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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 NUREG-1706, Concludes That There Are No Nuclear Plants with Y2K Issues Involving Safety Sys,Based on Review of Licensee Responses & Onsite Assessment of Licensee Y2K Activities as Described in NUREG-17061999-09-23023 September 1999 Concludes That There Are No Nuclear Plants with Y2K Issues Involving Safety Sys,Based on Review of Licensee Responses & Onsite Assessment of Licensee Y2K Activities as Described in NUREG-1706 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 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. 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 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 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 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 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 ML18107A4431999-07-0606 July 1999 Informs That Nj Dept of Environ Protection Bureau of Nuclear Engineering Has Reviewed Pse&G License Change Request S98-17 Re Permissible Enrichment Values for New Fuel Storage & Has No Comments ML20196J6301999-07-0101 July 1999 Requests Addl Info Re Status of Decommissioning Funding for Limerick Generating Station,Units 1 & 2,Peach Bottom Atomic Power Station,Units 1,2 & 3 & Salem Nuclear Generating Station,Units 1 & 2 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 1999-09-08
[Table view] Category:NRC TO PROFESSIONAL/INDUSTRIAL ASSOCIATION
MONTHYEARML20154H6501988-09-0909 September 1988 Forwards Rept of NRC Investigation Re Harassment & Intimidation of Authorized Nuclear Inspectors.Investigation Revealed That Four Authorized Operators Were Either Coerced, Pressured,Harassed or Threatened by Mgt.W/O Encl ML20149C3461987-04-0606 April 1987 Forwards Final Rept Re post-accreditation Audit of Training Programs at Plant Conducted in Mar 1987.Nonlicensed & Licensed Operator Training Programs Developed from Task Analysis Identified Skills & for Learning Objectives ML20149C2461986-12-0303 December 1986 Forwards Final Repts from NRC post-accreditation Audits Using Training & Review Criteria & Procedures Published as NUREG-1220 in Jul 1986.Both Job & Task Analyses Necessary for Full Implementation of performance-based Training ML20149C1231986-08-0808 August 1986 Forwards Final Rept on post-accreditation Audit of Training Programs Conducted on 860624-26.Strong Mgt Commitment to Training Improvement Exists at Facilities.Issuance of INPO Guidance Will Help to Improve Job Incumbent Training ML20147E0421986-01-28028 January 1986 Forwards Preliminary post-accreditation Audit Reviews at Susquehanna on 851021-23,at Dresden on 851118-21 & at Oconee on 851216-18 & Rept on INPO 851210 follow-up Visit at Susquehanna ML20137C3851985-12-30030 December 1985 Forwards AEOD/C504, Case Study Rept on Loss of Safety Sys Function Events. No Previously Unrecognized Safety Problems Discovered.Rept Contains Recommendations to Increase Awareness of Causes ML20128M8451985-04-25025 April 1985 Second Partial Response to FOIA 850129 Request for Documents Re APS Source Term Review.Documents in Apps C-E,excluding Documents Marked W/Asterisks,Encl & in Pdr.Documents W/ Asterisks Previously Placed in PDR ML20128M6211985-04-15015 April 1985 Partial Response to FOIA Request for Four Categories of Documents Re APS Source Term Review.Forwards Documents in App A.App B Documents Available in Pdr.App a Documents Being Placed in PDR NUREG-0770, Partial Response to FOIA Request for Four Categories of Documents Re APS Source Term Review.Forwards Documents in App A.App B Documents Available in Pdr.App a Documents Being Placed in PDR1985-04-15015 April 1985 Partial Response to FOIA Request for Four Categories of Documents Re APS Source Term Review.Forwards Documents in App A.App B Documents Available in Pdr.App a Documents Being Placed in PDR ML20147E9451985-03-0707 March 1985 Nominates L Clark & F Fogerty as Candidates for Consideration as Addl INPO Accrediting Board Members ML20149B7301985-01-24024 January 1985 Forwards Dj Shea Re Adequacy of INPO Job Task Analysis.Inpo Plans to Compare,Change or Validate Existing Generic Job Task Analysis Against Task Analysis Data Generated for Suppl 1 to NUREG-0737 Activities ML20128N6311985-01-16016 January 1985 Forwards Addl Results from Special Review & Audit of BMI-2104 Methodology.W/O Stated Encl ML20128N9791984-08-23023 August 1984 Forwards Most Recent Version of Six BMI-2104 Repts by Bmi. Vol I Re Pwr,Large Dry Containment (Surry),Vol II Re BWR, Mark I Design & Vol III Re Bwr,Mark III Design Encl.W/O Encl ML20128N0461984-06-18018 June 1984 Forwards Final Version of Vol V to BMI-2104, Surry Recalculated. W/O Encl ML20149B5801984-03-0101 March 1984 Advises That INPO Accreditation Process Offers Utils Mechanism to Meet Intent of Proposed Training Rule W/O Separate Set of Reporting Requirements.Final Accrediation Rept to Detail Observations Required ML20128M6791983-11-10010 November 1983 Forwards Draft Vols I-III to BMI-2104 Re Ongoing Source Term Reassessment Study.Also Forwards Presentations Made During Three Previous Peer Review Meetings & Official Transcripts.W/O Encls ML20028C5591982-12-15015 December 1982 Responds to FOIA Request for Documents Re VEPCO Noncompliance W/Transportation or Packaging Regulations, Violation Noted in EA-80-28 & Routine or spot-check Insp & Enforcement Activities.Documents Available in PDR ML20235D1331963-10-28028 October 1963 Forwards Geologic & Seismic Investigations of Proposed Nuclear Power Plant Site on Bodega Head,Sonoma County,Ca, Per .W/O Encl ML20234C0761963-10-23023 October 1963 Responds to Re Proposed Nuclear Reactor at Bodega Bay,Ca.Usgs Conducting Thorough Study of Geology of Bay.Cp Will Not Be Issued Until Commission Convinced That Facility Will Not Pose Risk to Public .W/O Encls ML20234B9321963-02-11011 February 1963 Informs That No Date Set for Public Hearing Re Util Proposed Nuclear Reactor Power Plant at Bodega Bay,Sonoma County,Ca, Per .When Date for Hearing Set,Ofc of Secretary of AEC Will Send Notification 1988-09-09
[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 NUREG-1706, Concludes That There Are No Nuclear Plants with Y2K Issues Involving Safety Sys,Based on Review of Licensee Responses & Onsite Assessment of Licensee Y2K Activities as Described in NUREG-17061999-09-23023 September 1999 Concludes That There Are No Nuclear Plants with Y2K Issues Involving Safety Sys,Based on Review of Licensee Responses & Onsite Assessment of Licensee Y2K Activities as Described in NUREG-1706 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 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
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- August 8, 1986 Mr. Ken Strahm Institute of Nuclear Power Operations Suite 1500 1100 Circle 75 Parkway Atlanta, Georgia 30339
Dear Mr. Strahm:
Enclosed is the final report from the staff's post-accreditation audit at Salem conducted in June 1986.
Based on staff observation, it appears that a strong management commitment to training program improvement exists at Salem.
Also, it is apparent that there is an effort to continually update and revise the training programs and task lists based on feedback and experience.
As in most of the other programs reviewed to date, deficiencies identified through use of the NRC Training Review and Criteria and acknowledged by the utility are:
an incomplete task analysis which would identify XSAs to serve as a basis for deriving learning objectives and a failure to identify which tasks are appropriate for continuing training.
In contrast to programs reviewed at other utilities, the learning objectives at Salem were complete and easily traced to tasks and test items.
As we have discussed, I believe that NRC issuance of the final rule on Operator Licensing will result in utilities applying performance-based training concepts to continuing training (i.e., requalification training).
Your plan to issue INP0 guidance related to continuing training will help to I
improve job incumbent training.
If you have any questions about the staff's training review activities, please contact me.
l Sincerely, ori Signed By yILL f. T. BU'9 l
l l
William T. Russell, Director l
Office of Nuclear Reactor Regulation
Enclosure:
As stated l
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4 POST-ACCREDITATION AUDIT OF TRAINING PROGRAMS AT SALEM A.
Introduction 1.0 Background.
On June 24 through 26, 1986, the NRC staff conducted a l
post-accreditation audit of training at Salem. All 10 of the eligible Salem training programs have received INP0 accreditation.
The Salem SRO and mechanical maintenance training programs were reviewed.
2.0 Approach.
Prior to the on site review, NRC staff selected the two programs for review and informed the utility.
Five tasks for each program were selected from the utility's task listing and the utility was informed so that the materials associated with those tasks were available for review.
One additional task for each program was selected on site during the review. The remainder of the review consisted of document reviaw, interviews and interactions with both training and operations staff and management, and classroom and simulator observations to answer the questions in the NRC's "Training Review Criteria and Procedures" (NUREG-1220, June 1986). The utility briefed the NRC review team on the general approach to training development at Salem and explained their approach to analysis.
The NRC review team consisted of three training and assessment specialists from NRR and two subject matter experts from Region I.
3.0 Criteria.
The criteria used by the staff to audit the implementation of performance-based training programs are taken directly from the "Commission Policy Statement on Training and Qualification of Nuclear Power Plant Personnel" (50 FR 11147) of March 20, 1985.
In its Policy Statement, the NRC states that the following five elements are essential to acceptable performance-based training programs:
(1)
Systematic analysis of the jobs to be performed, (2) Learning objectives that are derived from the analysis and that describe desired performance after training, (3) Training design and implementation based on the learning objectives, (4)
Evaluation of trainee mastery of the objectives during training, and (5) Evaluation and revision of the training based on the performance of trained personnel in the job setting.
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2 4.0 Documentation.
To support its review, the NRC requested that the following types of documentation be provided by the facility:
- Instructions / procedures related to:
- Systematic methods used to analyze jobs,
- Training organization goals, objectives, and plans,
- Responsibilities / authority of training organization personnel,
- Methods for evaluating / selecting instructional materials, methods, and media,
- Methods for organizing / sequencing of training,
- Methods for keeping training programs current,
- Maintenance of training records,
- Selection of candidates for training and the granting of waivers / exemptions from training,
- Evaluation of training programs, and
- Training, qualification, and evaluation of instructors.
- Task lists for the jobs being reviewed
- Documentation related to:
- Development / validation of task lists,
- Selection of tasks for formal training.
- Analysis of tasks,
-- -- Analysis of on-the-job performance problems and industry events, and
- Evaluation / audits of the training program (s).
- Roster / organization chart for the training organization
- Training schedule The above documentation is the type normally associated with participation in the INP0 accreditation process.
5.0 Scope of audit.
The programs audited and the tasks selected for review within those programs were:
PROGRAM TASKS (1) Senior Reactor Operator
' Evaluate system leakage that is not covered by Technical Specifications or that is covered by Technical Specifica-tions but does not exceed the maximum permissible leak rate
- Verify that post-maintenance retest requirements have been satisfied
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- Align the 4ky buses to the station power transformers
- Take corrective action for loss of coolant (2) Mechanical Maintenance
- Test electric motors (e.g.,
megger, check amperage, rotation, etc.) on bench
- Repair air operated valve operator
- Withdraw in-core instrumentation thimbles for refueling reactor
- Perform hydrostatic test on condenser / heat exchanger tubes
Results of Review The following discussion of the review findings parallels the elements of the Commission's Policy Statement on Training and Qualification.
1.0 Systematic Analysis of Jobs to be Performed l
1.1 Discussion.
Task analysis methods, procedures and products were reviewed using the documentation described in Section A.3 above to determine whether:
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- A systematic method was used for identifying the tasks that make up job (s) being evaluated.
- A systematic method was used for selecting tasks for which. raining is provided.
- Tasks requiring initial training only and those requiring continuing training were differentiated.
- Analysis of tasks chosen for training was adequate for development of learning objectives.
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- Approved procedures are implemented so that analysis information is kept current as job perfonnance requirements change.
1.2 Findings. Tasks for the Senior Reactor Operator (SRO) position at Salem were identified using the INPO generic task listing for the control room operator (CRO) position. The INP0 generic task analysis for the SR0 position was not available at the time that Salem was generating its SRO task inventory.
The INP0 CR0 generic task list was compared to a similar plant (i.e., McGuire) CR0 task list, and was reviewed by subject matter experts and by job incumbents to derive the Salem SR0 task list.
Position descriptions, technical manuals, regulatory requirements, Technical Specifications and procedures were also reviewed and compared against the task listing.
Knowledges, skills, and abilities were not identified from a task analysis, nor was a differentiation made between tasks requiring initial training and tasks requiring continuing training. The utility stated that all SR0 tasks have the potential to be included in continuing training.
Selection of tasks for SR0 continuing training is based on regulatory requirements, Training Review Group recomendations, and results of assessment tests prior to each offering of the continuing training program.
A plant-specific task list was developed for the mechanical maintena'nce positions which identifies for training all relevant tasks derived from plant work orders.
The identification of tasks for continuing training is not done from task analysis information using information about task consequences, frequency, or decay in performance over time but is done by instructors and the Training Review Group.
Knowledges and skills have not been identified for tasks.
Procedures are implemented to ensure that the task inventories for all job positions are being reviewed and revised as appropriate, to incorporate lessons learned through operating experience, plant modifications and other changes. The Nuclear Training Review Group reviews the task inventories at a minimum of every 5 years according to procedures but the task inventory had, in fact, been recently revised (i.e., less than a year since originally derived).
The training department has created a computerized job task inventory which allows for continual updating and use of task data.
2.0 Development of Learning Objectives 2.1 Discussion.
Learning objectives were reviewed for the subject programs to determine whether:
- There are learning objectives for each of the tasks selected for review.
- Learning objectives are derived from or related to the knowledge, skills and abilities needed for successful job performance.
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- Each learning objective states the job performance behaviors expected of trainees upon completion of training.
- Each learning objective states the job performance-based conditions under which the trainee actions will take place.
- Each learning objective states the specific. job performance-based standard for successful performance of the objective.
- Written procedures require modification of learning objectives when related job performance requirements change.
2.2 Findings.
For both the SRO and Mechanical Maintenance programs each task selected for review was supported by written learning objectives documented in lesson plans.
The learning objectives were written to support the task statements as they appear in the Salem task inventories and, therefore, have not been derived from identified knowledges, skills, and abilities that enable the trainee to perform the tasks.
The learning objectives describe the actions, conditions, and standards for task performance.
Where individual learning objectives did not contain actions, conditions, and standards, lesson plans did include a statement specifying the general conditions and standards under which training would occur.
Learning objectives are part of the lesson plans which are reviewed by instructors prior to each course offering and are reviewed and updated as part of the periodic program evaluation performed by the training department program review group.
3.0 Design / Implementation 3.1 Discussion.
Using the documentation described in Section A.3 above, the design and implementation of performance-based training was reviewed to determine whether:
- There is a written plan that clearly and specifically states the training organization's goals, objectives, plans and relationships with other parts of the facility's organization.
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- Responsibilities and authority of. training organization personnel are clearly stated in writing.
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- There are documented qualification and training requirements for the training staff that address both subject matter and instructional skills and knowledge appropriate for specific assignments.
- There is evidence that the appropriateness of instructional settings has been evaluated.
- The organization and sequencing of the initial training programs are based upon the relationships among learning objectives.
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- The organization and sequencing of continuing training is based upon the relationships among learning objectives.
- Lesson plans are available that provide for consistent training delivery.
- There is evidence that the appropriateness of existing instructional materials has been evaluated based upon identified trainee needs and learning objectives.
- Training is being conducted in an adequate manner as detemined through application of training observation checklists.
- There are adequate methods established for maintaining training records.
3.2 Findings. The Administrative Policies Manual clearly and specifically states the training organization goals, objectives and plans.
Training department goals are evaluated annually.
Responsibilities of training department personnel are specified in the Administrative Policies Manual and programs are in place to ensure that training staff visit the plant to evaluate training effectiveness and obtain feedback.
There is currently no written procedure to ensure both technical and instructional qualification of the training staff.
However, training staff technical skills and instructional skills competence are verified during the personnel recruitment process, are enhanced or maintained through training and retraining, and are regularly evaluated. Also, new procedures governing technical and management training are being implemented for training department staff.
l General procedural guidance exists describing selection of instructional settings.
Instructional settings appropriate to learning objectives are based on subject matter and instructor expertise and are evaluated l
I through the feedback process.
For new training. programs, hands-on I
training is always preferred when feasible.
The organization and sequencing of training has been detennined by subject matter experts.
For mechanical maintenance, sequencing was detemined partially during l
l review of preliminary task lists when tasks were identified as level I, l
II, or III craft jobs. A written procedure in the Instructional l
Development Manual generally describes considerations for sequencing training material. One apparent error of training sequencing was identified for SR0 training of transients prior to systems training.
There is no formal method for determining the organization and sequencing of continuing training. Student texts are often used as the basis for topic sequencing. Lesson plans were prepared for training courses which listed learning objectives, references, training material, student handouts, and classroom requirements.
There is evidence that appropriateness of instructional materials has been evaluated and t-
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> revised to address learning objectives and trainee needs.
Plant and industry events are reviewed and included in appropriate training classes.
Classroom and simulator training, as observed, were conducted satisfactorily.
Although the system for storage and retrieval of training records was somewhat cumbersome, trainee records, class records, and training evaluations were available.
4.0 Trainee Evaluation 4.1 Discussion. The methods for and use of trainee evaluations were reviewed using the documentation described in Section A.3 above to determine whether:
- Exemptions from training are based upon performance-based testing or other objective evaluation methods.
- Trainee evaluation is appropriate to job performance requirements and training objectives.
- Trainee performance is evaluated regularly during the training program and prompt, objective feedback provided on a regular basis.
- Trainees who perform below minimum standards are provided remedial training, retested,. and removed from the training program if minimum standards are not met.
- Job incumbents who perform below minimum standards during requalification or continuing training are removed from associated job l
duties and provided remedial training.
- Appropriate precautions are taken to preclude compromise of test contents.
4.2 Findings.
Exemptions from or waivers of training are allowed according to training procedures and have occasionally been granted for l
instructors. Waivers of training requirements must be approved by the station general manager or discipline manager based on an employee's I
background records or examination.
Trainee evaluations are based on written tests which are closely related to instructional objectives. Written exams for current course offerings are controlled to prevent compromise.
Trainees in the final 12 week phase of on-the-job maintenance training receive weekly supervisory evaluations which are general performance evaluations not directly related to learning objectives.
Trainees receive regular evaluations during training and receive remedial training and retesting or are removed from the program if minimum standards are not met. Job l
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. incumbents can and have been disqualified to perform certain duties if found to be deficient during evaluations and must be requalified upon successful completion of remedial training. A qualification summary report is generated for use by plant sup3rvisors to ensure assigning independent duties only to personnel who are currently qualified.
5.0 Program Evaluation 5.1 Discussion.
Training program evaluation methods were reviewed using the documentation described in Section A.3 above to determine whether:
- A method is in place to systematically evaluate the effectiveness of training programs and to revise the programs as required.
- Examination and operating test results are evaluated so that tests are improved and feedback is provided to improve training.
- Instructor critiques of training are used for program evaluction.
- Trainee critiques of training are used for program evaluation.
- On-the-job experiences are solicited from job incumbents and used for program evaluation.
- Feedback from supervisors about job performance is solicited for program evaluation.
- Both internal and external training program audits / evaluation findings are used for program evaluation.
- The performance of each member of the training staff is objectively evaluated on a regular basis.
5.2 Findings.
Salem has recently implemented the Performance Evaluation of Training Effectiveness and the On the Job Evaluation programs to provide feedback about job performance problems for training program t
enhancement.
In addition, an internal program review is conducted every 2 years for each training program which results in recomendations and actions for training program changes as appropriate.
The Training Related Occurrence Committee reviews Licensee Event Reports, incident reports and other lessons learned through operating experience for inclusion in training as appropriate. Quality assurance audits of training are also performed.
l Currently, no formal aggregate evaluation of trainee test performance is l
done to identify program weaknesses, but there are plans to begin such analyses to provide program feedback.
No formal instructor critiques of t
training for program review were done but instructors are responsible l
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-g-for review and modification of lesson plans as necessary prior to each Input to training program modifications is solicited course offering.
during regular informal meetings between plant staff and training department personnel.
Trainee critiques of training are formally solicited at the conclusion Trainee of training and as a 90-120 day follow-up to training.
critiques are reviewed and action plans for resolution of problems are Feedback from supervisors of trainees is developed as necessary.
similarly solicited 90-120 days following completion of training.
Follow-up training critiques are not solicited from participants in continuing training or any course less than 1 month in duration.
Training request forms are available to all plant personnel for use in recomending training changes. Training staff receive regular evaluations of their performance, including observations and individual development plan review and revision.
C.
Sumary of Findings The findings from the post-accreditation training audit at Salem indicate that comprehensive task inventories have been developed and The major used as the basis for developing good learning objectives.
weakness identified was the lack of documented knowledges, skills and abilities (KSAs) derived from a task analysis to use as the basis for Tasks for ensu' ring completeness of learning objectives and training.
continuing training were not identified from an analysis of consequences, frequency and decay over time.
The facility is clearly comitted to provide the maximum amount of hands-on training possible, as indicated by the extensive training equipment and facilities The training department is in the process of converting from available.
a cumbersome manual record-keeping system to an autwated records system and is planning to make better use of course and trir4e records for program evaluation.
Solicitation of post-traininr -
M from participants in continuing training is one import m -
St of program evaluation and feedback that is not done at Salen.
Mn vents i
interviewed were positive about the benefits of Wm 4 i..,;ng and
<s m Muing to bear witness to the fact that the training progr -
improve. A strong management comitment to trair, orcgraer.riprovement is evident at Salem.
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