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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217N8911999-10-15015 October 1999 Forwards Rept of Changes,Tests & Experiments at Pilgrim Nuclear Power Station for Period of 970422-990621,IAW 10CFR50.59(b).List of Changes Effecting Fsar,Encl ML20217D3951999-10-13013 October 1999 Forwards Request for Addl Info Re Util 990806 Submittal on USI A-46, Implementation Methodology Used at Pilgrim Nuclear Power Station, Per GL 87-02 ML20217E1581999-10-0808 October 1999 Forwards Insp Rept 50-293/99-05 on 990726-0905.Three Violations Noted & Being Treated as Ncvs.Violations Include Failure to Assure That Design Bases Correctly Translated Into Specifications ML20217C3151999-10-0606 October 1999 Forwards Scenario Package for Pilgrim Nuclear Power Station Nrc/Fema Evaluated Exercise Scheduled for 991207.Without Encl ML20217D5591999-10-0505 October 1999 Documents Pilgrim Nuclear Power Station Five Yr Survey of Main Breakwater.Survey Has Determined That Pilgrim Main Breakwater Is Intact & Remains Adequately Constructed to Perform Designed Safety Function ML20217C8051999-10-0505 October 1999 Forwards Proprietary Results of Audiologic Evaluations for Jp Giar,License SOP-10061-3.Attachment Clearly Shows Requirements for Operator Hearing Ability Are Met. Proprietary Info Withheld,Per 10CFR2.790(a)(6) ML20212J8301999-09-30030 September 1999 Informs of Completion of mid-cycle PPR of Pilgrim Nuclear Power Station.Staff Conducts Reviews for All Operating NPPs to Integrate Performance Info & to Plan Insp Activities at Facility Over Next Six Months ML20216J9961999-09-29029 September 1999 Forwards Resume of Person Identified as Acting RPM in Licensee to NRC Re Notification That Person Named in License Condition 11 of 20-07626-02,is No Longer Employed at Pilgrim Station.Resume Withheld,Per 10CFR2.790 ML20212F7871999-09-24024 September 1999 Advises That Util 990121 Application for Amend Being Treated as Withdrawn.Proposed Changes Would Have Modified Facility UFSAR Pertaining to Values for post-accident Containment Pressure Credited in Pilgrim Net Positive Head Analyses ML20212H1381999-09-23023 September 1999 Submits Info in Support of Request Filed on 990730 to Grant one-time Exemption from 10CFR50,App E,Authorizing Biennial Full Participation Emergency Preparedness Exercise to Be Conducted in 2002 Instead of 2001 ML20212H1441999-09-23023 September 1999 Withdraws 990121 Request for License Change Re Emergency Core Cooling Sys Net Positive Suction Head,Due to Incorrect Datum Preparation ML20216F3451999-09-16016 September 1999 Forwards Summary Rept Providing Results of ISI Conducted at PNPS on-line & Refueling Outage (RFO 12) ML20212C2861999-09-16016 September 1999 Forwards SER Accepting Licensee 981123 Request for Relief RR-E1,RR-E5,RR-E6 Pursuant to 10CFR50.55a(a)(3)(i) & Request for Relief RR-E2,RR-E3 & RR-E4 Pursuant to 10CFR50.55a(a)(3)(ii) ML20216E7111999-09-0909 September 1999 Forwards License Renewal Application Including Form NRC-398 & Form NRC-396 for Jp Giar,License SOP-10061-3.Without Encls ML20216E5891999-09-0707 September 1999 Forwards Copy of Pilgrim Station Organization Structure. Encl Refelcts Changes in Upper Mgt Level Structure.Changes Were Effective 990901 ML20211M4501999-09-0303 September 1999 Informs That Pilgrim Nuclear Power Station Plans to Conduct Full Participation Emergency Preparedness Exercise with Commonwealth of Ma on 991207,IAW 10CFR50,App E,Section IV.F.2 ML20211M9161999-08-31031 August 1999 Submits Review & Correction of Info in Reactor Vessel Integrity Database (Rvid),Version 2,re Pilgrim Station ML20211J8391999-08-30030 August 1999 Forwards Rev 1 to Provisional Decommissioning Trust Agreement for Plant,Changing Portions of Agreement to Permit Up to Two Distributions & Clarify Formula for Distribution ML20211H5701999-08-27027 August 1999 Forwards Insp Rept 50-293/99-04 on 990610-0725.Two Violations Identified Being Treated as non-cited Violations ML20211C3381999-08-19019 August 1999 Provides semi-annual LTP Update,Including Schedule, Commitment Descriptions,Progress Since Last Update & Summary of Changes.Rev Bars Indicate Changes in Status Since Last Submittal ML20210U5761999-08-18018 August 1999 Responds to Opposing Merger of Bec Energy & Commonwealth Energy Sys in Commonwealth of Massachusetts. Informs That for Sale,Nrc Responsible for Only Ensuring That Entergy Technically & Financially Qualified to Operate NPP ML20210U6691999-08-18018 August 1999 Forwards from Massachusetts State Senator T Murray Opposing Merger Between Bec Energy & Commonwealth Energy Systems ML20210U7521999-08-18018 August 1999 Forwards from Massachusetts State Senator T Murray Opossing Merger Between Bec Energy & Commonwealth Energy Systems ML20210U5151999-08-17017 August 1999 Forwards Notice of Withdrawal of Application for Approval of Indirect Transfer of FOL for Pilgrim in Response to .Approval No Longer Needed Since Beco Sold Interest in Pilgrim to EOI on 990713 ML20211B3841999-08-16016 August 1999 Forwards Response to NRC Second RAI Re Pressure Locking & Thermal Binding of SR power-operated Gate Valves ML20210U4831999-08-13013 August 1999 Forwards fitness-for-duty Program Performance Data Sheets for Period of 990101-0630,per 10CFR26.71(d) ML20210S0891999-08-0909 August 1999 Forwards Amend 11 to Indemnity Agreement B-48 Signed by Boston Edison Co & Entergy Nuclear Generation Co ML20210R6251999-08-0606 August 1999 Provides Supplementary Info on USI A-46 Implementation Methodology at Pilgrim Station,To Enable NRC to Perform Evaluation & Issuance of Plant Specific SER for Plant ML20210M9411999-08-0202 August 1999 Requests That NRC Treat Pending Actions Requested by Beco Prior to 990713,as Requests Made by Entergy.Ltr Requests That Minor Administrative Changes to License Amend 182 & Associated Ser, ,reflect 990713 Transfer ML20210H8761999-07-30030 July 1999 Requests That NRC Grant Exemption from Requirements of 10CFR50,App E,Section IV F,Which Would Authorize Rescheduling of 2001 Biennial Full Participation Emergency Preparedness Exercise for Pilgrim Station to 2002 ML20210H8661999-07-29029 July 1999 Provides Revised Response to GL 96-06 & Addresses NRC Insp Concern for Containment Penetration X-12.Info Submitted to Facilitate NRC Review & Closeout of Subject GL for Plant ML20216E2321999-07-26026 July 1999 Discusses GL 92-01,rev 1,suppl 1, Rv Structural Integrity. NRC Revised Info in Rvid & Releasing as Rvid Version 2 ML20216D4131999-07-22022 July 1999 Informs That J Conlon,License OP-11040-1,terminated Employment with Beco on 990703,per 10CFR50.74.Individual Will Not Participate in Util Licensed Operator Requalification Training Program ML20210E2231999-07-20020 July 1999 Discusses Arrangements Made by Dennis & M Santiago During 990615 Telephone Conversation for NRC to Inspect Licensed Operator Requalification Program at Pilgrim During Wk of 991004 ML20210C4151999-07-19019 July 1999 Informs That Util Intends to Submit Approx Eight Licensing Actions in FY00 & Eight in FY01,in Response to Administrative Ltr 99-02.Actions Are Not Expected to Generate Complex Reviews ML20210F3711999-07-14014 July 1999 Informs NRC That Effective 990713,listed Pilgrim Station Security Plans Have Been Transferred from Boston Edison to Entergy & Are Still in Effect ML20210A9441999-07-14014 July 1999 Responds to Re Changes to Pilgrim Nuclear Power Station Physical Security Plan Identified as Issue 2,rev 14, Addendum 1,respectively.No NRC Approval Is Required IAW 10CFR54(p) ML20209G2251999-07-0909 July 1999 Forwards Insp Rept 50-293/99-03 on 990419-0609.Five Severity Level IV Violations of NRC Requirements Identified & Being Treated as non-cited Violations,Consistent with App C. Several Individual Tagging Errors Occurred ML20209C4661999-07-0707 July 1999 Forwards SE Accepting Addendum on Proposed Change in Corporate Ownership Structure Involving Entergy Nuclear Generation Co ML20209C7761999-07-0606 July 1999 Submits Annual Summary Rept of Changes Made to QAP Description as Described in QA Manual,Vol Ii.Rept Covers Period of Jul 1998 Through June 1999.No Changes Made During Period ML20209C3851999-07-0606 July 1999 Forwards Redacted Draft of Decommissioning Trust Agreement Re Transfer of PNPS & NRC Operating License & Matls License from Boston Edison Co to Entergy Nuclear Generating Co ML20196J7251999-07-0101 July 1999 Informs of Completion of Licensing Action for GL 96-01, Testing of Safety-Related Logic Circuits, for Pilgrim Nuclear Power Station ML20209B9411999-06-30030 June 1999 Discusses Deferral of IGSCC Welds to RFO 13.Deferral of Welds to Refueling Outage 13 Does Not Impact Acceptable Level of Quality & Safety Per 10CFR50.55(a)(3)(i) Since Plant in Compliance W/Exam Percentage Requirements ML20209B9431999-06-30030 June 1999 Provides Formal Notification That Closing Date for Sale & Transfer of Pilgrim Station Scheduled to Occur on 990713. a Wang Will Be Verbally Notified of Time of Sale Closing ML20209B9791999-06-29029 June 1999 Forwards Rev 13A to Pilgrims COLR for Cycle 13,IAW TS 5.6.5 Requirements.Rev 13A Provides cycle-specific Limits for Operating Pilgrim During Remainder of Cycle 13 ML20196H2381999-06-29029 June 1999 Forwards SER Denying Licensee 980820 Request for Alternative Under PRR-13,rev 2 for Use of Code Case N-522 During Pressure Testing of Containment Penetration Piping ML20209A8761999-06-28028 June 1999 Forwards SER Authorizing Licensee 990317 Relief Request to Use ASME Code Case N-573 as Alternative to ASME Code Section XI Article IWA-4000 for Remainder of 10-year Interval Pursuant to 10CFR50.55a(a)(3)(i) ML20209A8701999-06-25025 June 1999 Responds to NRC Request for Info Re Y2K Readiness of Computer Sys at Nuclear Power Plants. Y2K Readiness Disclosure for Plant,Reporting Status of Facility Y2K Readiness Encl ML20210U5901999-06-25025 June 1999 Opposes Merger of Bec Energy & Commonwealth Energy Sys in Commonwealth of Massachusetts.Expresses Skepticism Re Claim by Companies That Consumers Will Benefit from Proposed Consolidation & four-year Freeze in Base Rates ML20209C3431999-06-22022 June 1999 Forwards Addendum 1,Rev 14 to Pilgrim Station Security Plan,Iaw 10CFR50.54(p)(2).Changes Proposed Have Been Implemented & Constitute Increase in Plant Defense Plan Commitments.Encl Withheld,Per 10CFR73.21 1999-09-09
[Table view] Category:NRC TO UTILITY
MONTHYEARML20062E0071990-11-14014 November 1990 Forwards List of Unimplemented GSIs at Facility,Per Generic Ltr 90-04 ML20062D6651990-11-0808 November 1990 Ack Receipt of Forwarding Util Evaluation of NRC Inspector General Rept 90N-02 Re Offsite Emergency Planning ML20058G9761990-11-0707 November 1990 Forwards Safety Insp Rept 50-293/90-20 on 900816-1008 & Notice of Violation ML20058C5501990-10-26026 October 1990 Requests Written Policies & Procedures Needed for NRC Preparation for Planned fitness-for-duty Insp ML20062B4311990-10-17017 October 1990 Advises That 901012 Response to Generic Ltr 90-03 Re Vendor Interface for safety-related Components,Acceptable ML20062B7161990-10-12012 October 1990 Extends Invitation to Attend 910220-21 Util Symposium/ Workshop in King of Prussia,Pa Re Engineering Role in Plant Support.Interest to Participate,Intent to Attend & Approx Number of Representatives to Attend Requested by 901115 ML20062B6281990-10-12012 October 1990 Forwards Insp Rept 50-293/90-21 on 900905-07.Insp Conducted to Review Event of 900902-03 Which Involved Number of Component Malfunctions & Operational Complications Following Shutdown ML20059N7251990-10-0101 October 1990 Requests That Matls Listed in Encl Be Furnished to Assist Maint Program Team Insp Scheduled for 901105-16 ML20059K6901990-09-11011 September 1990 Forwards Transcript of 900906 Public Meeting in Plymouth,Ma W/State & Local Officials Re Emergency Planning.W/O Encl ML20059H5871990-09-0101 September 1990 Advises That Reactor Operator & Senior Reactor Operator Exams Scheduled for 901203.Encl Listed Ref Matl Requested ML20059J6521990-08-29029 August 1990 Forwards Safety Insp Rept 50-293/90-09 on 900806-10.No Violations Noted.Concludes That Engineering & Technical Support Organizations Continue to Provide Strong Station Support ML20059A1481990-08-17017 August 1990 Forwards 900816 Summary of 900807 Meeting Re Inservice Testing Program ML20058P0471990-08-0909 August 1990 Forwards Safety Insp Rept 50-293/90-18 on 900709-13.No Violations Noted ML20058N0401990-08-0606 August 1990 Discusses Licensee Engineering Initiatives.Power Reactor Licenses in Region 1 Should Initiate Similar Program to Provide Sharing of Info & Experiences Involving Engineering Initiatives & Solution to Problems Common to All ML20056A4801990-07-30030 July 1990 Forwards Safeguards Insp Rept 50-293/90-16 on 900625-29.No Violations Noted.One Unresolved Item Identified ML20058L7051990-07-27027 July 1990 Forwards Safety Insp Rept 50-293/90-17 on 900625-29.No Violations Noted ML20055F2461990-06-29029 June 1990 Forwards Safety Insp Rept 50-293/90-13 on 900501-0611.No Violations Noted.Repetitive Failures of Diesel Driven Fire Pump Noted,Requiring Increased Mgt Attention ML20059M8421990-06-13013 June 1990 Forwards NRC Performance Indicators for First Quarter 1990. W/O Encl ML20247R8071989-09-21021 September 1989 Forwards SALP Rept 50-293/88-99 for 880516-890630.Instances of Deviation from Approved Practices & Lack of Attention to Detail Which Led to Challenges to Plant Equipment & Personnel Noted ML20247K6661989-09-0707 September 1989 Forwards Insp Rept 50-293/89-07 on 890525-0710 & Notice of Violation ML20246K5091989-08-24024 August 1989 Accepts Summary of QA Program Description Changes for 1989, Forwarded by ML20246L7821989-08-23023 August 1989 Forwards Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $25,000.Failures to Properly Plan, Supervise & Inspect Tagout of Circuit Breakers Directly Contributed to Event IR 05000293/19890071989-08-18018 August 1989 Approves Reactor Operation Up to 75% of Full Power Per Licensee Power Ascension Test Program.Nrc Findings Docketed in Insp Repts 50-293/89-07 & 50-293/89-08 & Status of Emergency Preparedness for Communities Encl ML20246G1861989-08-18018 August 1989 Approves Reactor Operation Up to 75% of Full Power Per Licensee Power Ascension Test Program.Nrc Findings Docketed in Insp Repts 50-293/89-07 & 50-293/89-08 & Status of Emergency Preparedness for Communities Encl ML20246J4811989-08-18018 August 1989 Clarifies NRC Position Re Definition of Extremity for Purposes of Setting Occupational Exposure Limits.Due to Misunderstanding,No Enforcement Action Planned If Licensee Procedures Incorporated Misunderstanding ML20246D7261989-08-18018 August 1989 Submits Response to Re Plant Power Ascension Program.Util Proposal to Defer Phase 2 of Shutdown from Outside Control Room Test to Planned Fall 1989 mid-cycle Outage Accepted ML20245F1781989-07-31031 July 1989 Forwards Insp Rept 50-293/89-06 on 890411-0524.No Violations Noted.Licensee Actions W/Respect to 890503 Turbine Trip/Reactor Scram Demonstrated Excellent Approach to Problem Investigation & Resolution ML20247D0181989-07-18018 July 1989 Ack Receipt of Re Response to NRC Bulletin 89-003, Inadequate Latch Engagement in Hfa Type Relays Mfg by Ge. Necessary Actions Performed to Address Issues in Bulletin ML20246N3921989-07-14014 July 1989 Forwards Safety Insp Rept 50-293/89-09 on 890619-22.No Violations Noted ML20246D4961989-07-0606 July 1989 Advises That 880713 Response to NRC Bulletin 88-004, Potential Safety-Related Pump Loss Acceptable ML20246A7561989-06-26026 June 1989 Approves Reactor Operation Up to 50% Full Power,Per Util Power Ascension Test Program & Confirmatory Action Ltr 86-10.Assessment of Licensee Readiness for Release from NRC Approval Point 3 & Related Info Encl ML20246B5961989-06-22022 June 1989 Forwards,For Info,Nrr Ack Receipt of Petition Filed by Ecology Ctr of Southern CA & Stating That Petition Being Treated Under 10CFR2.206 of Commission Regulations ML20245A5371989-06-0909 June 1989 Forwards Insp Rept 50-293/89-05 on 890311-0410.Weaknesses Noted Re Evaluation of Failure Rate & Root Causes for Failures of Airlock Doors & Interlocks ML20244C2121989-06-0707 June 1989 Responds to Util 881011 Response to Generic Ltr 87-02, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors. Implementation Schedule Contingent Upon Resolution of Procedure ML20244C2751989-06-0606 June 1989 Forwards Draft Safety Evaluation Re Plant Compliance W/ 10CFR50.62, ATWS Rule. Requests Response to NRC Concerns Re Diversity & Testability of Alternate Rod Injection & Reactor Pump Trip Sys NUREG-1275, Informs That Util Fulfilled Requirements of Generic Ltr 88-14, Instrument Air Supply Sys Problems Affecting Safety Related Sys1989-06-0202 June 1989 Informs That Util Fulfilled Requirements of Generic Ltr 88-14, Instrument Air Supply Sys Problems Affecting Safety Related Sys ML20247P5501989-06-0101 June 1989 Forwards Request for Addl Info on Proposed Tech Specs Change Re Visual Insp of High Energy Piping.Listed Concerns Based on Review of Bechtel Calculation 17322-S5,Rev 1 ML20247M2661989-05-26026 May 1989 Forwards Director'S Decision,Ltr of Transmittal & Fr Notice in Response to Ocre 2.206 Petition Expressing Concerns Re 880309 Power Oscillation Event at LaSalle Unit 2 & Request to Reopen Rulemaking on ATWS Issue.W/O Encls ML20246P6051989-05-15015 May 1989 Forwards Notice of Withdrawal of Application for Amend to License DPR-35.Amend Would Modify Tech Specs Re ECCS Surveillance Requirements ML20247D5481989-05-0808 May 1989 Forwards Augmented Insp Team Rept 50-293/89-80 on 890413-19 & 17-26.Team Concluded That Safety Significance of 890412 Pressurization Transient Was Minor,Though Event Raised Concerns Re Proximate Human Factors & Equipment ML20246N7951989-05-0404 May 1989 Forwards Mgt Meeting Rept 50-293/89-04 on 890328-30 W/Commonwealth of Ma & Local Officials ML20247A6911989-05-0303 May 1989 Extends Invitation to Attend Power Reactor Operator Licensing Seminar on 890531 in King of Prussia,Pa.Agenda & Info Re Lodging Arrangements Encl ML20245H8371989-04-26026 April 1989 Forwards SAIC-89/1121, In-Progress Audit Rept of Dcrdr at Boston Edison Co Pilgrim Nuclear Power Station & SAIC-89-1119, In-Progress Audit Rept for Boston Edison Co Pilgrim Nuclear Poser Station Spds ML20245H9551989-04-26026 April 1989 Forwards Insp Rept 50-293/89-01 on 890206-0310 & Notice of Violation ML20245J1441989-04-25025 April 1989 Advises That 880921 & 890302 Responses to NRC Bulletin 88-007 & Suppl 1, Power Oscillations in BWRs Meet Requirements of Both Bulletins ML20244E4611989-04-14014 April 1989 Requests Prompt Review & Reporting of Status of Implementation of TMI Action Plan Items at Facility.Printout of All TMI Items Annotated Where Tracking Sys Indicates That Implementation Not Complete Encl ML20244C2771989-04-10010 April 1989 Informs of Completion of Followup on Plant Regulatory Effectiveness Review Effort & Activities Re TAC 56995. Previous Compensatory Measures Removed as Result of Implementing Corrective Action ML20244A6931989-04-0707 April 1989 Forwards Mgt Meeting Rept 50-293/89-43 on 890309 to Discuss Util Followup Actions to 890304 Reactor Scram ML20244A6281989-04-0303 April 1989 Forwards Insp Rept 50-293/88-37 on 881227-890205.Violation Noted Re Failure to Control Locked High Radiation Area Access ML20235V7311989-03-0303 March 1989 Forwards Safety Evaluation Accepting Revised Temp Profile, Per GE EAS-98-0887, Drywell Temp Analysis for Pilgrim Nuclear Power Station. Profile Requested to Be Documented in Next Updated FSAR 1990-09-11
[Table view] Category:OUTGOING CORRESPONDENCE
MONTHYEARML20217D3951999-10-13013 October 1999 Forwards Request for Addl Info Re Util 990806 Submittal on USI A-46, Implementation Methodology Used at Pilgrim Nuclear Power Station, Per GL 87-02 ML20217E1581999-10-0808 October 1999 Forwards Insp Rept 50-293/99-05 on 990726-0905.Three Violations Noted & Being Treated as Ncvs.Violations Include Failure to Assure That Design Bases Correctly Translated Into Specifications ML20212J8301999-09-30030 September 1999 Informs of Completion of mid-cycle PPR of Pilgrim Nuclear Power Station.Staff Conducts Reviews for All Operating NPPs to Integrate Performance Info & to Plan Insp Activities at Facility Over Next Six Months ML20212F7871999-09-24024 September 1999 Advises That Util 990121 Application for Amend Being Treated as Withdrawn.Proposed Changes Would Have Modified Facility UFSAR Pertaining to Values for post-accident Containment Pressure Credited in Pilgrim Net Positive Head Analyses ML20212C2861999-09-16016 September 1999 Forwards SER Accepting Licensee 981123 Request for Relief RR-E1,RR-E5,RR-E6 Pursuant to 10CFR50.55a(a)(3)(i) & Request for Relief RR-E2,RR-E3 & RR-E4 Pursuant to 10CFR50.55a(a)(3)(ii) ML20211H5701999-08-27027 August 1999 Forwards Insp Rept 50-293/99-04 on 990610-0725.Two Violations Identified Being Treated as non-cited Violations ML20210U7521999-08-18018 August 1999 Forwards from Massachusetts State Senator T Murray Opossing Merger Between Bec Energy & Commonwealth Energy Systems ML20210U5761999-08-18018 August 1999 Responds to Opposing Merger of Bec Energy & Commonwealth Energy Sys in Commonwealth of Massachusetts. Informs That for Sale,Nrc Responsible for Only Ensuring That Entergy Technically & Financially Qualified to Operate NPP ML20210U6691999-08-18018 August 1999 Forwards from Massachusetts State Senator T Murray Opposing Merger Between Bec Energy & Commonwealth Energy Systems ML20210U5151999-08-17017 August 1999 Forwards Notice of Withdrawal of Application for Approval of Indirect Transfer of FOL for Pilgrim in Response to .Approval No Longer Needed Since Beco Sold Interest in Pilgrim to EOI on 990713 ML20216E2321999-07-26026 July 1999 Discusses GL 92-01,rev 1,suppl 1, Rv Structural Integrity. NRC Revised Info in Rvid & Releasing as Rvid Version 2 ML20210E2231999-07-20020 July 1999 Discusses Arrangements Made by Dennis & M Santiago During 990615 Telephone Conversation for NRC to Inspect Licensed Operator Requalification Program at Pilgrim During Wk of 991004 ML20210A9441999-07-14014 July 1999 Responds to Re Changes to Pilgrim Nuclear Power Station Physical Security Plan Identified as Issue 2,rev 14, Addendum 1,respectively.No NRC Approval Is Required IAW 10CFR54(p) ML20209G2251999-07-0909 July 1999 Forwards Insp Rept 50-293/99-03 on 990419-0609.Five Severity Level IV Violations of NRC Requirements Identified & Being Treated as non-cited Violations,Consistent with App C. Several Individual Tagging Errors Occurred ML20209C4661999-07-0707 July 1999 Forwards SE Accepting Addendum on Proposed Change in Corporate Ownership Structure Involving Entergy Nuclear Generation Co ML20196J7251999-07-0101 July 1999 Informs of Completion of Licensing Action for GL 96-01, Testing of Safety-Related Logic Circuits, for Pilgrim Nuclear Power Station ML20196H2381999-06-29029 June 1999 Forwards SER Denying Licensee 980820 Request for Alternative Under PRR-13,rev 2 for Use of Code Case N-522 During Pressure Testing of Containment Penetration Piping ML20209A8761999-06-28028 June 1999 Forwards SER Authorizing Licensee 990317 Relief Request to Use ASME Code Case N-573 as Alternative to ASME Code Section XI Article IWA-4000 for Remainder of 10-year Interval Pursuant to 10CFR50.55a(a)(3)(i) ML20195K3071999-06-15015 June 1999 Forwards Safety Evaluation Granting Licensee Request to Use Guidance of GL 90-05 to Repair Flaws in ASME Class 3 Salt Svc Water Sys Piping for Plant ML20195K3851999-06-11011 June 1999 Forwards Copy of Notice of Consideration of Approval of Application Re Proposed Corporate Merger & Opportunity for Hearing.Application Seeks Approval of Proposed Indirect Transfer of FOL for Plant ML20196K9921999-06-0404 June 1999 Informs That NRC Ofc of NRR Reorganized Effective 990328.As Part of Reorganization,Division of Licensing Project Mgt Created ML20207E7351999-05-27027 May 1999 Responds to Requesting Reduction in IGSCC Insp Frequency Per GL 88-01 to Be Performed During Upcoming RFO 12.Forwards SE Re Reduction of IGSCC Insp of Category D Welds Due to Implementation of H Water Chemistry ML20207B6341999-05-26026 May 1999 Informs That Licensee 990415 Submittal Re Financial Position of Entergy Intl Ltd,Llc Will Be Marked as Proprietary & Withheld from Public Disclosure Pursuant to 10CFR2.790(b)(5) & Section 103(b) of Atomic Energy Act ML20207B7391999-05-24024 May 1999 Forwards from Kc Goss of FEMA to Cl Miller Forwarding FEMA Analysis of Prompt Alert & Notification Sys for Pilgrim Nuclear Power Station.Based on Review,No Significant Problems Exist with Alert & Notification Sys ML20207B0701999-05-24024 May 1999 Responds to Sent to Ofc of Congressional Affairs Requesting Info on Concerns Raised by One Constituent,J Riel Re Y2K Compliance of Pilgrim NPP in Plymouth,Ma ML20207C0321999-05-18018 May 1999 Forwards Fifth Rept Which Covers Month of Apr 1999. Commission Approved Transfer of TMI-1 Operating License from Gpu to Amergen & Transfer of Operating License for Pilgrim Station from Beco to Entergy Nuclear Generating Co ML20206U7501999-05-17017 May 1999 Forwards Insp Rept 50-293/99-02 on 990308-0418.Two Severity Level 4 Violations Occurred & Being Treated as NCVs ML20206M1891999-05-11011 May 1999 Forwards SE of 980826 Request to Use Guidance of GL 90-05 to Repair Flaws in ASME Class 3 Salt Svc Sys Piping for Plant ML20206E0551999-04-29029 April 1999 Discusses Bulletin 96-03 Issued on 960506 & Beco Responses ,970207,981230,990121 & 990309 for Pilgrim Npp. Determined That Actions Taken Should Minimize Potential for Clogging of ECCS Suction Strainers ML20206B3031999-04-20020 April 1999 Forwards Insp Rept 50-293/99-01 on 990125-0307.Two Violations of NRC Requirements Occurred & Being Treated as non-cited Violations Consistent with App C of Enforcement Policy.Security Program Was Also Inspected ML20205Q9491999-04-0909 April 1999 Informs That on 990225 NRC Staff Completed PPR of Pilgrim Nuclear Power Station.Staff Conducts Reviews for All Operating NPPs to Develop an Integrated Understanding of Safety Performance ML20205B9391999-03-24024 March 1999 Forwards Second Request for Addl Info Re GL 95-07, Pressure-Locking & Thermal-Binding of Safety-Related Power-Operated Gate Valves ML20204C7871999-03-17017 March 1999 Informs That Application Submitting Transfer of Facility Operating License & Matls License & Proposed Amend, Will Be Marked as Proprietary & Be Withheld from Public Disclosure Pursuant to 10CFR2.709(b)(5) ML20199K8321999-01-22022 January 1999 Forwards Request for Addl Info Re Transfer of Facility Operating License for Plant ML20199H5811999-01-20020 January 1999 Submits Exemption Withdrawal of 10CFR70.24(a) Re Criticality Accident Monitoring Requirements ML20198L7781998-12-22022 December 1998 Forwards Insp Rept 50-293/98-10 on 981020-1208.No Violations Noted.Nrc Regional Specialists Reviewed EP & Fire Protection Programs.Ep Program Was Found to Be Well Implemented ML20198J0891998-12-21021 December 1998 Forwards NRC Response to Me Lampert Re Transfer of Ownership of Pilgrim Station in Response to Senator Kerry Ltr Dtd 981019.NRC Will Terminate License Only When Licensee Remediates Site to Levels Specified in Regulations ML20198J1041998-12-21021 December 1998 Forwards NRC Response to Me Lampert Re Transfer of Ownership of Pilgrim Station in Response to Congressman Markey Ltr Dtd 981019.NRC Will Terminate License Only When Licensee Remediates Site to Levels Specified in Regulations ML20137T2211998-12-17017 December 1998 Responds to to Chairman Jackson Re Concerns About Possible Sale of Pilgrim Station & Waste Disposal Issues.No Application for License Received Nor Contract of Sale Between Beco & Entergy.Record Copy ML20198J1161998-12-17017 December 1998 Responds to to Chairman Jackson in Which Recipient Expressed Concern About Possible Sale of Pilgrim Station & About Waste Disposal Issues.Nrc Has Not Received Application for Transfer of License to Date ML20198P2781998-12-17017 December 1998 Final Response to FOIA Request for Documents.Forwards App a Records Being Released in Entirety.App B Records Being Withheld in Entirety (Ref FOIA Exemption 4) ML20198B2021998-12-0909 December 1998 Advises of Planned Insp Effort Resulting from Licensee Irpm Review.Details of Insp Plan for Next 6 Months & Historical Listing of Plant Issues Encl ML20197H8521998-12-0909 December 1998 Responds to Ltr Sent to Chairman SA Jackson on 981028 Re Concern That NRC Will Not Perform Environ Assessment in Connection with Consideration of Approval of Transfer of License for Plants to Permit Sale ML20196J1201998-12-0404 December 1998 Ack Receipt of 971217 & 30 & 980112,0309,0423 & 0630 Ltrs Informing NRC of Steps Taken to Correct Violations Noted in Insp Repts 50-293/97-02,50-293/97-11,50-293/97-13, 50-293/97-80 & 50-293/98-01.Actions Found Acceptable ML20196B5421998-11-24024 November 1998 Forwards Plant SRO & RO Initial Exam Rept 50-293/98-301OL During Wk of 981016-23 ML20196F7631998-11-24024 November 1998 Forwards Insp Rept 50-293/98-203 on 980928-1023.No Violations Noted.Three Issues Identified Re Containment Flooding,Surveillance Testing Criteria & Protection for RBCCW System from High Energy Line Break Inside Drywell ML20196C1191998-11-20020 November 1998 Forwards Insp Rept 50-293/98-08 on 980907-1019.No Violations Noted.During Insp Period,Chemical Decontamination of Residual Heat Removal Sys Was Well Planned & Implemented Which Reduced Radiation Doses in Heat Removal Quadrants ML20195H7361998-11-16016 November 1998 Informs of Individual Exam Results for Applicants on Initial Exam Conducted on 981016 & 981019-23 at Facility.Nine Applicants Were Administered Exam & Nine Passed.Licenses Issued & Individual Test Results Encl.Without Encl ML20155C4781998-10-29029 October 1998 Forwards RAI Re Resoultion to GL 96-06 Issues at Plant,Unit 1.Response Requested by 981130 ML20154J7881998-10-0808 October 1998 Authorizes Mb Santiago to Administer Initial Written Exams to Applicants Listed (Except Applicants Redlined), on 981016.NRC Region I Operator Licensing Staff Will Administer Operating Tests During Week of 981019 1999-09-30
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SEP 1 1990 Docket No. 50-293 {
Boston Edison Company ;
ATTN: Mr. Ralph G. Bird :
Senior Vice President - Nuclear t Pilgrim Nuclear Power Station RFD #I Rocky Hill doad t Plymouth, Massachusetts 02360 ;
Gentlemen:
SUBJECT:
REACTOR OPERATOR AND SENIOR REACTOR OPERATOR LICENSING EXAMINATIONS 6
In a telephone conversation between Mr. T. Eas11ck, Chief Examiner, and Mr. H. t Balfour, arrangements were made for the administration of licensing examinations at the Pilgrim Nuclear. Power Station.
The examinations are scheduled for the wetk of December 3,1990.
To meet the above schedule, it will be necessary for you to furnish the refer- ;
ence material listed in Enclosure 1, " Reference Material Requirements for Reactor / Senior Reactor Operator Licensing Examinations," by October 3,1990.
Any delay in receiving approved, properly bound and indexed reference material, or the submittal of inadequate or incomplete reference material-may result in the examination being rescheduled. Mr. Balfour has been advised of our 1 reference material requirements, and the address where each set is to be ;
mailed.
You are responsible for providing adequate space and accommodations for admini-stration of the written examinations. Enclosure 2, " Requirements for Admini-stration of Written Examination," describes our requirements for conducting these examinations.
Enclosure 3 contains the Rules and Guidelines that will be in effect during the .
administration of the written examination. The facility management is respons- '
ible for ensuring that all applicants are aware of these rules. <
The facility staff review of the written examination will be conducted in accordance with requirements specified in Enclosure 4, " Requirements for '
Facility Review of Written Examinations."
To better document simulator examinations, de Chief Examiner will have the simulator operater record predetermined piont conditions (i.e., plant pressure, temperature, etc.), for each simulator scenario. The applicants will be ,
responsible for providing this information, w th any appeal.of a simulator i operating examination. Therefore, your training staff should retain the original simulator examination scenario information until all applicants who i took examinations have either passed the operating examination, accepted the denial of their license, or filed an appeal.
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l Preliminary reactor operator and senior reactor license applications shop 1d be ,
submitted et ine 30 d y* before the first examination dates so that we all ]
be able to review the training ano expei;;. ace of the candidates, process the !
medical certifications, and prepare final exactner assignments after applicant eligibility has been determined. If the applications are not received at least l 30 days before the. examination dates, it is likMy that a postponement will be necessary. Final signed applications certifying completion of all training requirements should be received by the Region fourteen (14) days before the !
first examination date. ,
Mr. Balfour has been informed of the above requirements.
This request is covered by Office of Management and Budget Clearance Number J 3150-0101 which expires May 31, 1992. The estimated average burden is 7.7 ,
hours per response, including gathering, xeroxing and mailing-the required I material. Send comments regarding this burden estimate or any other aspect of this collection of information, including suggestions for reducing this burden, to the Records and Reports Management Branch, Division of Information Support Services, Office of Information Resources Management, U.S. NucleatiRegulatory Commission, Washington, D. C. 20555; and to the Paperwork Reduction Project .
(3150-0101), Office of Management and Budget, We.shington, D. C. 20503. #
t Thank you for your consideration in this matter. If you have any questions ;
regarding the examination procedures and requirements, please contact the undersigned at (215) 337-5210.
Sincerely, ,
Original Signed 41, RICHARD J. CONTE :
Richard J. Conte, Chief BWR Section Operations Branch ;
Division of Reactor Safety
Enclosures:
1.. Reference Material Requirements for Reactor / Senior Reactor Operator Licensing Examinations
- 2. Requirements for Administration of Written Examinations
- 3. NRC Rules and Guidelines for Written Examinations
- 4. Requirements for Facility Review of Written Examinations cc w/ enc 1:
H. Balfour, Training Manager. ,
K. Highfill, Vice President, Nuclear Operations R. Anderson, Plant Manager .
l J. Dietrich, licensing Division Manager ;
E. Robinson, Nuclear Information Manager R. Swanson, Regulatory Af fairs Manager i
0FFICIAL RECORD COPY EASLICK/90-DAY /8/20/90 - 0001.1.0 08/28/90
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Boston Edison Company 3 i
cc w/ enc 1. (cont'd.): {
The Honorable John F. Kerry The Honorable Edward J. Markey :
The Honorable Edward P. Kirby The Honorable Peter V. Forman .
The Honorable Edward M. Kennedy The Honorable Lawrence R. Alexander The Honorablo Nicholas J. Costello .
B. McIntyre, Chairman, Department of Public Utilities l Chairman, Plymouth Board of Selectmen ,
Chairman, Duxbury' Board of Selectmen ;
Plymouth Civil Defense 31 rector R. Hallisey, Department of Public Health, Commonwealth of Massachusetts. :
R. Adams, Department of Labor and Industries, Commonwealth of Massachusetts ;
D. Tibbetts, Acting flassachusetts Secretary of Energy Resources !
Sarah Woodhouse, Legislative Assistant i A. Nogee, MASSPIRG J. W. McCormack, FEMA Regional Administrator PublicDocumentRoom(PDR).
Local Public Document Room (LPDR)
NuclearSafetyInformationCenter(NSIC)
NRC Resident Inspector Commonwealth of Massachusetts, SLO Designee bec w/ enc 1:
Region I Docket Room (with concurrences) i Management Assistant, DRMA (w/o enc 1) !
T. Easlick, DRS V. Curley, DRS R. Conte, DRS T. Martin, RA R. Bellamy, DRSS J. Johnson, DRP J. Rogge, DRP !
J. Macdonald, SRI - Pilgrim (with concurrences)
J. Caldwell, 200 R. Wessman, NRR R. Eaton, NRR ;
OL Facility File '
DRS files (3)
DRS:RI DRS:R Easlick/afk/dmg 2[DRS:RI Easlick Cont 08/27/90 08/47/90 08(3 0FFICIAL RECORD COPY EASLICK/90-DAY /8/20/90 - 0002.0.0 06/16/87 t
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. ENCLOSURE 1 i
REFERENCE MATERIAL REQUIREMENTS FOR REACTOR /SEtlIOR REACTOR OPERATOR LICENSING EXAMINATIONS
- 1. Existing learning objectives, Job Performance Measures, student handouts.
l and lesson plans (including training manuals, plant orientation manual, system descriptions, etc.). .'
A copy of the facility Job and Task Analysis (JTA), specifying the know-ledges and abilities required of an operator at the facility. Each parti- :
cular knowledge and/or ability will include an importance rating correlat-ing it to ensuring the health and the safety of the public. If a JTA is not furnished, the Knowledges and Abilities Catalog for Nuclear Power Plant Operators, NUREG 1122 (1123) will be used to establish content .
validity for the examination.
All Job Performance Measures (JPMs) used to ascertain the competence of the operators in performing tasks within the control room complex and, as identifie,.d in the facility JTAs, outside of the control room, i.e.., local operations'.
Training materials shall include all substantive written material used for preparing applicants for initial R0 and SRO licensing and for limited fuel handler SRO licensing. The written material shall include learning objectives and the details presented during lectures, rather than out-
, lines. Training materials shall be identified by.plent end unit, bound, l' tabbed, and indexed. FAILURE TO PROVIDE COMPLETE, PROPERLY BOUND AND l INDEXE0 PLANT REFERENCE MATERIAL MAY RESULT IN THE RETURN OF THE MATERIAL TO THE PERSON WHO IS THE HIGHEST LEVEL ce CORPORATE MANAGEMENT WHO IS-RESPONSIBLE FOR PLANT OPERATIONS (E.G ACE PRESIDENT OF NUCLEAR OPERA-TIONS). ACCOMPANYING THE MATERIAL W'. m BE A COVER LETTER EXPLAINING THE- .
DEFICIENCIES IN THE REFERENCE MATERIAL AND THE FACT THAT THIS WAS THE REASON THE EXAMINATIONS WERE CANCELLED OR POSTPONED. Training materials, '
which include the following, shall be provided:
l System descriptions including descriptions of all operationally :
1 relevant flow paths, components, controls and instrumentation. !
System training material should draw parallels to the actual proce-dures used for operating the applicable system.
l Complete and operationtily useful descriptions of all safety-system interactions and, where available, BOP system interactions under
- emergency and abnormal conditions, including consequences of anti-cipated operator error, maintenance error, and equipment failure.
l 1.
Training material used to clarify and strengthen understanding of emergency operating procedures.
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Enclosure 1- 2 !
- 2. Complet,e Proc.f"re Index (including surveillance procedures, etc.) I
- 3. All administrative procedures (as applicable to reactor operation or ,
safety) t 4, All integrated plant procedures (rormal or general operating procedures) ,
- 5. All emergency procedures (emergency instructions, abnormal or special procedures)
- 6. Standing ordere (important orders that are safety related and may super-sede the regu'ar procedures)
- 7. Surveillar.e procedures (procedures that are run frequently, i.e. Weekly i or that can be run on the simulator) ,
- 8. Fuel-handling and core-loading procedurce, (initial core-loading proce-dure, when appropriate)
- 9. All annunciator / alarm" response procedures.
- 10. Radiation protection manual (radiation control manual' or procedures')-
4 l 11. Emergency plan implementing procedures
- 12. Technical Specifications (and interpretations, if available) for all units for which licenses are sought.
- 13. System operating procedures ,
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- 14. Piping and Instrumentation diagrams, electrical single-line diagrams, or flow diagrams
- 15. Technical Data Book, and/or Plant curve information as used by operators and facility precautions, limitations, and set points (PLS) for the facility
- 16. Questions and answers specific to the facility training program which may be used in written or operating examinations. (Voluntary by licensee).
- 17. The following on the plant reference simulation facility:
- a. List of all preprogrammed initial conditions ,
- b. List of all :.eset malfunctions with a clear identification number.
The list shall include cause and effect information. Specifically, for each malfunction a concise description of the expected result, or s range of.results, that will occur upon implementation shall be provided. Additionally, an indication of which annunciators are to-be initially expected should be given.
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. Enclosure 1 3
- c. A description.of simulator failure capabilities for valves, breakers, indicators and alarms.
- d. Where the capability exists, an explanation of the ability to vary the severity of a particult malfunction shall_be provided, i.e.,
ability to vary the size of . given LOCA or steam leak, or the abil-ity.to cause'a. slow failure of a component such as a feed pump,.
turbine generator or major valve (e.g., drifting shut of a main feed- i water control valve) l
- e. An identification of modeling conditions / problems that may impact the examination.
- f. Identification of any known performance test discrepancies not yet corrected. ;
- g. Identification of differences between the simulator and the reference .
plant's control room "
- h. Copies of facili.ty generated scenarios that expose the applicants to. ,
situations of degraded pressure control (PWR), degraded-heat removal l
capability (PWR and BWR) and containment challenges (PWR and BWR) may ,
be provided (voluntary by ' licensee)
- 1. Simulator instructors manual. (Voluntary by licensee).
- j. Description of the scenarios used'for the. training class-(voluntary by licensee). .
- 18. Additional material required by the examiners to develop examinations-that -
meet the requirements of +hese standards and the regulations.
The above reference material shall be approved, final issues and'shall be so marked. If a plant has not finalized some of the material, the Chief Examiner shall verify with the facility that the most complete, up-to-date material is i available and that agreement has been reached with the licensee foi limiting changes before the administration of the examination.: All procedures and reference material shall be bound with appropriate indices or tables of
!. contents so that they can be used efficiently. Failure to provide complete, properly bound and indexed plant reference material could result'in cancella-tion or rescheduling of the examinations.
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. ENCLOSURE 2 REQVIREMENTS FOR ADMINISTRATION OF WRITTEN EXAMINATIONS
- 1. A single room shall be provided for administration of the written examir.a-tion. The location of this room and supporting restroom facilities shall. i be such as to prevent contact with all other facility and/or contractor personnel during the written examination' If necessary, the f acility.
should make arrangements for the use of a suitable room at a local school, motel, or other building. Obtaining this room is the responsibility of . I the licensee.
- 2. Minimum spacing is required to ensure. examination integrity as determined- i by the Chief Examiner. Minimum spacing should be one applicant per table, with a three foot space between tables, l i
- 3. Suitable arrangements shall be made by the facility if the a$plicants are to have lunch, coffee, or other refreshments. These arrangements'shall comply with Item I above and shall be reviewed by the examiner and/or ;
proctor, ,
- 4. The facility licensee shall provide pads of 8-1/2 by 11 inch lined paper in unopened packages for each applicant's use in completing the examina- i tion. The. examiner shall distribute these pads to~the applicants. -
l 5. Applicaats may bring pens, pencils, calculators or slide rules into the examination room. Only black ink or dark pencils should be used for writing answers to questions.
- 6. The licensee shall provide one set of steam tables.for each applicant.
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The examiner shall distribute the steam tables to the applicants. No wall '
charts, models, and/or other training materials shall be present in the examination room. No other equipment or reference material shall be allowed unless provided by the examiner.
/. The facility staff shall be provided a copy of the Written Exanination and Answer Key after the last. candidate has handed in his written examination.
- The facility staff shali have five (5) working days to provide formal l written comments with supporting documentation regarding written exami-neon questions and answers .o the chief examiner, l
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ENCLOSURE _3 ,
NRC RULES AND GUIDELINES FOR WRITTEN EXAMINATIONS
- 1. Check identification badges.
- 2. Pass out examinations and all handouts. Remind applicants not to review examination until ins'tructed to do so.
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READ THE FOLLOWING INSTRUCTIONS VERBATIM: ;
During the administration of this examination the following rules apply: _
- 1. Cheating on the examination means an automatic denial of your applicatica and could result in more severe penalties. !
- 2. After the examination has been completed, you must sign the statement on the cover sheet indicating that the work is your own t,nd you have not received or given assistance in completing the examination. This must be done after you complate the examination. ,
t READ THE FOLLOWING INSTRUCTIONS ,
- 1. Restroom trips are to be limited and only one applicant at a time may leave. You must avoid all contacts with anyone outside the examination room to avoid even the appearanct r possibility of cheating.
! 2. Use black ink or dark pencil only to facilitate legible _ reproductions.
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- 3. Prir.t your name in the blank provided in the uoper right-hand corner of the examination cover sheet ar.d each answer sheet.
l 4. Mark your answers on the answer sheet provided. USE rJNLY THE PAPER ~
PROVIDED AND DO NOT WRITE ON THE BACK SIDE OF THE PAGE.
l S. Before you turn in your examination, consecutively number each answer -
sheet, including any additional pages inserted when writing your answers '
on the examination question page, r
- 6. Use abbreviations only if they are commonly used in facility literature.
Avoid using symbols such as < or > signs to avoid a simple transposition '
error resulting in an incorrect answer. Write it out.
- 7. The point value for each question is indicated in parentheses after the question.
- 8. Show all calculations, methods, or assumptions used to obtain'an. answer to any short answer questions.
Enclosure 3 2 l
- 9. Partial credit may be given, except on multiple choice questions. There-fore, ANSWER ALL PARTS OF THE QUESTION AND 00 NOT LEAVE ANY ANSWER BLANK.
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- 10. Proportional grading will be applied. Any additional wrong information that is provided may count against you. . For example, if a nuestion 15-worth one point and asks for four responses. eech of.which is worth 0.25
- points, and you give five responses, each of your responses will be worth 0.20 points. If one of your five responses is incorrect, 0.20 will be deducted and your total credit for.that question will be 0.80 instead of i 1.00 even though you got the four correct answers.
- 11. If the intent of a questier is unclear, ask questions of the examiner '
only, t
- 12. When turning in your examination, assemt ~ e the completed examination with examination questions, examination aids 1d answer sheets. In addition,-
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- 13. Ensure that all information you wish to have evaluated as part of your :
answer is on your answer sheet. Scrap paper will be disposed of immedi- "
ately following the examination.
14 To pass the examination, you must achieve C. vvera'.1 grade of 80% >r i greater.
- 15. There is a time limit of (four) 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for completion of the examination.
f P.s When you are done and have turned in your examination, leave.the examine-tion area (DEFINE THE AREA). If you are found in this area wn:le the examination is still in progress, your license may be denied or re=Lked, l
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4 ENCLOSURE 4 REQUIREMENTS FOR FACILITY REVIEW 0F WRITTEN EXAMINATIONS
- 1. At the option of the Chief Examiner, the facility may review the written examination up to two weeks prior to its administration. This review may take place'at the facility or.in the Regional office. The review will be conducted using the s'ame material sent to the NRC for exam generation <
purposes. The Chief Examiner will coordin.te the details of_the review with the facility. An NRC examiner will a* ways be present'during the- !
review. -!
When this option of. examination review is utilized, the facility reviewers will sign the following statement prior to being allowed access to the examination. The examination or written notes will not be retained by the '
facility.
- a. Pre-Examination Security Agreement ,
I 4 acknowledge that I have acquired specialized know- ,
ledge concerning the examination scheduled for j at as of the date of my signature below. .I ,
agree that I will not knowingly divulge any information concerning this examination to any unauthorized persons. I understand that I am not to participate in any instruction involving those applicants scheduled to be administered the above examination from this date until after the examination has been administered. I further under-stand that violation of the conditions of this agreement may result in the examination being cancelled and/or enforcement action against ,
myself or the facility licensee by whom I am employed or represent. ,
Signature /Date In addition, the facility staff reviewers will sign the following statement af ter the written examination has-been administered.
- b. Post-Examination Security Agreement I did not:.to the best of knowledge, divulge any information concerning the examinations administered during the week of at to any unauthorized persons. I did not participate in providing any instruction to those -
applicants who were administered the examination from the date I . +
entered into this security agreement until the completion of exami-nation administration. ,
Signature /Date
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e Enclosure 4 2.
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- 2. Regardless of whether the above examination review option is exercised, ;
immediately following the administration of the written examination, the !
facility staff shall be provided a marked up copy of the examination and the answer key. The copy of the written examination shall include pen and ink changes made to questions during the examination administration.
If the facility did not review the examination prior to .its administra-tion, they will. have 'five'(5) working days from the day of the written '
excmination to submit < formal comments. If the facility reviewed'the . ,
examination prior to its administration, any additional comments must'be -
given to an examiner prior to his/her. leaving the site at the end of the.
week of the written examination administration. In either case, the comments will be addressed to the responsible Regional Office by the :
highest on site level of corporate management for plant operations, e.g...
- Vice President for Nuclear Operations. A copy of the submittal will be forwarded to the Chief Examiner, as appropriate. . Comments not submitted within the required time frame will'be considered for inclusion in the grading process on a case-by-case basis by the Regional Office Section
- Lhief. Should the comment submittal deadline not be met, a long delay in grading the examinati.on may occur .
- 3. The following fermat should be adhered to for submittal of specific comments:
- a. Listing of NRC Question, answer and ' reference
- b. Facility comment / recommendation !
- c. Reference (to support facility comment).
l NOTES: 1. No change to the examination will be made without submittsi of of a reference to support the facility comment. Any supporting .
documentation that was not previously supplied, should be -
provided. -
- 2. Comments made without a concise facility recommendation will not be addressed.
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- 4. A two hour post-examination review may be held at the discretion of the Chief Examiner. If this review is held, the facility staff should be ,
informed that only written comments that are properly supported will be-considered in the grading of the examination, s
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