31 LOOP A RECIRC FLO\l RPS 5 1025.0 412616 08/01/86 y y 1BBFT*N024A*B31 LOOP B RECIRC FLO\J RPS 5 1025.0 412239 12/01/87 y y 1BBFT*N024C*B31 LOOP B RECIRC FLO\l RPS 5 1025.0 412379 08/01/86 y y 1RBFT*N024D*B31 LOOP B RECIRC FLO\J RPS 5 1025.0 412380 08/01/86 y y e l T* N080C -*821 REACTOR \IATER LEVEL LO\l RPS 4 1000.0 411996 08/01/86 y y 1RBLT*N080D*B21 REACTOR \IATER LEVEL LO\J f<PS 4 1000.0 414745 08/01/86 y y 1BBLT*N085A*B21 REACTOR SHROUD LEVEL PAM 5 1000.0 412240 08/01/86 y N 1RBLT*N085B*B21 REACTOR SHROUD LEVEL PAM 5 1000.0 412225 08/01/86 y N 1BBLT.*N091A*B21 REAC LVL CS/RHR/HPCI ESF 5 1000.0, 412617 12/01/85 y y
'"BLT*N091B*B21 REAC LVL CS/RHR/ADS/RCIC ESF 5 1000.0 412233 08/01/86 y y 1BBLT*N091C*B21 REAC LVL CS/RHR/HPCI ESF 5 1000.0 412718 . 12/01/85 y y
l':t<J" No. 2 nrt09!90 8.2 ATTACHMENT 2 HOPE CREEK SUSPECT TRANSMITTER DATABASE SUS.
INSTRUMENT ID DESCRIPTION CLASS R COOE STATIC PR. SERIAL # INSTALL DATE LOT TRIP
~RBLT*N091F*B21 REAC LVL CS/RHR/ADS/RCIC ESF 5 1000.0 412237 01/01/86 y y 11lnLT*N091G*B21 REAC LVL CS/RHR/HPCI ESF 5 1000.0 412238 12/01/85 y y 11lRLT*N097D*B21 REACTOR WARTER LEVEL-RCIC RCIC 5 1000.0 412376 02/01/89 y y 11lRLT-N097H-B21 REACTOR WATER LEVEL-RCIC RCIC 5 1000.0 412365 08/01/86 y y 1nBPT-N050A-C71 DRYUELL PRESSURE RPS 5 2.0 412526 08/01/86 y y 1RRPT*N050B-C71 DRYUELL PRESSURE RPS 5 2.0 412527 08/01/86 y y 1RRPT-N050C-C71 DRYUELL PRESSURE RPS 5 2.0 412528 08/01/86 y y 1RRPT*N094B*B21 DU PRESS/CS/RHR/RCIC/AOS ESF 5 2.0 412531 08/01/86 y y 1RRPT*N094C-B21 DU PRESS/CS/RHR/HPCI ESF 5 2.0 412532 08/01/86 y y
~RRPT*N094D-B21 DU PRESS/CS/RHR/RCIC/AOS ESF 5 2.0 412533 08/01/86 y y 1RBPT-N094E-B21 DU PRESS CS/RHR/HPCI ESF 5 2.0 412534 08/01/86 y y 1RBPT
- N094F-B21 DU PRESS CS/RHR/RCIC/ADS ESF 5 2.0 412535 08/01/86 y y 1BBPT-N094G-B21 DU PRESS CS/RHR/HPCI ESF 5 2.0 412536 08/01/86 y y 1RRPT-N094H-B21 CONT PRES CS/RHR/RCIC/ADS ESf 5 2.0 412537 08/01/86 y y lRCFT-4435 RHR LOOP B FLO\I ESF 5 167.0 415219 04/01/86 y N 1RCFT *44628 RHR CONTNMNT SPRY FLU B ESF 5 167.0 413670 08/01/86 y N
f'"CJ" No. 3 nr/09/90 8.2 ATTACHMENT 2 HOPE CREEK SUSPECT TRANSMITTER DATABASE
.SUS.
INSTRUMENT ID DESCRIPTION CLASS R ~ODE STATIC PR. SERIAL # INSTALL DATE LOT TRIP e 1RCFT-N015A-E11 1RCFT-N015C-E11 RHR LOOP A FLO\I RHR LOOP C FLO\I ESF ESF 5
5 167.0 412216 167.0 412218 08/01/86 08/01/86 y
y N
N 1RC.FT-N015D-E11 RHR LOOP D FLO\I ESF 5 167.0 412219 ' 08/01/86 y N 1BDPT-N053-E51 RCIC PUMP SUCTION HOR TRP RCIC 5 5.0 414902 01/01/86 y y 1REPDT-N056-E21 CORE SPRAY DIFF PRESSURE ESF 5 1000.0 412618 01/01/86 y y 1BGFT-N036A-G33 R\ICU INLET ESF 5 1020.0 412224 08/01/86 y y 1BGFT
- N041A-G33 R\ICU DISCH TO FEED\IATER ESF 5 1080.0 412222 08/01/86 y y 1BGFT*N041D-G33 R\ICU DISCH TO FEED\IATER ESF 5 1080.0 415032 04/01/89 y y 1BHPT-N004B-C41 SLC PMP B DISCH HOR SLC 9 1235.0 410675 08/01/86 y N e lRJLT-4805-1 lBJLT-4805-2 SUPPRESSION POOL SUPPRESSION POOL PAM RSP 5
5 0.0 412524 0.0 412717 01/01/86 01/01/86 y
y y
N lEGFT-254981 SACS PMP DISCH LOOP B EAS 5 135.0 412930 04/01/86 y N 1EGFT-254983 SACS PMP DISCH LOOP B RSP 5* 135.0 415214 04/01/86 y N 1EGPDT-2529A FUEL POOL HEAT EXCH A EAS 5 110.0 415216 04/01/86 y y lEGf"'T-25298 FUEL POOL HEAT EXCH B EAS 5 110.0 415215 04/01/86 y y irrrr-N003-E51 RCIC PUMP DISCH FLO\I RCIC 5 1275.0 412523 08/01/86 y y
Pnqr No. 4 01/(19/90 8.2 ATTACHMENT 2 HOPE CREEK SUSPECT TRANSMITTER DATABASE SUS.
INSTRUMENT ID DESCRIPTION CLASS R CODE. STATIC PR. SERIAL # INSTALL DATE LOT TRIP
~rDFT-N008~E41 HPCI PMP DISCH*TURB CNTRL ESF 5 112D.O 412366 08/01/86 y N 1GSPT-4960A3 DRYIJELL*CONT ATM CONTROL PAM 5 2.0 412722 04/01/88 y N 1GUFT-9394C DELUGE FLO\I CONTROL CVH 2 ESF 4 25.0 415227 05/01/86 y y 1KPFT-6053A MSIV !NBD SEAL GAS SPLY ESF 4 5.0 415226 04/01/86 y y lRCFT-0664-024 PASS LIQ SHPL RTN/SUPPR PASS 4 1000.0 414746 08/01/86 y N 1SALT-N402F-B21 RPV LVL FOR RRCS*LVL 2 T ATUS 5 1000.0 406061 08/01/86 .Y y 1SMLT-N081A-B21 REAC LVL FOR NS4 LEVEL 2 ESF 5 1000.0 412786. 12/01/85 y y 1SMLT-N081C-B21 REAC LVL FOR NS4 LEVEL 2 ESF .5 1000.0 412230 12/01/85 y y 191PT*N075B*B21 CONDENSER LO\I VACUUM ESF 5 0.0 412627 08/01/86 y y e*T*N075C*B21 CONDENSER LO\I VACUUM ESF 5 0.0 412737 08/01/86 y y
'9MPT*N075D*B21 CONDENSER LO\I VAUUH ESF 5 0.0 412735 08/01/86 y y