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MONTHYEARML20236X7951998-08-0606 August 1998 Requests for Addl Info Re Safety/Relief Valve Setpoint Tolerance Change for Plant Project stage: Other ML20154B3341998-09-29029 September 1998 Requests That Encl Info on GE Rept NEDC-32511P Be Reviewed & Revised Proprietary Version of Subj Rept Be Submitted.Some Info in Rept Should Not Be Exempt from Public Disclosure & Should Be Released & Placed in PDR Project stage: Other ML20196H0301998-12-0101 December 1998 Informs That NEDC-32511P,rev 1,dtd Oct 1998 Marked as Proprietary,Will Be Withheld from Public Disclosure Pursuant to 10CFR2.790(b)(5) & Section 103(b) of Atomic Energy Act of 1954,as Amended Project stage: Other 1998-08-06
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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 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 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 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 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 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 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 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 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 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 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 ML20196J4421999-07-0101 July 1999 Forwards Request for Addl Info Re Increase of Allowable Main Steam Isolation Valve (MSIV) Leak Rate & Deletion of MSIV Sealing Sys for Plant 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 ML20196F9441999-06-21021 June 1999 Forwards Insp Rept 50-354/99-03 on 990419-0529.Violations Noted.Two Violations of NRC Requirements Occurred Re Reactor Bldg Ventilation Setpoints & Control Rod Drop Analyses 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 ML20209B6441999-06-21021 June 1999 Offers No Comments on Licensee 990529 Request for Revs to Plant Radiological Effluent Ts,Per GL 89-01 ML20209C0621999-06-21021 June 1999 Forwards NPDES Discharge Monitoring Rept,May 1999, for Hcgs.Rept Prepared Specifically for EPA & Nj Dept of Environ Protection 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 ML20212J0541999-06-17017 June 1999 Responds to Requesting That NRC Staff ...Allow BWR Plants Identified to Defer Weld Overlay Exams Until March 2001 or Until Completion of NRC Staff Review & Approval of Proposed Generic Rept,Whichever Comes First 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 ML20195J1101999-06-0707 June 1999 Informs of Completion of Review of Providing Updated Status on Implementation of Commitments Made in Response to GL 89-13.Confirms Revs Made to Previous Commitments to Resolve Monitoring Pressure Drop Problem ML20195J1051999-06-0707 June 1999 Informs That NRC Office of Nuclear Reactor Regulation Reorganized Effective 990328.As Part of Reorganization,Div of Licensing Project Mgt Created.Jw Clifford Will Be Section Chief for Hope Creek Generating Station ML20207F2681999-06-0303 June 1999 Responds to by Forwarding Gfes & NRC Written Exam Grades for List of Hope Creek Operators Submitted by DE Jackson.Absence of Gfes Grade Indicates That Operator Previously Issued RO or SRO License.Without Encl ML20207D0201999-05-27027 May 1999 Discusses 990512 Meeting to Identify Insp Activities at Hope Creek Facility Over Next Six Months & Informs of Planned Insps in Order for Licensee to Have Opportunity to Prepare & Provide Region I with Feedback on Schedule Conflicts ML18107A3611999-05-27027 May 1999 Forwards Responses to NRC 990301 & 990323 RAIs for Salem & Hope Creek Generating Stations Relating to GL 96-05 ML20207A3451999-05-20020 May 1999 Discusses Completion of Licensing Action for NRC Bulletin 96-003, Potential Plugging of ECCS Strainers by Debris in Bwrs ML20195B9931999-05-20020 May 1999 Forwards NPDES Discharge Monitoring Rept,Apr 1999, for Hgcs.Rept Prepared Specifically for EPA & Nj Dept of Environ Protection ML20206Q4461999-05-14014 May 1999 Forwards SE Accepting GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Plant ML20206U8451999-05-14014 May 1999 Forwards Insp Rept 50-354/99-02 on 990308-0418.Violations Re Fuel Handling Errors & Missed Temp Monitoring During Reactor Vessel Head Tensioning Occurred & Being Treated as non-cited Violation 1999-09-08
[Table view] Category:OUTGOING CORRESPONDENCE
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 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 ML20217C4391999-10-0606 October 1999 Informs That Util Authorized to Administer Initial NRC Retake Written Exam to Applicant Listed,During Week of 991011 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 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 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 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 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 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 ML20196J4421999-07-0101 July 1999 Forwards Request for Addl Info Re Increase of Allowable Main Steam Isolation Valve (MSIV) Leak Rate & Deletion of MSIV Sealing Sys for Plant ML20196F9441999-06-21021 June 1999 Forwards Insp Rept 50-354/99-03 on 990419-0529.Violations Noted.Two Violations of NRC Requirements Occurred Re Reactor Bldg Ventilation Setpoints & Control Rod Drop Analyses ML20212J0541999-06-17017 June 1999 Responds to Requesting That NRC Staff ...Allow BWR Plants Identified to Defer Weld Overlay Exams Until March 2001 or Until Completion of NRC Staff Review & Approval of Proposed Generic Rept,Whichever Comes First ML20195J1051999-06-0707 June 1999 Informs That NRC Office of Nuclear Reactor Regulation Reorganized Effective 990328.As Part of Reorganization,Div of Licensing Project Mgt Created.Jw Clifford Will Be Section Chief for Hope Creek Generating Station ML20195J1101999-06-0707 June 1999 Informs of Completion of Review of Providing Updated Status on Implementation of Commitments Made in Response to GL 89-13.Confirms Revs Made to Previous Commitments to Resolve Monitoring Pressure Drop Problem ML20207F2681999-06-0303 June 1999 Responds to by Forwarding Gfes & NRC Written Exam Grades for List of Hope Creek Operators Submitted by DE Jackson.Absence of Gfes Grade Indicates That Operator Previously Issued RO or SRO License.Without Encl ML20207D0201999-05-27027 May 1999 Discusses 990512 Meeting to Identify Insp Activities at Hope Creek Facility Over Next Six Months & Informs of Planned Insps in Order for Licensee to Have Opportunity to Prepare & Provide Region I with Feedback on Schedule Conflicts ML20207A3451999-05-20020 May 1999 Discusses Completion of Licensing Action for NRC Bulletin 96-003, Potential Plugging of ECCS Strainers by Debris in Bwrs ML20206U8451999-05-14014 May 1999 Forwards Insp Rept 50-354/99-02 on 990308-0418.Violations Re Fuel Handling Errors & Missed Temp Monitoring During Reactor Vessel Head Tensioning Occurred & Being Treated as non-cited Violation ML20206Q4461999-05-14014 May 1999 Forwards SE Accepting GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Plant ML20206Q6211999-05-14014 May 1999 Informs That on 990119 Licensee Provided NRC with Several Revised TS Bases Pages for Plant.Ts Bases Pages B 3/4 6-1 & B 3/4 6-2 Were Revised ML20206R2691999-05-12012 May 1999 Informs That During 990504 Telcon Between J Caruso & H Hanson,Arrangements Were Made for Administration of Licensing Written Retake Exam at Hope Creek Nuclear Generating Station During Week of 990927 ML20206C8431999-04-22022 April 1999 Forwards SER Authorizing Util 980728 Submitted Relief Requests Associated with Changes Made to Repair Plan for Core Spray Nozzle Weld N5B ML20205S7911999-04-19019 April 1999 Forwards Insp Rept 50-354/99-01 on 990124-0307.Violations Noted.Some Human Performance Errors Occurred During Numerous Outage Activities,Util Appropriately Reacted to Each of Errors & Initiated Corrective Actions ML20205R0861999-04-14014 April 1999 Informs That Final Review of Hard Copy of PPR Re Hope Creek, Issued 990409 Had Error.Electronic Version e-mailed Was Not Effected.Forwards Pp with Correction in Margin.Without Encl ML20205R0461999-04-14014 April 1999 Forwards Associated Page with Correction Marked in Margin of PPR of Salem Issued 990409.During Final Review of Hard Copy, Error Was Noted.Without Encl IR 05000354/19983021999-04-0909 April 1999 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-354/98-302 Issued on 990226.Response Indicates That Licensee Corrected Violation & Initiated Measures to Prevent Recurrence ML20205N2481999-04-0909 April 1999 Discusses Hope Creek Generating Station Plant Performance Review Conducted for Period April 1998 Through Jan 1999 & Informs of NRC Planned Insp Effort Resulting from Ppr. Historial Listing & Insp Plans for Next Few Months Encl ML20205G5961999-03-19019 March 1999 Forwards Safety Evaluation of Relief Request Re ASME Code Case N-567, Alternate Requirements for Class 1,2 & 3 Replacement Components Section Xi,Div 1. Request Acceptable ML20205F8771999-03-18018 March 1999 Forwards SE Authorizing Licensee 971222 Relief Requests Re Second 10-year Interval for Pumps & Valves IST Program for Hope Creek Generating Station ML20207D5741999-03-0101 March 1999 Discusses Pse&G 980604 Updated Response to GL 96-05 Indicating Intent to Implement Provisions of JOG Program on MOV Periodic Verification at Hope Creek Generating Station. Forwards RAI Re GL 96-05 Program at Hope Creek ML20198H6211998-12-24024 December 1998 Forwards Notice of Withdrawal of 970826,as Suppl 980424 & 0924 Amend Request for FOL NPF-57.Proposed Change Would Have Modified Facility TSs Pertaining to Filtration,Recirculation & Ventilation Sys Surveillance Testing Requirements ML20198L3571998-12-22022 December 1998 Forwards Insp Rept 50-354/98-11 on 981101-1212.No Violations Noted.Insp Generally Characterized by safety-conscious Operations,Effective Engineering & Maint Practices & Careful Radiological Work Controls ML20198H6661998-12-17017 December 1998 Informs That Attachment 1 to Ltr LR-N98404,dtd 980825 Marked as Proprietary,Will Be Withheld from Public Disclosure Pursuant to 10CFR2.790(b)(5) & Section 103(b) of Atomic Energy Act of 1954,as Amended ML20196K1371998-12-0909 December 1998 Advises of Planned Insp Effort Resulting from Hope Creek Insp Review Planning Meeting Conducted on 981110.Details of Insp Plan for Next 6 Months Encl ML20197H3841998-12-0707 December 1998 Informs That Licensee Authorized to Administer Initial Written Exams to Listed Applicants on 981222.NRC Region I Operator Licensing Staff Will Administer Operating Tests ML20196H0301998-12-0101 December 1998 Informs That NEDC-32511P,rev 1,dtd Oct 1998 Marked as Proprietary,Will Be Withheld from Public Disclosure Pursuant to 10CFR2.790(b)(5) & Section 103(b) of Atomic Energy Act of 1954,as Amended ML20196F7991998-11-30030 November 1998 Forwards Rept Representing Results of 981026-29 Audit of Year 2000 Pragram at Hope Creek Generating Station.Audit Conducted as Followup to NRC GL 98-01, Year 2000 Readiness of Computer Sys at Npps, Issued 980511 ML20196D0711998-11-23023 November 1998 Forwards Insp Rept 50-354/98-10 on 980920-1031 & Notice of Violation Re Preforming Single Cell Charge on safety-related Battery Cell in Configuration Prohibited by Station Procedures ML20154Q7071998-10-16016 October 1998 Forwards Exam Rept 50-354/98-03OL Conducted by NRC During Periods of 980304-12,0519-21,22-28 & 0629.All Five Reactor Operator Applicants & Four of Five Senior Reactor Applicants Passed Exams ML20154P4011998-10-0909 October 1998 First Final Response to FOIA Request for Records.Records in App a Available in Pdr.Records in App B Partially Withheld (Ref FOIA Exemption 3) IA-98-323, First Final Response to FOIA Request for Records.Records in App a Available in Pdr.Records in App B Partially Withheld (Ref FOIA Exemption 3)1998-10-0909 October 1998 First Final Response to FOIA Request for Records.Records in App a Available in Pdr.Records in App B Partially Withheld (Ref FOIA Exemption 3) ML20154J8501998-10-0909 October 1998 Forwards Insp Rept 50-354/98-08 on 980809-0919 & Notice of Violation Re Inadequate Corrective Actions to Resolve Steam Leaks from Piping Located in Torus Room ML20154F1121998-10-0202 October 1998 Forwards Insp Rept 50-354/98-09 on 980817-26 & 0908.No Violations Identified.Major Areas Inspected:Maint, Engineering & Mgt Meeting ML20154B3341998-09-29029 September 1998 Requests That Encl Info on GE Rept NEDC-32511P Be Reviewed & Revised Proprietary Version of Subj Rept Be Submitted.Some Info in Rept Should Not Be Exempt from Public Disclosure & Should Be Released & Placed in PDR ML20154B3781998-09-25025 September 1998 Informs That Facility Scheduled to Administer NRC Generic Fundamentals Exam on 981007.Sonalysts,Inc Authorized Under Contract to Support NRC in Administration of Activities. Ltr & Encls Provide Instructions & Guidelines IR 05000354/19980061998-09-11011 September 1998 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-354/98-06 Issued on 980721 IR 05000354/19980021998-09-11011 September 1998 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-354/98-02 on 980423.Response Indicated Violations Corrected & Measures Initiated to Prevent Recurrence ML20151W9711998-09-10010 September 1998 Informs That as Part of NRC PRA Implementation Plan, Commission Has Assigned Two Senior Reactor Analysts (Sras) to Each Regional Ofc.T Shedlosky & J Trapp Have Been Assigned as SRAs in Region I 1999-09-08
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UNITED STATES NUCLEAR REGULATORY COMMISSION W.- -Q
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WASHINGTON, D.C. 20066 4001 September 29, 1998 Mr. Harold W. Keiser Chief Nuclear Officer & President Nuclear Business Unit Public Service Electric & Gas Company Post Office Box 236 Hancocks Bridge, NJ 08038
SUBJECT:
REQUEST FOR WITHHOLDING INFORMATION FROM PUBLIC DISCLOSURE, HOPE CREEK GENERATING STATION - SAFETY / RELIEF VALVE TOLERANCE ANALYSIS (TAC NO. MA1674)
Dear Mr. Keiser:
By Public Service Electric and Gas Company's letter (LR-N97117) dated April 28,1998, and General Electric Company's (GE) affidavit executed by George B. Stramback, dated April 22, 1998, (Attachment 4 to the letter), you submitted GE Report NEDC-32511P, " Safety Review for Hope Creek Generating Station Safety / Relief Valve Tolerance Analyses," dated April 1996, (Attachment 5 to the letter), and requested that it be withheld from public disclosure pursuant to 10 CFR 2.790.
GE stated that the sutandled information should be considered exempt from mandatory public disclosure for the following reasons:
(a)
Information that discloses a process, method, or apparatus, including supporting data and analyses, where prevention of its use by General Electric's competitors without license from General Electric constitutes a competitive economic advantage over other companies.
(b)
Information which, if used by a competitor, would reduce (the) expenditure of resources or improve [the, ompetitive position in the design, manufacture, shipment, installation, assurance of qs JIity, or licensing of a similar product.
(c)
The information identified in [ Attachment 5 to letter LR-N97117] is classified as proprietary because it contains detailed results of analytical models, methods and processes, including computer codes, which GE has developed, obtained NRC approval of, and applied to perform evaluations of loss-of-coolant accident for the BWR.
.)
The developmen', and approval of the BWR loss-of-coolant accident analysis computer codes used in this analysis was achieved at significant cost, on the order of several million dollars, to GE.
The development of the evaluation process along with the interpretation and application of f
the analytical results is derived from the extensive experience database that constitutes a major GE asset.
9810050170 980929 PDR ADOCK 05000354 P
PDR EC Rd CEUE3 08PV
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i H. Keiser We have reviewed your submittal and the material in accordance with the requirements of i
10 CFR 2.790 and, on the basis of GE's statements, have determined that some of the information in GE report NEDC-32511P contains proprietary commercial information. However, the staff has concluded that some of the information in repwt NEDC-32511P that is denoted as proprietary (i.e., marked with vertical bars in the right hand margin of affected pages) should not be exempt from public disclosure and should be released and placed in the Public Document Room (PDR). The specific information that we believe should not be exempt from mandatory public disclosure is listed in the enclosure to this letter along with the reasons for our conclusions.
Therefore, we request that you review the enclosed information and submit a revised proprietary version of GE report NEDC-32511P. In addition, a nonproprietary version of the report should also be submitted to allow for proper docketing pursuant 610 CFR 2.790(b)(1)(i). Upon receipt of this information, we will proceed with our determination as to whether the GE report should be withheld from public disclosure.
We request that the information requested above be provided within 30 days of receipt of thic letter. The 30 day response timeframe was discussed with Mr. James Priest of your staff on September 9,1998, if circumstances result in the need to revise your response date, or if you have any questions, please contact m2 at (301) 415-1420.
1 Sincerely, l
original signed by:
Richard B. Ennis, Project Manager Project Directorate 1-2 Division of Reactor Projects - I!il Office of Nuclear Reactor Regulation Docket No. 50-354
Enclosure:
Proprietary Finding on GE Report NEDC-32511P cc: See next page DISTRIBUTION Docket File REnnis GThomas PUBLIC TClark GHammer PDI-2 Reading TCollins JZwolinski MSiemien RCapra JLinville, RGN-l
/
n a%
OFFICE PDI-2/PM PDI-3/LA SRXB/BC OGCfn U PDI-2/D NAME REnnis:mw TClarkM TCollins MSiemien RCapra "
DATE 9/ lb /98 f / /(,/98 9 / /X /98 i/N/98
'/4 /98 OFFICIAL RECORD COPY DOCUMENT NAME: HCMA1674. GEN
s e
H. Keiser.
We have reviewed your submittal and the material in accordance with the requirements of 10 CFR 2.790 and, on the basis of GE's statements, have determined that some of the information in GE report NEDC-32511P contains proprietary commercial information. However, the staff has concluded that some of the information in report NEDC-32511P that is denoted as l
proprietary (i.e., marked with vertical bars in the right hand margin of affected pages) should not I
be exempt from public disclosure and should be released and placed in the Public Document Room (PDR). The specific information that we believe should not be exempt from mandatory public disclosure is listed in the enclosure to this letter along with the reasons for our conclusions.
Therefore, we request that you review the enclosed information and submit a revised proprietary version of GE report NEDC-32511P. In addition, a nonproprietary version of the report should also be submitted to allow for proper docketing pursuant to 10 CFR 2.790(b)(1)(i). Upon receipt of this information, we will proceed with our determination as to whether the GE report should be withheld from public disclosure.
We request that the information requested above be provided within 30 days of receipt of this i
l letter. The 30 day response timaframe was discussed with Mr. James Priest of your staff on September 9,1998. If circumstances result in the need to revise your response date, or ;f you have any questions, please contact me at (301) 415-1420.
Sincerely, original signed by:
Richard B. Ennis, Project Manager Project Directorate 1-2 Division of Reactor Projects - t/11 Office of Nuclear Reactor Regulation Docket No. 50-354 i
Enclosure:
Proprietary Finding on GE Report NEDC-32511P cc: See next page DISTRIBUTION Docket File REnnis GThomas PUBLIC TClark GHammer PDl-2 Reading TCollins JZwolinski MSiemien RCapra JLinville, RGN l OFFICE PDI-2/PM PDI-3/LA SRXB/BC OGC D
PDI-2/D NAME REnnis:mw TClark M TCollins MSiemien RCapra "
DATE 9 / IG /98 T / /(-/98 G / /X /98 i/N/98 i4 /98
/
OFFICIAL RECORD COPY l
DOCUMENT NAME: HCMA1674. GEN 1
l
r H. Keiser,
We have reviewed your submittal and the material in accordance with the requirements of 10 CFR 2.790 and, on the basis of GE's statements, have determined that some of the information in GE report NEDC-32511P contains proprietary commercial information. However, the staff has concluded that some of the information in report NEDC-32511P that is denoted as proprietary (i.e., marked with vertical bars in the right hand margin of affected pages) should not be exempt from public disclosure and should be released and placed in the Public Document Room (POR). The specific information that we believe should not be exempt from mandatory public disclosure is listed in the enclosure to this letter along with the reasons for our conclusions.
Therefore, we request that you review the enclosed information and submit a revised proprietary version of GE report NEDC-32511P. In addition, a nonproprietary version of the report should also be submitted to allow for proper docketing pursuant to 10 CFR 2.790(b)(1)(i). Upon receipt of this information, we will proceed with our determination as to whether the GE report should be withheld from public disclosure.
We request that the information requested above be provided within 30 days of receipt of this letter. The 30 day response timeframe was discussed with Mr. James Priest of your staff on September 9,1998. If circumstances result in the need to revise your response date, or if you have any questions, please contact me at (301) 415-1420.
Sincerely, Richard B. Ennis, Project Manager Project Directorate 1-2 Division of Reactor Projects 1/11 Office of Nuclear Reactor Regulation Docket No. 50-354
Enclosure:
Proprietary Finding on GE Report NEDC-32511P cc: See next page
Mr. Harold W. Keiser Hope Creek Generating Station Public Service Electric & Gas Company cc-Jeffrie J. Keenan, Esquire Manager-Joint Generation Nuclear Business Unit-N21 Atlantic Energy P.O. Box 236 6801 Black Horse Pike Hancocks Bridge, NJ 08038 Egg HarborTwp., NJ 08234-4130 Hope Creek Resident inspector Richard Hartung U.S. Nuclear Regulatory Commission Electric Service Evaluation Drawer 050g Board of Regulatory Commissioners Hancocks Bridge, NJ 08038 2 Gateway Center, Tenth Floor Newark, NJ 07102 Mr. Louis Storz Sr. Vice President - Nuclear Operations Lower Alloways Creek Township Nuclear Department clo Mary O. Henderson, Clerk P.O. Box 236 Municipal Building, P.O. Box 157 Hancocks Bridge, NJ 08038 Hancocks Bridge, NJ 08038 General Manager - Hope Creek Operations Mr. Elbert Simpson Hope Creek Generating Station Senior Vice President-P.O. Box 236 Nuclear Engineering Hancocks Bridge, NJ 08038 Nuclear Department P.O. Box 236 Director-Licensing Regulation & Fuels Hancocks Bridge, NJ 08038 Nuclear Business Unit - N21 P.O. Box 236 Hancocks Bridge, NJ 08038 Regional Administrator, Region i U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Dr. Jill Lipoti, Asst. Director Radiation Protection Programs NJ Department of Environmental Protection and Energy CN 415 Trenton, NJ 08625-0415 L
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PROPRIETARY FINDING ON GE REPORT NEDC-32511P 1)
General comment Since vertical lines in the right-hand margins were used by GE to denote proprietary information, and since a nonproprietary version of the report was not submitted, it is sometimes difficult to identify the exact portions of the text affected. It would have been better to use brackets to identify the specific text that is considered to be proprietary.
2)
Page 3-1, Bullets 1 through 5 (assumptions and initial conditions)
It is not clear why some of these assumptions and initial conditions would be considered proprietary. The information in bullets 1,2,4, and 5 can be found on pages 3 2 and 3-3 and these pages do not have any information marked as proprietary. Either remove the
. marking for bullets 1,2,4, and 5 or provide a rationale for the staff to evaluate.
3)
Page 4-1,1st paragraph it is not clear why the first two sentences of this paragraph are proprietary. This information does not appear to contain detailed results of analytical models, methods or processes. Either remove the marking or provide a rationale for the staff to evaluate.
4)
Pages 5-1,5-2, and 5-3, Sections 5.2 and 5.3 it is not clear why all of the text within the marked portions of Sections 5.2 and 5.3 is proprietary. The source of some of the information is from the Hope Creek Updated Final Safety Analysis Report (UFSAR) as referenced within these sections. Either remove the markings for the affected text or provide a rationale for the staff to evaluate.
5)
Pages 6-2,6-3,6-4,6-5,6-8,6-9,6-10,6-11, and 6-13 it is not clear why a large portion of the information in Section 6 is maied as proprietary.
Much of the information does not appear to contain detailed results of analytical models, methods, or processes. For example, pages 6-4,6-9, and 6-10 provide lists of valve numbers which should not be considered as proprietary information, in addition, this section lists design basis information which can found in the Hope Creek UFSAR (e.g.,
HPCI system flow rate and HPCI design basis injection time as shown on pages 6-2 and 6-3). Either remove the markings for the affected text or provide a rationale for the staff to
)
evaluate.
1 6)
Page 8-1, Bullets 1 through 6 (assumptions)
It is not clear why some of these assumptions would be considered proprietary. The information in bullets 1 and 4 can be found on page 6-1 (second paragraph) and page 8-3 which are not marked as proprietary. The information in bullets 2 and 5 can be found in the Hope Creek Technical Specifications. Either remove the marking for bullets 1,2,4, and 5 or provide a rationale for the staff to evaluate.
ENCLOSURE
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