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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217J3341999-10-19019 October 1999 Forwards Request for Addl Info Re Sale of Portion of Land Part of Oyster Creek Nuclear Generating Station Site Including Portion of Exclusion Area ML20217E0181999-10-0606 October 1999 Provides Nj Dept of Environ Protection Comments on Oyster Creek Nuclear Generating Station TS Change Request 267 Re Clarifications to Several TS Sections ML20216J7591999-09-30030 September 1999 Informs NRC That Remediation Efforts for Software Sys Etude & Rem/Aacs/Cico Have Been Completed According to Schedule & Now Y2K Ready 05000219/LER-1998-011, Forwards LER 98-011-02, Three Small Bore Pipe Lines Did Not Meet Design Bases for Siesmic & Thermal Allowables. Engineering Std Will Not Be Completed Until End of 4th Quarter of 1999 Due to Scheduling Conflicts1999-09-30030 September 1999 Forwards LER 98-011-02, Three Small Bore Pipe Lines Did Not Meet Design Bases for Siesmic & Thermal Allowables. Engineering Std Will Not Be Completed Until End of 4th Quarter of 1999 Due to Scheduling Conflicts ML20212J6721999-09-30030 September 1999 Informs of Completion of mid-cycle PPR of Oyster Creek Nuclear Generating Station on 990913.No Areas Identified in Which Licensee Performance Warranted Addl Insp Beyond Core Insp Program.Historical Listing of Plant Issues Encl ML20216K1421999-09-29029 September 1999 Provides NRC with Name of Single Point of Contact for Purpose of Accessing Y2K Early Warning Sys,As Requested by NRC Info Notice 99-025 ML20217D1661999-09-27027 September 1999 Forwards Proprietary Completed NRC Forms 396 & 398,in Support of License Renewal Applications for Listed Individuals,Per 10CFR55.57.Encl Withheld ML20217B2531999-09-24024 September 1999 Informs That on 980903,Region I Field Ofc of NRC Ofc of Investigations Initiated Investigation to Determine Whether Crane Operator Qualification/Training Records Had Been Falsified at Oyster Creek Nuclear Generating Station ML20212E1971999-09-16016 September 1999 Forwards Rev 11 of Gpu Nuclear Operational QAP, Reflecting Organizational Change in Which Functions & Responsibilities of Nuclear Safety & Technical Support Div Were Assigned to Other Divisions ML20212A7921999-09-13013 September 1999 Forwards Second RAI Re GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, Issued on 950817 to Plant ML20212B5571999-09-10010 September 1999 Forwards Rev 11 to Oyster Creek Emergency Dose Calculation Manual, IAW 10CFR50,App E,Section V ML20211N2941999-09-0303 September 1999 Responds to NRC 990802 Telcon Request for Environ Impact Assessment of TS Change Request 251 Concerning Movement of Loads Up to 45 Tons with RB Crane During Power Operations ML20211J9831999-09-0202 September 1999 Discusses 990804 Telcon Re Sale of Portion of Oyster Creek Nuclear Generating Station Land.Requests Info Re Location of All Areas within Property to Be Released Where Licensed Radioactive Matl Present & Disposition of Radioactive Matl ML20211J6771999-08-30030 August 1999 Submits Response to NRC 990802 Telcon Request for Gpu to Provide Environ Impact Assessment for Tscr 251 ML20211K2391999-08-23023 August 1999 Forwards fitness-for-duty Performance Data Repts for TMI, Oyster Creek & Corporate Headquarters Located in Parsippany, Nj ML20211C0161999-08-19019 August 1999 Advises That Info Submitted by Ltr,Dtd 990618, Licensing Rept for Storage Capacity Expansion of Oyster Creek Spent Fuel Pool, Holtec Rept HI-981983,rev 4,will Be Withheld from Public Disclosure,Per 10CFR2.790 ML20211B9011999-08-18018 August 1999 Forwards Rev 0 to EPIP 1820-IMP-1720.01, Emergency Public Info Implementing Procedure ML20210U4341999-08-17017 August 1999 Responds to to Chairman Dicus of NRC on Behalf of Fm Massari Concern About Oyster Creek Nuclear Generating Station Not Yet Being Fully Y2K Compliant ML20210Q7331999-08-12012 August 1999 Responds to Re TS Change Request (TSCR)264 from Oyster Creek Nuclear Generating Station.Questions Re Proposed Sale of Property within Site Boundary & Exclusion Area ML20210L6311999-08-0606 August 1999 Discusses Licensee Response to GL 92-01,Rev1,Suppl 1, Rv Structural Integrity, for Plant.Staff Has Revised Info in Rv Integrity Database & Releasing as Rvid Version 2 ML20210D2801999-07-22022 July 1999 Submits Response to Administrative Ltr 99-02 Operating Reactor Licensing Action Estimates. Estimate of Licensing Actions Projected for Fy 2000 Encl.No Projection Provided for Fy 2001 ML20209H5001999-07-14014 July 1999 Forwards Revised TS Pages 3.1-15 & 3.1-17 Which Include Ref to Note (Aa) & Approved Wording of Note H of Table 3.1.1, Respectively ML20210U4411999-07-12012 July 1999 Forwards Article from Asbury Park Press of 990708 Faxed to Legislative Officer by Mutual Constitute Fm Massari Indicating That Oyster Creek Nuclear Generating State Not Fully Y2K Compliant ML20209G1451999-07-0909 July 1999 Forwards Rev 1 to 2000-PLN-1300.01, Oyster Creek Generating Station Emergency Plan. Attachment 1 Contains Brief Summary of Changes,Which Became Effective on 990702 ML20209E0821999-07-0707 July 1999 Forwards TS Change Request 269 for License DPR-16,changing Component Surveillance Frequencies to Indicate Frequency of Once Per Three Months ML20209B7501999-07-0101 July 1999 Responds to NRC Request for Info Re Y2K Readiness at Nuclear Power Plants.Generic Ltr 98-01 Requested Response on Status of Facility Y2K Readiness by 990701.Licensee Y2K Readiness Disclosure for Ocngs,Encl ML20196G1361999-06-23023 June 1999 Provides Status of Corrective Actions Proposed in in Response to Insp Rept 50-219/98-80 & Revised Schedule for Completion of Actions Which Are Not Yet Complete ML20196E6421999-06-22022 June 1999 Forwards Revised Pages of TS Change Request 261,dtd 990618. Replacement Requested Due to Several Dates Being Omitted on Certain Pages ML20195G6541999-06-0707 June 1999 Discusses 981204 Initiation to Investigate Whether Contract Valve Technician,Was Discriminated Against for Raising Concern Re Use of Untrained/Unqualified Workers Performing Valve Repairs.Technician Was Not Discriminated Against ML20195G6631999-06-0707 June 1999 Discusses 981204 Intiation to Investigate Whether Contract Valve Technician Was Discriminated Against for Raising Concern Re Use of Untrained/Unqualified Workers Performing Valve Repairs.Technician Was Not Discriminated Against ML20209B0561999-06-0404 June 1999 Informs That NRR Has Reorganized,Effective 990328.Forwards Organizational Chart ML20195D0551999-06-0303 June 1999 Forwards TS Change Request 226 to License DPR-16,permitting Operation with Three Recirculation Loops.Certificate of Svc & Tss,Encl ML20195C5511999-05-25025 May 1999 Forwards Book of Controlled Drawings Currently Ref But Not Contained in Plant Ufsar.Drawings Were Current at Time of Submittal ML20206N7711999-05-11011 May 1999 Forwards Rev 0 to Oyster Creek Emergency Plan, IAW 10CFR50.47(b) & 10CFR50.54(q).Changes Became Effective on 990413 ML20206H9441999-04-28028 April 1999 Forwards Application for Amend to License DPR-16,requesting Approval to Handle Loads Up to & Including 45 Tons Using Reactor Bldg Crane During Power Operations,Per NRC Bulletin 96-002 ML20206B6991999-04-26026 April 1999 Forwards Copy of Rev 11 to UFSAR & Rev 10 to Oyster Creek Fire Hazards Analysis Rept. Without Fire Hazard Analysis ML20206D3801999-04-26026 April 1999 Forwards Rev 11 to UFSAR, & Rev 10 to Fire Hazards Analysis Rept, for Oyster Creek Nuclear Generating Station, Per 10CFR50.712(e) ML20206A9931999-04-22022 April 1999 Forwards Number of Personnel & Person Rems by Work & Job Function Rept for Period Jan-Dec 1998. Included in Rept Is Listing of Number of Station,Util & Contractor Personnel as Well as Diskette Reporting 1998 Occupational Radiation ML20206C8261999-04-22022 April 1999 Submits Financial Info IAW Requirements of 10CFR50.71(b) & 10CFR140.21 ML20205P8411999-04-15015 April 1999 Forwards TS Change Request 267 to License DPR-16,modifying Items in Sections 2 & 3 of Ts,Expanding Two Definitions in Section 1 & Modifying Bases Statements in Sections 2,3 & 4. Certificate of Svc Encl ML20205P5381999-04-14014 April 1999 Ack Receipt of Re Request for Exception to App J. Intended Correction Would Need to Be Submitted as Change to TS as Exceptions to RG 1.163 Must Be Listed in Ts,Per 10CFR50,App J ML20205P9401999-04-12012 April 1999 Informs NRC That Gpu Nuclear Is Modifying Oyster Creek FSAR to Reflect Temp Gradient of 60 F & to Correct Historical Record ML20205P0651999-04-0909 April 1999 Discusses 990225 PPR & Forwards Plant Issues Matrix & Insp Plan.Results of PPR Used by NRC Mgt to Facilitate Planning & Allocation of Insp Resources 05000219/LER-1998-015, Forwards LER 98-015-01,as Original Submittal on 981028 Inadvertently Indicated That Suppl Would Be Submitted.Suppl Should Not Have Been Required as Only Change Is on Cover Page1999-04-0505 April 1999 Forwards LER 98-015-01,as Original Submittal on 981028 Inadvertently Indicated That Suppl Would Be Submitted.Suppl Should Not Have Been Required as Only Change Is on Cover Page ML20205J3281999-04-0101 April 1999 Discusses Arrangements Made on 990323 for NRC to Inspect Licensed Operator Requalification Program at Oyster Creek Nuclear Generating Station During Week of 990524 ML20205H1081999-03-31031 March 1999 Forwards Current Funding Status for Decommissioning Funds Established for OCNPP,TMI-1,TMI-2 & SNEC ML20205F0611999-03-25025 March 1999 Submits Info on Sources & Levels of Property Insurance Coverage Maintained & Currently in Effect for Oyster Creek Nuclear Generating Station,Iaw 10CFR50.54(w)(3) ML20205E1171999-03-24024 March 1999 Forwards Rev 39 to Oyster Creek Security Plan & Summary of Changes,Iaw 10CFR50.54(p).Rev Withheld ML20207F0331999-03-0404 March 1999 Forwards Insp Rept 50-219/98-12 During Periods 981214-18, 990106-07 & 20-22.Areas Examined During Insp Included Implementation of GL 89-10 & GL 96-05.No Violations Noted ML20207K2471999-02-25025 February 1999 Forwards Fitness for Duty Performance Data Repts for TMI, Oyster Creek & Corporate Headquarters Located in Parsippany, Ny 1999-09-30
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20217E0181999-10-0606 October 1999 Provides Nj Dept of Environ Protection Comments on Oyster Creek Nuclear Generating Station TS Change Request 267 Re Clarifications to Several TS Sections 05000219/LER-1998-011, Forwards LER 98-011-02, Three Small Bore Pipe Lines Did Not Meet Design Bases for Siesmic & Thermal Allowables. Engineering Std Will Not Be Completed Until End of 4th Quarter of 1999 Due to Scheduling Conflicts1999-09-30030 September 1999 Forwards LER 98-011-02, Three Small Bore Pipe Lines Did Not Meet Design Bases for Siesmic & Thermal Allowables. Engineering Std Will Not Be Completed Until End of 4th Quarter of 1999 Due to Scheduling Conflicts ML20216J7591999-09-30030 September 1999 Informs NRC That Remediation Efforts for Software Sys Etude & Rem/Aacs/Cico Have Been Completed According to Schedule & Now Y2K Ready ML20216K1421999-09-29029 September 1999 Provides NRC with Name of Single Point of Contact for Purpose of Accessing Y2K Early Warning Sys,As Requested by NRC Info Notice 99-025 ML20217D1661999-09-27027 September 1999 Forwards Proprietary Completed NRC Forms 396 & 398,in Support of License Renewal Applications for Listed Individuals,Per 10CFR55.57.Encl Withheld ML20212E1971999-09-16016 September 1999 Forwards Rev 11 of Gpu Nuclear Operational QAP, Reflecting Organizational Change in Which Functions & Responsibilities of Nuclear Safety & Technical Support Div Were Assigned to Other Divisions ML20212B5571999-09-10010 September 1999 Forwards Rev 11 to Oyster Creek Emergency Dose Calculation Manual, IAW 10CFR50,App E,Section V ML20211N2941999-09-0303 September 1999 Responds to NRC 990802 Telcon Request for Environ Impact Assessment of TS Change Request 251 Concerning Movement of Loads Up to 45 Tons with RB Crane During Power Operations ML20211J6771999-08-30030 August 1999 Submits Response to NRC 990802 Telcon Request for Gpu to Provide Environ Impact Assessment for Tscr 251 ML20211K2391999-08-23023 August 1999 Forwards fitness-for-duty Performance Data Repts for TMI, Oyster Creek & Corporate Headquarters Located in Parsippany, Nj ML20211B9011999-08-18018 August 1999 Forwards Rev 0 to EPIP 1820-IMP-1720.01, Emergency Public Info Implementing Procedure ML20210D2801999-07-22022 July 1999 Submits Response to Administrative Ltr 99-02 Operating Reactor Licensing Action Estimates. Estimate of Licensing Actions Projected for Fy 2000 Encl.No Projection Provided for Fy 2001 ML20209H5001999-07-14014 July 1999 Forwards Revised TS Pages 3.1-15 & 3.1-17 Which Include Ref to Note (Aa) & Approved Wording of Note H of Table 3.1.1, Respectively ML20210U4411999-07-12012 July 1999 Forwards Article from Asbury Park Press of 990708 Faxed to Legislative Officer by Mutual Constitute Fm Massari Indicating That Oyster Creek Nuclear Generating State Not Fully Y2K Compliant ML20209G1451999-07-0909 July 1999 Forwards Rev 1 to 2000-PLN-1300.01, Oyster Creek Generating Station Emergency Plan. Attachment 1 Contains Brief Summary of Changes,Which Became Effective on 990702 ML20209E0821999-07-0707 July 1999 Forwards TS Change Request 269 for License DPR-16,changing Component Surveillance Frequencies to Indicate Frequency of Once Per Three Months ML20209B7501999-07-0101 July 1999 Responds to NRC Request for Info Re Y2K Readiness at Nuclear Power Plants.Generic Ltr 98-01 Requested Response on Status of Facility Y2K Readiness by 990701.Licensee Y2K Readiness Disclosure for Ocngs,Encl ML20196G1361999-06-23023 June 1999 Provides Status of Corrective Actions Proposed in in Response to Insp Rept 50-219/98-80 & Revised Schedule for Completion of Actions Which Are Not Yet Complete ML20196E6421999-06-22022 June 1999 Forwards Revised Pages of TS Change Request 261,dtd 990618. Replacement Requested Due to Several Dates Being Omitted on Certain Pages ML20195D0551999-06-0303 June 1999 Forwards TS Change Request 226 to License DPR-16,permitting Operation with Three Recirculation Loops.Certificate of Svc & Tss,Encl ML20195C5511999-05-25025 May 1999 Forwards Book of Controlled Drawings Currently Ref But Not Contained in Plant Ufsar.Drawings Were Current at Time of Submittal ML20206N7711999-05-11011 May 1999 Forwards Rev 0 to Oyster Creek Emergency Plan, IAW 10CFR50.47(b) & 10CFR50.54(q).Changes Became Effective on 990413 ML20206H9441999-04-28028 April 1999 Forwards Application for Amend to License DPR-16,requesting Approval to Handle Loads Up to & Including 45 Tons Using Reactor Bldg Crane During Power Operations,Per NRC Bulletin 96-002 ML20206D3801999-04-26026 April 1999 Forwards Rev 11 to UFSAR, & Rev 10 to Fire Hazards Analysis Rept, for Oyster Creek Nuclear Generating Station, Per 10CFR50.712(e) ML20206B6991999-04-26026 April 1999 Forwards Copy of Rev 11 to UFSAR & Rev 10 to Oyster Creek Fire Hazards Analysis Rept. Without Fire Hazard Analysis ML20206C8261999-04-22022 April 1999 Submits Financial Info IAW Requirements of 10CFR50.71(b) & 10CFR140.21 ML20206A9931999-04-22022 April 1999 Forwards Number of Personnel & Person Rems by Work & Job Function Rept for Period Jan-Dec 1998. Included in Rept Is Listing of Number of Station,Util & Contractor Personnel as Well as Diskette Reporting 1998 Occupational Radiation ML20205P8411999-04-15015 April 1999 Forwards TS Change Request 267 to License DPR-16,modifying Items in Sections 2 & 3 of Ts,Expanding Two Definitions in Section 1 & Modifying Bases Statements in Sections 2,3 & 4. Certificate of Svc Encl ML20205P9401999-04-12012 April 1999 Informs NRC That Gpu Nuclear Is Modifying Oyster Creek FSAR to Reflect Temp Gradient of 60 F & to Correct Historical Record 05000219/LER-1998-015, Forwards LER 98-015-01,as Original Submittal on 981028 Inadvertently Indicated That Suppl Would Be Submitted.Suppl Should Not Have Been Required as Only Change Is on Cover Page1999-04-0505 April 1999 Forwards LER 98-015-01,as Original Submittal on 981028 Inadvertently Indicated That Suppl Would Be Submitted.Suppl Should Not Have Been Required as Only Change Is on Cover Page ML20205H1081999-03-31031 March 1999 Forwards Current Funding Status for Decommissioning Funds Established for OCNPP,TMI-1,TMI-2 & SNEC ML20205F0611999-03-25025 March 1999 Submits Info on Sources & Levels of Property Insurance Coverage Maintained & Currently in Effect for Oyster Creek Nuclear Generating Station,Iaw 10CFR50.54(w)(3) ML20205E1171999-03-24024 March 1999 Forwards Rev 39 to Oyster Creek Security Plan & Summary of Changes,Iaw 10CFR50.54(p).Rev Withheld ML20207K2471999-02-25025 February 1999 Forwards Fitness for Duty Performance Data Repts for TMI, Oyster Creek & Corporate Headquarters Located in Parsippany, Ny ML20206S2541999-01-20020 January 1999 Confirms Resolution of Thermo-Lag Fire Barriers in Fire Zones OB-FZ-6A & OB-FZ-6B (480 Switchgear Rooms) IAW Previous Commitments Contained in Gpuns Ltrs to NRC & 971001 ML20199J2631999-01-18018 January 1999 Requests That Listed Changes Be Made to Correspondence Distribution List for Oyster Creek Generating Station ML20199D0271999-01-11011 January 1999 Requests Listed Addl Info in Order to Effectively Review TS Change Request 264 Re Ownership of Property within Exclusion Area ML20199A6521999-01-0707 January 1999 Notifies That Reactor Operators G Scienski,License SOP-11319 & D Mcmillan,License SOP-3919-4 Have Terminated Licenses at Oyster Creek Nuclear Generating Station, Effective 990101 ML20198T1061999-01-0606 January 1999 Forwards Rev 15 to Gpu Nuclear Corporate Emergency Plan for TMI & Oyster Creek Nuclear Station. with Summary of Changes Which Reflect Use of EALs Approved in NRC Ltr to Gpun on 980908 & Other Changes Not Related to Use of New EALs ML20198K0331998-12-23023 December 1998 Forwards Change Request 268 for Amend to License DPR-16. Amend Would Change TS to Specify Surveillance Frequency of Once Per Three Months ML20198H0181998-12-22022 December 1998 Forwards Attachment Addressing New Info & Modifying 980505 Submittal Re Request for Change to Licensing Bases for ECCS Overpressure,In Response to NRC Bulletin 96-03, Potential Plugging of ECCS by Debris in Bwrs ML20198H8521998-12-16016 December 1998 Dockets Completion of Physical Inventory Performed in July 1997,as Addl Info to Nuclear Matl Balance Rept Submitted on 980416 ML20196H4461998-12-0202 December 1998 Provides Final Response to NRC GL 96-01, Testing of Safety-Related Logic Circuits ML20196B4471998-11-23023 November 1998 Provides Required Response 2 to NRC Bulletin 96-003, Potential Plugging of ECC Suction Strainers in Bwrs. During Recently Completed 17R Refueling Outage,New Strainers Were Installed ML20195J8451998-11-12012 November 1998 Forwards Rev 11 to 1000-PLN-7200.01, Gpu Nuclear Operational QA Plan, as Change Previously Made Without Appropriate Notification to NRC ML20195C7201998-11-11011 November 1998 Forwards 120-day Required Response to GL 98-04, Potential for Degradation of ECCS & CSS After LOCA Because of Construction & Protective Coating Deficiencies & Foreign Matl in Containment, ML20195E1221998-11-10010 November 1998 Notifies NRC of First Time Usage of Code Case N-504 & Inclusion Into OCNGS ISI Program,As Accepted by RG 1.147, Inservice Insp Code Case Acceptability ML20155J6851998-11-0505 November 1998 Forwards TS Change Request 266,to Modify Safety Limits & Surveillances of LPRM & APRM Sys & Related Bases to Ensure APRM Channels Respond within Necessary Range & Accuracy & Verify Channel Operability ML20155H5641998-11-0202 November 1998 Informs That Bne Has No Comments on Proposed Change 259 to Ts,Correcting Required Water Level in Condensate Storage Tank So That Design Basis Is Correctly Implemented ML20155G3741998-10-29029 October 1998 Forwards Response to NRC 980619 RAI Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design-Basis Accident Conditions 1999-09-30
[Table view] |
Text
m g GPU Nuclear Corporation
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Q Post Office Box 388 Route 9 South Forked River, New Jersey 08731-0388 609 971-4000 Writer's Direct Dial Nurnber:
C321-93-2361 December 13, 1993 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 ,
Dear Sir:
Subject:
Dyster Creek Nuclear Generating Station Docket No. 50-219 Response to Operator Requalification Examination Report 93-17 As requested, enclosed 'is a description of our approach to programmatically address the simulator scenario weaknesses identified in section 3.2 of your inspection report dated September 15, 1993.
Also being provided as discussed with your staff are three ES-601-1 Examination Security Agreement forms. Additionally, we have enclosed our finalized Biennial Exam Report.
If you should have any questions or require further information, please contact Brenda DeMerchant, OC Licensing Engineer at (609) 971-4642.
Very tr ly cursu /
200032 Jot n J. Ba t>n V e Presi nt & Director yster Creek JJB/BDEM:jc Administrator, Region 1 Senior NRC Resident Inspector DR ADObkbOh 9 gg3 GPU Nuclear Corporation is a subsca<y of Genera! Puolic Uhaties Corporation fg,
1993 OYSTER CREEK BIENNIAL REQUALIFICATION
- EXAMINATION RESULTS RESPONSE TO DYNAMIC SIMULATOR SCENARIO DEFICIENCY !
The Oyster Creek Dynamic Simulator Exam Bank will be revised to meet the intent of NUREG 1021 ES-604 quantitative and qualitative guidelines prior to the biennial requalification examination to be administered in 1995. Also, any dynamic simulator examination scenarios used during the 1994 annual operating examination will be revised to meet the intent of NUREG 1021.
Included in the process of revision will be enhancing the scenario description and scenario objectives, clarifying scenario end points and critical tasks, and adding additional malfunctions. The addition of malfunctions will enhance prioritization of actions especially while exercising the Technical Specifications, abnormal procedures and EOPs. A checklist for simulator scenario development has been generated to ensure that all of the above actions are completed. This checklist has been included as attachment ,
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Attachment 1 OYSTER CREEK
' SIMULATOR SCENARIO REVIEW CHECKLIST FORMAT
- 1. General Description accurately describes scenario
- 2. Setup information contained entirely in body of scenario
- 3. Multiple console instructor actions listed in bullet form
- 4. Plant parameter cues listed in appropriate operator actions
- 5. Critical tasks contain measurable performance standards ,
- 6. Scenario objectives are specific to scenario OUANTITATIVE ATTRIBUTES ,
- 1. Total malfunctions (4-8) ,
- 2. Malfunctions that occur after EOP entry (1-4)
- 3. Abnormal Events (1-2)
- 4. Major Transients (1-2) 1
- 5. EOPs used beyond primary scram response EOP (1-3) i
- 6. EOP contingency procedures used (O'3)
_ 7. Approximate scenario run time (45-60 minutes)*
- 8. EOP run time (40-70% of scenario)* l l
- 9. Critical tasks (2-5) ]
- 10. Technical Specifications used l
I OUALITATIVE ATTRIBUTE )
- 1. Scenario contains at least ' one event- that requires prioritization of operator actions indicates that this item will be ! checked ' during ' simulator validation l
i l
l ES-601 Examimtion Security Awec.minuit Form ES-601-1 l
- 1. Preexamimtion I acknowledge that I have aaguired srwinlized knowleckJe about the l requalification exammation scheduled for the week (s) indicated in this agreement as of the date of my signature and agree that I will not knowingly divulge any information about this examination to any unauthorized pa w s. I understand that I am not to participate in any instnaction involvirry those licensees scbuhiled to be achinistered this roqualification exammation frm this date until cmpletion of examination nrhirtistration. I further urrierstand that violation of the mnditions of this a#eermut my result in cancellation of the examina-tion and/or an enforcumult action against me or the facility licensee by i whm I am employed or whm I tesesent.
- 2. Post-examination I did not, to the best of my knowledge, divulge arry information u.auu.ni2rf the examination (s) administered during the week (s) indicated to any unauthorized persons. I did not participate in instructing those licensees who were acininistered this regualification examination (s) frm the date that I entered into this security ay weiinent until the -
ocx:pletion of examination administration.
Dcamimtion Period ((jI[/ffl to [!/J[/If8 Printed Name Pre-examination Post-examination certification (1) Certification (2) i/SEs [ $2 a Ct./Mw StLveRJ MMf4%
/S Date4)f/hT Date 6AZFR 3 0f~ YI* &l+ %
. YS Date d'k//VJ Date '!-J145 0/ua n. itw->> y (/ftn ff hw Date hyy/q) CA%4te*Y Date f-t1-13 6m %m M% if Date Chn/11 KV Date alain J0 huksat ru niA Mt Date 6Dc/?3 MJ& Date tH<H.3 P1- heallow MW' Date ?hMS Th$9 h W m Date ll/3Pr3 S M % pl/ # W / n <iff Date 7//9/43 f/// 4%?/p% Date //YkM3 f.RwL f . '%in ,. - Date 7 b M ' sf Ww Date % 1Lnf LJsun.aL t)/h/4 A- Date '7 - n 9 3 JLJayA ' Date /1-It-b i). aPAc . iC _ Date w O M 3 t@Ah Date // ep f $
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Mu A TJIen MfM%c - Date im -n "fl W S G % m -- Date 11 11A3 ITM dea \ -.rAl . Q~ Date >. r s . i t 4o M ' Date ie-n'1]
Examiner Starrlards 31 of 40 Rev. 7, January 1993 P
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E:eination Smrity Acrent Fcm ES-601-1 ES-501
- 1. Preexamination I ackrowledge that I have acquired spcialized knowleiJe about the roqualification examination scheduled fcr the week (s) inlicatcd in this agrec:ent as of the date of ry signature ard agree that I will rot Prowingly divulge any information about this examination to any unauthorized persons. I urderstard that I am rot to participate in any instruction involving those licensees scheduled to be Mministered this requalification enmination frcn this date urrtil cccpletion of examination Mministration. I further understand that violation of the corxiitions of this agreement may result in cancellation of the examim-tian nnd/cr an enfw.wt action against re or the facility licensee by whao I am caployed or whcn I represent.
- 2. Post-examination I did not, to the test of my knculedge, divulge arr/ infomation corcermng the examination (s) administered during the week (s) irriicated to any unauthorized persons. I did not participate in instructing thcce licensees who were administered this requalification en mination(s) frca the date that I entered into this security agreement until the ccrpletion of examination administration.
Examimtion Period Y !'l b'l?3 to 8!/ M$
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Date /pf/>
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ES-601 Examiraticn Security Acreement Fcrm ES-601-1
- 1. Preexaminatien I acknculeck;e trat I have acquired specialized knculedge about tre recpHficaticn examiraticn scheduled fcr the week (s) iniicated in this agreement as of the dat of rf sigrature and agree that I will not kncvirgly divulge any infermtien aboat this examimtion to any crauthcrized perscns. I urxkrst.arri that I am not to participate in any irtwden irrmlvirg these licensees scru'nled to be n&inistered this requalificatien examiration frca this date until ccepletion of exa:rination n&inistration. I furtrar urrierstand that violation of the cx:xxiitions of this agreemnt ray recult in cancellaticn of the examina-tien and/or an enforcement acticn against me er the facility licensee by when I am enplayed cr whcn rI rew.
- 2. Pcstexaminatien I did not, to the test cf rf kncwledge, divulge any inferraticn wmuing the examiratien(s) n&inistered durirg the wek(s) indicated to any unauthcrized perr.crs. I did nct participate in irstructirg thcce licensecs who w.re n&inistered this requalificaticn examiration(s) frcn the date that I entered into this recurity agreement until the ccrpletion of examiraticn administraticn.
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<ga w i- pagg Date Date 31 of 40 Rev. 7, January 1993
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GPU NUCLEAR I OYSTER CREEK OPERATIONS TRAINING FINAL BIENNIAL EXAM REPORT Examination Dates: August 10 through September 10,1993 Examination Team: ;
NRC EXAM TEAM GPUN EXAM TFAM T. Walker - Lead Examiner J. Sims - Lead Examiner
- A. Burritt B. Havens i C. Tyner C. Silvers -
S. Sowell ;
H. Tritt ;
G. Young !
Submitted: M l'fik/T3 G. P. Young, Ilequal program Coordinator -
l Reviewed: -
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(L G. Tritt, Lead Instmetor Reviewed: Y maw " 7 3 :
N. L. Boulware, Lead Instmetor Approved:
. W. Cropfdf' Operations Training Manager Concurred: ' tw J ///u/f3
[D. kowalski, Manager Plant training Concurred: \ _ 2 H3 SO 9S P. F. scallon, Manager Plant dperations #
1993 OYSTER CREEK BIENNIAL REOUALIFICATION EXAAflNATION RESULTS .
EXAh1INATION
SUMMARY
l Biennial examinations were administered under the cognizance of the NRC to seven Reactor Operators and seven Senior Reactor Operators during the week'of' August 9, 1993. These operators 'were divided into three crews; two operating crews and one staff _
crew. The examinations were graded concurrently by the NRC and.GPUN. All three ,
crews performed satisfactorily during the simulator examination and no individual crew member required remediation. All fourteen operators passed both the JPM walkthroughs and the written examination. Oyster Creek's licensed operator requalification program was determined by the NRC and GPUN to be satisfactory based on the criteria established in E.S. 601 of NUREG 1021, revision 7. .,
Biennial examinations were administered by GPUN to sixteen Reactor Operators, nineteen Senior Reactor Operators and seventeen SRO Certs from August 16,1993 to. ]
September 10, 1993. There were eight crews; four licensed operating crews, one .
licensed staff crew and thme certified staff crews. Seven cmws performed satisfactorily 1 during the simulator examination and no individual crew member required remediation. !
One certified staff crew failed the simulator examination and was successfully remediated 1 on November 12,1993. Fifty-one operators /certs passed both the JPM walkthroughs and the written examination. One Reactor Operator failed the written exam and then successfully passed a second written exam on September 7,1993.
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1993 OYSTER CREEK
. BIENNIAL REQUALIFICATION EXAMINATION RESULTS INTRODUCTION On June 21,1993, all the Biennial Requalification Exam reference materials, including i the sample plan, were delivered to the NRC Regional Office. ,
On July 8,1993, the test outline and the proposed exam'were sent to the NRC Regional !
Office. !
On July 26, 1993, an exam entrance meeting was conducted by the NRC at Oyster Creek. Criteria for a satisfactory licensed operator requalification program was established ( 2 of the 3 crews and 75% of the individuals must pass the exam ). The l NRC exam team met with the GPUN exam team to validate the written, JPM and Dynamic Simulator exam materials. The validation was completed on July 27.
On August 2,1993, the revised exam was sent to the NRC Regional Office. On August 5, six test questions and one JPM were revised as requested by the NRC.
On August 10, 1993, the written exam was administered to founeen participants. . On August 10 and 11, the dynamic simulator exams were conducted for three crews. On ,
August 12, the JPMs were administered to fourteen participants.
On August 13,1993, an exam exit meeting was conducted by the NRC at Oyster Creek.
P NRC EXAM TEAM GPUN EXAM TEAM T. Walker - Lead Examiner J. Sims - Lead Examiner A. Burritt B. Havens C. Tyner C. Silvers S. Sowell H. Tritt G. Young From August 16 to September 10, 1993, biennial examinations were administered by GPUN to fifty-two operators /cens (eight crews).
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1993 OYSTER CREEK BIENNIAL REQUALIFICATION EXAMINATION RESULTS EXAM PREPARATION The following items were noted about GPUN's exam preparation process:
- Good detailed Sample Plan and Test Outline. Could be made more self-explanatory.
- Good cooperation and coordination with NRC exam team.
4 The following items were noted and incorporated into the administered exam as discovered by the NRC/GPUN exam preparation process:
JPM Standards were improved by adding detail to the actions required by the -
operator.
Dynamic Simulator Scenario difficulty was increased by placing ABN required -
a ctions at the beginning of the scenario and adding more malfunctions during the i scenario.
Written test items were revised to orient questions more toward required operator actions.
- All support information for each written test item was reviewed in detail to provide all required links to references, tasks, objectives and lesson plans.
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. 1993 OYSTER CREEK BIENNIAL REQUALIFICATION EXAMINATION RESULTS EXAM RESULTS NRC MONITORED RESULTS m
Facility: Oyster Creek Overall Results Total Passed Failed Exam Dates: 08/10/93 # # % # %
to 'I 08/12/93 Ros 7 7 100 0 0 ,
NRC Examiners: SROs 9 9 100 0 0 l T. Walker TOTAL 16 16 100 0 0 t A. Burritt C. Tyner CREWS 3 3 100 0 0 ,
L OYSTER CREEK MONITORED RESULTS ,
.w:
Facili+y: Oyster Creek overall Results Total Passed Failed Exam Dates: 08/09/93 # # % # %
to 1 09/10/93 ROs 23 22 96 . 'l 4
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SROs 26 26 100 0 0 CERTS 17 17 100 0 0 -
TOTAL 66 65 98 1 2 CREWS 11 10 91 :I 9 NOTES: 'A Reactor Operator failed the written exam, took it agair on 09/07/93 and passed it A Staff crew failed the simulator portion, took it again on 11/12/93 and passed it. >
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1993 OYSTER CREEK BIENNIAL REQUALIFICATION EXAMINATION RESULTS GENERIC STRENGTHS -
- EOP Suppon Procedures During Dynamic Simulator Transients; Anticipation of plant response was timely and well communicated to the crew.
- Effective cooperation between the NRC and GPUN exam teams contributed to a very smooth overall process. Good all-around biennial examination. Good performance by operating and staff crews.
AREAS FOR IMPROVEMFET Knowledge of normal plant operating procedures for filling the Torus.
- Alarm recognition and panel awareness Complete three-point communication
- Consistent self-checking l Prioritization decisions when in multiple EOP legs l Re-evaluate. need for Support Procedure 30, Confirmation of Primary Containment Isolation.
Determining EOP actions based on Secondary Containment parameters Understanding of what constitutes a Primary system How a rod block is caused or cleared Procedure usage for Control Room HVAC JPM techniques were rusty for both evaluators and operators.
Ensure the conditions are the same in the Simulator and the Control Room (key placement).
Dynamic Simulator; Floor Evaluators must cover back panels to observe all operator actions.
7 1993 OYSTER CREEK BIENNIAL REQUALIFICATION EXAMINATION RESULTS i
AREAS FOR IMPROVEMENT (Cont.)
Simulator Fidelity; Performed well, however, the noise level was a concern (after the Biennial exam was completed, carpet was installed on the simulator floor)
Written Exam; Minor revisions, used some substitute questions. Orient questions to solicit required operator actions !
JPMs; Minor changes in performance standards, substituted some JPMs to better .
evaluate tasks i Dynamic Scenarios; Bank did not meet guidelines in standard, Prioritization of actions were simplistic, shon on malfunctions after EOP entry, short on Technical Specifications exemised GENERIC WEAKNESSES Proper prioritization of the steps in Support Procedure 21, Alternate Insertion of Control Rods RAPS not always referenced -
Timely positive pressure control with the EMRVs was not consistent Knowledge of which RPV level instruments were usable .
Knowledge of effect of 125 VDC loss on 4160V/460V breakers Effect of pump switch position on auto-initiated Core Spray Interpretation of Tech Specs based on O.O.S equipment Knowledge of modification to Containment Spray logic Knowledge of when CRD pump interlocks are in effect
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