Similar Documents at Salem |
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217M2101999-10-19019 October 1999
Forwards NRC Rept Number 17, Requal Tracking Rept from Operator Licensing Tracking Sys.Rept Was Used by NRC to Schedule Requalification Exam for Operators & Record Requal Pass Dates
ML18107A5601999-10-18018 October 1999
Submits 30-day Fuel Clad Temp Rept,Iaw 10CFR50.46.Rept Describes Changes to Calculated Peak Clad Temp (PCT) for Salem Generating Station Large & Small Break LOCA Analyses
ML18107A5531999-10-0808 October 1999
Forwards Summary Rept of Plant Startup & Power Ascension Testing for Sgs,Unit 2 Cycle 11,per Requirements of TS 6.9.1.1
ML18107A5561999-10-0707 October 1999
Requests Relief Associated with Containment Examinations at Hope Creek & Salem Generating Stations.Attachment 1 Includes Proposed Alternatives & Supporting Justification for Relief Requests
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
IR 05000272/19990071999-09-28028 September 1999
Forwards Insp Repts 50-272/99-07 & 50-306/99-07 on 990721- 0831.One Potentially Safety Significant Issue Identified Dealing with Control Room Special Ventilation System.Four Addl Issues of Low Safety Significance Identified
ML18107A5341999-09-22022 September 1999
Provides Data Re Operator Licensing Exam for Salem & Hope Creek Station,In Response to NRC Form 536 (7-1999)
ML18107A5421999-09-22022 September 1999
Forwards Discharge Monitoring Rept for Salem Generating Station for Aug 1999.Rept Is Required by & Prepared Specifically for EPA & Nj Dept of Environ Protection
ML20212B3631999-09-14014 September 1999
Forwards Rev 13 to Salem - Hope Creek Security Plan,Iaw 10CFR50.54(p).Summary of Proposed Changes to Plan,Encl. Encl Withheld
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
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.
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
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
ML18107A4981999-08-26026 August 1999
Forwards Response to NOV That Resulted from Predecisional Enforcement Conference Conducted on 990624.Corrective Actions:Communications to Supervisors Reinforced Employee Right & Duty to Raise Nuclear Safety Issues
ML18107A5051999-08-24024 August 1999
Informs That Nj Dept of Environ Protection Bureau of Nuclear Engineering Has Reviewed Request IAW Requirements of 10CFR50.91(b) & Has No Comments Re Amend to FOL Change Request S99-02 to Modify TS Re Penetration Valves
ML18107A4921999-08-23023 August 1999
Provides Suppl Info Re 971024 Amend Request to Modify TS 3/4 7.7, Auxiliary Bldg Exhaust Air Filtration Sys. Util Withdraws from Request All Proposed Changes Associated with Filter Testing,Per Issuance of GL 99-02
ML18107A4911999-08-20020 August 1999
Forwards Revised Plant Attribute Libraries for Salem & Hope Creek Generating Stations,Iaw 10CFR50,App E,Vi, Emergency Response Data Sys, 3.b.Changes Are Identified by Rev Bars
ML18107A4861999-08-19019 August 1999
Forwards NPDES Discharge Monitoring Rept, for Salem Generating Station for Month of Jul 1999.Rept Required by & Prepared Specifically for EPA & Nj Dept of Environ Protection
ML18107A4831999-08-18018 August 1999
Submits Licensee Comments on NRC 990730 Ltr Which Provided Notification of Close Out of TAC Numbers MA0567 & MA0568 Re GL 92-01,Rev 1,Suppl 1
ML18107A4801999-08-13013 August 1999
Requests That Pse&Gs Contact in NUREG-0383, Directory of Compliance for Radioactive Matl Packages, Be Changed
ML18107A4751999-08-0505 August 1999
Forwards Fitness for Duty Performance Data Rept for Six Month Period Ending 990630
ML20210M7571999-08-0404 August 1999
Forwards Response to Requesting Addl Info Re Status of Decommissioning Funding for Lgs,Pbaps & Sngs. Attachment Provides Restatement of Questions Followed by Response
ML18107A4531999-07-20020 July 1999
Forwards Discharge Monitoring Rept for Salem Generating Station, for June 1999.Rept Is Required by & Prepared for EPA & Nj Dept of Environ Protection
ML18107A4431999-07-0606 July 1999
Informs That Nj Dept of Environ Protection Bureau of Nuclear Engineering Has Reviewed Pse&G License Change Request S98-17 Re Permissible Enrichment Values for New Fuel Storage & Has No Comments
ML20196J6301999-07-0101 July 1999
Requests Addl Info Re Status of Decommissioning Funding for Limerick Generating Station,Units 1 & 2,Peach Bottom Atomic Power Station,Units 1,2 & 3 & Salem Nuclear Generating Station,Units 1 & 2
ML18107A4181999-06-30030 June 1999
Submits Response to NRC Request for Info Re Y2K Readiness at Npps,Per GL 98-01,suppl 1.Disclosure Encl
ML20209B6751999-06-29029 June 1999
Ack Receipt of from Dr Powell in Response to NRC Re Fitness for Duty.Attachment 2 of Will Be Withheld from Public Disclosure,Per 10CFR2.790
ML18107A4131999-06-25025 June 1999
Provides Further Clarification of Licensing & Design Basis for 125 Vdc Battery Margins for Sgs & HCGS for Meeting Station SBO & Loca/Loop Loading Requirements,Per Util 990426 Ltr & Discussion with NRC
ML18107A4091999-06-22022 June 1999
Forwards Discharge Monitoring Rept for May 1999,containing Info as Required by Permit NJ0005622.Rept Prepared Specifically for EPA & Nj Dept of Environ Protection
ML18107A4061999-06-21021 June 1999
Provides Supplemental Info to Proposed License Amend, Modifying TS 3/4 7.7, Auxiliary Bldg Exhaust Air Filtration Sys. Info Re Acceptance Criterion Discussed
ML18107A3691999-06-11011 June 1999
Forwards Corrected Monthly Operating Rept for Apr 1999 for Salem Generating Station,Unit 1.Original Submittal Contained Typo for year-to-date Value for Numbers of Hours Generator Was on Line (Service Hours)
ML18107A3641999-06-0404 June 1999
Requests Enforcement Discretion for TS 3/4.6.2.3 Re Containment Cooling Sys for Salem Generating Station,Unit 1
ML18107A3561999-06-0303 June 1999
Informs That Nj Dept of Environ Protection Bureau of Nuclear Engineering Has Reviewed Pse&G License Change Request S99-05 & Has No Comments
ML18107A3611999-05-27027 May 1999
Forwards Responses to NRC 990301 & 990323 RAIs for Salem & Hope Creek Generating Stations Relating to GL 96-05
ML18107A3301999-05-24024 May 1999
Forwards Suppl Info Re GL 95-07, Pressure Locking & Thermal Binding of Safety Related Power Operated Gate Valves. Encl Contains Methodology Used in Determination of Pressure Locking Susceptibility of PORVs Block Valves
ML18107A3371999-05-21021 May 1999
Forwards NPDES Discharge Monitoring for Salem Generating Station for Apr 1999, Containing Info as Required by Permit NJ0005622
ML18107A3291999-05-20020 May 1999
Forwards Redacted Response to NRC 990322 RAI Re Notification of Licensed Operator That Tested Positive for Alcohol. Attachment 2 Withheld,Per 10CFR2.790(a)(6)
ML18107A3031999-05-18018 May 1999
Provides Summary of Changes to NRC Commitments That Have Been Made But Not Reported by Other Means,Iaw with NEI Process for Managing NRC Commitments
ML18107A2891999-05-13013 May 1999
Forwards Rev 36 to Pse&G Nuclear Business Unit Emergency Plan. Rev 36 Incorporates Changes to Section 1-3,6 & 7 & 9-17.Attached Copy Includes All Sections of EP for Completeness
ML18107A2951999-05-12012 May 1999
Submits SG Tube Plugging Rept,Per Plant TS 4.4.6.5.a.Total of 47 Tubes Were Plugged During SG Tube Insps,Which Were Completed During Plant Tenth RFO
ML18107A2861999-05-11011 May 1999
Forwards Rev 0 to NFS-0174, COLR for Salem Unit 2 Cycle 11. COLR Rept Was Received by Util as Part of Reload SE
ML18107A2481999-04-29029 April 1999
Forwards 1998 Annual Radiological Environ Operating Rept for Salem & Hope Creek Generating Stations. Rept Summarizes Results of Radiological Environ Surveillance Program for 1998
ML18107A2511999-04-27027 April 1999
Submits 30-day Fuel Clad Temp Rept for Salem Generating Station,Units 1 & 2.Rept Describes Changes to Calculated Peak Clad Temp (PCT) for Plant Large & Small LOCA & Small Break LOCA Analyses
ML18107A2631999-04-26026 April 1999
Provides Clarification on Licensing & Design Basis for 125 Vdc Battery Margins for Sgs & HCGS for Meeting SBO & Loca/ LOOP Loading Requirements
ML18107A2371999-04-26026 April 1999
Forwards Corrected Response to NRC RAI Re Licensee Request for Change to TS Permissible Enrichment Values for New Fuel Storage.Incorrect Attachment Was Provided with Util 990412 Ltr to Nrc.Encl Supersedes 990412 Submittal
1999-09-08
[Table view]
Category:INCOMING CORRESPONDENCE
MONTHYEARML18107A5601999-10-18018 October 1999
Submits 30-day Fuel Clad Temp Rept,Iaw 10CFR50.46.Rept Describes Changes to Calculated Peak Clad Temp (PCT) for Salem Generating Station Large & Small Break LOCA Analyses
ML18107A5531999-10-0808 October 1999
Forwards Summary Rept of Plant Startup & Power Ascension Testing for Sgs,Unit 2 Cycle 11,per Requirements of TS 6.9.1.1
ML18107A5561999-10-0707 October 1999
Requests Relief Associated with Containment Examinations at Hope Creek & Salem Generating Stations.Attachment 1 Includes Proposed Alternatives & Supporting Justification for Relief Requests
ML18107A5501999-10-0505 October 1999
Provides Current Status of Pse&G Actions Re GL 98-01, Y2K Readiness of Computer Sys at Npps, for Salem Nuclear Generating Station,Units 1 & 2 & Hope Creek Nuclear Generating Station
ML18107A5521999-10-0505 October 1999
Encourages NRC to Support Abb Combustion Engineering Nuclear Power Request for Priority Review of Generic TR Re Crossflow Ultrasonic Flow Measurement Sys
ML18107A5591999-10-0505 October 1999
Informs That Nj Dept of Environ Protection Has No Comments on License Change Request S99-07 for Sgs,Units 1 & 2
ML18107A5341999-09-22022 September 1999
Provides Data Re Operator Licensing Exam for Salem & Hope Creek Station,In Response to NRC Form 536 (7-1999)
ML20212B3631999-09-14014 September 1999
Forwards Rev 13 to Salem - Hope Creek Security Plan,Iaw 10CFR50.54(p).Summary of Proposed Changes to Plan,Encl. Encl Withheld
ML18107A5321999-09-13013 September 1999
Forwards Revised 10CFR50.92 Evaluation to Clarify Util Response to Question Number 1 Re Amend to Modify TS 3/4 8.1, AC Power Sources.
ML18107A5331999-09-13013 September 1999
Provides Notification That PSEG Intends to Utilize ASME Code Case N-481 During Second ISI Interval at Sgs Units 1 & 2
ML18107A5351999-09-13013 September 1999
Informs That NRC Has Reviewed Pse&G Request Proposing to Modify TS Which Allow EDG to Be Operated for 24 Surveillance Test During Any Mode,Iaw 10CFR50.91(b) & Has No Comments
ML18107A5231999-09-0808 September 1999
Forwards Salem Generating Station Semiannual Radioactive Effluent Release Rept for Jan-June 1999. Rept Summarizes Liquid & Gaseous Releases & Solid Waste Shipments from Salem Generating Station for Period of Jan-June 1999
ML18107A5221999-09-0808 September 1999
Requests Approval to Use ASME Code Case N546,which Provides Alternative Qualification Requirements That Allow Personnel Most Familiar with Walkdown of Plant Sys,Like License Operators to Perform VT-2 Examinations
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
ML18107A4431999-07-0606 July 1999
Informs That Nj Dept of Environ Protection Bureau of Nuclear Engineering Has Reviewed Pse&G License Change Request S98-17 Re Permissible Enrichment Values for New Fuel Storage & Has No Comments
ML18107A4181999-06-30030 June 1999
Submits Response to NRC Request for Info Re Y2K Readiness at Npps,Per GL 98-01,suppl 1.Disclosure Encl
ML18107A4131999-06-25025 June 1999
Provides Further Clarification of Licensing & Design Basis for 125 Vdc Battery Margins for Sgs & HCGS for Meeting Station SBO & Loca/Loop Loading Requirements,Per Util 990426 Ltr & Discussion with NRC
ML18107A4061999-06-21021 June 1999
Provides Supplemental Info to Proposed License Amend, Modifying TS 3/4 7.7, Auxiliary Bldg Exhaust Air Filtration Sys. Info Re Acceptance Criterion Discussed
ML18107A3691999-06-11011 June 1999
Forwards Corrected Monthly Operating Rept for Apr 1999 for Salem Generating Station,Unit 1.Original Submittal Contained Typo for year-to-date Value for Numbers of Hours Generator Was on Line (Service Hours)
ML18107A3641999-06-0404 June 1999
Requests Enforcement Discretion for TS 3/4.6.2.3 Re Containment Cooling Sys for Salem Generating Station,Unit 1
ML18107A3561999-06-0303 June 1999
Informs That Nj Dept of Environ Protection Bureau of Nuclear Engineering Has Reviewed Pse&G License Change Request S99-05 & Has No Comments
ML18107A3611999-05-27027 May 1999
Forwards Responses to NRC 990301 & 990323 RAIs for Salem & Hope Creek Generating Stations Relating to GL 96-05
ML18107A3301999-05-24024 May 1999
Forwards Suppl Info Re GL 95-07, Pressure Locking & Thermal Binding of Safety Related Power Operated Gate Valves. Encl Contains Methodology Used in Determination of Pressure Locking Susceptibility of PORVs Block Valves
ML18107A3291999-05-20020 May 1999
Forwards Redacted Response to NRC 990322 RAI Re Notification of Licensed Operator That Tested Positive for Alcohol. Attachment 2 Withheld,Per 10CFR2.790(a)(6)
ML18107A3031999-05-18018 May 1999
Provides Summary of Changes to NRC Commitments That Have Been Made But Not Reported by Other Means,Iaw with NEI Process for Managing NRC Commitments
ML18107A2891999-05-13013 May 1999
Forwards Rev 36 to Pse&G Nuclear Business Unit Emergency Plan. Rev 36 Incorporates Changes to Section 1-3,6 & 7 & 9-17.Attached Copy Includes All Sections of EP for Completeness
ML18107A2951999-05-12012 May 1999
Submits SG Tube Plugging Rept,Per Plant TS 4.4.6.5.a.Total of 47 Tubes Were Plugged During SG Tube Insps,Which Were Completed During Plant Tenth RFO
ML18107A2861999-05-11011 May 1999
Forwards Rev 0 to NFS-0174, COLR for Salem Unit 2 Cycle 11. COLR Rept Was Received by Util as Part of Reload SE
ML18107A2481999-04-29029 April 1999
Forwards 1998 Annual Radiological Environ Operating Rept for Salem & Hope Creek Generating Stations. Rept Summarizes Results of Radiological Environ Surveillance Program for 1998
ML18107A2511999-04-27027 April 1999
Submits 30-day Fuel Clad Temp Rept for Salem Generating Station,Units 1 & 2.Rept Describes Changes to Calculated Peak Clad Temp (PCT) for Plant Large & Small LOCA & Small Break LOCA Analyses
ML18107A2371999-04-26026 April 1999
Forwards Corrected Response to NRC RAI Re Licensee Request for Change to TS Permissible Enrichment Values for New Fuel Storage.Incorrect Attachment Was Provided with Util 990412 Ltr to Nrc.Encl Supersedes 990412 Submittal
ML18107A2631999-04-26026 April 1999
Provides Clarification on Licensing & Design Basis for 125 Vdc Battery Margins for Sgs & HCGS for Meeting SBO & Loca/ LOOP Loading Requirements
ML18107A2411999-04-22022 April 1999
Forwards Draft Revised Pages 4.1 & 4.2 of Nuclear Business Unit Emergency Plan for Hope Creek & Salem Generating Stations.Changes Are Noted in Italics
ML18107A1841999-04-14014 April 1999
Forwards PSEG Annual Rept for 1998, & PECO Annual Rept for 1998. Stockholders Annual Rept of Each Owner & Cash Flow Statements Showing 1998 Actual & 1999 Projected Cash Flow with Explanation Encl
ML18107A1981999-04-12012 April 1999
Responds to 990312 RAI Re Request for Change to TSs Permissible Enrichment Values for New Fuel Storage,Which Was Submitted on 990202
ML18107A1691999-04-12012 April 1999
Forwards Proprietary & non-proprietary Epips,Including Rev 17 to EPIP 807,rev 1 to NC.EP-EP.ZZ-0801(Q) & Rev 2 to NC.EP-EP.ZZ-0806(Q) & Revised EPIPs Table of Contents. Proprietary Info Withheld
ML20205K4541999-04-0808 April 1999
Forwards Revised Info Re 990330 NRC Nuclear Power Reactor Licensee Financial Qualifications & Decommissioning Funding Assurance Status Rept
ML18106B1491999-04-0505 April 1999
Forwards Drafts of Proposed Changes to Pages 4.1 & 4.2 of Emergency Plan,Which Are Contained on Page 4.2 & Noted in Italics & Underlined
ML20205F8981999-03-31031 March 1999
Provides Info Re Status of Decommissioning Funding for LGS, Units 1 & 2,PBAPS,Units 1,2 & 3 & Sgs,Units 1 & 2,per Requirements of 10CFR50.75(f)(1)
ML18106B1431999-03-31031 March 1999
Forwards Pse&G Rept on Financial Min Assurance for Period Ending 981231 for Hope Creek,Salem,Units 1 & 2 & Pbaps,Units 2 & 3,IAW 10CFR50.75
ML18107A2201999-03-30030 March 1999
Forwards Final Exercise Rept for 980303,full-participation Plume Exposure Pathway Exercise & 980505-07, full-participation Ingestion Pathway Exercise of Offsite Radiological Emergency Response for Salem & Hope Creek
1999-09-08
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Text
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' Public Service Electric and Gas Company Stanley LaBruna Public Service Electric and Gas Company P.O. Box 236, Hanccicks Bridge, NJ 08038 609-339-4800 Vice President - Nuclear Operations
- &IAY 1 6 1991 NLR-N91063 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:
ADDITIONAL INFORMATION REGARDING INSERVICE TESTING PROGRAM SALEM GENERATING STATION UNIT NOS. 1 AND 2 DOCKET NOS. 50-272 AND 50-311 Public Service Electric & Gas Company (PSE&G) hereby submits, in Enclosures 1 and 2 to this letter, a revision to the Inservice Testing (IST) Program for Salem Unit Nos. 1 and 2. The current program for the second ten year cycle, was submitted in response to Generic Letter 89-04, by letter dated, October 3, 1989 (ref:
NLR-N89196), and modified by letter dated, March 14, 1991 (ref:
NLR-N91015). This request is submitted in accordance with Section 4.0.5 of Appendix A to Technical Specifications and Section XI of the ASME Boiler and Pressure Vessel Code.
There are no additional relief requests included in this revision. Enclosure 1 contains a list of changes to the IST Program. Enclosure 2 contains the replacement pages for the IST Program.
Should there be any questions with regard to this submittal, please do not hesitate to contact us.
Sincerely, Enclosures (2)
,' 9105220236 910516---~
PDR ADOCK 05000272 p PDR
' . ::::=
/--:;//,
Document Control Desk NLR-N91063
~
./
2 M' 1 6 1991 c Mr. J. c. Stone Licensing Project Manager 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 Mr. Emanuel Mossa New Jersey Department of Labor and Industry PO Box 1503, Labor and Industry Building Trenton, NJ 08625
1
' I I
I I
ENCLOSURE 1 CHANGES TO THE IST PROGRAM
ADDITIONAL CHANGES IN SALEM IST PROGRAM SUBMITTAL UNIT 1 VALVE CHANGES NUMBER 1AF128 REMOVED VALVE FROM PROGRAM BECAUSE VALVE WAS REMOVED FROM SYSTEM.
1CC117 VALVE HAS BEEN REMOVED FROM TECHNICAL SPECIFICATIONS AS A CONTAINMENT ISOLATION VALVE.
1CC195 DELETED VALVE FROM PROGRAM. SYSTEM ISOLATION MAINTAINED BY MANUAL VALVE 1CC146 WHICH IS KEPT CLOSED.
1cc210 DELETED VALVE FROM PROGRAM. SYSTEM.ISOLATION MAINTAINED BY MANUAL VALVE 1CC145 WHICH IS KEPT CLOSED.
1DA70A VALVE WAS IMPROPERLY IDENTIFIED DURING PREVIOUS REVIEW AS RELIEVE VALVE. IT IS AN INTERNAL PUMP PRESSURE REGULATOR.
1DA70B VALVE WAS IMPROPERLY IDENTIFIED DURING PREVIOUS REVIEW AS RELIEVE VALVE. IT IS AN INTERNAL PUMP PRESSURE REGULATOR.
1DA70C VALVE WAS IMPROPERLY IDENTIFIED DURING PREVIOUS REVIEW AS RELIEVE VALVE. IT IS -AN INTERNAL PUMP PRESSURE REGULATOR.
11DF36. VALVE WAS IMPROPERLY IDENTIFIED DURING PREVIOUS REVIEW AS RELIEVE VALVE. IT IS AN INTERNAL PUMP PRESSURE REGULATOR.
12DF36 VALVE WAS IMPROPERLY IDENTIFIED DURING PREVIOUS REVIEW AS RELIEVE VALVE. IT IS AN INTERNAL PUMP PRESSURE REGULATOR.
11DF66 VALVE WAS IMPROPERLY IDENTIFIED DURING PREVIOUS REVIEW AS RELIEVE VALVE. *IT IS AN INTERNAL PUMP PRESSURE REGULATOR.
.12DF66 VALVE WAS IMPROPERLY IDENTIFIED DURING PREVIOUS REVIEW AS RELIEVE VALVE. IT IS AN INTERNAL PUMP PRESSURE REGULATOR.
13DF66 VALVE WAS IMPROPERLY IDENTIFIED DURING PREVIOUS REVIEW AS RELIEVE VALVE. IT IS AN INTERNAL PUMP PRESSURE REGULATOR.
lSJlO VALVE REMOVED FROM SYSTEM. REMOVED VALVE FROM PROGRAM.
11SJ54 VALVE REMOVED FROM PROGRAM. THE VALVE IS ADMINISTRATIVELY LOCKED OPEN AND POWER IS REMOVED.
12SJ54 VALVE REMOVED FROM PROGRAM. THE VALVE IS ADMINISTRATIVELY LOCKED OPEN AND POWER IS REMOVED.
13SJ54 VALVE REMOVED FROM PROGRAM. THE VALVE IS ,. ~-*;." - .:,-
ADMINISTRATIVELY LOCKED OPEN AND POWER IS REMOVED.
14SJ54 VALVE REMOVED FROM PROGRAM. THE VALVE IS ADMINISTRATIVELY LOCKED OPEN AND POWER IS REMOVED.
1SJ78 BORON INJECTION TANK ISOLATED. VALVE REMOVED FROM SYSTEM.
1SJ79 BORON INJECTION TANK* ISOLATED. VALVE REMOVED FROM SYSTEM.
11SJ93 VALVE REMOVED FROM PROGRAM. VALVE IS A PASSIVE VALVE WITH NO SAFETY FUNCTION.
12SJ93 VALVE REMOVED FROM PROGRAM. VALVE IS A PASSIVE VALVE WITH NO SAFETY FUNCTION.
13SJ93 VALVE REMOVED FROM PROGRAM. VALVE IS A PASSIVE VALVE WITH NO SAFETY FUNCTION.
14SJ93 VALVE REMOVED FROM PROGRAM. VALVE IS A PASSIVE VALVE WITH NO SAFETY FUNCTION.
1SJ107 BORON INJECTION TANK ISOLATED. VALVE REMOVED FROM SYSTEM.
1SJ108 BORON INJECTION TANK ISOLATED. VALVE REMOVED FROM.
SYSTEM.
11SS93 VALVE HAS BEEN REMOVED FROM TECHNICAL
- SPECIFICATIONS AS A CONTAINMENT ISOLATION VALVE.
12SS9~,_ VALVE HAS BEEN REMOVED FROM TECHNICAL*
SPECIFICATIONS AS A CONTAINMENT ISOLATION VALVE.
13SS93. VALVE HAS BEEN REMOVED FROM TECHNICAL SPECIFICATIONS AS A CONTAINMENT ISOLATION VALVE.
14SS93 VALVE HAS BEEN REMOVED FROM TECHNICAL SPECIFICATIONS AS A CONTAINMENT ISOLATION VALVE.
ADDITIONAL CHANGES IN SALEM IST PROGRAM SUBMITTAL UNIT 2 VALVE CHANGES NUMBER 2CC117 VALVE HAS BEEN REMOVED FROM TECHNICAL SPECIFICATIONS AS A CONTAINMENT ISOLATION VALVE.
2CC195 DELETED VALVE FROM PROGRAM. SYSTEM ISOLATION MAINTAINED BY MANUAL VALVE 1CC146 WHICH IS KEPT CLOSED.
2CC210 DELETED VALVE FROM PROGRAM. SYSTEM ISOLATION MAINTAINED BY MANUAL.VALVE 1CC145 WHICH IS KEPT CLOSED.
'>:-~ ~'J.*::r;~ef~~i~J.;ii;i~ ~?. :;:,,.~~ .
2DA70A VALVE WAS IMPROPERLY IDENTIFIED DURING PREVIOUS REVIEW AS RELIEVE VALVE. IT IS AN INTERNAL PUMP PRESSURE REGULATOR.
2DA70B VALVE WAS IMPROPERLY ~DENTIFIED DURING PREVIOUS REVIEW AS RELIEVE VALVE. IT IS AN INTERNAL PUMP PRESSURE REGULATOR.
2DA70C VALVE WAS IMPROPERLY IDENTIFIED DURING PREVIOUS REVIEW AS RELIEVE VALVE. IT IS AN INTERNAL PUMP PRESSURE REGULATOR.
21DF36 VALVE WAS IMPROPERLY IDENTIFIED DURING PREVIOUS REVIEW AS RELIEVE VALVE. IT IS AN INTERNAL PUMP PRESSURE REGULATOR.
- 22DF36 VALVE WAS IMPROPERLY IDENTIFIED DURING PREVIOUS REVIEW AS RELIEVE VALVE. IT IS AN INTERNAL PUMP PRESSURE REGULATOR.
21DF66 VALVE WAS IMPROPERLY IDENTIFIED DURING PREVIOUS REVIEW AS RELIEVE VALVE. IT IS AN INTERNAL PUMP PRESSURE REGULATOR.
22DF66 -VALVE WAS IMPROPERLY IDENTIFIED DURING PREVIOUS REVIEW AS RELIEVE VALVE. IT*IS AN INTERNAL PUMP PRESSURE REGULATOR.
23DF66 VALVE WAS IMPROPERLY IDENTIFIED DURING PREVIOUS
- REVIEW AS RELIEVE VALVE. IT IS AN INTERNAL PUMP PRESSURE REGULATOR.
.21SJ54 VALVE REMOVED FROM PROGRAM. THE VALVE IS ADMINISTRATIVELY LOCKED OPEN AND POWER IS REMOVED.
22SJ54 VALVE REMOVED FROM PROGRAM. THE VALVE IS ADMINISTRATIVELY LOCKED OPEN AND POWER IS REMOVED.
23SJ54 VALVE REMOVED FROM PROGRAM. THE VALVE IS ADMINISTRATIVELY LOCKED OPEN AND POWER *rs REMOVED.
24SJ54 VALVE REMOVED FROM PROGRAM. THE VALVE IS ADMINISTRATIVELY LOCKED OPEN AND POWER IS REMOVED.
2SJ78 BORON INJECTION TANK ISOLATED. VALVE REMOV~D FROM SYSTEM.
2SJ79 BORON INJECTION TANK ISOLATED. VALVE REMOVED FROM SYSTEM.
2SJ87 TANK TEMPERATURE MONITORED DAILY. VALVE HAS NO SAFETY FUNCTION. REMOVED FROM PROGRAM.
21SJ93 VALVE REMOVED FROM PROGRAM. VALVE IS A PASSIVE VALVE WITH NO SAFETY FUNCTION.
22SJ93 VALVE REMOVED FROM PROGRAM. VALVE IS A PASSIVE VALVE WITH NO SAFETY FUNCTION.
23SJ93 VALVE REMOVED FROM.PROGRAM. VALVE IS* A PASSIVE VALVE WITH NO SAFETY FUNCTION.
24SJ93 VALVE REMOVED FROM PROGRAM. VALVE IS A PASSIVE VALVE WITH NO SAFETY FUNCTION.
2SJ107 BORON INJECTION TANK ISOLATED. VALVE REMOVED FROM SYSTEM.
2SJ108 BORON INJECTION TANK ISOLATED. VALVE REMOVED FROM SYSTEM.
21SS93 VALVE HAS BEEN REMOVED FROM TECHNICAL
- SPECIFICATIONS AS A CONTAINMENT ISOLATIQN VALVE.
22SS93 VALVE HAS BEEN REMOVED FROM TECHNICAL
- SPECIFICATIONS AS A CONTAINMENT ISOLATION VALVE~
23SS93 VALVE HAS BEEN REMOVED FROM TECHNICAL SPECIFICATIONS AS A CONTAINMENT ISOLATION VALVE.
24SS93 *vALVE HAS BEEN REMOVED FROM TECHNICAL SPECIFICATIONS AS A CONTAINMENT ISOLATION VALVE.
