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Category:CORRESPONDENCE-LETTERS
MONTHYEARML17347B5881990-03-0101 March 1990 Responds to Generic Ltr 90-01, Request for Voluntary Participation in NRC Regulatory Impact Survey. Info Covers Time Spent by Key Power Plant Managers in Responding to Operational Insps & Audits ML15217A1031990-02-28028 February 1990 Forwards Semiannual Radioactive Effluent Release Rept for Jul-Dec 1989 for McGuire Nuclear Station Units 1 & 2 & Revised Process Control Programs & Offsite Dose Calculation Manuals ML18094B3221990-02-28028 February 1990 Forwards Executed Amend 14 to Indemnity Agreement B-74 ML20055C3921990-02-26026 February 1990 Approves Util 900214 Request for Use of B&W Steam Generator Plugs W/Alloy 690 as Alternative to Alloy 600.Alternate Matl Is nickel-base Alloy (ASME Designation SB-166) ML20011F3821990-02-26026 February 1990 Confirms Amount Electronically Transferred to Us Dept of Treasury,Nrc on 900223 for Payment of NRC Review Fees of 10CFR50 Applications & 10CFR55 Svcs Per 10CFR170,for Period of 890101-0617 for Listed Invoices ML20006G0621990-02-22022 February 1990 Forwards Revised Proprietary Pages to DPC-NE-2004, Core Thermal Hydraulic Methodology Using VIPRE-01, Reflecting Minor Methodology Changes Made During Review & Approval Process.Pages Withheld ML20006E5881990-02-20020 February 1990 Forwards Proprietary Response to NRC 890725 Questions Re Vipre Core Thermal Hydraulic Section of Topical Rept DPC-NE-3000 & Rev 2 to Pages 3-69,3-70,3-78 & 3-79 of Rept. Encls Withheld (Ref 10CFR2.790) ML20006E1441990-02-16016 February 1990 Forwards Suppl to Rev 1 to Updated FSAR for Braidwood Station,Units 1 & 2 & Byron Station,Units 1 & 2,per 881214 & 891214 Submittals ML20006E9071990-02-16016 February 1990 Discusses Plants Design Control Program.Util Adopted Concept of Design Change Implementation Package (Dcip).Dcip Will Contain or Ref Design Change Notice Prepared Per Approved Procedures ML20006E4201990-02-14014 February 1990 Requests NRC Approval for Use of Alloy 690 Steam Generator Tube Plugs for Facility,Prior to 900301,pending Final ASME Approval of Code Case for Alloy 690 ML18094B3291990-02-14014 February 1990 Forwards Printouts Containing RW-859 Nuclear Fuel Data for Period Ending 891231 & Diskettes ML20011E6151990-02-12012 February 1990 Forwards Revs 1 to Security Plan & Security Training & Qualification Plan & Rev 2 to Security Contingency Plan. Salem Switchyard Project Delayed.Revs Withheld (Ref 10CFR73.21) ML20011E5571990-02-0808 February 1990 Forwards Us Bankruptcy Court for Eastern District of Tennessee Orders & Memorandum on Debtors Motion to Alter or Amend Order & Opinion Re Status of Sales Agreement Between DOE & Alchemie.Doe Believes Agreement Expired on 890821 ML20011E4991990-02-0606 February 1990 Discusses Liability & Funding Requirements Re NRC Decommissioning Funding Rules & Verifies Understanding of Rules.Ltr from NRC Explaining Liability & Requirements of Rule Requested ML20011E5981990-02-0505 February 1990 Requests That Listed Individuals Be Deleted from Svc List for Facilities.Documents Already Sent to Dept of Environ Protection of State of Nj ML20006D6911990-02-0202 February 1990 Provides Alternative Design Solution to Dcrdr Implementation at Facilities.Simpler Design Devised,Using Eyelet Screw Inserted in Switch Nameplate Which Is Identical to Providing Caution Cards in Close Proximity to Switch Handle ML20006C5661990-01-31031 January 1990 Provides Certification Re Implementation of Fitness for Duty Program Per 10CFR26 at Plants ML20006D6611990-01-29029 January 1990 Advises That 900117 License Amend Request to Remove Certain cycle-specific Parameter Limits from Tech Specs Inadvertently Utilized Outdated Tech Specs Pages.Requests That Tech Specs Changes Made Via Amends 101/83 Be Deleted ML20006B7961990-01-29029 January 1990 Forwards Summaries of Latest ECCS Evaluation Model Changes ML20006C6711990-01-29029 January 1990 Responds to Generic Ltr 89-13, Svc Water Sys Problems Affecting Safety-Related Equipment. Plants Have Established Preventive Maint Program for Intake Structure & Routine Treatment of Svc Water Sys W/Biocide to Control Biofouling ML18153C0951990-01-29029 January 1990 Forwards Response to Generic Ltr 89-13, Svc Water Sys Problems Affecting Safety-Related Equipment. Belief in Appropriateness to Address Generic Ltr 89-13 Concerns within Context of Established Programmatic Improvements Noted ML20011E2521990-01-29029 January 1990 Forwards Proprietary Safety Analysis Physics Parameters & Multidimensional Reactor Transients Methodology. Three Repts Describing EPRI Computer Code Also Encl.Proprietary Rept Withheld (Ref 10CFR2.790) ML18153C0871990-01-26026 January 1990 Responds to NRC Bulletin 89-003, Potential Loss of Required Shutdown Margin During Refueling Operations. Refueling Procedures to Be Revised & Familiarization Sessions Will Be Conducted Prior to Each Refueling Outage ML20006D2431990-01-26026 January 1990 Provides Info Re Emergency Response Organization Exercises for Plants.Exercises & Callouts Would Necessitate Activation of Combined Emergency Operations Facility Approx Eight Times Per Yr,W/Some Being Performed off-hours & Unannounced ML18094B2861990-01-26026 January 1990 Forwards Response to Generic Ltr 89-13, Svc Water Problems Affecting Safety-Related Equipment. Aggressive Program of Monitoring,Insp & Matl Replacement Initiated in Advance of Generic Ltr 89-13 Issuance ML19354E4191990-01-25025 January 1990 Comments Re Issuance of OL Amends & Proposed NSHC Determination Re Transfer of Operational Mgt Control of Plants & Views on anti-trust Issues Re Application for Amend for Plants ML17347B5451990-01-24024 January 1990 Informs of Plans to Apply ASME Code Case N-356 at Plants to Allow Certification Period to Be Extended to 5 Yrs.Rev to Inservice Insp Programs Will Include Use of Code Case ML19354E6711990-01-24024 January 1990 Requests Approval to Use Alloy 690 Plugs as Alternative to Requirements of 10CFR55(a),codes & Stds for Plants Prior to 900226 ML19354E4451990-01-22022 January 1990 Submits Update on Status of RHR Sys Iconic Display at Facilities,Per Generic Ltr 88-17 Re Loss of Dhr.Computer Graphics Display Data in Real Time & Reflect Status of Refueling Water Level & RHR Pump Parameters ML19354E4461990-01-22022 January 1990 Forwards Proprietary Rev 1 to DPC-NE-2001, Fuel Mechanical Reload Analysis Methodology for MARK-BW Fuel, Adding Section Re ECCS Analysis Interface Criteria & Making Associated Administrative Changes.Rev Withheld ML20005G7161990-01-20020 January 1990 Forwards Rev 1 to Updated FSAR for Braidwood & Byron Units 1 & 2.Changes in Rev 1 Include Facility & Procedures Which Were in Effect as of 890610.W/o Encl ML20006A8001990-01-19019 January 1990 Forwards Response to NRC 891220 Ltr Re Violations Noted in Plant Insps.Response Withheld (Ref 10CFR73.21) ML16152A9091990-01-18018 January 1990 Forwards Public Version of Rev 33 to Crisis Mgt Implementing Procedure CMIP-1, Recovery Manager & Immediate Staff & Rev 24 to CMIP-2, News Group Plan. W/900131 Release Memo ML18153C0771990-01-17017 January 1990 Forwards North Anna Power Station Emergency Plan Table 5.1, 'Min Staffing Requirements for Emergencies' & Surry... Table 5.1, 'Min Staffing Requirements...', for Approval,Per 10CFR50.54(q),NUREG-0654 & NUREG-0737,Suppl 1 ML20006A2011990-01-16016 January 1990 Responds to NRC Bulletin 89-002 Re Stress Corrosion Cracking of High Hardness Type 410 Stainless Steel in Anchor Darling Swing Check Valves.Eight Subj Valves Identified in Peach Bottom Units 1 & 2 & Will Be Returned to Mfg ML20006A6241990-01-16016 January 1990 Forwards Draft Qualified Master Trust Agreement for Decommissioning of Nuclear Plants,For Review.Licensee Will Make Contributions to Qualified & Nonqualified Trust as Appropriate ML18153C0731990-01-15015 January 1990 Responds to NRC Bulletin 89-002, Stress Corrosion Cracking of High-Hardness Type 410 Stainless Steel Internal Preloaded Bolting in Anchor Darling Model S350W Swing Check Valves or or Valves.... Util Replaced Studs in twenty-five Valves ML20005G6431990-01-10010 January 1990 Responds to Generic Ltr 89-21 Re Implementation of USI Requirements,Consisting of Revised Page to 891128 Response, Moving SER Ref from USI A-10 to A-12 for Braidwood ML20006B8821990-01-10010 January 1990 Reissued Ltr Correcting Date of Util Ltr to NRC Which Forwarded Updated FSAR for Byron/Braidwood Plants from 881214 to 891214.W/o Updated FSARs ML20006A8201990-01-10010 January 1990 Forwards Errata to Rev 3 to BAW-1543,Tables 3-20 & E-1 of Master Integrated Reactor Vessel Surveillance Program Reflecting Changes in Insertion Schedule for A5 Capsule for Davis-Besse & Crystal River ML20005G7601990-01-0404 January 1990 Forwards Public Version of Rev 33 to Crisis Mgt Plan. Privacy Info Should Be Deleted Prior to Placement in Pdr.W/ D Grimsley 900118 Release Memo ML18094B2331990-01-0303 January 1990 Certifies Util Implementation of fitness-for-duty Program, Per 10CFR26.Training Element Required by Rule Completed on 891215.Chemical Testing for Required Substances Performed at Min Prescribed cut-off Levels,Except for Marijuana ML18153C0491990-01-0303 January 1990 Advises of Implementation of fitness-for-duty Program Which Complies w/10CFR26.Util Support Objective of Providing Assurances That Nuclear Power Plant Personnel Will Perform Tasks in Reliable & Trustworthy Manner ML20005F4641990-01-0303 January 1990 Advises That Licensee Implemented 10CFR26 Rule Re fitness-for-duty Program W/One Exception.Util Has Not Completed Background Check for Some of Program Administrators.Checks Expected to Be Completed by 900105 ML17347B5051990-01-0202 January 1990 Certifies That Util Has fitness-for-duty Program Which Meets Requirements of 10CFR26.Util Adopted cut-off Levels Indicated in Encl ML20042D3731990-01-0202 January 1990 Forwards Revised Crisis Mgt Implementing Procedures, Including Rev 32 to CMIP-1,Rev 29 to CMIP-4,Rev 33 to CMIP-5,Rev 38 to CMIP-6,Rev 37 to CMIP-7,Rev 32 to CMIP-9, Rev 1 to CMIP-14 & Rev 30 to CMIP-21 ML17347B4961989-12-28028 December 1989 Responds to Generic Ltr 89-10, Safety-Related Motor- Operated Valve Testing & Surveillance. Util Considering Expansion of Plants to Include Addl safety-related & Position Changeable Valves W/ Emphasis on Maint & Testing ML20042D3381989-12-28028 December 1989 Forwards Response to Generic Ltr 89-10, Safety-Related Motor-Operated Valve Testing & Surveillance. Util Will Comply W/Ltr Recommendations W/Noted Exceptions.Response to Be Completed When Ltr Uncertainties Cleared ML18094B2291989-12-27027 December 1989 Requests to Apply ASME Section XI Code Case N-460 to Facilities Re Reduction in Exam Coverage on Class 1 & 2 Welds.Fee Paid ML18094B2201989-12-27027 December 1989 Advises of Intent to Provide follow-up Response to Generic Ltr 89-10 by 900831 to Describe Status of Program, Recommendation Exceptions & Any Schedule Adjustments 1990-03-01
[Table view] Category:EDUCATIONAL INSTITUTION TO NRC
MONTHYEARML20195C1421988-06-13013 June 1988 Informs That Dk Gehmlich,Associate Dean for Academic Affairs,Replaced Re Stephenson as Reactor Administrator Effective on 880609.Current Membership of Reactor Safety Committee Listed ML20151A3451988-03-0303 March 1988 Informs That Listed Personnel Make Up New Reactor Operations Staff at Triga (R-126) & Agn (R-25) Reactors ML20235B8211987-08-0707 August 1987 Requests That Sending of Unneeded Circular Info Be Discontinued.School No Longer Has Nuclear Reactor ML20207R8261987-03-0202 March 1987 Forwards Ltr Requesting Commission to Review Director'S Decision DD-87-02,per 2.206 (c)(1),to Determine If Director Grossly Abused Discretion by Misrepresenting Petition,Not Responding to Important Points & Deceiving Petitioners ML20206G9281987-02-0606 February 1987 Discusses Scoping Analysis for Direct Heating in Plant. Analysis of Plant Containment Continuing.Aim to Develop Methodology That Can Be Used in Categorizing Other Containments ML20203G3381986-06-12012 June 1986 FOIA Request for Documents Re Reactor & Senior Reactor Operator Licensing Exam Results for Jan 1983 - Dec 1984 ML20141N3711985-12-17017 December 1985 Appeals Denial of FOIA Request for Four Categories of Documents Re Fraudulent Computer Programs ML20138F5071985-10-25025 October 1985 FOIA Request for Four Categories of Documents Re Leak Rate Testing ML20141N2851985-10-21021 October 1985 Responds to 850927 Order to Show Cause Re Removal of Highly Enriched Fuel from Research Reactor.Indefinite Stay of Execution Requested for Listed Reasons,Per Item 3 of Order ML20141N2821985-10-0808 October 1985 Responds to 850927 Order to Show Cause Re Removal of Highly Enriched U to Secure Facility.No Unirradiated High Enriched U Kept on Hand ML20147E7671984-09-24024 September 1984 Forwards INPO Accreditation:Board Members Perspective, Presented at ANS 1984 Annual Meeting in New Orleans.Proposed Rule Should Contain Min Requirements to Avoid Discouraging INPO Initiatives ML20128N9521984-04-30030 April 1984 Forwards Comments Re Quest Study of Surry Tmlb Scenario. Clarification Needed Re Where Data Obtained for Solid Triangle (Sascha) Data Points in Figure A-3 ML20210E6661984-02-27027 February 1984 Forwards Newspaper Ad Re Reasons for 840211 Civil Disobedience Over Plant Emergency Plan ML20210E7141984-02-0101 February 1984 Provides General Concept of Evacuation Time Estimates Re Baseline Scenarios Such as Normal & Adverse Weather.Time Estimates Technically Sound & Based on Best Available Data ML20210E7101984-01-30030 January 1984 Forwards Repts on Fog & Rain.Copies of Questions on Plant & Responses to Date Requested.W/O Encls ML20210E6701984-01-0909 January 1984 Ack 831230 Response to Concerns Over Emergency Response Plan at Plant,Including FEMA Response from R Vickers.Fema Response Inadequate Re Evacuation Time Considerations & Evacuation Routes ML18089A4731983-12-20020 December 1983 Forwards Summary of Facility Evacuation Time Estimates Based on Review Against NUREG-0654,Rev 1.No Deficiencies Noted ML20210E7001983-12-0909 December 1983 Ack 851202 Response to Re Concerns in Emergency Response Plans.Concerns Expressed Re Rebuilding of Twin Bridges & Siren Backup ML20210E6841983-11-0404 November 1983 Forwards Examples from Newspaper Re Concerns Over Plants Emergency Response Plan ML20105B3561982-06-0101 June 1982 Submits Rept Re Security Incident in Response to 10CFR73.71(c) Detailing Loss of Security Effectiveness, Responses Made & Efforts to Revise Sys & Procedures to Reduce Chance of Recurrence.Portions Deleted ML20239A4041964-08-17017 August 1964 Forwards Bodega Bay Meteorological Hazard Implications Repts for Info.W/O Encls ML20234B7891964-08-0505 August 1964 Discusses Ongoing Studies of Sonoprobe Lines in Tomales Bay. About 150 Miles of Lines Completed & Indicate Complex Structures.Sonoprobe Survey Will Also Be Conducted by Scripps Institution of Oceanography.Related Info Encl ML20234E3421964-04-25025 April 1964 Discusses 640318 Visit to Proposed Reactor Site Re Geology of Bodega Head.Controversy Lies W/Displacement of Shaft Fault.Diagrams Encl ML20234F5981964-04-0808 April 1964 Advises That F Neumann Suffered Stroke & Remains in Critical Condition in Hosp.Ha Coombs & Author Available to Assist AEC in Connection W/F Neumann Work ML20235C6131964-03-27027 March 1964 Ack Receipt of Re Amend 6 to PG&E Application for Bodega Bay Reactor & Notes That Amend Supersedes Amend 4. Comments on Questions Raised at Preceeding Meeting in Washington,Dc Not Completed ML20234D7781963-07-16016 July 1963 Ack Receipt of & Inquires If Possibly Incomplete. Expresses Doubt as to Whether Dilution Factor Determined by Diffusion or Dye Extrapolated to Apply to Heat Loss of Large Water Flow ML20234D2791963-07-15015 July 1963 Advises That Matl Sent Earlier Will Probably Be Revised Following Receipt of Written Matl from Pg&E.Suggestions from Legal Staff to Answer Encl Ltrs Opposing Proposed Plant at Bodega Bay Requested ML20234F4431963-07-10010 July 1963 Informs That by End of Wk,All Modified Illustrations to Be Completed.Forwards Results on El Centro Analysis,Per Discussion of Resultant Accelerations & Velocities at Last Meeting.Illustrations to Be Included in Final Rept ML20234D9771963-06-24024 June 1963 Ack Receipt of Forwarding Matl Re Engineering Plans for Proposed Bodega Head Power Plant.Some Questions Still Unanswered & Commented on in Replies to Recent Inquiries ML20234D9131963-06-21021 June 1963 Informs of Expected Arrival on 630624 & Reservation on Jet Leaving 630626 ML20235A8491963-06-19019 June 1963 Forwards Rept on Seismological Aspects of Proposed Nuclear Power Plant on Bodega Head,Ca,Per 630613 Conference ML20235A5611963-06-0808 June 1963 Urges AEC to Consider Listed Facts in Deciding Util Application for Nuclear Power Generating Plant at Bodega Head,Ca,Including Fact That Proposed Site Located Near San Andreas Fault.Tj Edmonds Ltr to President Kennedy Encl ML20235A3161963-06-0505 June 1963 Comments on ACRS 630418 Rept Re Proposed Reactor at Bodega Head.Committee May Have Been Misled Re Potential Impact of Condensor Coolant Discharge on Local Marine Life.L Watters to President Kennedy Encl ML20234F5011963-05-29029 May 1963 Forwards Critical Review of Gw Housner Paper Entitled Behavior of Structures During Earthquakes, Ref in Hazards Rept Submitted to AEC in Connection W/Bodega Head Power Plant.Citizen Ltrs to President Kennedy & Udall Encl ML20239A5571963-05-22022 May 1963 Forwards Answers to Three Questions Raised at Urbana Conference Re Estimate of Magnitude of Max Credible Earthquake,Credible Ground Acceleration (Peak & Average) & Amount of Permanent (Faulting) Displacement of Head ML20234B2281959-12-18018 December 1959 Requests Statement of Limits Now in Force or Being Proposed for Some Larger Power Reactors in Us.Requests Specific Info on First Seven Reactors Listed on Page 6 of Info Bulletin TID-8200 1988-06-13
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML17347B5881990-03-0101 March 1990 Responds to Generic Ltr 90-01, Request for Voluntary Participation in NRC Regulatory Impact Survey. Info Covers Time Spent by Key Power Plant Managers in Responding to Operational Insps & Audits ML18094B3221990-02-28028 February 1990 Forwards Executed Amend 14 to Indemnity Agreement B-74 ML15217A1031990-02-28028 February 1990 Forwards Semiannual Radioactive Effluent Release Rept for Jul-Dec 1989 for McGuire Nuclear Station Units 1 & 2 & Revised Process Control Programs & Offsite Dose Calculation Manuals ML20011F3821990-02-26026 February 1990 Confirms Amount Electronically Transferred to Us Dept of Treasury,Nrc on 900223 for Payment of NRC Review Fees of 10CFR50 Applications & 10CFR55 Svcs Per 10CFR170,for Period of 890101-0617 for Listed Invoices ML20006G0621990-02-22022 February 1990 Forwards Revised Proprietary Pages to DPC-NE-2004, Core Thermal Hydraulic Methodology Using VIPRE-01, Reflecting Minor Methodology Changes Made During Review & Approval Process.Pages Withheld ML20006E5881990-02-20020 February 1990 Forwards Proprietary Response to NRC 890725 Questions Re Vipre Core Thermal Hydraulic Section of Topical Rept DPC-NE-3000 & Rev 2 to Pages 3-69,3-70,3-78 & 3-79 of Rept. Encls Withheld (Ref 10CFR2.790) ML20006E1441990-02-16016 February 1990 Forwards Suppl to Rev 1 to Updated FSAR for Braidwood Station,Units 1 & 2 & Byron Station,Units 1 & 2,per 881214 & 891214 Submittals ML20006E9071990-02-16016 February 1990 Discusses Plants Design Control Program.Util Adopted Concept of Design Change Implementation Package (Dcip).Dcip Will Contain or Ref Design Change Notice Prepared Per Approved Procedures ML20006E4201990-02-14014 February 1990 Requests NRC Approval for Use of Alloy 690 Steam Generator Tube Plugs for Facility,Prior to 900301,pending Final ASME Approval of Code Case for Alloy 690 ML20011E6151990-02-12012 February 1990 Forwards Revs 1 to Security Plan & Security Training & Qualification Plan & Rev 2 to Security Contingency Plan. Salem Switchyard Project Delayed.Revs Withheld (Ref 10CFR73.21) ML20011E5571990-02-0808 February 1990 Forwards Us Bankruptcy Court for Eastern District of Tennessee Orders & Memorandum on Debtors Motion to Alter or Amend Order & Opinion Re Status of Sales Agreement Between DOE & Alchemie.Doe Believes Agreement Expired on 890821 ML20011E4991990-02-0606 February 1990 Discusses Liability & Funding Requirements Re NRC Decommissioning Funding Rules & Verifies Understanding of Rules.Ltr from NRC Explaining Liability & Requirements of Rule Requested ML20011E5981990-02-0505 February 1990 Requests That Listed Individuals Be Deleted from Svc List for Facilities.Documents Already Sent to Dept of Environ Protection of State of Nj ML20006D6911990-02-0202 February 1990 Provides Alternative Design Solution to Dcrdr Implementation at Facilities.Simpler Design Devised,Using Eyelet Screw Inserted in Switch Nameplate Which Is Identical to Providing Caution Cards in Close Proximity to Switch Handle ML20006C5661990-01-31031 January 1990 Provides Certification Re Implementation of Fitness for Duty Program Per 10CFR26 at Plants ML20006C6711990-01-29029 January 1990 Responds to Generic Ltr 89-13, Svc Water Sys Problems Affecting Safety-Related Equipment. Plants Have Established Preventive Maint Program for Intake Structure & Routine Treatment of Svc Water Sys W/Biocide to Control Biofouling ML20011E2521990-01-29029 January 1990 Forwards Proprietary Safety Analysis Physics Parameters & Multidimensional Reactor Transients Methodology. Three Repts Describing EPRI Computer Code Also Encl.Proprietary Rept Withheld (Ref 10CFR2.790) ML20006B7961990-01-29029 January 1990 Forwards Summaries of Latest ECCS Evaluation Model Changes ML18153C0951990-01-29029 January 1990 Forwards Response to Generic Ltr 89-13, Svc Water Sys Problems Affecting Safety-Related Equipment. Belief in Appropriateness to Address Generic Ltr 89-13 Concerns within Context of Established Programmatic Improvements Noted ML20006D6611990-01-29029 January 1990 Advises That 900117 License Amend Request to Remove Certain cycle-specific Parameter Limits from Tech Specs Inadvertently Utilized Outdated Tech Specs Pages.Requests That Tech Specs Changes Made Via Amends 101/83 Be Deleted ML18153C0871990-01-26026 January 1990 Responds to NRC Bulletin 89-003, Potential Loss of Required Shutdown Margin During Refueling Operations. Refueling Procedures to Be Revised & Familiarization Sessions Will Be Conducted Prior to Each Refueling Outage ML20006D2431990-01-26026 January 1990 Provides Info Re Emergency Response Organization Exercises for Plants.Exercises & Callouts Would Necessitate Activation of Combined Emergency Operations Facility Approx Eight Times Per Yr,W/Some Being Performed off-hours & Unannounced ML18094B2861990-01-26026 January 1990 Forwards Response to Generic Ltr 89-13, Svc Water Problems Affecting Safety-Related Equipment. Aggressive Program of Monitoring,Insp & Matl Replacement Initiated in Advance of Generic Ltr 89-13 Issuance ML19354E4191990-01-25025 January 1990 Comments Re Issuance of OL Amends & Proposed NSHC Determination Re Transfer of Operational Mgt Control of Plants & Views on anti-trust Issues Re Application for Amend for Plants ML19354E6711990-01-24024 January 1990 Requests Approval to Use Alloy 690 Plugs as Alternative to Requirements of 10CFR55(a),codes & Stds for Plants Prior to 900226 ML17347B5451990-01-24024 January 1990 Informs of Plans to Apply ASME Code Case N-356 at Plants to Allow Certification Period to Be Extended to 5 Yrs.Rev to Inservice Insp Programs Will Include Use of Code Case ML19354E4451990-01-22022 January 1990 Submits Update on Status of RHR Sys Iconic Display at Facilities,Per Generic Ltr 88-17 Re Loss of Dhr.Computer Graphics Display Data in Real Time & Reflect Status of Refueling Water Level & RHR Pump Parameters ML19354E4461990-01-22022 January 1990 Forwards Proprietary Rev 1 to DPC-NE-2001, Fuel Mechanical Reload Analysis Methodology for MARK-BW Fuel, Adding Section Re ECCS Analysis Interface Criteria & Making Associated Administrative Changes.Rev Withheld ML20005G7161990-01-20020 January 1990 Forwards Rev 1 to Updated FSAR for Braidwood & Byron Units 1 & 2.Changes in Rev 1 Include Facility & Procedures Which Were in Effect as of 890610.W/o Encl ML20006A8001990-01-19019 January 1990 Forwards Response to NRC 891220 Ltr Re Violations Noted in Plant Insps.Response Withheld (Ref 10CFR73.21) ML16152A9091990-01-18018 January 1990 Forwards Public Version of Rev 33 to Crisis Mgt Implementing Procedure CMIP-1, Recovery Manager & Immediate Staff & Rev 24 to CMIP-2, News Group Plan. W/900131 Release Memo ML18153C0771990-01-17017 January 1990 Forwards North Anna Power Station Emergency Plan Table 5.1, 'Min Staffing Requirements for Emergencies' & Surry... Table 5.1, 'Min Staffing Requirements...', for Approval,Per 10CFR50.54(q),NUREG-0654 & NUREG-0737,Suppl 1 ML20006A6241990-01-16016 January 1990 Forwards Draft Qualified Master Trust Agreement for Decommissioning of Nuclear Plants,For Review.Licensee Will Make Contributions to Qualified & Nonqualified Trust as Appropriate ML20006A2011990-01-16016 January 1990 Responds to NRC Bulletin 89-002 Re Stress Corrosion Cracking of High Hardness Type 410 Stainless Steel in Anchor Darling Swing Check Valves.Eight Subj Valves Identified in Peach Bottom Units 1 & 2 & Will Be Returned to Mfg ML18153C0731990-01-15015 January 1990 Responds to NRC Bulletin 89-002, Stress Corrosion Cracking of High-Hardness Type 410 Stainless Steel Internal Preloaded Bolting in Anchor Darling Model S350W Swing Check Valves or or Valves.... Util Replaced Studs in twenty-five Valves ML20005G6431990-01-10010 January 1990 Responds to Generic Ltr 89-21 Re Implementation of USI Requirements,Consisting of Revised Page to 891128 Response, Moving SER Ref from USI A-10 to A-12 for Braidwood ML20006A8201990-01-10010 January 1990 Forwards Errata to Rev 3 to BAW-1543,Tables 3-20 & E-1 of Master Integrated Reactor Vessel Surveillance Program Reflecting Changes in Insertion Schedule for A5 Capsule for Davis-Besse & Crystal River ML20006B8821990-01-10010 January 1990 Reissued Ltr Correcting Date of Util Ltr to NRC Which Forwarded Updated FSAR for Byron/Braidwood Plants from 881214 to 891214.W/o Updated FSARs ML20005G7601990-01-0404 January 1990 Forwards Public Version of Rev 33 to Crisis Mgt Plan. Privacy Info Should Be Deleted Prior to Placement in Pdr.W/ D Grimsley 900118 Release Memo ML18094B2331990-01-0303 January 1990 Certifies Util Implementation of fitness-for-duty Program, Per 10CFR26.Training Element Required by Rule Completed on 891215.Chemical Testing for Required Substances Performed at Min Prescribed cut-off Levels,Except for Marijuana ML20005F4641990-01-0303 January 1990 Advises That Licensee Implemented 10CFR26 Rule Re fitness-for-duty Program W/One Exception.Util Has Not Completed Background Check for Some of Program Administrators.Checks Expected to Be Completed by 900105 ML18153C0491990-01-0303 January 1990 Advises of Implementation of fitness-for-duty Program Which Complies w/10CFR26.Util Support Objective of Providing Assurances That Nuclear Power Plant Personnel Will Perform Tasks in Reliable & Trustworthy Manner ML17347B5051990-01-0202 January 1990 Certifies That Util Has fitness-for-duty Program Which Meets Requirements of 10CFR26.Util Adopted cut-off Levels Indicated in Encl ML20042D3731990-01-0202 January 1990 Forwards Revised Crisis Mgt Implementing Procedures, Including Rev 32 to CMIP-1,Rev 29 to CMIP-4,Rev 33 to CMIP-5,Rev 38 to CMIP-6,Rev 37 to CMIP-7,Rev 32 to CMIP-9, Rev 1 to CMIP-14 & Rev 30 to CMIP-21 ML20042D3381989-12-28028 December 1989 Forwards Response to Generic Ltr 89-10, Safety-Related Motor-Operated Valve Testing & Surveillance. Util Will Comply W/Ltr Recommendations W/Noted Exceptions.Response to Be Completed When Ltr Uncertainties Cleared ML17347B4961989-12-28028 December 1989 Responds to Generic Ltr 89-10, Safety-Related Motor- Operated Valve Testing & Surveillance. Util Considering Expansion of Plants to Include Addl safety-related & Position Changeable Valves W/ Emphasis on Maint & Testing ML18094B2291989-12-27027 December 1989 Requests to Apply ASME Section XI Code Case N-460 to Facilities Re Reduction in Exam Coverage on Class 1 & 2 Welds.Fee Paid ML18094B2201989-12-27027 December 1989 Advises of Intent to Provide follow-up Response to Generic Ltr 89-10 by 900831 to Describe Status of Program, Recommendation Exceptions & Any Schedule Adjustments ML18153C0261989-12-26026 December 1989 Responds to Generic Ltr 89-10 Re safety-related motor-operated Valve Testing & surveillance.Motor-operated Valve Program Structured to Allow Similar Approach to motor-operated Dampers.Results Will Be Submitted in 30 Days ML20005E1911989-12-26026 December 1989 Forwards Revised Page 2 Correcting Plant Implementation Date for USI A-24 Requirements in Response to Generic Ltr 89-21 1990-03-01
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h mg 24 Septenber 1984 Mr. Hugh L. Thompson, Director Division of Human Factors Safety Office ef Nuclear Reactor Regulation U.S. Nuclear Reactor Regulation Washington, D.C. 20555
Dear Hugh:
Reference is made to your letter to me dated 17 September 1984 requesting my views on several matters relating to proposed NRC rulemaking for trainin and qualifications of civilian nuclear power plant personnel (SECY-84-76.
I wish to address the first paragraph of your letter wherein you indicate that "we have been told that you have indicated a belief that a rule is not necessary." I can think of only two occasions in which I have publicly discussed the proposed rulemaking and industry's concerr s. One of these occasions was in a paper entitled, "INPO Accreditation: A Board Member's Perspective," which I presented at the 1984 Annual Meetir 9 of the ANS in New Orleans in June 1984 (copy attached). Although I madi a modestly snide remark about the proposed rule (page 3), I did not take any position on whether a rule is necessary. The second occasion was in a letter to you dated 27 April 1984 responding to your request for coments (copy attached).
My third coment' was: "Whether the NRC position should be made through rulemaking or by policy statement, and whether one or the other is permitted or required by Section 306 of P.L.97-425 are matters that I am not prepared to address." My position remains unchanged on this point, as I beligve that a determination of what is required or necessary according to Section 306 is a legal question that should best be addressed by OELD, OGC and others.
However, putting aside the legal question of whether a rule is necessary, I do have some additional views on the question from a policy standpoint. In my penultimate coninent to you on 27 April I indicated:
In sumary, in light of what I sincerely belien =.re laudable utility industry initiatives for the inprovement of training, I recomend that at this time the Comission act in a manner which results in a minimum amount of requireinents, a limited amount of prescriptive guidance, a prudent amount of monitoring, and a maximum amount of encouragement for continued utility initiatives towards attaining quality in training and excellence in nuclear power plant operations.
The above coment was intended to be a pleading for promulgat5ng only minimum requirements through a rule, if a rule is legally necessary under Section 305. From a policy perspective, my position remains the same.
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Hugh L. Thompson 2 24 September 1984 The reasons I recommend minimum requirements in any rule that enight be found necessary under Section 306 are the following. INP0 and the nuclear utility industry are striving to attain quality in training that goes beyond meeting the minimum requirements of a prescriptive regulation. If the NRC comes along and codifies into requirements the voluntary commitments, it is argued that the nuclear utility industry support of INP0 would be destroyed.
Although I do not know if this would occur, it is a risk that I recommend strongly against taking. I have observed support for INPO accreditation grow over the past two years. Further, I have had occasion to personally ob-serve what this support has accomplished from the standpoint of utility commitments towards training facilities, training staffs and the quality of training programs; not only for licensed personnel, but also for other nuclear facility personnel. Rules and regulations would not have produced this sup-port or this commitment. To unwittingly destroy this support and comnitment would be regulatory foolhardiness. As I indicated to you on 27 April: "To destroy this initiative would set back training program improvements to pre-TMI-2 acci6ent days.'
You asked me also to provide comments on the various merits or problems underlying the three proposed versions contained in SECY 84-76A and SECY 84-76B (Alternatives I and II). Because of a need to divert my time to prepare for providing testimony to Congress on the HEU/ LEU conversion question for non-power reactors, I will provide my comments on SECY 84-76A & B at a later date.
Sincerely yours, d
For est J. Remick East Hamilton Avenue tate College, PA 16801 FJR:ge cc: R. F. Fraley, ACRS Z. T. Pate, INPO Attachments L
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.- IUP0 ACCREDITATION A BOARD MEMBER'S PERSPECTIVE 1984 ANNUAL MEETING THE AMERICAN NUCLEAR SOCIETY NEW ORLEANS, LOUIS!ANA JUNE 3-8, 1984 '
BY ;
FORREST J. REMICK THE PENNSYLVANIA STATE UNIVERSITY i 1
. IN AUGUST 19'83, A MILESTONE WAS REACHED AT THE INSTITUTE OF NUCLEAR POWER OPERATIONS (INP0) WHEN THE FIRST UTILITY TRAINING PROGRAMS WERE ACCREDITED. .
. LICENSED OPERATOR TRAINING, NON-LICENSED OPERATOR TRAINING, LICENSED OPERATOR REQUALIFICATION TRAINING ANS SHIFT TECHNICAL, ADVISOR TRAIN-ING PROGRAMS WERE ACCREDITED FOR DUKE POWER COMPANY'S OCONEE NUCLEAR STATION.
. ACCREDITATION FOLLOWED IN JANUARY 1984 FOR THREE TRAINING PROGRAMS AT ARKANSAS POWER AND l!GHT COMPANY'S ARKANSAS NUCLEAR ONE AND FOR EIGHT TRAINING PROGRAMS AT IENNESSEE VALLEY AUTHORITY'S SEQUOYAH NUCLEAR PLANT.
l . AND IN MAY 1984 THREE TRAINING PROGRAMS WERE ACCREDITED AT CAROLINA l POWER AND l!GHT COMPANY'S H. B. ROBINSON STEAM ELECTRIC PLANT AND AT BALTIMORE GAS AND ELECTalC COMPANY'S CALVERT CLIFFS NUCLEAR POWER I PLANT.
. IHUS, 21 TRAINING PROGRAMS AT 5 PLANTS OR STATIONS HAVE BEEN ACCREDITED TO DATE, AND THE INP0 ACCREDITATION PROGRAM IS WELL UNDERWAY.
. THE INSTITUTE OF NUCLEAR POWER OPERATIONS WAS ESTABLISHED BY TH'-
NUCLEAR UTILITY INDUSTRY IN ORDER TO PURSUE AND ATTAIN QUALITY AND EXCELLENCE IN NUCLEAR POWER PLANT OPERATION.
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.'THE PURPOSE OF INP0'S ACCREDITATION PROGRAM IS TO ASSIST MEMBER UTILITIES, WHICH INCLUDES ALL U.S. NUCLEAR UTILITIES, IN DEVELOP!NG TRAINING PROGRAMS THAT WILL PROVIDE WELL-QUALIFIED, COMPETENT PERSONNEL WHO WILL OPERATE THEIR NUCLEAR POWER PLANTS WITH QUALITY AND EXCELLENCE.
. INP0 HAS ESTABLISHED CRITERIA FOR:
. . IRAINING PROGRAMS PROGRAM CONTENT TRAINEE EVALUATION AND QUAL 1rlCATION METHODS
. . IRAINING PROCESS ORGANIZATION AND ADMINISTRATION RESOURCES AND FACILITIES PROGRAM DEVELOPMENT AND IMPLEMENTATION
. . IRAINING STAFF SIZE AND WORKuvAD QUALIFICATIONS '
DEVELO'PMENT AND EVALUATION
. IO OBTAIN ACCREDITATION, A UTItlTY MUST DEMONSTRATE ThAT ITS TRAINING MEETS THESE INP0 ACCREDITATION CRITERIA.
. INP0 ASSISTS ITS MEMBERS IN DEVELOPING TRAINING PROGRAMS WHICH ARE BASED ON A CLOSED-LOOP, SYSTEMATIC APPROACH AND WHICH WILL MEET THESE CRITERIA.
. THE PROGRAMS MUST BE PERFORMANCE-BASED. IHAT IS, THEY MUST BE BASED ON AN ANALYSIS OF THE JOBS, TASKS, SKILLS AND KNOWLEDGE REQUIRED FOR THE JOB POSITION THAT THE TRAINEE WILL OCCUPY.
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. IHE INP0 APPROACH AND CRITERIA ARE GENERALLY CONSISTENT WITH THE SYSTEMS APPROACH TO TRAINING (SAI) WHICH THE NUCLEAR REGULATORY COMMISSION IS CONSIDERING FOR PROMULGATION AS A MODIFICATION OF 10 CFR PART 50.
. HOWE ER, INP0 ACCREDITATION CURRENTLY INCLUDES TEN TRAINING PROGRAMS, WHEREAS EARLY DRAFTS OF THE NRC PROPOSED RULE INCLUDED TRAINING PROG'AMS d FO'R THE TWENTY-FIVE JOB POSITIONS LISTED IN APPENDIX B 0F ANSI /ANS-3.1--1981.
. THE NRC PROPOSED RULE INCLUDED ESSENTIALLY ALL PERSONNEL AT A NUCLEAR POWER PLANT EXCEPT CLERICAL AND JANITORIAL POSITIONS.
. THE TEN TRAINING PROGRAMS CURRENTLY COVERED BY INPO INCLUDE:
.. OPERATIONS AREA NON-LICENSED OPERATORS l! CENSED OPERATORS LICENSED OPERATOR REQUALIFICATION-
.. MAINTENANCE AND IECHNICAL SUPPORT AREA SHIFT IECHNICAL ADvtSOR INSTRUMENT AND CONTROL IECHNICIAN ELECTRICAL MAINTENANCE PERSONNEL MECHANICAL MAINTENANCE PERSONNEL CHEMISTRY IECHNICIAN RADIOLOGICAL PROTECTION TECHNICIAN
, MANAGER AND IECHNICAL STAFF
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. I INDICATED THAT TO BE ACCREDITED, TRAINING PROGRAMS MUST BE BASED ON A SYSTEMATIC APPROACH. IN GENERAL, THIS MEANS THAT THEY MUST CONTAIN THE FOLLOWING ESSENTIAL INGREDIENTSI
.. A SYSTEMATIC ANALYSIS OF JOBS TO DETERMINE WHAT TASKS THE PERFORMER OF THE JOB MUST BE ABLE TO PERFORM.
.. PERFORMANCE-BASED LEARNING OBJECTIVES DERIVED FROM THE ANALYSIS
- i. IRAINING DESIGNED, DEVELOPED AND IMPLEMENTED TO ACHIEVE THE PERFORMANCE-BASED OBJECTIVES.
.. EVALUATION OF TRAINEES CONDUCTED DURING TRAINING. SUCH EVALUATION SHOULD BE MADE AGAINST PERFORMANCE STANDARDS STATED IN THE LEARNING OBJECTIVES.
.. EVALUATION OF THE EFFECTIVENESS OF THE TRAINING PROGRAM.
SUCH EVALUATION SHOULD INCLUDE PROVISIONS FOR REVISION BASED ON TRAINEES' DEMONSTRATED ABILITY TO PERFORM IN ACTUAL JOB SETTING.
IRAINING SYSTEM MANAGEMENT MODELS THAT GENERALLY CONTAIN THESE INGREDIENTS INCLUDE INSTRUCTIONAL SYSTEM DEVELOPMENT (ISD), TRAINING
- SYSTEM DEVELOPMENT (TSD), CRITERION REFERENCED INSTRUCTION (CRI), THE NRC'S PROPOSED SYSTEMS APPROACH TO TRAINING (SAT), ETC.
. INP0'S ACCREDITATION PROCESS HAS THREE MAJOR PARTS:
- .. ACCREDITATION SELF-EVALUATION 4
CONDUCTED BY THE UTILITY RESULTS IN SELF-EVALUATION REPORT (SER)
. . ACCREDITATION IEAM EVALUATION CONDUCTED BY INP0 AND PEER EVALUATORS RESULTS IN ACCREDITATION REPORT
.. ACCREDITATION DECISION BY ACCREDITING BOARD s
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. IHE MEMBERSHIP OF THE ACCREDIT!NG BOARD CONSISTS OF FIVE MEMBERS AS FOLLOWS:
.. TWO MEMBERS FROM INP0 MEMBER UTILITIES BILLY R. CLEMENTS, VICE PRESIDENT, NUCLEAR, TEXAS UTILITIES GENERATING COMPANY CORDELL REED, VICE PRESIDENT, COMMONWEALTH EDISON COMPANY, CHAIRMAN OF THE ACCREDITING BOARD '
.. ONE MEMBER FROM A NON-NUCLEAR, INDUSTRIAL IRAINING ORGANIZATION JOHN E. CARROLL, UNITED AIRLINES (RET.)
.. ONE MEMBER FROM THE POST-SECONDARY EDUCATION COMMUNITY RUSSELL R. O'NEILL, DEAN OF ENGINEERING AND APPLIED SCIENCE (RET.), UNIVERSITY OF CALIFORNIA AT LOS ANGELES
.. ONE MEMBER RECOMMENDED BY THE NRC FORREST J. REMICK, ASSISTANT VICE PRESIDENT FOR l RESEARCH AND GRADUATE STUDIES, IHE PENNSYLVANIA STATE UNIVERSITY 4
. IN ADDITION, EACH ACCREDITING BOARD MEMBER HAS AN ALTERNATE. IHE ALTERNATE MEMBERS IN THE SAME ORDER ARE:
. . DENNIS E. GILBERTS, SENIOR VICE PRESIDENT, NORTHERN STATES POWER COMPANY SAMUEL J. TUTHILL, SENIOR VICE PRESIDENT, IOWA ELECTRIC LIGHT AND POWER COMPANY .
.. CHARLES J. SENER, ASSISTANT VICE PRESIDENT, BELL -
COMMUNICATIONS RESEARCH, INC. '
.. WILLIAM R. KIMEL, DEAN, COLLEGE OF ENGINEERING, UNIVERSITY OF MISSOURI-COLUMBIA l
.. GORDON E. ROBINSON, ASSOCIATE PROFESSOR OF NUCLEAR ENGINEERING, IHE PENNSYLVANIA STATE UNIVERSITY
. WHEN ACCREDITATION IS AWARDED, THE ACCREDITATION WILL NORMALL REMAIN QN EFFECT FOR FOUR YEARS, WITH A REPORT SUBMITTED TO THE INP0 ACCREDITING BOARD FOR APPROVAL AT THE END OF TWO YEARS.
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'. IT IS MY VIEW THAT IF A UTILITY IS TO REAP THE POTENTIAL FULL BENEFITS OF THE ACCREDITATION PROCESS, IT MUST MAKE IT ABUNDANTLY CLEAR AT THE ONSET THAT:
,, EXCELLENCE IN NUCLEAR POWER PLANT OPERATION IS THE GOAL OF THE UTILITY. .
.. EXCELLENCE WILL BE ATTAINED THROUGH THE QUALITY OF PLANT OPERATION PERSONNEL AND THROUGH.THE QUALITY OF THEIR TRAINING.
.. THE ACCREDITATION PROCESF WILL BE UTILIZED FULLY TO DEVELOP AND EVALUATE THE QUALITY OF THE TRAINING PROGRAMS.
.. A CONSCIENTIOUS, THOROUGH, OPEN AND HONEST SELF-EVALUATION WILL BE MADE OF THE QUALITY OF THE TRAINING PROGRAMS AND HOW WELL THEY MEET THE INP0 CRITERIA.
.. THE SELF-EVALUATION REPORT WILL TELL IT AS IT IS.
. . WEAKNESSES OR SHORTCOMINGS WILL BE ADDRESSED AND CORRECTIVE ACTION WILL BE INITIATED 'AMEDIATELY.
. I BELIEVE THAT IF WELL DONE, SELF-EVALUATION IS THE MOST IMPORTANT PART OF THE ACCREDITATION PROCESS.
. HOWEVER, TO BE WELL DONE, SOME OF THE MOST VALUABLE PLANT OPERATIONS PERSONNEL MUST BE A PART OF THE SELF-EVALUATION TEAM. IHE TEAM SHOULD NOT CONSIST SOLELY OF TRAINING PERSONNEL.
. FURTHER, THE SELF-EVALUATION TEAM MUST BE TOUGH; THEY MUST BE TOUGHER THAN AN NRC INSPECTOR, TOUGHER THAN AN INPO EVALUATOR.
. A WELL-DONE SELF-EVALUATION WILL REQUIRE A MAJOR EFFORT. HOWEVER, THE GREATER THE EFFORT REQUIRED, THE MORE IT IS PROBABLY NEEDED.
. AS PART OF THE SELF-EVALUATION, IT IS IMPORTANT'THAT IN-DEPTH QUESTIONS BE ADDRESSED. A DESCRIPTION OF WHAT IS BE!NG DONE BY WHOM TO WHOM IS FAR FROM BEING ADEQUATE.
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'.buESTIONSSHOULDINCLUDE:
.. WHAT IS THE TRA!NING PROGRAM SPECIFICALLY ATTEMPTING TO ACCOMPLISH 7
.. IHAT IS, WHAT KNOWLEDGE AND SKILLS MUST PLANT PERSONNEL POSSESS TO PERFORM ' 9 TASKS OF THEIR JOB 7 i
.. IS THE TRAINING PROGRAM EFFECTIVELY DESIGNED TO ENABLE i PLANT PE.RSONNEL TO ACQUIRE THE KNOWLEDGE AND SKILLS 7 ;
. WHAT ARE THE HONEST STRENGTHS AND SUCCESSES OF THE TRAINING PROGRAMS 7 IHESE SHOULD BE ENUMERATED. l
.. WHAT ARE THE WEAKNESSES, LIMITATIONS AND INADEQUACIES 7 l
-(E.G., DO THE RESULTS OF THE TRAINING PROGRAM MEET THE !
TRUE DESIRES OF THE TRAINING STAFF AND THE OPERATIONS i STAFF 7 ARE THEY TRULY SATISFIED WITH THE PRODUCT 7)
IF NOT, OPENLY ADMIT IT. HOWEVER, CORRECTIVE ACTION I
SHOULD BE UNDERTAKEN IMMEDI ATELY. ONE SHOULD NOT WA!T FOR INP0 TO POINT OUT THE INADEQUACIES.
. .. WHAT WOULD IT TAKE TO RAISE THE PROGRAM TO ONE OF EXCELLENCE 7 j
. A COMPETENT SELF-EVALVATION TEAM CAN PROVIDE BETTER IN-DEPTH INSIGHT j INTO THE QUALITY OF THE TRAINING PROGRAMS THAN OTHERS WILL BE ABLE >
I TO DO.
I l . FURTHER, IF THE SELF-EVALUATION TEAM ACCURATELY ASSESSES THE
) STRENGTHS AND WEAKNESSES OF THE TRAIN!HG PROGRAMS, IT WILL BE
, MOSTLY THEIR IDEAS AND RECOMMENDATIONS THAT WILL LEAD THE WAY TO EXCELLENCE--IN CONTRAST TO RECOMMENDATIONS IMPOSED BY l OUTSIDERS OR BY TOP MANAGEMENT. !
! . IHE lilP0 ACCREDITATION TEAM VISIT WILL PROVIDE AN INDEPENDENT i
CHECK ON THE THOROUGHNESS OF THE SELF-EVALVATION, AND WILL PROVIDE i AN -!NDEPENDENT COMPARISON OF HOW THE TRAINING PROGRAMS MEET THE INP0 CRITERI A AND STACK UP WITH THE STATE OF THE ART.
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. IHE INP0 EVALUATION TEAM WILL BE COMPOSED OF PEERS FROM OTHER UTILITIES AS WELL AS PROFESSIONAL INP0 EVALUATION TEAM MEMBERS. i THE TEAM MAY INCLUDE FROM TIME TO TIME AN ACCREDITING BOARD MEMBER <
OR AN NRC OBSERVER. INCIDENTALLY, SERVING AS AN INP0 PEER EVALUATOR CAN BE AN EXCELLENT OPPORTUNITY TO PREPARE FOR ONE'S OWN ACCREDITATION SELF-EVALUATION.
. I BELIEVE THAT WALT COAKLEY WILL BE DISCUSSING SOME OF THE TRAINING WEAKNESS $S IDENTIFIED BY THE INP0 ACCREDITATION TEAMS. WITHOUT STEALING HIS THUNDER, THERE ARE SEVERAL OBSERVATIONS l'D LIKE TO MAKE FROM THE PERSPECTIVE OF A BOARD MEMBER:
l
.. I STRONGLY BELIEVE THAT THE PURSUIT AND ATTAINMENT OF EXCELLENCE IN OPERATIONS IS ABSOLUTELY DEPENDENT ON THE QUALITY OF PLANT PERSONNEL AND ON THE QUALITY OF THEIR TRAINING.
. . IHEREFORE, ACCREDITATION, WHICH I BELIEVE CAN HELP ATTAIN QUALITY IN TRAINING, MAY BE ONE OF THE MOST -
IMPORTANT PROGRAMS CURRENTLY IN PROGRESS AT INP0.
.. I SINCERELY BELIEVE THAT THE ACCREDITATION PROCESS HAS AND IS LEADING TO SIGNIFICANT IMPROVEMEN'TS IN THE QUALITY OF TRAINING. IT IS A TREMENDOUS UNDERTAKING AND IS COSTLY. HOWEVER, IT IS MY IMPRESSION THAT THOSE INVOLVED AGREE THAT IT IS LEADING TO THE IMPROVEMENT OF QUALITY IN TRAINING PROGRAMS.
. . IO BE ACCREDITED, TRA!NING PROGRAMS MUST BE SYSTEMATICALLY DESIGNED AND IMPLEMENTED AND MUST BE PERFORMANCE-BASED.
--MY OBSERVATION: MANY TRAINING PROGRAMS ARE SYSTEMATICALLY DESIGNED, BUT WHEN IT COMES TO SYSTEMATIC IMPLEMENTATION, I
THE RECORD IS MUCH MORE SPOTTY.
.. IHIS SYSTEMATIC APPROACH AND PERFORMANCE-BASED TRAINING MUST INCLUDE THE IN-PLANT, ON-THE-JOB PORTION OF THE '
TRAINING AS WELL AS THE TRAINING CONDUCTED AT THE TRAINING CENTER.
--MY OBSERVATION: IN-PLANT, ON-THE-JOB TRAINING IS LESS l s, SYSTEMATIC AND LESS PERFORMANCE-BASED.
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j PERFORMANCE-BASED TRAINING THAT IS SYSTEMATICALLY APPROAC MUST EXTEND TO INCLUDE MAINTENANCE AND KEY CRAFT PERSONNEL.
--MY OBSERVATION: THERE IS STILL MUCH TO BE DONE IN THE AREA 0F TRAINING PROGRAMS FOR MAINTENANCE AND CRAFT !
PERSONNEL. '
.. IRAINING AND PLANT OPERATIONS CANNOT BE VIEWED AS COMPLETELY SEPARATE FUNCTIONS. IRAINING CANNOT BE LOOKED AT BY PLANT f
OPERATIONS PERSONNEL AS SOMEONE ELSE S RESPONSIBILITY.
TRAINING MUST BE THE JOINT RESPONSIBILITY OF BOTH OPERATIONS j- AND TRAINING PERSONNEL.
.. IOP-NOT'HC OPERATIONS PERSONNEL, INCLUDING LICENSED PERSONNEL, SHOULD BE ENCOURAGED TO ROTATE IN AND OUT OF TRAINING.
q --MY OBSERVATION: SUCHROTAYIONISSOMETIMESDISCOURAGED, NOT CONSIDERED IMPORTANT OR RESULTS IN APPRECIABLE PAY RFDUCTION. POLICIES SHOULD BE DEVELOPED TO ENCOURAGE
- 6UCH ROTATION.
..'IHE EVALUATION OF TRAINING PROGRAM EFFECTIVENESS MUST BE ROUTINELY AND SYSTEMATICALLY PERFORMED. IHIS EVALUATION l CLOSES THE LOOP OF THE TRAINING PROCESS.
--MY OBSERVATION: MORE ATTENTION MUST BE DIRECTED TOWARDS IMPROVING THIS EVALUATION.
. THE SELF-EVALUATION MUST BE DONE THOROUGHLY, CONSCIENTIOUSLY, ;
AND PROFESSIONALLY. THE REPORT SHOULD TELL IT AS IT IS.
IF DONE OTHERWISE, ONE ONLY KIDS ONESELF.
- . IF A UTILITY HAS DONE A THOROUGH. JOB 0F SELF-EVALUATION, THERE SHOULD BE FEW SURPRISES FOLLOWING THE INP0 ACCREDITATION TEAM VISIT AND UPON l
RECEIPT OF THE' ACCREDITATION REPORT. -
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. FURTHER, IF THE TRAINING PROGRAMS GENERALLY MEET THE INP0 CRITERIA,
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AND IF THE WEAKNESSES AND SHORTCOMINGS HAVE BEEN THOROUGHLY ADDRESSED !
l WITH EFFECTIVE CORRECTIVE ACTIONS, ACCREDITATION BY THE ACCREDITING '
f BOARD SHOULD BE FORTHCOMING. '
! . MORE IMPORTANTLY, THE INDUSTRY GOAL OF ATTAINING QUALITY AND EXCELLENCE i IN NUCLEAR POWER PLANT OPERATION SHOULD BE MORE READILY ACHIEVED.
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