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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 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 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 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 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 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 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 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 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 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 ML18095A3241990-06-28028 June 1990 Forwards Retyped Pages to 871224 License Change Request 87-15 & Modified,Per 900620 Ltr 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 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 ML18095A3211990-06-26026 June 1990 Requests 30-day Extension Until 900730 to Provide Completion Schedule to Resolve Audit Findings Re Station Blackout 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 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 ML18095A3161990-06-25025 June 1990 Forwards Supplemental Info Re Response to Generic Ltr 88-14. All Committed Actions Complete as of 900613 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 1990-09-04
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Text
- 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 Ch'1ef Nuclear Officer May 23, 1988 NLR-N88079
- u. s. Nuclear Regulatory Commission Document Control Desk Washington D. c. 20555 Gentlemen:
SUPPLEMENTAL RESPONSE TO IE BULLETIN 85-03 REQUEST FOR ADDITIONAL INFORMATION SALEM AND HOPE CREEK GENERATING STATIONS DOCKET NOS
- 5 0- 2 7 2 , 5 0-311, AND. 5 0- 3 5 4 Please find at.tached the Public Service Electric and Gas Company !
(PSE&G) responses to your request for additional information
- I relative to PSE&Gs implementation of I&E Bulletin 85-03, Motor Operated Valve Common.Mode Failures During Plant Transients Due To Improper Switch Settings. Attachment 1 contains information pertinent to Salem Units*l and 2. Attachment 2 and its Table provide Hope Creek specific information. It should be noted that on May 4, 1988, in a telephone conference with Mr. P. Swetland, NRC Region 1 Office of Inspection and Enforcement and Mr.
R. Kiessel, NRR Generic Communication Branch, PSE&G requested and was granted a two week extension in the original due date.
If there are any questions regarding the attached information, please feel free to contact us.
Sincerely, Attachments 88052501 53 8E:052:3 PDR ADOt_"'.1.:'~. 0~000272 Q - ""'
DCO
Document Control Desk 2 05-23-88 c Mr. D. c. Fischer USNRC Licensing Project Manager Mr. G. W. Rivenbark USNRC Licensing Project Manager Mr. R. J. Kiessel U.S. Nuclear Regulatory Commission Generic Communication Branch Washington, D.C. 20555 Mr. G. w. Meyer USNRC Senior Resident Inspector Mr. R. W. Borchardt USNRC Senior Resident Inspector Mr. w. T. Russell, Administrator USNRC Region I Mr. D. M. Scott, Chief Bureau of Nuclear Engineering Department of Environmental Protection 380 Scotch Road Trenton, NJ 08628
ATTACHMENT 1 SALEM GENERATING STATION RESPONSE Question 1 Has water hammer due to valve closure been considered in the determination of pressure differentials? If not, explain.
PSE&G Response Pressure rise due to water hammer was not considered in the determination of differential pressure across the safety injection valves. The motor operated valve closure times (10 seconds) are orders of magnitude longer than the sonic transit times of the system piping runs. Therefore, the occurrence of transient pressure increases within the piping due to the rapid closure of system valves is not considered a credible event.
Question 2 If MOVATS is planned for application to some MOVs which are not included in its data base, commit to and describe an alternate method for determining the extra thrust necessary to overcome pressure differentials for these valves.
PSE&G Response The MOVATS data base was not referenced for the determination of thrust values. All differential pressure determinations and thrust calculations were performed by PSE&G using the methods discussed in our 5-27-86 and 1-5-88 responses to the bulletin.
Question 3 MOVs 1SJ30, 11SJ33, 12SJ33, 1SJ67, 1SJ68, 11SJ134, 12SJ134, and 1SJ135 of the HPSI System are not listed in the response of 05-27-86. However, similar suction, miniflow and discharge valves 8806A, 8923A, 8923B, 8814A, 8814B, 8821A, 8821B, and 8835 are identified on Page 25 of the WOG Report of March 1986. Revise the response of 05-27-86 to include these MOVs, or justify their exclusion. As required by Action item a of the bulletin, assume inadvertent equipment operations.
Note: Similarly located valves are used for Unit 2 also.
PSE&G Response The MOVs listed above were excluded from the 5-27-88 response on the basis of a clarification provided by Mr. R. J. Kiessel of the NRC to the effect that only those valves in the highest head portion of the safety injection system needed to be addressed.
This interpretation was confirmed via telecon with Mr. Kiessel again on 5-4-88. These valves are not part of the high pressure portion of the safety injection system and are therefore not required to be addressed in the bulletin response. These valves 1 of 2
have however been captured within the Salem Station MOVATS Program and the applicable data is available for inspection at the site.
Question 4 Revise Page 2 of Attachment 1 of the response dated 05-27-86 to include values of differential pressure for both opening and closing the MOVs, as required by Action Item a of the bulletin.
PSE&G Response As identified in our 5-27-88 response, the values of differential pressure specified in Table 1 are the maximum values of differential pressure and the direction in which they exist. This value was utilized to select switch settings in both directions of valve operation. Table 1 of our 1-5-88 response reflects the application of this maximum value of differential pressure to both the open and closed direction.
Question 5 The proposed program for action items b, c, and d of the bulletin is incomplete. Provide the following details as a minimum:
(a) commitment to a training program for setting switches, maintaining valve operators, using signature testing equipment and interpreting signatures, and (b) consideration of pipe break conditions as required by the bulletin.
PSE&G Response 5.a) A training program has been developed which provides basic
- instruction on MOVATS data acquisition and signature analysis for plant electrical maintenance personnel.
5.b) Pipe break conditions have been considered in the determination of differential pressures. In each case, atmospheric pressure was assumed to exist on the downstream side of the valve disc. Depending on the system configuration, either the maximum static head of the fluid reservoir or the maximum discharge head of the pump was assumed to exist on the upstream side of the valve disc.
2 of 2
ATTACHMENT 2 HOPE CREEK GENERATING STATION RESPONSE Question 1 If MOVATS is planned for application to some MOVs which are not included in its data base, commit to and describe an alternate method for determining the extra thrust necessary to overcome pressure differentials for these valves.
PSE&G Response All "Q" valve operators are included in Hope Creek's MOVATS Program. All valve operator seating thrusts, valve limit switch settings, motor current values and valve timing have been set and documented in accordance with system design specifications and vendor testing. This is addressed in further detail in our 5-27-86 submittal.
Question 2 Revise Table 1 of the response dated 05-27-86 to include the following MOVs, or justify their exclusion. As required by Action Item a of the bulletin, assume inadvertent equipment operations.
2.a) HPCI MOV V005 is shown normally open in Zone E-3 of Drawing M-55-1 Revision 20, and as MOV 3 on Page 68 of the BWROG Report NEDC-31322. dated September 1986. How would suction from the CST be ensured if this MOV were to be (a) actuated inadvertently to the closed position upon intended initiation of the system or (b) left closed inadvertently?
PSE&G Response If the valve is inadvertently closed, the HPCI turbine will trip. If the condition still exists that requires HPCI, the valve will auto open and the turbine will restart. If the valve is inadvertently left closed, it will receive an auto open signal on HPCI initiation. The valve operator is in the Hope Creek MOVATS Program, but was excluded from the original submittal because it is a low differential pressure application and is normally open. Refer to revised Table 1.
2.b) RCIC MOV VOOl is shown normally open in Zone F-3 of Drawing M-49-1 Revision 14, and as MOV 3 on Page 72 of the BWROG Report. The question in Item 2(a) above applies here also.
PSE&G Response Same response as 2.a.
2.c) HPCI MOV FD-V006 is shown normally open in Zone C-7 of Drawing M-55-1 Revision 20, and as MOV VI on Page .71 of the BWROG Report. How would steam exhaust from the HPCI Turbine to the suppression pool be ensured if this MOV were to be 1 of 6
___J
(a) actuated inadvertently to the closed position upon intended initiation of the system or (b) left closed inadvertently?
PSE&G Response The valve operator is key locked open. If it were inadvertently closed, the exhaust rupture discs off the turbine would rupture. If it was left closed, the turbine would not start and the control room would receive an out-of-service alarm. The valve operator is in the Hope Creek MOVATS Program, but was excluded from the original submittal because it is a low differential pressure application and is normally open. Refer to revised Table 1.
2.d) RCIC MOV FC-V005 is shown normally open in zone C-6 of Drawing M-49-1 Revision 14, and as MOV VI on page 74 of the BWROG Report. The question in Item 2(c) above also applies to exhaust from the RCIC Turbine.
PSE&G Response Same response as 2.c.
2.e) RCIC MOV V022 is shown normally open in Zone E-3 of Drawing M-50-1 Revision 16, arid as MOV X on page 74 of the BWROG Report. How would steam supply to the RCIC Turbine be ensured if this MOV were to be operated inadvertently as described in Item 2(a) above?
PSE&G Response The valve is a mechanical overspeed trip valve which is normally open. If the turbine overspeeds, a mechanical latching mechanism releases the valve disc, which closes by spring force. The valve operator is only used to re-latch and open the valve after the turbine trips. The valve operator is in the Hope Creek MOVATS Program, but was excluded from the original submittal for the reasons stated above. Refer to revised Table 1.
Question 3 Revise Table 1 of the response dated 05-27-86 to include the following MOVs, or justify their. exclusion. Note that they have safety actions for both opening and closing.
3.a) HPCI MOV V009 is shown normally closed in Zone A-7 of Drawing M-55-1 Revision 20, and as MOV 4 on Page 68 of the BWROG Report. Both opening and closing are safety actions, per Page 55*
2 of 6
PSE&G Response The valve operator is in the Hope Creek MOVATS Program. It was excluded from the original submittal because it is a low differential pressure application. Refer to revised Table 1.
3.b) RCIC MOV V003 is shown normally closed in Zone B-7 of Drawing M-49-1 Revision 14, and as MOV 4 on Page 72 of the BWROG Report. Both opening and closing are safety actions, per Page 59.
PSE&G Response Same response as 3.a.
3.c) HPCI MOV BJ-V028 is shown normally closed in Zone c-5 of drawing M-56-1 Revision 13, and as MOV 9 on Page 68 of the BWROG Report. Both opening and closing are safety actions, per Page 56 and note (f) on Page 66.
PSE&G* Response Hope Creek considers this valve's safety function to be in the open direction only. The valve operator is in the Hope Creek MOVATS Program. It.was excluded from the original submittal because of low differential pressure across the valve disc when the valve is automatically opened at HPCI turbine start. Refer to revised Table 1.
3.d) RCIC MOV BD-V022 is shown normally closed in Zone D-6 of Drawing M-50-1 Revision 16, and as MOV 9 on Page 72 of the BWROG Report. Both opening and closing are safety actions, per Page 60 and note (f) on Page 66.
PSE&G Response Same response as 3.c.
Question 4 Revise Table 1 of the response dated 5-25-86 to include the following MOVs, or justify their exclusion. Note that each has a safety action for either opening or closing.
4.a) RClC MOV FC-VOll is shown normally open in Zone B-6 of Drawing M-49-1 Revision 14, and as MOV 7 on Page 72 of the BWROG Report. Per Page 59, opening is a safety action.
PSE&G Response This operator is key locked and normally open. The valve operator is in the Hope Creek MOVATS Program. It was excluded from the original submittal because it is a low 3 of 6
differential pressure valve that is normally key locked open. Refer to revised Table 1.
4.b) HPCI MOV FD-V051 is shown normally closed in Zone F-6 of Drawing M-55-1 Revision 20, and as MOV IV on Page 71 of the BWROG Report. Per Page 57, closing is a safety action.
PSE&G Response This valve operator is in the Hope Creek MOVATS Program. It was excluded from the original submittal because it is normally closed. Refer to revised Table 1.
4.c) HPCI MOVs FD-V007 and FD-VOlO are shown normally open in zones C-7 and C-8 of Drawing M-56-1 Revision 13, and as MOVs VII and VIII on Page 70 of the BWROG Report. Per Page 58, closing is a safety action.
PSE&G Response These valves are normally open. They will isolate on high drywell pressure of 1.68 psig and low system pressure. The valve operators are in the Hope Creek MOVATS Program. They were excluded from the original submittal because they are low differential pressure valves that are normally open.
Refer to revised Table 1.
- 4.d) RCIC MOVs FC-V006 and FC-V007 are shown normally open in zones C-7 and C-8 of Drawing M-49-1 Revision 14, and as MOVs VII and VIII on Page 74 of the BWROG Report. Per Page 62, closing is a safety action.
PSE&G Response Same response as 4.c.
Question 5 Revise Table 1 of the response dated 05-27-86 to include the following MOVs, or justify their exclusion. According to pages 55 and 60 of the BWROG ~eport (for HPCI and RCIC respectively),
these valves have no safety action; however, utilities are expected to report differential pressures for testing, per Note (o) on Page 66.
5.a) HPCI MOVs VOlO and V004 are shown normally closed in zones E-5 and F-5 of Drawing M-55-1 Revision 20, and as MOVs 5 and 6 on Page 68 of the BWROG Report.
PSE&G Response Hope Creek considers these valves to have a safety function.
If they are open during testing of the system, and the system is required to perform its intended function, these 4 of 6
valves must close to prevent flow diversion from the reactor vessel. The valve operators are in the Hope Creek MOVATS Program. They were excluded from the original submittal because it was understood that test valves were not to be considered in the system review. Refer to revised Table 1.
5.b) RCIC MOV V012 is shown normally closed in Zone E-5 of Drawing M-49-1 Revision 14, and as MOV 5 on Page 72 of the BWROG Report.
PSE&G Response Same response as 5.a.
Question 6 The proposed program for action items b, c and d of the bulletin is incomplete. Provide the following details as a minimum:
6.a) commitment to a training program for setting switches, maintaining valve operators, using signature testing equipment and interpreting signatures, PSE&G Response PSE&G has a formal training program to instruct technicians and engineers in setting switches, maintaining valve operators, use of MOVATS equipment and signature interpretation.
6.b) description of a method possibly needed to extrapolate valve stem thrust determined by testing at less than maximum differential pressure.
PSE&G Response As stated in our 5-27-86 response, the torque switch settings were established based upon the calculated system design-(maximum) differential pressures. Vendor testing of representative valves at design differential pressures was performed to verify the calculations and the switch settings selected.
6.c) consideration of pipe break conditions as required by the bulletin.
PSE&G Response As stated in our 5-27-88 response, safety related valves have existing circuitry which permits the valve to be fully opened or closed at the control room operators demand.
Should the valve be subjected to a condition that is above its maximum differential pressure and fails to fully stroke either open or closed, the control room operator depresses 5 of 6
and holds the control room panel valve operator switch and the valve operator will move the valve to its requested position.
6 of 6
TABLE 1 PAGE 1 OF 5 QUESTION 2(a)- HPCI Pump Suction from CST:
VALVE VALVE.OPERATOR DIFFERENTIAL PRESSURE DATA ID# BJ-V005 ID# - l-BJ-HV-F004 NORMAL OPEN - 10 PSI MANUFACTURER - ANCHOR/DARLING MANUFACTURER - LIMITORQUE NORMAL CLOSE - 10 PSI TYPE - GATE MODEL - SMB-00 ABNORMAL OPEN - 125 PSI SIZE - 16" MOTOR RPM - 1900 ABNORMAL CLOSE - 125 PSI RATING - 150 LB. OUTPUT SPEED - 40 SECONDS TORQUE SET/OPEN - 1.75 TORQUE SET/CLOSE - 1.0 QUESTION 2(b)- RCIC Pump Suction from CST:
VALVE VALVE OPERATOR DIFFERENTIAL PRESSURE DATA ID# BD-VOOl ID# BD-HV-FOlO NORMAL OPEN - 5 PSI MANUFACTURER - ANCHOR/DARLING MANUFACTURER - LIMITORQUE NORMAL CLOSE - 5 PSI TYPE - GATE MODEL - SMB-000 ABNORMAL OPEN - 125 PSI SIZE - 6" MOTOR RPM - 1750 ABNORMAL CLOSE - 125 PSI RATING - 150 LB. OUTPUT SPEED - 18 SECONDS TORQUE SET/OPEN - 1.5 TORQUE SET/CLOSE - 1.25 QUESTION 2(c)- HPCI Turbine Exhaust:
VALVE - VALVE OPERATOR
- DIFFERENTIAL PRESSURE DATA ID# FD-V006 ID# FD-HV-F071 NORMAL OPEN - 0 PSI MANUFACTURER - ANCHOR/DARLING MANUFACTURER - LIMITORQUE NORMAL CLOSE - 50 PSI TYPE - GATE MODEL - SMB-0 ABNORMAL OPEN - 200 PSI SIZE - 20" MOTOR RPM - 1900 ABNORMAL CLOSE - 200 PSI RATING - 150 LB. OUTPUT SPEED - 50 SECONDS TORQUE SET/OPEN - 2.5 TORQUE SET/CLOSE - 2.25 QUESTION 2(d)- RCIC Turbine Exhaust:
VALVE VALVE OPERATOR DIFFERENTIAL PRESSURE DATA ID# - l-FC-V005 ID# FC-HV-F059 NORMAL OPEN - 0 PSI MANUFACTURER - ANCHOR/DARLING MANUFACTURER - LIMITORQUE NORMAL CLOSE - 10 PSI TYPE - GATE MODEL - SMB-00 . ABNORMAL OPEN - 150 PSI SIZE - 10" MOTOR RPM - 1900 ABNORMAL CLOSE - 150 PSI RATING - 150 LB. OUTPUT SPEED - 33 SECONDS TORQUE SET/OPEN - 2.125 TORQUE SET/CLOSE - 2.25 REV. 1 - 5/20/88
TABLE 1- PAGE 2 OF 5 QUESTION 2(e)- RCIC Mechanical Overspeed Trip Valve:
VALVE VALVE OPERATOR DIFFERENTIAL PRESSURE DATA ID# FC-V022 ID# FC-HV-F060 NORMAL OPEN - 0 PSI MANUFACTURER - SHUTTE & KOERTING MANUFACTURER - LIMITORQUE NORMAL CLOSE - 1120 PSI TYPE - GLOBE MODEL - SMB-000 ABNORMAL OPEN - 1340 PSI SIZE - 3 II MOTOR RPM - 1900 ABNORMAL CLOSE - 1340 PSI RATING - 1500 LB. OUTPUT SPEED - 10 SECONDS TORQUE SET/OPEN - 2.0 TORQUE SET/CLOSE - 2.0 QUESTION 3(a)- HPCI Suction from Torus:
VALVE VALVE OPERATOR DIFFERENTIAL PRESSURE DATA ID# BJ-V009 ID# BJ-HV-F042 NORMAL OPEN - 5 PSI MANUFACTURER - ANCHOR/DARLING MANUFACTURER - LIMITORQUE NORMAL CLOSE - 5 PSI TYPE - GATE MODEL - ~MB-00 ABNORMAL OPEN - 125 PSI SIZE - 16" MOTOR RPM - 1900 ABNORMAL CLOSE - 125 PSI RATING - 150 LB. OUTPUT SPEED - 43 SECONDS TORQUE SET/OPEN - 1. 0 TORQUE SET/CLOSE - 1. 0 QUESTION 3(b)- RCIC Suction from Torus:
VALVE VALVE OPERATOR DIFFERENTIAL PRESSURE DATA ID# BD-V003 ID# BD-HV-F031 NORMAL OPEN - 5 PSI MANUFACTURER - ANCHOR/DARLING MANUFACTURER - LIMITORQUE NORMAL CLOSE - 5 PSI TYPE - GATE MODEL - SMB-000 ABNORMAL OPEN - 125 PSI SIZE RATING
- 6"
- 150 LB.
MOTOR RPM
-OUTPUT SPEED 1900 16 SECONDS ABNORMAL CLOSE TORQUE SET/OPEN TORQUE SET/CLOSE
- 125
- 1. 5
- 1. 5 PSI e
QUESTION 3(c)- HPCI Lube Oil Cooler Supply:
VALVE VALVE OPERATOR DIFFERENTIAL PRESSURE DATA ID# BJ-V028 ID# BJ-HV-F059 NORMAL OPEN - 305 PSI MANUFACTURER - ROCKWELL MANUFACTURER - LIMITORQUE NORMAL CLOSE - 305 PSI TYPE - GLOBE MODEL - SMB-000 ABNORMAL OPEN - 550 PSI SIZE - 2" MOTOR RPM - 1900 ABNORMAL CLOSE - 550 PSI RATING - 1500 LB. OUTPUT SPEED - 22 SECONDS TORQUE SET/OPEN - 3.0 TORQUE SET/CLOSE - 2.5 REV. 1 - 5/20/88
TABLE 1 PAGE 3 OF 5 QUESTION 3(d)- RCIC Lube Oil Cooler Supply:
VALVE VALVE OPERATOR DIFFERENTIAL PRESSURE DATA ID# - 1-BD-V022 ID# BD-HV-F046 NORMAL OPEN - 1275 PSI MANUFACTURER -* ROCKWELL MANUFACTURER - LIMITORQUE NORMAL CLOSE - 1275 PSI TYPE - GLOBE MODEL - SMB-000 ABNORMAL OPEN - 1620 PSI SIZE - 2" MOTOR RPM - 1900 ABNORMAL CLOSE - 1620 PSI RATING - 1500 LB. OUTPUT SPEED - 21 SECONDS TORQUE SET/OPEN - 2.0 TORQUE SET/CLOSE - 2.0 QUESTION 4(a)- RCIC Vacuum Pump Discharge:
VALVE . VALVE OPERATOR DIFFERENTIAL PRESSURE DATA ID# - 1-FC-VOll ID# FC-HV-F060 NORMAL OPEN - 0 PSI MANUFACTURER - ROCKWELL MANUFACTURER - LIMITORQUE NORMAL CLOSE - 10 PSI TYPE - GLOBE MODEL - SMB-000 ABNORMAL OPEN - 100 PSI SIZE - 2" MOTOR RPM - i900 ABNORMAL CLOSE - 100 PSI RATING - 1500 LB. OUTPUT SPEED - 22 SECONDS TORQUE SET/OPEN - 1.5 TORQUE SET/CLOSE - 1.5 QUESTION 4(b)- HPCI Isolation Valve Bypass:
VALVE VALVE OPERATOR DIFFERENTIAL PRESSURE DATA ID# - 1-FD-V051 ID# FD-HV-FlOO NORMAL OPEN - 1120 PSI MANUFACTURER - ROCKWELL MANUFACTURER - LIMITORQUE NORMAL CLOSE - 0 PSI TYPE SIZE RATING GLOBE 2"
1500 LB.
MODEL MOTOR RPM OUTPUT SPEED SMB-000 1700 29 SECONDS ABNORMAL OPEN ABNORMAL CLOSE TORQUE SET/OPEN 1250 1250 2.0 PSI
.PSI e TORQUE SET/CLOSE - 2.0 QUESTION 4(c)l- HPCI Vacuum Relief Isolation:
VALVE VALVE OPERATOR DIFFERENTIAL PRESSURE DATA
- ID# FD-V007 ID# FD-HV-F075 NORMAL OPEN - 0 PSI MANUFACTURER - ANCHOR/DARLING MANUFACTURER - LIMITORQUE NORMAL CLOSE - 35 PSI TYPE - GATE MODEL - SMB-000 ABNORMAL OPEN - 200 PSI SIZE - 3 II MOTOR RPM - 1700 ABNORMAL CLOSE - 200 PSI RATING - 150 LB. OUTPUT SPEED - 15 SECONDS TORQUE SET/OPEN - 2.0 TORQUE SET/CLOSE - 2.0 REV. 1 - 5/20/88
TABLE 1 PAGE 4 OF 5 QUESTION 4(c)2- HPCI Vacuum Relief Isolation:
VALVE VALVE OPERATOR DIFFERENTIAL PRESSURE DATA ID# FD-VOlO ID# FD-HV-F079 NORMAL OPEN - 0 PSI MANUFACTURER - ANCHOR/DARLING MANUFACTURER - LIMITORQUE NORMAL CLOSE - 35 PSI TYPE - GATE MODEL - SMB-000 ABNORMAL OPEN - 200 PSI SIZE 3" MOTOR RPM - i700 ABNORMAL CLOSE - 200 PSI RATING - 150 LB. OUTPUT SPEED - 14 SECONDS TORQUE SET/OPEN - 1.75 TORQUE SET/CLOSE - 2.5 QUESTION 4(d)l- RCIC Vacuum Relief Isolation:
VALVE VALVE OPERATOR DIFFERENTIAL PRESSURE DATA ID# FC-VOOG ID# FC-HV-F062 NORMAL OPEN - 0 PSI MANUFACTURER - ANCHOR/DARLING MANUFACTURER - LIMITORQUE NORMAL CLOSE - 10 PSI TYPE - GATE MODEL - SMB-000 ABNORMAL OPEN - 200 PSI SIZE - 3" MOTOR RPM - 1700 ABNORMAL CLOSE - 200 PSI RATING - 150 LB. OUTPUT SPEED - 13 SECONDS TORQUE SET/OPEN - 1. 0 TORQUE SET/CLOSE - 1. 25 QUESTION 4(d)2- RCIC Vacuum Relief Isolation:
VALVE VALVE OPERATOR DIFFERENTIAL PRESSURE DATA ID# - l-FC-V007 ID# FC-HV-F084 NORMAL OPEN - 0 PSI MANUFACTURER - ANCHOR/DARLING MANUFACTURER - LIMITORQUE NORMAL CLOSE - 10 PSI TYPE - GATE MODEL - SMB-000 ABNORMAL OPEN - 200 PSI SIZE - 3" MOTOR RPM - 1700 ABNORMAL CLOSE - 200 PSI RATING - 150 LB. OUTPUT SPEED - 14 SECONDS TORQUE SET/OPEN - 3.0 TORQUE SET/CLOSE - 2.5 QUESTION 5(a)l- HPCI Pump Test Line to CST:
VALVE VALVE OPERATOR DIFFERENTIAL PRESSURE DATA ID# BJ-VOlO ID# BJ-HV-F008 NORMAL OPEN - 1300 PSI MANUFACTURER - ANCHOR/DARLING MANUFACTURER - LIMITORQUE NORMAL CLOSE - 1300 PSI TYPE - GLOBE MODEL - SMB-3 ABNORMAL OPEN - 1500 PSI SIZE - 10" MOTOR RPM - 1900 ABNORMAL CLOSE - 1500 PSI RATING* - 900 LB. OUTPUT SPEED - 34 SECONDS TORQUE SET/OPEN - 1.5 TORQUE SET/CLOSE - 1.5 REV. 1 - 5/20/88
TABLE 1 PAGE 5 OF 5 QUESTION 5(a)2- HPCI/RCIC Pump Test Line to CST:
VALVE VALVE OPERATOR. DIFFERENTIAL PRESSURE DATA ID# AP"-V004 ID# AP-HV-FOll NORMAL OPEN - 1300 PSI MANUFACTURER - ANCHOR/DARLING MANUFACTURER - LIMITORQUE NORMAL CLOSE - 1300 PSI TYPE - GATE MODEL - SMB-1 ABNORMAL OPEN - 1500 PSI SIZE - 10" MOTOR RPM - 1900 ABNORMAL CLOSE - 1500 PSI RATING 9.00 LB. OUTPUT SPEED 32 SECONDS TORQUE SET/OPEN 3.25 TORQUE SET/CLOSE - 3.25 QUESTION 5(b)- RCIC Pump Test Line to CST:
VALVE VALVE OPERATOR DIFFERENTIAL PRESSURE DATA ID# BD-V012 ID# BD-HV-F022 NORMAL OPEN 1275 PSI MANUFACTURER - ANCHOR/DARLING MANUFACTURER - LIMITORQUE NORMAL CLOSE - 1275 PSI TYPE - GLOBE MODEL - SMB-0 ABNORMAL OPEN - 1500 PSI SIZE - 4" MOTOR RPM - 1900 ABNORMAL CLOSE - 1500 PSI RATING - 900 LB. OUTPUT SPEED - 19 SECONDS TORQUE SET/OPEN - 2.0 TORQUE SET/CLOSE - 2.5 REV. 1 - 5/20/88