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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 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 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) 05000354/LER-1999-009, Forwards LER 99-009-00, License Condition Violation - Min FW Temp Limits. Commitments Made by Util Encl1999-09-20020 September 1999 Forwards LER 99-009-00, License Condition Violation - Min FW Temp Limits. Commitments Made by Util Encl ML20217K7781999-09-16016 September 1999 Forwards Discharge Monitoring Rept for Hope Creek Generating Station for Month of Aug 1999. Rept Is Required by & Prepared Specifically for EPA & Nj Dept of Environ Protection ML20212B3631999-09-14014 September 1999 Forwards Rev 13 to Salem - Hope Creek Security Plan,Iaw 10CFR50.54(p).Summary of Proposed Changes to Plan,Encl. Encl Withheld ML20212B4021999-09-13013 September 1999 Submits Supplemental Info Related to Hope Creek License Change Request (LCR) H98-08,submitted to NRC on 981230, Re Flood Protection TS Changes 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 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 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 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 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 ML20209B6441999-06-21021 June 1999 Offers No Comments on Licensee 990529 Request for Revs to Plant Radiological Effluent Ts,Per GL 89-01 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 ML20209C0621999-06-21021 June 1999 Forwards NPDES Discharge Monitoring Rept,May 1999, for Hcgs.Rept Prepared Specifically for EPA & Nj Dept of Environ Protection 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 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 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 ML18107A3611999-05-27027 May 1999 Forwards Responses to NRC 990301 & 990323 RAIs for Salem & Hope Creek Generating Stations Relating to GL 96-05 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 ML20195B9931999-05-20020 May 1999 Forwards NPDES Discharge Monitoring Rept,Apr 1999, for Hgcs.Rept Prepared Specifically for EPA & Nj Dept of Environ Protection ML20207A3451999-05-20020 May 1999 Discusses Completion of Licensing Action for NRC Bulletin 96-003, Potential Plugging of ECCS Strainers by Debris in Bwrs 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 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 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 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 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 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 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 ML20205N2111999-04-0909 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 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 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) 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 ML20151Z1111998-09-11011 September 1998 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-354/98-06 Issued on 980721 ML20151Z5941998-09-11011 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
[Table view] |
See also: IR 05000354/1996009
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January 8, 1997
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Mr. L. F. Storz, Senior Vice President
- Nuclear Operations -
Public Service Electric & Gas Company
PO Box 236 l
Hancocks Bridge, NJ 08038 i
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SUBJECT: NRC INSPECTION NOS. 50-354/96-09
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Dear Mr. Storz
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i This letter refers to your Decemer 26,1996 correspondence, in response to our December ;
5,1996 letter. ;
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] Thank you for informing us of the corrective and preventive actions documented in your
! letter. These actions will be examined during a future inspection of your licensed program.
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Your cooperation with us is appreciated.
Sincerely,
ORIGINAL SIGNED BY
R0B DEPRIEST FOR:
Larry E. Nicholson, Chief l
Projects Branch 3
Division of Reactor Projects
Docket No. 50-354
9701130188 970108
PDR ADOCK 05000354
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Mr. L. F. Storz 2
cc:
L. Eliason, Chief Nuclear Officer and President - Nuclear Business Unit
E. Simpson, Senior Vice President - Nuclear Engineering
E. Salowitz, Director - Nuclear Business Support
D. Powell, Manager, Licensing and Regulation
A. Tapert, Program Administrator
J. Benjamin, Director - Quality Assurance & Safety Review
M. Bezilla, General Manager - Hope Creek Operations
i cc w/cy of Licensee's Letter:
I C. Schaefer, External Operations - Nuclear, Delmarva Power & Light Co.
l R. E. Selover, Esquire
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M. Wetterhahn, Esquire
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P. MacFarland Goelz, Manager, Joint Generation Department,
Atlantic Electric Company
i Consumer Advocate, Office of Consumer Advocate
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W. Conklin, Public Safety Consultant, Lower Alloways Creek Township
R. Kankus, Joint Owner Affairs ,
State of New Jersey
State of Delaware
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Mr. L. F. Storz 3
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Distribution w/ copy of Licensee's Response Letter:
Region I Docket Room (with concurrences) ,
PUBLIC l
D. Jaffe, Project Manager, NRR
W. Dean, OEDO
J. Stolz, PDI-2, NRR
L. Nicholson, DRP
S. Barber, DRP
D. Screnci, PAO
Nuclear Safety information Center (NSIC)
NRC Resident inspector
Kay Gallagher, DRP
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DOCUMENT NAME: a: reply.hc
To receive e copy of this document, indicate in the boa: "C" = Copy without attachment / enclosure "E" = Copy eth attachment / enclosure
"N" = No copy
0FFICE RI:DRP g ,l RI:DRP /14 l \g '
RDePriest/Q/
NAME
DATE 1/7f97
LNicholson "' @
1/2f/97
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0FFICIAL RECORD COPY
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Pubhe Serwce
Electne and Gas
Company
Louis F. Storz Pubke Service Electnc and Gas Com ny P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-5700
Senor V.ce President . Nuclear Operatens D C 2 61996
LR-N96435
United States Nuclear Regulatory Commission !
Document Control. Desk '
Washington, DC 20555
Gentlemen:
REPLY TO A NOTICE OF VIOLATION
OFFSITE SAFETY REVIEW STAFFING AND REVIEW ISSUES )
INSPECTION REPORT NO. 50-354/96-09-01 .
HOPE CREEK GENERATING STATION
FACILITY OPERATING LICENSE NPF-57 :
DOCKET NO. 50-354 !
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Pursuant to the provisions of 10CFR2.201, this letter submits the 1
response of Public Service Electric and Gas Company to the notice
of violation issued to the Hope Creek Generating Station (HCGS) !
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in a letter dated December 5, 1996, from L. Nicholson (NRC) to
L. Eliason (PSE&G). !
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Should you have any questions or comments on this transmittal, do l
not hesitate to contact us.
Sincerely,
.
Out2 -
L. F. Storz
Senior Vice President -
Nuclear Operations
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Attachment
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DEC 2 619?fi
Document Control Desk -2-
LR-N96435
,
The following items represent commitments that Public Service
Electric & Gas (PSE&G) made to the Nuclear Regulatory Commission
(NRC) relative to this NOV Response to Inspection Report
50-354/96-09-01.
a. To address generic implications, a review of other
practices which could be interpreted as violating the
Technical Specifications (i.e. training, long term
l illness, extended vacation, staffing, etc.) will be
l conducted and appropriate remedies established by
January 31, 1997.
f b. A self-assessment will be performed to evaluate
j effectiveness of corrective actions to assure the new *
l
expectations have be achieved. This self-assessment
! will be conducted by June 30, 1997,
c. A sampling of prior LCR's will be performed to assure
proper reviews were applied. This sampling will be
completed by February 27, 1997.
d. A request for the revision of the procedure that
controls the LCR process has been initiated to ensure j
that LCR submittals and revisions that affect the .j
material nature of the LCR are reviewed and approved by
OSR. The procedure revision will be completed by
March 30, 1997.
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Document Control Desk -3-
LR-N96435
C Mr. H. J. Miller, Administrator - Region I
U. S. Nuclear Regulatory Commission
475 Allendale Road
King of Prussia, PA 19406
Mr. David Jaffe
Licensing Project Manager - Hope Creek
U. S. Nuclear Regulatory Commission
one White Flint North
Mail Stop 14E21
11555 Rockville Pike
Rockville, MD 20852
Mr. R. Summers
USNRC Senior Resident Inspector (X24)
Mr. K. Tosch, Manager IV
Bureau of Nuclear Engineering
33 Arctic Parkway
CN 415
Trenton, NJ 08625
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ATTACHMENT
REPLY TO NOTICE OF VIOLATION
OFFSITE SAFETY REVIEW STAFFING AND REVIEW ISSUES
INSPECTION REPORT NO. 50-354/96-09
HOPE CREEK GENERATING STATION
FACILITY OPERATING LICENSE NPF-57
DOCKET NO. 50-354 LR-N96435
I. INTRODUCTION
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During the NRC's Resident Inspection conducted at Hope Creek l
Generating Station between September 22, 1996 and
November 9, 1996, a violation of NRC requirements was
identified. As a result, the NRC issued a notice of
violation (VIO 354/96-09-01) in a letter dated December 5,
[ 1996 from L. Nicholson (NRC) to L. Eliason (PSE&G). This
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response addresses the violation.
In accordance with the provisions of 10CFR2.201, Public
Service Electric and Gas Company hereby submits a written
response to the notice of violation which includes: (1) the
reason for the violation; (2) the corrective steps that have
been taken and the results achieved; (3) the corrective
steps that will be taken to avoid further violations; and
(4) the date when full compliance will be achieved.
II. REPLY TO THE NOTICE OF VIOLATION
1. Description of the Notice of Violation i
" Technical Specification 6.5.2, Nuclear Safety Review and
Audit, requires, in part, that Hope Creek will have an Offsite
Safety Review (OSR) staff consisting of at least four ,
dedicated, full time engineers; and, that the OSR staff shall :
review, in part, proposed changes to the Technical
Specifications or the Operating License.
Contrary to the above, OSR staffing and review requirements
were not met for the following two examples:
(i) from September 26, 1996 until October 9, 1996, the Hope
Creek OSR did not have a staff consisting of at least four
dedicated, full-time engineers; and,
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} Reply to Notice of Violation '
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j (ii) License Change Request (LCR) 95-23, dated October 7, 1995
and LCR 95-23 revision, dated October 27, 1995, were not
reviewed by the OSR.
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j This is a Severity Level IV violation (supplement I) . " ,
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2A. . Response to Notice of Violation - Inadequate OSR' staffing
j levels
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j PSE&G has reviewed the circumstances described by the NRC and ;
j concurs with the facts cited in the first example.
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j i. Description of Event ;
j On September 23, 1996, one of the Offsite Safety Review (OSR) ,
l engineers was voluntarily transferred out of the Nuclear I
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Safety Review organization, thus creating a vacancy in the OSR
! staff. Both permanent and temporary replacements were being
j pursued in accordance with the normal Human Resource
! processes, the interim short term vacancy had not been
j previously interpreted to be a violation of the Technical
i Specification staffing level requirements.
I On October 8, 1996, an NRC inspector identified that there
- were fewer than the four full-time engineers currently
j assigned to the Hope Creek OSR staff. The NRC inspector
! considered this interim staffing situation a violation of the
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Technical Specification requirements. Upon identification of
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the issue by the NRC inspector, OSR management filled the
staff position with a qualified engineer on October 8, 1996
{ and an action request in accordance with the corrective action j
i program was generated. As a result of the aforementioned OSR l
j staff engineer transfer, a deficient staffing condition ;
i existed for a total of ten working days. !
A prior violation identified by the NRC (Violation 50-272/96-
05) also involved Technical Specification staffing ,
requirements. Specifically, the staffing issue of that j
violation entailed the crediting of the OSR supervisor as one
of the full time dedicated members of the OSR staff. The
prior violation involved a situation that is distinguishable
from this event, and therefore the previously developed
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Attachment LR-N96435 l
Reply to Notice of Violation l
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corrective actions were not encompassing to address the issue
identified in the current violation.
ii. Reason for the Violation
The OSR staffing deficiency was the result of management work
practices and policies that were less than adequate.
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Specifically, prior convention and past practice were used in
that an active pursuit of a replacement was in progress. This
lack of a questioning attitude resulted in the violation of
the Technical Specifications.
28. Response to Notice of Violation - Review of License Change ,
j Request (LCR) package 95-23 l'
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PSE&G has reviewed the circumstances described by the NRC and
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concurs with the facts cited in the second example.
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i. Description of the Event
During an examination of license change request (LCR) reviews
performed by OSR, the NRC inspector identified that LOR 95-23
was not appropriately reviewed by OSR. Technical
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Specification S 6. 5.2 and procedures NC.NA-AP. ZZ-0035 (Q) ,
" Nuclear Licensing and Reporting" and ND.SN-AP.ZZ-0001 (Q) , !
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" Independent Safety Review Program", require, in part, that !
l the OSR review proposed changes to the Technical l
l Specifications to evaluate technical merit and verify the
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adequacy of the significant hazards analysis. Specifically, a
substantial draft of the LCR was reviewed by OSR on October 5,
i 1995; however, the subsequent submittal of October 7, 1995 and
l a revision thereto on October 27, 1995 were not formally
l reviewed by OSR.
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l ii. Reason for the Violation l
The deficient review of LCR 95-23 was the result of management
! work practices and administrative controls in place that were
l less than adequate to comply with Technical Specification
requirements. The document was reviewed by OSR on October 5,
l 1995 and its technical content was subsequently modified by a i
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letter from Engineering on October 6, 1995 (NE-95-1595) . The l
version of the LCR reviewed by SORC and submitted to the NRC
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on October 7, 1995 captured the engineering changes; however,
an additional formal review was not conducted by OSR.
Likewise, a revision to the LCR submitted on October 27, 1995,
was not formally reviewed by OSR.
Prior practice was that an additional formal review was not
needed or warranted for modified submittals unless it was
determined that the significant hazards analysis was effected.
The incorporated engineering information and revised amendment
request were judged to not effect the significant hazards
analysis and therefore they were not routed back to OSR for
formal review. The practice was to communicate subsequent
changes to OSR through document routing and verbal follow-up,
which was the case for LCR 95-23. Both documents were
subsequently transmitted to the OSR organization as recorded
on the correspondence distribution routing sheets attached to I
the October 7 and 27, 1995 submitttls. l
3. Corrective Steps That Have Been Taken and Results Achieved
a. The open OSR staffing position was immediately filled
with a qualified staff member.
b. Management expectations regarding staffing vacancies l
and compliance with Technical Specification staffing I
requirements has been communicated to quality assurance
management, including OSR and NSR management, thereby
heightening management awareness,
c. LCR 95-23 as submitted on October 7 and 27, 1995, has
been formally reviewed by OSR, with no concerns j
identified,
d. The practice regarding formal OSR reviews of LCR's has
been clarified. Specifically, the need to have any
subsequent material changes that effect the proposed
marked-up Technical Specification pages or the
significant hazards review, has been contmun.cated to
the OSR and Licensing organizations, thereL 3
heightening employee awareness.
e. A review of other OSR review activities similar to the
LCR review process has been conducted to ensure that
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! Attachment LR-N96435
Reply to Notice of Violation
OSR is reviewing the materially complete document at
the time of the OSR formal review. No other process
weaknesses were identified.
4. Corrective Steps that Will Be Taken to Avoid Further
Violations
a. To address generic implications, a review of other
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practices which could be interpreted as violating the
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Technical Specifications (i.e., training, long term
i illness, extended vacation, staffing, etc.) will be
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conducted and appropriate remedies established by
January 31, 1997.
b. A self-assessment will be performed to evaluate
i effectiveness of corrective actions to assure the new
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expectations have be achieved. This self-assessment
will be conducted by June 30, 1997.
c. A sampling of prior LCR's will be performed to assure
proper reviews were applied. This sampling will be
completed by February 27, 1997.
d. A request for the revision of the procedure that
controls the LCR process has been initiated to ensure
that LCR submittals and revisions that affect the
material nature of the LCR are reviewed and approved by
OSR. The procedure revision will be completed by
March 30, 1997.
5. Date When Full Compliance Will Be Achieved
PSE&G is now in full compliance with the OSR staffing
requirements at Hope Creek and Salem. PSE&G has
formally reviewed LCR 95-23 and is therefore in
compliance with the OSR review requirements.
Additional committed reviews assure full compliance.
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