Similar Documents at Salem |
---|
Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217M2101999-10-19019 October 1999 Forwards NRC Rept Number 17, Requal Tracking Rept from Operator Licensing Tracking Sys.Rept Was Used by NRC to Schedule Requalification Exam for Operators & Record Requal Pass Dates 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 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 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 ML18107A5401999-09-24024 September 1999 Discusses Closeout of GL 97-06, Degradation of Steam Generator Internals for Sngs,Units 1 & 2 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 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) 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 ML20212B3631999-09-14014 September 1999 Forwards Rev 13 to Salem - Hope Creek Security Plan,Iaw 10CFR50.54(p).Summary of Proposed Changes to Plan,Encl. Encl Withheld ML18107A5321999-09-13013 September 1999 Forwards Revised 10CFR50.92 Evaluation to Clarify Util Response to Question Number 1 Re Amend to Modify TS 3/4 8.1, AC Power Sources. ML18107A5331999-09-13013 September 1999 Provides Notification That PSEG Intends to Utilize ASME Code Case N-481 During Second ISI Interval at Sgs Units 1 & 2 ML18107A5351999-09-13013 September 1999 Informs That NRC Has Reviewed Pse&G Request Proposing to Modify TS Which Allow EDG to Be Operated for 24 Surveillance Test During Any Mode,Iaw 10CFR50.91(b) & Has No Comments 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 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-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 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 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 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 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 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 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-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 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 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 ML18107A4831999-08-18018 August 1999 Submits Licensee Comments on NRC 990730 Ltr Which Provided Notification of Close Out of TAC Numbers MA0567 & MA0568 Re GL 92-01,Rev 1,Suppl 1 ML18107A4801999-08-13013 August 1999 Requests That Pse&Gs Contact in NUREG-0383, Directory of Compliance for Radioactive Matl Packages, Be Changed 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 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 ML18107A4701999-07-30030 July 1999 Discusses Closure of Listed TACs in Response to Requests for Addl Info Re GL 92-01 ML18107A4531999-07-20020 July 1999 Forwards Discharge Monitoring Rept for Salem Generating Station, for June 1999.Rept Is Required by & Prepared for EPA & Nj Dept of Environ Protection 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 ML18107A4431999-07-0606 July 1999 Informs That Nj Dept of Environ Protection Bureau of Nuclear Engineering Has Reviewed Pse&G License Change Request S98-17 Re Permissible Enrichment Values for New Fuel Storage & Has No Comments 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 LR-N990251, Submits Response to NRC Request for Info Re Y2K Readiness at Npps,Per GL 98-01,suppl 1.Disclosure Encl1999-06-30030 June 1999 Submits Response to NRC Request for Info Re Y2K Readiness at Npps,Per GL 98-01,suppl 1.Disclosure Encl ML18107A4181999-06-30030 June 1999 Submits Response to NRC Request for Info Re Y2K Readiness at Npps,Per GL 98-01,suppl 1.Disclosure Encl ML20209B6751999-06-29029 June 1999 Ack Receipt of from Dr Powell in Response to NRC Re Fitness for Duty.Attachment 2 of Will Be Withheld from Public Disclosure,Per 10CFR2.790 LR-N990289, 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 & Discussion with NRC1999-06-25025 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 & Discussion with NRC 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 ML18107A4091999-06-22022 June 1999 Forwards Discharge Monitoring Rept for May 1999,containing Info as Required by Permit NJ0005622.Rept Prepared Specifically for EPA & Nj Dept of Environ Protection LR-N990273, Provides Supplemental Info to Proposed License Amend, Modifying TS 3/4 7.7, Auxiliary Bldg Exhaust Air Filtration Sys. Info Re Acceptance Criterion Discussed1999-06-21021 June 1999 Provides Supplemental Info to Proposed License Amend, Modifying TS 3/4 7.7, Auxiliary Bldg Exhaust Air Filtration Sys. Info Re Acceptance Criterion Discussed 1999-09-08
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20217M2101999-10-19019 October 1999 Forwards NRC Rept Number 17, Requal Tracking Rept from Operator Licensing Tracking Sys.Rept Was Used by NRC to Schedule Requalification Exam for Operators & Record Requal Pass Dates 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 ML18107A4701999-07-30030 July 1999 Discusses Closure of Listed TACs in Response to Requests for Addl Info Re GL 92-01 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 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 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 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 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 ML18107A4201999-06-0404 June 1999 Informs That NRR Reorganized,Effective 990328.Organization Chart Encl 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 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 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 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 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 ML18106B0731999-02-11011 February 1999 Discusses Closure of TAC Re Generic Implication of part- Length Control Rod Drive Mechanism Housing Leak ML20206S5951999-02-0303 February 1999 First Final Response to FOIA Request for Documents.Documents Listed in App a Already Available in Pdr.Documents Listed in App B Being Released in Their Entirety ML18106B0181999-01-0707 January 1999 Forwards Request for Addl Info Re Proposed Amend That Would Modify TS Section 3/4 7.6, Control Room Emergency Air Conditioning Sys ML18106A9921998-12-18018 December 1998 Responds to Re Fire Protection Matl Used at Salem Nuclear Generating Station.In 1993,NRC Identified Deficiencies in Electrical Raceway Fire Barrier Sys at Which Time Compensatory Measures Were Put in Place ML20198H1851998-12-15015 December 1998 Responds to to President Clinton Re Rept by Gao, Issued 970530 on NRC Oversight of Nuclear Power Industry ML18106A9911998-12-0808 December 1998 Forwards Synopsis of Investigation Rept 1-98-013 Re Fire Protection Operator Falsified Six Daily Fire Insp Logs During Feb & March 1998.Concludes That Operator Deliberately Violated Fire Protection Program Procedures ML20198B7611998-12-0303 December 1998 Informs That on 981007,generic Fundamentals Exam Was Administered to 148 Candidates at 21 Facilities.Summary of Statistical Results of Exam Listed.Contents of Exam Along with Associated Input Data Needed for Updating Catalog Encl IR 05000272/19980081998-11-24024 November 1998 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-272/98-08 & 50-311/98-08 ML18106A9751998-11-10010 November 1998 Forwards Exam Forms with Answers,Results Summary for Plant & Individual Answer Sheets of GFE Section of Written Operator Licensing Exam,Administered on 981007.Without Encl ML20155J7191998-11-0505 November 1998 Fourth Final Response to FOIA Request for Documents.Records Listed in App G Being Released in Entirety.Documents Listed in App H Being Withheld in Part (Ref FOIA Exemption 5) ML18106A9341998-10-22022 October 1998 Forwards SE Related to USI A-46 Program Implementation.Nrc Has Determined That Util Actions Completed & Proposed Resolution of Outlier Items Will Result in Safety Enhancements.Usi A-46 Program Complete 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) 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) ML18106A8981998-10-0505 October 1998 Forwards SRO Initial Exam Repts 50-272/98-302 & 50-311/98-302 for Exams Conducted on 980914-24.All Three SRO Applicants Passed All Portions of Exams 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 ML18106A8841998-09-24024 September 1998 Provides Individual Exam Results for Applicants on Initial Written Exam & Operating Tests Conducted at Salem Facility on 980914-17.W/o Encls ML18106A8701998-09-15015 September 1998 Forwards SE Accepting 960518 Request for Approval to Incorporate W WRB-2 Correlation Into Licensing Basis for Plant,Units 1 & 2 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 ML20151V8401998-09-10010 September 1998 Informs That Util Authorized to Administer Initial Written Exams to Listed Applicants on 980917.NRC Region I Operator Licensing Staff Will Administer Operating Tests on 980914- 16 ML18106A8571998-09-0202 September 1998 Informs That Licensee 980310 Response to GL 97-05, Steam Generator Tube Insp Technique, Includes Info Requested. Staff Did Not Identify Any Concerns W/Techniques Employed at Plant Re Conformance W/Current Licensing Basis for Facility ML20238F1581998-08-31031 August 1998 Informs That as Result of Review of Records,Duplication of Costs Charged for Insp Conducted at Salem Unit 2 Was Found. Amount Overcollected Will Be Transferred to Licensee within 10 Days from Date of Ltr IR 05000272/19980051998-08-27027 August 1998 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-272/98-05, 50-311/98-05 & 50-354/98-06 ML18106A8311998-08-21021 August 1998 Forwards Insp Repts 50-272/98-06 & 50-311/98-06 on 980622-0801.One Apparent Violation of Maint Procedure Requirements That Led to Failure to Meet TS Operability Requirements for AFW Sys,Identified.Nov Not Encl ML18106A8061998-08-0707 August 1998 Responds to Request for Statistics on Allegations Received by NRC Re Salem & Hope Creek.Encl Tables Provide Comparison to Allegations Received at Other Operating Sites for CY93-97 & First Seven Months of 1998 ML18106A7991998-08-0606 August 1998 Discusses Improved Std TS Guidance for Plants,Per Licensee ML18106A7941998-07-24024 July 1998 Summarizes Discussions Re Salem Units 1 & 2.Based on Discussions NRC Concluded That Plant Units 1 & 2 Have Sustained Improvement to Be Removed from NRC Watch List IR 05000272/19980031998-07-14014 July 1998 Ack Receipt of Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-272/98-03 & 50-311/98-03 ML18106A7031998-07-10010 July 1998 Forwards Insp Repts 50-272/98-05 & 50-311/98-05 on 980504-0621 & Nov.Violations Include Failure of Staff to Adhere to Established Procedures,Including Procedures Requiring 10CFR50.59 Reviews & Test Equipment Calibration IR 05000272/19982021998-07-0909 July 1998 Forwards Insp Repts 50-272/98-202,50-311/98-202 & 50-354/98-202 on 980420-23.No Violations Noted.Enclosure Contains Safeguards Info & Being Withheld Ref 10CFR73.21 ML18106A6991998-07-0808 July 1998 Forwards Senior Reactor Operator Retake Exam Repts 50-272/98-301(OL) & 50-311/98-301(OL) on 980626.Staff Administered Exam to One SRO Candidate Who Failed Initial Written Exam in Jan 1998.Candidate Passed & Issued License ML18106A6891998-07-0202 July 1998 Provides Individual Exam Result for Applicant on Initial Retake Written Exam Conducted at Salem Facility on 980626. Info Considered Proprietary in Accordance w/10CFR2.790.W/o Encls 1999-09-24
[Table view] |
See also: IR 05000272/1996014
Text
.
~I -
\\.,. -
. **
September 30, 1996
EA 96-344
Mr. Leon R. Eliason
Chief Nuclear Officer & President
Nuclear Business Unit
Public Service Electric and Gas Company
P. 0. Box 236
Hancocks Bridge, New Jersey 08038
SUBJECT:
INSPECTION REPORT NOS. 50-272/96-14, 50-311 /96-14 AND
50-354/96-08
Dear Mr. Eliason:
This refers to the inspection conducted August 15 - September 3, 1996, at the
Salem/Hope Creek Nuclear Generation Station. The purpose of that inspection was to
review the implementation of your Physical Security Program. At the conclusion of th~
inspection, an exit meeting was conducted at our King of Prussia,* Pennsylvania office and
the findings were discussed with Mr. L. Storz and other members of your staff.
Areas exa,mined during the inspection are identified in the attached report. Within these
areas, the inspection consisted of selective examinations of procedures and representative
records, interviews with personnel and observations by the inspectors.
Based on the results of this inspection, six apparent violations were identified and are
being considered for escalated enforcement action in accordance with the '~General
Statement of Policy and Procedure for NRC Enforcement Actions." (Enforcement Policy),
(60 FR 34381 ); (June 30, 1995). The apparent violations involved: 1) the failure to
control photo badge key cards; 2) the failure to properly search an individual prior to
granting access to the protected area; 3) the failure to notify the nuclear shift supervisor of
a potential threat event; 4) the failure to deactivate photo badge key cards for individuals
who no longer required site access; 5) the failure to complete training for security
supervisors prior to assigning them supervisory duties; and 6) the failure to test an
intrusion detection system in accordance with procedures. The NRC is seriously concerned
about the implementation of the security program, particularly the access control function,
since three of the apparent violations were in that area.
At the exit meetiri-g on September 3, 1996, members of your staff provided specific short-
term corrective actions that had already been implemented for the apparent violations
pending completion and review of investigations being conducted by Public Service Gas &
Electric Company and the Wackenhut Company, the security contractor. Your staff also
committed to meet with us in the future to discuss the results of the investigations. The
hand-out provided by your staff at that meeting is enclosed with the inspection report.
'}
9610070156 960930
PDR
ADOCK 05000272
G
PDR
~F DI /1
' .
Mr. Leon R. Eliason
2
Because specific corrective actions were provided at that meeting, it may not be necessary
to conduct a predecisional enforcement conference in order to enable the NRC to make an
enforcement decision. However, a Notice of Violation is not presently being issued for
these inspection findings.
Before the NRC makes its enforcement decision, we are providing you an opportunity to
either: ( 1 ) respond to the apparent violations addressed in this inspection report within
30 days of the date of this letter, or (2) request a predecisional enforcement conference. If
you choose not to provide a response and would prefer participating in a predecisional ,
enforcement conference, please contact Mr. L. Nicholson of this office at (610) 337-5128
within 7 days of the date of this letter.
,
Your response should be clearly marked as a "Response to Apparent Violations in
Inspection Report Nos. 50-272/96-14, 50-311/96-14 and 50-354/96-08 and should
include for each apparent violation (1) the reason for the apparent violation, or, if
contested, the basis for disputing the apparent 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. Your response
should be submitted under oath or affirmation and may reference or include previous
docketed correspondence, if the correspondence adequately addresses the required,
response. If an adequate response is not received within the time,specified or an extension
of time has not been granted by the NRC, the NRC will proceed with its enforcement
decision or schedule a predecisional enforcement conference.
In addition, please be advised that the number and characterization of apparent violations
for the events described in. the enclosed inspection report may change as a result of further
NRC review. You will be advised by separate correspondence of the results of our
deliberations on this matter.
Based on our review of the information provided to us during the exit meeting, we find that
the additional interim measures implemented by your staff to address the performance
issues in this report are appropriate. Those interim measures, if implemented well, provide
assurance that the safety objectives of the security program are being achieved for the
Salem/Hope Creek Station. From the discussions during the exit meeting, we understand
that your staff agreed not to make substantive changes to those interim measures prior to
contacting us. If this understanding is incorrect, please notify us immediately.
Nonetheless, the NRC will remain concerned about security area performance until your
staff implements comprehensive, durable corrective actions responsive to the root causes
of problems found. Consequently, NRC considers closeout of concerns in the security
program to be a restart item for Salem.
Mr. Leon R. Eliason
3
In accordance with 10 CFR 2. 790 of the NRC's "Rules of Practice," a copy of this letter,
its enclosure(s), and your response (if you choose to provide one) will be placed in the NRG
Public Document Room (PDR). To the extent possible, your response should not include
any personal privacy, proprietary, or safeguards information so that it can be placed in the
PDR without redaction.
Docket Nos. 50-272; 50-311; 50-354
License Nos. DPR-70, DPR-75, NPF-57
Enclosures:
Sin~erely,
James T. Wiggins, Director
Division of Reactor Safety
1. Inspection Report 50-272;96-14, 50-311 /96-14 and 50-354/96-08
2. Handout provided by licensee at exit meeting
cc w/encl:
L. Storz, Senior Vice President - Nuclear Operations
E. Simpson, Senior Vice President - Nuclear Engineering
E. Salowitz, Director - Nuclear Business Support
C. Schaefer, External Operations - Nuclear, Delmarva Power & Light Co.
D. Garchow, General Manager - Salem Operations
J. Benjamin, Director - Quality Assurance & Nuclear Safety Review
D. Powell, Manager, Licensing and Regulation
R. Kankus, Joint Owner Affairs
A .. Tapert, Program Administrator
R. Fryling, Jr.,. Esquire
M. Wetterhahn, Esquire
M. Bezilla, General Manager - Hope Creek Operations
P. MacFarland Goelz, Manager, Joint Generation
Atlantic Electric
. 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
. *
Mr. Leon R. Eliason
Distribution w/encl:
Region I Docket Room (with concurrences}
Kay Gallagher, DRP
G. Smith
R. Keimig
L. Nicholson, DRP
S. Barber, DRP
G. Kelly, DRS
N. Della Greca, DRS
D. Screnci, PAO
NRC Resident Inspector
PUBLIC
Distribution w/encl: (Via E-Mail}
L. Olshan, NRR
W. Dean, OEDO
J. Stolz, PDl-2, NRR
M. Callahan, OCA
D. Jaffee, Project Manager, NRR
Inspection* Program Branch, NRR (IPAS)
L. Cunningham, NRR
4
I L__
EXECUTIVE SUMMARY
Salem/Hope Creek Nuclear Station
NRC Inspection Report Nos. 50-272/96-14,
50-311 /96-14 and 50-354/96-08
An inspection of the physical security program was conducted during the period of
August 15-September 3, 1996. Areas inspected included: protected area detection
equipment; alarm stations and communications; testing maintenance and compensatory
measures; access control of personnel; training and qualification; management support;
audits; and fitness-for-duty. The purpose of this inspection was to determine if the
security program, as implemented, met the licensee's commitments and NRC regulatory
requirements.
Six apparent violations were identified during the inspection. The violations included: 1)
the .failure to control photo badge key cards; 2) the failure to properly search an individual
prior to granting access to the protected area; 3) the failure to notify the nuclear shift
supervisor of a potential threat event; 4) the failure to deactivate photo badge key cards
for individuals who no longer required site access; 5) the failure to complete training for
security supervisors prior to assigning them supervisory duties; and 6) the failure to test an
intrusion detection system in accordance with procedures.
The exit meeting for the inspection was held in the NRC's Region I office, in King of
Prussia, PA on September 3, 1996. Senior management from the licensee's organization
and from Region I were in attendance. The scope and findings of the inspection were
discussed. The licensee presented some preliminary information from its investigation and
the investigation by its contractor which were initiated shortly after events occurred on
August 14 and 19. Those events brought into question the performance of several
security force members. The licensee also present short-term corrective measures for the
apparent violations 1, 2, 4, and 5 identified above. Apparent violations 3 and 6 were
identified subsequent to the inspection and brought to the licensee's attention on
September 25, 1996, via a telephone call.
ii