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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
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
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
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
ML18107A5341999-09-22022 September 1999
Provides Data Re Operator Licensing Exam for Salem & Hope Creek Station,In Response to NRC Form 536 (7-1999)
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
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
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.
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
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
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
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
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
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
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
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)
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
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
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.
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
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
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
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
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
1999-09-08
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Text
Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236 Nuclear Business Unit aueao 1999 LR-N990389 United States Nuclear Regulatory Commission Document Control Desk
TRANSMITTAL OF PLANT ATTRIBUTE LIBRARIES (PALs)
FOR SALEM NUCLEAR GENERATING STATION UNIT NOS. 1AND2, AND HOPE CREEK GENERATING STATION FACILITY OPERATING LICENSES DPR-70, DPR-75 AND NPF-57 DOCKET NOS. 50-272, 50-311 AND 50- 354 In accordance with 10CFR50 Appendix E, VI "Emergency Response Data System", 3.b., this letter transmits revised Plant Attribute Libraries (PALs) for Salem and Hope Creek Generating Stations. The revision to the PALs is required to support changes being made in the operating systems for the Emergency Response Data System (EROS) computers. Specifically the Safety Parameter Display System (SPDS), which is a feeder computer to EROS, is being modified to make SPDS Y2K compliant.
- Attachments 1 and 2 are the revised PALs for Hope Creek and Salem respectively. Changes are identified by revision bars.
Should you have any questions, please contact Jack D. Southers, Senior Engineer, at (856) 339-5630.
Sincerely Gabor Salamon Manager Licensing
' J I .
! \
"~9083000s0 '990820 PDR ADOCK 05000272 F PDR 95-2168 RC:\/ i;*o
. e Document Control Desk 2 LR-N990389 Att3chments C Mr. H.J. Miller, Administrator - Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. P. Milano, Licensing Project Manager - Salem .
U. S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 0881 Rockville, MD 20852 Mr. R Ennis, Licensing Project Manager - Hope Creek U.S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 0881 Rockville, MD 20852 Mr. S. Morris (X24)
USNRC Senior Resident Inspector-Salem USNRC Senior Resident Inspector-Hope Creek (X24)
Mr. K. Tosch, Manager IV Bureau of Nuclear Engineering PO Box415 Trenton, NJ 08625 Mr. J. Jolicoeur, Office for Analysis and Evaluation U. S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 4A43 Rockville, MD 20852
DOCUMENT CONTROL DESK LR-N990389 ATTACHMENT 1 HOPE CREEK PLANT ATTRIBUTES LIBRARY
HOPE CREEK I. Contacts NOTE: Please provide name, title, mailing address, and phone number.
A. Survey Coordinator (i.e. contact for later clarification of questionnaire answers):
Jack Southers Senior Engineer Public Service Electric and Gas Co.
MCN47 PO Box 236 Hancock's Bridge, NJ 08038 856-339-5630 B. Computer Hardware Specialist(s):
Jack Southers Senior Engineer Public Service Electric and Gas Co.
MCN47 PO Box 236 Hancock's Bridge, NJ 08038 856-339-5630 C. Systems Software Specialist(s):
Jack Southers Senior Engineer Public Service Electric and Gas Co.
MCN47 PO Box 236 Hancock's Bridge, NJ 08038 856-339-5630 D. Application-level Software Specialist(s):
Jack Southers Senior Engineer ~.
Public Service Electric and Gas Co.
MCN47 PO Box 236
_Hancock's Bridge, NJ 08038 856-339-5630 E. Telephone Systems Specialist(s):
Pat O'Connell Project Manager - lnfonnation Technologies Public Service Electric and Gas Co.
MCN41 PO Box 236 Hancock's Bridge, NJ 08038 856-339-1225
. HOPECREEK
- -- -II. - Selection of Data Feeders A. How many data feeders are there (six 'maximum)?
There will be one data feeder. The Hope Creek ERDS Computer will transmit data received from Hope Creek Safety Parameter Display System (SPDS) Computer.
B. Identify the selected data feeders and provide the following for each.
( 1) a short description of the categories of data points it will provide (e.g. met. Rad. or plant -
data points. By unit) and (2) the rationale for selecting it if another system can also can also provide its categories of data points The Safety Parameter Display System (SPDS) is the ERDS data feeder:
(1) The SPDS will provide existing Hope Creek plant data points, as defined ni the Data Point Library (PPL).
(2)(a) ERDS parameters are readily available on SPDS, since the SPDS is used to aid control room personnel in determining the safety status of the plant during emergency conditions.
(b) Choosing SPDS as the feeder for Hope Creek and Salem aids in maintaining consistency in design and maintenance.
C. Which data feeder is the site time determining feeder? This should be the feeder which is providing the majority of the data points.
SPDS is the only data feeder.
-1 HOPE CREEK III. DATA FEEDER INFORMATION Note: A new Section IV must be filled out for each feeder system selected.
General Questions
- 1. Identification of data Feeder
- a. What is the name in local parlance given to this data feeder (e.g. Emergency response Information System)? Please give both the acronym and the words forming it.
The SPDS (Safety Parameter Display System) is the data feeder.
- b. Is this the site time determining feeder?
Yes, the SPDS is the only data feeder.
- c. How often will this feeder transmit an update set to the ERDS (in seconds)?
The SPDS will transmit data at least every 15 seconds to the Hope Creek ERDS computer..
- 2. Hardware/Software Environment
- a. Identify the manufacturer and model number of the data feeder hardware.
The SPDS resides on redundant ENCORE 8780 computers.
- b. Identify the Operating System.
The SPDS utilizes the ENCORE MPX Operating System, version 3.3 U02.
- c. What method of timekeeping is implemented on this feeder system (Daylight Savings, Standard, Greenwich)?
Daylight Savings Time is the method of timekeeping on the SPDS.
- d. In what time zone is this feeder located?
Hope Creek is in the Eastern Time Zon.e.
- 3. Data Communication Details
- a. Can this data feeder provide asynchronous serial data communication (RS-232-C) with full-modem control?
Yes, the SPDS can provide asynchronous serial data communication.
- b. Will this feeder transmit in ASCII or EBCDIC?
The SPDS will transmit in ASCII.
HOPE CREEK
- c. Can this feeder transmit at a serial baud of2400 bps? If not, at what baud rate can it transmit?
- The SPDS can transmit at 2400 bps.
- d. Does the operating system support XON/XOFF flow control?
The SPDS supports XON/XOFF.
I. Are there any problems forseen with the NRC using XON/XOFF to control the transmission of data?
No problems are forseen using XON/XOFF.
- e. If it is not feasible to reconfigure a serial port fro the ERDS linkup (i.e. change the baud rate, parity, etc.), please explain why.
- f. Do any ports currently exist for the ERDS linkup?
Yes, the Hope Creek ERDS computer has ports available for the ERDS linkup, from the SPDS computers and to the NRC.
- 1. If not, is it possible to add additional ports?
NIA
- 2. If yes, will the port be used solely by the ERDS or shared with other non-emergency-time users? Give details.
The Hope Creek ERDS Computer ports used for the link will be dedicated for ERDS.
- 4. Data Feeder Physical Environment and Management
- a. Where is the data feeder located in terms of the TSC, EOF, and control room?
The SPDS Computers are located in the Hope Creek Computer room. The main control rooms are located in a separate building.
- b. Is the data feeder protected from loss of supply of electricity?
The SPDS power is fed by an UPS.
- c. Is there a human operator for this data feeder?
No, there is no human operator for normal SPDS operations.
- 1. If so, how many hours a day is the feeder attended?
NIA
HOPE CREEK
- IV. DATA FEEDER INFORMATION Note: A new Section IV must be filled out for each feeder system selected.
General Questions
- 1. Identification of data Feeder
- a. What is the name in local parlance given to this data feeder (e.g. Emergency response Information System)? Please give both the acronym and the words forming it.
Hope Creek ERDS (Emergency Response Data System) Computer System.
- b. Is this the site time determining feeder?
No, the Hope Creek ERDS computer is not a data feeder. It is only a "personal computer" used for ERDS data transmission.
- c. How often will this feeder transmit an update set to the ERDS (in seconds)?
EROS will transmit data to the NRC every 15 seconds.
- 2. Hardware/Software Environment
- a. Identify the manufacturer and model number of the data feeder hardware.
The ERDS computer will be an Hewlett Packard Vectra.
- b. Identify the Operating System.
The Operating System will be Windows NT 4.0
- c. What method of timekeeping is implemented on this feeder system (Dayl_ight Savings, Standard, Greenwich)?
- The ERDS will implement Daylight Savings Time.
- d. In what time zone is this feeder located?
Hope Creek is in the Eastern Time Zone.
- 3. Data Communication Details
- a. Can this data feeder provide asynchronous serial data communication (RS-232-C) with full-modem control?
Yes, the ERDS will provide asynchronous serial data communication.
- b. Will this feeder transmit in ASCII or EBCDIC?
The EROS will transmit in ASCII.
HOPE CREEK
- c. Can this feeder transmit at a serial baud of2400 bps? Ifnot, at what baud rate can it transmit?
The ERDS can transmit at 2400 bps.
- d. Does the operating system support XON/XOFF flow control?
The ERDS supports XON/XOFF.
- 1. Are there any problems forseen with the NRC using XON/XOFF to control the transmission of data?
No problems are forseen using XON/XOFF.
- e. If it is not feasible to reconfigure a serial port for the ERDS linkup (i.e. change the baud rate, parity, etc.), please explain why.
NIA
- f. Do any ports currently exist for the ERDS linkup?
An ERDS port will exist for the Hope Creek NRC ERDS linkup.
- 1. If not, is it possible to add additional ports?
NIA
- 2. If yes, will the port be used solely by the ERDS or shared with other non-emergency-time users? Give details.
The Hope Creek ERDS Computer ports used for the link will be dedicated for ERDS.
- 4. Data Feeder Physical Environment and Management
- a. Where is the data feeder located in terms of the TSC, EOF, and control room?
The ERDS Computers are located in the Hope Creek Computer room. The main control rooms are located in a separate building.
- b. Is the data feeder protected from loss of supply of electricity?
The ERDS power is fed by an UPS.
- c. Is there a human operator for this data feeder?
No, there is no human operator for normal ERDS operations.
I. If so, how many hours a day is the feeder attended?
NIA
i
- I DOCUMENT CONTROL DESK LR-N990389 ATTACHMENT 2 SALEM PLANT ATTRIBUTES LIBRARY
SALEM UNITS 1 & 2 L Contacts NOTE: Please provide name, title, mailing address, and phone number.
A. Survey Coordinator (i.e. contact for later clarification of questionnaire answers):
Jack Southers Senior Engineer Public Service Electric and Gas Co.
MCN47 PO Box236 Hancock's Bridge, NJ 08038 856-339-5630 B. Computer Hardware Specialist(s):
Jack Southers Senior Engineer Public Service Electric and Gas Co.
MCN47 PO Box 236 Hancock's Bridge, NJ 08038 856-339-5630 C. Systems Software Specialist(s):
Jack Southers Senior Engineer Public Service Electric and Gas Co.
MCN47 PO Box 236 Hancock's Bridge, NJ 08038 856-339-5630 D. Application-level Software Specialist(s):
Jack Southers Senior Engineer Public Service Electric and Gas Co.
MCN47 PO Box236 Hancock's Bridge, NJ 08038 856-339-5630 E. Telephone Systems Specialist(s):
Pat O'Connell Project Manager - Information Technologies Public Service Electric and Gas Co.
MCN41 PO Box 236 Hancock's Bridge, NJ 08038 856-339-1225
SALEM UNITS 1 & 2 II. Selection of Data Feeders A. How many data feeders are there (six'maximum)?
There will be one data feeder. The Salem ERDS Computer will transmit data received from Salem Safety Parameter Display System (SPDS) Computer.
B. Identify the selected data feeders and provide the following for each.
(I) a short description of the categories of data points it will provide (e.g. met. Rad. or plant data points. By unit) and (2) the rationale for selecting it if another system can also can also provide its categories of data points The Safety Parameter Display System (SPDS) is the ERDS data feeder:
(1) The SPDS will provide existing Salem plant data points, as defined in the r>ata Point Library (DPL),
(2)(a) ERDS parameters are readily available on SPDS, since the SPDS is used to aid control room personnel in determining the safety status of the plant during emergency conditions.
(b) Choosing SPDS as the feeder for Hope Creek and Salem aids in maintaining consistency in design and maintenance.
C. Which data feeder is the site time determining feeder? This should be the feeder which is providing the majority of the data points.
SPDS is the only data feeder.
SALEM UNITS 1 & 2 III. DATA FEEDER INFORMATION Note: A new Section IV must be filled out for each feeder system selected.
General Questions
- 1. Identification of data Feeder
- a. What is the name in local parlance given to this data feeder (e.g. Emergency response Information System)? Please give both the acronym and the words forming it.
The SPDS (Safety Parameter Display System) is the data feeder.
- b. Is this the site time determining feeder?
Yes, the SPDS. is the only data feeder.
- c. How often will this feeder transmit an update set to the ERDS (in seconds)?
The SPDS will transmit data at least every 15 seconds to the Salem ERDS computer.
- 2. Hardware/Software Environment
- a. Identify the manufacturer and model number of the data feeder hardware.
The SPDS resides on redundant ENCORE 8780 computers.
- b. Identify the Operating System.
The SPDS utilizes the ENCORE MPX Operating System, version 3.4 U02.
- c. What method of timekeeping is implemented on this feeder system (Daylight Savings, Standard, Greenwich)?
Daylight Savihgs Time is the method of timekeeping on the SPDS.
- d. In what time zone is this feeder located?
Salem is in the Eastern Time Zone.
- 3. Data Communication Details
- a. Can this data feeder provide asynchronous serial data communication (RS-232-C) with full-modem control?
Yes, the SPDS can provide asynchronous serial data communication.
- b. Will this feeder transmit in ASCII or EBCDIC?
The SPDS will transmit in ASCII.
- c. Can this feeder transmit at a serial baud of2400 bps? If not, at what baud rate can it
\
transmit?
The SPDS can transmit at 2400 bps.
SALEM UNITS 1 & 2
- d. Does the operating system support XON/XOFF flow control?
The SPDS supports XON/XOFF.
- 1. Are there any problems forseen with the NRC using XON/XOFF to control the transmission of data?
No problems are forseen using XON/XOFF.
- e. If it is not feasible to reconfigure a serial port for the ERDS linkup (i.e. change the baud rate, parity, etc.), please explain why.
NIA
- f. Do any ports currently exist for the ERDS linkup?
Yes, the Salem ERDS computer has ports available for the ERDS linkup, from the SPDS computers and to the NRC.
- 1. If not, is it possible to add additional ports?
NIA
- 2. If yes, will the port be used solely by the ERDS or shared with other non-emergency-time users? Give details.
The Salem ERDS Computer ports used for the link will be dedicated for ERDS.
- 4. Data Feeder Physical Environment and Management
- a. Where is the data feeder located in terms of the TSC, EOF, and control room?
The SPDS Computers are located in the Salem TSC. The main control rooms are located in a separate building.
- b. Is the data feeder protected from loss of supply of electricity?
The SPDS power is fed by an UPS.
- c. Is there a human operator for this data feeder?
No, there is no human operator for normal SPDS operations.
- 1. If so, how many hours a day is the feeder attended?
NIA
SALEM UNITS 1 & 2
- IV. DATA FEEDERINFORMATION Note: A new Section IV must be filled out for each feeder systein selected.
General Questions
- 1. Identification of data Feeder
- a. What is the name in local parlance given to this data feeder (e.g. Emergency response Information System)? Please give both the acronym and the words forming it.
Salem ERDS (Emergency Response Data System) Computer System.
- b. Is this the site time determining feeder?
No, the Salem ERDS computer is not a data feeder. It is only a "personal computer" used for ERDS data transmission.
- c. How often will this feeder transmit an update set to the ERDS (in seconds)?
ERDS will transmit data to the NRC every 15 seconds.
- 2. Hardware/Software Environment
- a. Identify the manufacturer and model number of the data feeder hardware.
The ERDS computer will be an Hewlett Packard Vectra.
- b. Identify the Operating System.
The Operating System will be Windows NT 4.0
- c. What method of timekeeping is implemented on this feeder system (Dayljght Savings, Standard, Greenwich)?
The ERDS will implement Daylight Savings Time.
- d. In what time zone is this feeder located?
Salem is in the Eastern Time Zone.
- 3. Data Communication Details
- a. Can this data feeder provide asynchronous serial data communication (RS-232-C) with full-modem control?
Yes, the ERDS will provide asynchronous serial data communication.
- b. Will this feeder transmit in ASCII or EBCDIC?
The ERDS will transmit in ASCII.
SALEM UNITS 1 & 2
- c. Can this feeder transmit at a serial baud of2400 bps? If not, at what baud rate can it transmit?
The ERDS can transmit at 2400 bps.
- d. Does the operating system support XON/XOFF flow control?
The ERDS supports XON/XOFF.
- 1. Are there any problems forseen with the NRC using XON/XOFF t9 control the transmission of data?
No problems are forseen using XON/XOFF.
- e. If it is not feasible to reconfigure a serial port for the ERDS linkup (i.e. change the baud rate, parity, etc.), please explain why.
NIA
- f. Do any ports currently exist for the ERDS linkup?
An ERDS port will exist for the Salem Unit I NRC ERDS linkup and an ERDS port will exist for the Salem Unit 2 NRC ERDS linkup.
- 1. If not, is it possible to add additional ports?_
NIA
- 2. If yes, Will the port be used solely by the ERDS or shared with other non-emergency-time users? Give details.
The Salem ERDS Computer ports used for the link will be dedicated for ERDS.
- 4. Data Feeder Physical Environment and Mana_gement
- a. Where is the data feeder located in terms of the TSC, EOF, and control room?
The ERDS Computers are located in the Salem TSC. The main control rooms are located in a separate building.
- b. Is the data feeder protected from loss of supply of electricity?
The ERDS power is fed by an UPS.
- c. Is there a human operator for this data feeder?
No, there is no human operator for normal ERDS operations.
- 1. If so, how many hours a day is the feeder attended?
NIA
