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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 LR-N990450, 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 Analyses1999-10-18018 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 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 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 LR-N990409, Requests Relief Associated with Containment Examinations at Hope Creek & Salem Generating Stations.Attachment 1 Includes Proposed Alternatives & Supporting Justification for Relief Requests1999-10-0707 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 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 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 ML18107A5401999-09-24024 September 1999 Discusses Closeout of GL 97-06, Degradation of Steam Generator Internals for Sngs,Units 1 & 2 NTD-99-302, Provides Data Re Operator Licensing Exam for Salem & Hope Creek Station,In Response to NRC Form 536 (7-1999)1999-09-22022 September 1999 Provides Data Re Operator Licensing Exam for Salem & Hope Creek Station,In Response to NRC Form 536 (7-1999) ML18107A5421999-09-22022 September 1999 Forwards Discharge Monitoring Rept for Salem Generating Station for Aug 1999.Rept Is Required by & Prepared Specifically for EPA & Nj Dept of Environ Protection ML18107A5371999-09-20020 September 1999 Forwards Insp Repts 50-272/99-06 & 50-311/99-06 on 990719-0806 (Region I-Inoffice) 990809-19 & 0901.NRC Has Determined That Three Violations of NRC Requirements Have Occurred.Violations Being Treated as non-cited 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 LR-N000420, Provides Notification That PSEG Intends to Utilize ASME Code Case N-481 During Second ISI Interval at Sgs Units 1 & 21999-09-13013 September 1999 Provides Notification That PSEG Intends to Utilize ASME Code Case N-481 During Second ISI Interval at Sgs Units 1 & 2 LR-N990405, Forwards Revised 10CFR50.92 Evaluation to Clarify Util Response to Question Number 1 Re Amend to Modify TS 3/4 8.1, AC Power Sources1999-09-13013 September 1999 Forwards Revised 10CFR50.92 Evaluation to Clarify Util Response to Question Number 1 Re Amend to Modify TS 3/4 8.1, AC Power Sources ML18107A5351999-09-13013 September 1999 Informs That NRC Has Reviewed Pse&G Request Proposing to Modify TS Which Allow EDG to Be Operated for 24 Surveillance Test During Any Mode,Iaw 10CFR50.91(b) & Has No Comments ML18107A5331999-09-13013 September 1999 Provides Notification That PSEG Intends to Utilize ASME Code Case N-481 During Second ISI Interval at Sgs Units 1 & 2 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 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-N990406, 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 Examinations1999-09-0808 September 1999 Requests Approval to Use ASME Code Case N546,which Provides Alternative Qualification Requirements That Allow Personnel Most Familiar with Walkdown of Plant Sys,Like License Operators to Perform VT-2 Examinations LR-N990392, 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 19991999-09-0808 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 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 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 LR-N990385, 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 Issues1999-08-26026 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 LR-N990396, Forwards Ninety Day Rept for ISI Activities Conducted at Sgs,Unit 2 During Ninth Extended Outage & Tenth Refueling Outage.List of Encl,Provided1999-08-26026 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 LR-N990363, 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 99-021999-08-23023 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 LR-N990389, 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 Bars1999-08-20020 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 ML18107A4911999-08-20020 August 1999 Forwards Revised Plant Attribute Libraries for Salem & Hope Creek Generating Stations,Iaw 10CFR50,App E,Vi, Emergency Response Data Sys, 3.b.Changes Are Identified by Rev Bars ML18107A4861999-08-19019 August 1999 Forwards NPDES Discharge Monitoring Rept, for Salem Generating Station for Month of Jul 1999.Rept Required by & Prepared Specifically for EPA & Nj Dept of Environ Protection ML18107A4831999-08-18018 August 1999 Submits Licensee Comments on NRC 990730 Ltr Which Provided Notification of Close Out of TAC Numbers MA0567 & MA0568 Re GL 92-01,Rev 1,Suppl 1 LR-N990375, Submits Licensee Comments on NRC Which Provided Notification of Close Out of TAC Numbers MA0567 & MA0568 Re GL 92-01,Rev 1,Suppl 11999-08-18018 August 1999 Submits Licensee Comments on NRC Which Provided Notification of Close Out of TAC Numbers MA0567 & MA0568 Re GL 92-01,Rev 1,Suppl 1 LR-N990140, Requests That Pse&Gs Contact in NUREG-0383, Directory of Compliance for Radioactive Matl Packages, Be Changed1999-08-13013 August 1999 Requests That Pse&Gs Contact in NUREG-0383, Directory of Compliance for Radioactive Matl Packages, Be Changed 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 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 ML18107A5401999-09-24024 September 1999 Discusses Closeout of GL 97-06, Degradation of Steam Generator Internals for Sngs,Units 1 & 2 ML18107A5371999-09-20020 September 1999 Forwards Insp Repts 50-272/99-06 & 50-311/99-06 on 990719-0806 (Region I-Inoffice) 990809-19 & 0901.NRC Has Determined That Three Violations of NRC Requirements Have Occurred.Violations Being Treated as non-cited 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 ML18107A4701999-07-30030 July 1999 Discusses Closure of Listed TACs in Response to Requests for Addl Info Re GL 92-01 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 ML18107A4361999-07-16016 July 1999 Accepts Commitment to NRC Re Licensee Providing Clarification Concerning Licensing & Design Basis for 125 Vdc Battery Margins for Hope Creek & Salem Generating Stations for Meeting SBO & Loca/Loop Loading Requirements 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 ML18107A4251999-07-0606 July 1999 Forwards Insp Repts 50-272/99-04 & 50-311/99-04 on 990419-0529.Two Violations of NRC Requirements Occurred & Being Treated as non-cited Violations,Consistent with App C of Enforcement Policy 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 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 ML20209B6751999-06-29029 June 1999 Ack Receipt of from Dr Powell in Response to NRC Re Fitness for Duty.Attachment 2 of Will Be Withheld from Public Disclosure,Per 10CFR2.790 ML18107A4141999-06-23023 June 1999 Forwards SE Accepting Licensee Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design Basis Accident Conditions, for Plant,Units 1 & 2 ML18107A3891999-06-23023 June 1999 Discusses Evaluation of Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety Related Power Operated Gate Valves. Safety Evaluation Encl 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 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 ML18107A4201999-06-0404 June 1999 Informs That NRR Reorganized,Effective 990328.Organization Chart Encl 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 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 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 ML18107A2751999-05-0303 May 1999 Forwards Insp Repts 50-272/99-03 & 50-311/99-03 on 990315- 19.No Violations Were Identified ML18107A2701999-04-30030 April 1999 Refers to Investigation Conducted by OI After Chemistry Supervisor at Salem Facility Made Change to Procedure Without Proper Review & Signed Record Indicating That Independent Verifications Had Been Performed 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 ML18107A2161999-04-19019 April 1999 Forwards Ltr from Lg Canton,Regional Director,Fema Region II to Hj Miller,Nrc Region I,Forwarding FEMA Final Exercise Rept for 980303 Plume Exposure Pathway Exercise & 980505-07 Ingestion Pathway Exercise for Salem/Hope Creek Stations 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 ML18107A1761999-04-15015 April 1999 Responds to 981019 & s Requesting Approval of Proposed Changes to QA Program,Per Section 17.2 of Respective UFSAR Per 10CFR50.54(a)(3).Forwards SE Re Changes to QA Program 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 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 IR 05000311/19980121999-04-0707 April 1999 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Rept 50-311/98-12.Review of Effectiveness of Corrective Actions in Rept, as Part of Independent Assessment of RCS & LER Completed IR 05000272/19990011999-04-0101 April 1999 Forwards Insp Repts 50-272/99-01 & 50-311/99-01 on 990117-0307.No Violations Identified.Expresses Concern About Two Human Errors That Caused Plant Events,One Which Challenged Safety Sys ML18106B1091999-03-23023 March 1999 Forwards RAI Re NRC GL 96-05, Periodic Verification of Design-Basis Capability of Safety-Related Motor-Operated Valves 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 ML18106B0741999-02-18018 February 1999 Provides Authorization to Administer Written Exams to Listed Applicants on 990226 at Salem Generating Station,Hancocks Bridge,New Jersey.Nrc Region I Operator Licensing Staff Will Administer Operating Tests on 990222-25 & 990301-05 1999-09-08
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EA 97-420 EA 97-422 Mr. Leon R. Eliason Chief Nuclear Officer & President Nuclear Business Unit October 1, 1997 Public Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038
SUBJECT:
PREDECISIONAL ENFORCEMENT CONFERENCES RELATIVE TO NRC INVESTIGATIONS 1-96-031 AND 1-96-024
Dear Mr. Eliason:
This letter refers to* investigations conducted at the Salem and Hope Creek Nuclear Generating Stations by the NRC Office of Investigations (01) Field Office, Region I. The purpose of the investigations was to determine whether certain activities authorized by your license were conducted in accprdance with NRC requirements. A redacted copy of
. one investigation report and a synopsis of the other are enclosed.
Based on the findings of the first investigation ( 1-96-031), an apparent violation was identified and is being considered for escalated enforcement action in accordance with the "General Statement of Policy and Procedures for NRC Enforcement Actions" (Enforcement Policy), NUREG-1600. The apparent violation involves Title 10, Code of Federal Regulations (CFR), Section 50. 7 (Employee protection). 10 CFR 50. 7 prohibits a licensee from discriminating against any employee for engaging in certain protected activities. The investigation indicates that a contract security officer employed by the Wackenhut Corporation was discriminated against for her involvement in raising safety concerns, causing you to be in apparent violation of 10 CFR 50. 7.
Specifically, on August 22, 1996, the security officer was placed on annual leave without pay for allegedly speaking with an NRC representative the previous day regarding a security incident that occurred on June 5, 1996. The June 5, 1996 incident involved the failure to test an intrusion detection system, as documented in NRC inspection report no.
50-272/96:..14, 50-311/96-14, and 50-354/96-08, as an apparent violation. A severity level IV violation was issued on December 11, 1996, for this problem.
In accordance with NRC policy, an opportunity is provided to hold an Enforcement Conference with you to discuss this matter. Since our evaluation is c~ntinuing we are not issuing any Notice of Violation at this time.
Additionally, we would like to discuss the results of the second NRC investigation ( 1 024) that includes an apparent deliberate violation of 10 CFR 50.9 (Completeness and Accuracy of Information). More specifically, security personnel falsely documented that compensatory measures were in place at designated security posts within the required time\\\\(
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2 following the crash of the Salem Generating Station security computer system on May 25, 1 996. Based on evidence developed during the NRC investigation, the deliberate actions of two Wackenhut Corporation security personnel resulted in inaccurate information regarding the posting of compensatory measures being recorded in the Safeguards Event Log. A synopsis of NRC investigation report no. 1-96-024 is enclosed.
In particular, regarding the inaccurate information issue, we want to understand all of the corrective actions you have taken to address the deliberate misconduct by Wackenhut personnel, upon identification of the log inaccuracy as presented in your and Wackenhut Nuclear Services Division's final "Event Investigation And Security Program Evaluation,"
dated August, 1996. Also, we want to understand all subsequent action(s) you have taken, including reporting of this issue upon the discovery of this matter and issuance of the final investigation report, per 10 CFR 73.71 (Reporting of Safeguards Events).
In accordance with previous discussions between Mr. Louis Storz of Public Service Electric and Gas Company, and Mr. James Linville of this office, predecisional enforcement conferences have been scheduled with you to discuss these matters, on October 24, 1997, beginning at* 10:00 a.m., at our Region I office in King of Prussia, Pennsylvania.
The first conference will be open to public observation. The second conference will be
- conducted immediately following the first conference and will be closed to public observation. Both enforcement conferences will be transcribed. As discussed with Mr.
Storz, Wackenhut Corporation Management has been asked to attend both conferences and we specifically requested that, at a minimum, the two Wackenhut employees involved in the documentation inaccuracy attend the second conference. Additionally, you are welcome to bring any additional PSE&G or Wackenhut personnel to either of these conferences.
We have offered the security officer involved in the first issue, the opportunity to observe the open enforcement conference with your organization. We have informed her that we will arrange for her to answer questions at the end of this conference without licensee presence, if she should so desire, in order to preclude any perception of duress, and that she may be accompanied by legal counsel or representation.
The provision to hold an enforcement conference does not mean that the NRC has determined that enforcement action will be taken. The purpose of these conferences is to discuss the apparent violations, cause(s) and safety significance, and to provide you the opportunity to point out any errors in our understanding of the apparent violations. In addition, this is an opportunity for you to provide any information concerning your perspectives on the nature of the apparent violations, aggravating or mitigating circumstances that the NRC should consider, and other information that will help the NRC determine the appropriate enforcement action.
Also, we want to understand any differences between the corrective actions you have taken for each of these apparent violations and those actions implemented previously, associated with other past security.related problems and harassment and intimidation for which the NRC has taken enforcement action against you (reference EA 96-344 and EA 96-177).
3 You will be advised by separate correspondence of the results of our deliberations on these matters. No response regarding these issues is required at this time.
If you have any questions on either matter, please contact Mr. Michael Modes of our office at 1-800-432-1156, extension 5198.
In accordance with 10 CFR 2. 790 of the NRC's "Rules of Practice," a copy of this letter and its enclosures will be placed in the NRC Public Document Room.
Sincerely, Original Signed By:
James T. Wiggins, Director Division of Reactor Safety Docket Nos. 50-272; 50-311; 50-354
Enclosures:
1.
- 2.
Investigation Report No. 1-96-031 {redacted version)
Investigation Report No. 1-96-024 (synopsis)
4 cc w/encl:
L. Storz, Senior Vice President - Nuclear Operations E. Simpson, Senior Vice President - Nuclear Engineering E. Salowitz, Director - Nuclear Business Support A. F. Kirby, Ill, External Operations - Nuclear, Delmarva Power & Light Co.
J. A. Isabella, Manager, Joint Generation Atlantic Electric D. Garchow, General Manager - Salem Operations M. Bezilla, General Manager - Hope Creek Operations J. McMahon, Director - Quality Assurance & Nuclear Safety Review D. Powell, Manager - Licensing and Regulation R. Kankus, Joint Owner Affairs A. c: Tapert, Program Administrator Jeffrey J. Keenan, Esquire Consumer Advocate, Office of Consumer Advocate William Conklin, Public Safety Consultant, Lower Alloways Creek Township Public Service Commission of Maryland State of New Jersey State of Delaware
Distribution w/encls:
Region I Docket Room.(with concurrences)
W. Axelson, ORA C. O'Daniell, DRP D. Screnci, PAO D. Holody, OE, RI J. Lieberman, OE
- Nuclear Safety i'ntormation Center (NSIC)
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