Action Plan,Eop Task Force. Task Force to Restore EOP Process Documentation to Regulatory & Industry Stds,To Ensure Compliance W/Listed NUREGsML20059H596 |
Person / Time |
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Site: |
Crystal River ![Duke Energy icon.png](/w/images/7/75/Duke_Energy_icon.png) |
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Issue date: |
01/14/1994 |
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From: |
Fleming P FLORIDA POWER CORP. |
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To: |
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Shared Package |
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ML20059H594 |
List: |
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References |
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RTR-NUREG-0800, RTR-NUREG-1358, RTR-NUREG-800, RTR-NUREG-CR-0899, RTR-NUREG-CR-1875, RTR-NUREG-CR-1977, RTR-NUREG-CR-1999, RTR-NUREG-CR-899 PROC-940114, NUDOCS 9401310022 |
Download: ML20059H596 (6) |
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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20212C1121999-09-16016 September 1999 Criticality Safety Analysis of W Spent Fuel Storage Racks in Pool B of Crystal River Unit 3 ML20212C0961999-09-16016 September 1999 Proposed ITS & Bases Changes Strikeout & Shadowed Text & Revision Bar Format,Increasing Licensed Capacity for Spent Fuel Assembly Storage in SFP & Revising Configuration for Storage of Fresh Fuel ML20211L1011999-09-0202 September 1999 Proposed Tech Specs Re Once Though SG Tube Surveillance Program,Alternate Repair Criteria (ARC) for Axial Tube End Crack (Tec) Indications ML20212C0991999-08-31031 August 1999 Criticality Safety Analysis of Crystal River Unit 3 Pool a for Storage of 5% Enriched Mark B-11 Fuel in Checkerboard Arrangement with Water Holes ML20209D2971999-07-0808 July 1999 Proposed Tech Specs,Changing ITS for CREVS & VFTP & Correcting Typo in ITS Section 5.6.2.12 ML20195B8091999-05-26026 May 1999 Proposed Tech Specs,Revising ITS Bases That Will Update NRC Copies of ITS ML20195B7081999-05-17017 May 1999 Proposed ITS Section 3.3.8, EDG Lops, SR 3.3.8.1,revising Note for Surveillance & Deleting Note for Frequency ML20206S7691999-05-12012 May 1999 Proposed Improved Tech Specs Pages 3.4-21 Through 3.4-21D ML20206N1401999-05-10010 May 1999 Proposed ITS Administrative Controls Section 5.8, High Radiation Area ML20206M0961999-05-0707 May 1999 Proposed Tech Specs,Revising Wording for SR 3.5.2.5 to Be More Consistent with NUREG-1430,Rev 1 & Clarifying Process of Valve Position Verification ML20206H6541999-05-0505 May 1999 Proposed Tech Specs,Proposing Alternate Repair Criteria for Axial Tube End crack-like Indications in Upper & Lower Tubesheets of CR-3 OTSGs ML20204D9211999-03-18018 March 1999 Proposed Tech Specs Re OTSG Tubes Surveillance Program,Tube Repair Roll Process ML20205A7651999-03-18018 March 1999 Rev 29 to AR-305, Es E Annunciator Response ML20205A7961999-03-15015 March 1999 Rev 22 to AR-301, ESA Annunciator Response ML20205A8051999-03-15015 March 1999 Rev 33 to AR-303, ESC Annunciator Response ML20205A8211999-03-15015 March 1999 Rev 35 to AR-403, PSA H Annunciator Response ML20205A3441999-03-12012 March 1999 Rev 25 to AR-402, PSA G Annunciator Response ML20204D5781999-03-0909 March 1999 Rev 10 to AP-513, Toxic Gas ML20204D5821999-03-0808 March 1999 Rev 22 to AR-603, Tgf O Annunciator Response ML20207H7741999-03-0303 March 1999 Rev 15 to AR-602, Tgf N Annunciator Response ML20207J6591999-03-0202 March 1999 Rev 18 to AR-504, ICS L Annunciator Response ML20207J6461999-03-0202 March 1999 Rev 21 to AR-301, ESA Annunciator Response ML20206S7561999-02-28028 February 1999 Rev 2 to Pressure/Temp Limits Rept, Dtd Feb 1999 ML20203C7461999-02-0303 February 1999 Rev 2 to AR-801, FSA Annunciator Response ML20202E6551999-01-27027 January 1999 Proposed Tech Specs Re OTSG Tubes Surveillance Program,Insp Interval Extension ML20202B1411999-01-22022 January 1999 Rev 22 to AR-401, PSA F Annunciator Response ML20199G5201999-01-15015 January 1999 Rev 11 to AP-961, Earthquake ML20199G5581999-01-12012 January 1999 Rev 4 to AP-404, Loss of Decay Heat Removal ML20199G5691999-01-12012 January 1999 Rev 4 to AP-604, Waterbox Tube Failure ML20198T2411999-01-0606 January 1999 Rev 19 to AR-701, Ssf P Annunciator Response ML20196G6771998-12-0101 December 1998 Rev 17 to Annunciator Response AR-702, Ssf Q Annunciator Response ML20196D6761998-11-30030 November 1998 Proposed Tech Specs LCO 3.9.3,allowing Both Doors in Personnel Air Locks & Single Door in Oeh to Be Open During Refueling Operations ML20196G5851998-11-25025 November 1998 Rev 32 to AR-303, ESC Annunciator Response ML20196G3371998-11-25025 November 1998 Reissued Rev 15 to AR-702, Ssf Q Annunciator Response ML20195K4551998-11-24024 November 1998 Proposed Tech Specs,Installing diesel-driven EFW Pump to Remove Interim ITS & Provide Resolution to EDG Capacity Limitations ML20196F6691998-11-24024 November 1998 Rev 11 to AP-330, Loss of Nuclear Svc Cooling ML20195K0031998-11-23023 November 1998 Proposed Tech Specs Re LAR Number 241,rev 0 for High Pressure Injection Sys Mods ML20196F7721998-11-23023 November 1998 Rev 3 to EOP-12, Station Blackout ML20196F7031998-11-23023 November 1998 Rev 3 to AP-404, Loss of Decay Heat Removal ML20196F7541998-11-23023 November 1998 Rev 7 to EOP-08, LOCA Cooldown ML20196F7461998-11-23023 November 1998 Rev 6 to EOP-07, Inadequate Core Cooling ML20196F7241998-11-23023 November 1998 Rev 2 to AP-510, Rapid Power Reduction ML20196F7161998-11-23023 November 1998 Rev 9 to AP-470, Loss of Instrument Air ML20196F8711998-11-23023 November 1998 Rev 28 to AR-305, Es E Annunciator Response ML20196F9451998-11-19019 November 1998 Rev 7 to AP-1080, Refueling Canal Level Lowering ML20196F9381998-11-19019 November 1998 Rev 27 to AP-770, Emergency Diesel Generator Actuation ML20195H6581998-11-17017 November 1998 Proposed Improved Tech Specs (Its),Revising 5.7.2 by Changing Type of Structural Integrity Assessment Required from Probabilistic to Deterministic ML20196D8321998-11-13013 November 1998 Rev 1 to Crystal River Unit 3 ASME Section Xi,Isi Program Interval 3 & Ten Yr NDE Program ML20195H8761998-11-0505 November 1998 Rev 23 to AR-302, Esb Annunciator Response ML20155F4021998-10-30030 October 1998 Proposed Revised Improved Tech Specs (ITS) Section 5.6.2.19, ITS Section 3.4.11,Bases 3.4.11 & 3.4.3 Re PTLR & LTOP Limits 1999-09-02
[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20205A7651999-03-18018 March 1999 Rev 29 to AR-305, Es E Annunciator Response ML20205A8051999-03-15015 March 1999 Rev 33 to AR-303, ESC Annunciator Response ML20205A7961999-03-15015 March 1999 Rev 22 to AR-301, ESA Annunciator Response ML20205A8211999-03-15015 March 1999 Rev 35 to AR-403, PSA H Annunciator Response ML20205A3441999-03-12012 March 1999 Rev 25 to AR-402, PSA G Annunciator Response ML20204D5781999-03-0909 March 1999 Rev 10 to AP-513, Toxic Gas ML20204D5821999-03-0808 March 1999 Rev 22 to AR-603, Tgf O Annunciator Response ML20207H7741999-03-0303 March 1999 Rev 15 to AR-602, Tgf N Annunciator Response ML20207J6591999-03-0202 March 1999 Rev 18 to AR-504, ICS L Annunciator Response ML20207J6461999-03-0202 March 1999 Rev 21 to AR-301, ESA Annunciator Response ML20203C7461999-02-0303 February 1999 Rev 2 to AR-801, FSA Annunciator Response ML20202B1411999-01-22022 January 1999 Rev 22 to AR-401, PSA F Annunciator Response ML20199G5201999-01-15015 January 1999 Rev 11 to AP-961, Earthquake ML20199G5581999-01-12012 January 1999 Rev 4 to AP-404, Loss of Decay Heat Removal ML20199G5691999-01-12012 January 1999 Rev 4 to AP-604, Waterbox Tube Failure ML20198T2411999-01-0606 January 1999 Rev 19 to AR-701, Ssf P Annunciator Response ML20196G6771998-12-0101 December 1998 Rev 17 to Annunciator Response AR-702, Ssf Q Annunciator Response ML20196G3371998-11-25025 November 1998 Reissued Rev 15 to AR-702, Ssf Q Annunciator Response ML20196G5851998-11-25025 November 1998 Rev 32 to AR-303, ESC Annunciator Response ML20196F6691998-11-24024 November 1998 Rev 11 to AP-330, Loss of Nuclear Svc Cooling ML20196F7161998-11-23023 November 1998 Rev 9 to AP-470, Loss of Instrument Air ML20196F7031998-11-23023 November 1998 Rev 3 to AP-404, Loss of Decay Heat Removal ML20196F8711998-11-23023 November 1998 Rev 28 to AR-305, Es E Annunciator Response ML20196F7541998-11-23023 November 1998 Rev 7 to EOP-08, LOCA Cooldown ML20196F7241998-11-23023 November 1998 Rev 2 to AP-510, Rapid Power Reduction ML20196F7461998-11-23023 November 1998 Rev 6 to EOP-07, Inadequate Core Cooling ML20196F7721998-11-23023 November 1998 Rev 3 to EOP-12, Station Blackout ML20196F9451998-11-19019 November 1998 Rev 7 to AP-1080, Refueling Canal Level Lowering ML20196F9381998-11-19019 November 1998 Rev 27 to AP-770, Emergency Diesel Generator Actuation ML20196D8321998-11-13013 November 1998 Rev 1 to Crystal River Unit 3 ASME Section Xi,Isi Program Interval 3 & Ten Yr NDE Program ML20195H8761998-11-0505 November 1998 Rev 23 to AR-302, Esb Annunciator Response ML20154E5161998-10-0101 October 1998 Rev 10 to AP-961, Earthquake ML20154C2691998-09-29029 September 1998 Rev 19 to AR-304, ESD Annunciator Response ML20154C2751998-09-29029 September 1998 Rev 18 to AR-701, Ssf P Annunciator Response ML20154E5361998-09-28028 September 1998 Rev 34 to AR-403, PSA H Annunciator Response ML20154F0841998-09-28028 September 1998 Rev 21 to AR-503, ICS K Annunciator Response ML20154E5271998-09-28028 September 1998 Rev 20 to AR-301, ESA Annunciator Response ML20154Q0061998-09-24024 September 1998 Rev 8-0 to Crystal River Unit 3 Security Training & Qualification Plan ML20237B4431998-08-10010 August 1998 Rev 14 to AR-703, Ssf R Annunciator Response ML20236W9711998-07-30030 July 1998 Rev 24 to AR-402, PSA G Annunciator Response ML20236P9891998-07-13013 July 1998 Rev 22 to AR-501, ICS I Annunciator Response ML20249C1531998-06-20020 June 1998 Rev 4 to EOP-14, Emergency Operating Procedure Enclosures ML20249A3341998-06-0505 June 1998 Rev 10 to AP-330, Loss of Nuclear Service Cooling ML20247E6861998-05-0606 May 1998 Rev 20 to AR-603, Tgf O Annunciator Response ML20217Q4621998-04-30030 April 1998 Rev 15 to Crystal River Unit 3 ASME Section XI Pump & Valve Program Inservice Testing Program ML20247E6621998-04-30030 April 1998 Rev 10 to AP-250, Radiation Monitor Actuation ML20216A9981998-04-24024 April 1998 Rev 30 to AR-303, ESC Annunciator Response ML20217E1481998-04-20020 April 1998 Rev 21 to AR-302, Esb Annunciator Response ML20217C1441998-04-17017 April 1998 Rev 20 to ICS K Annunciator Response ML20217C2631998-04-17017 April 1998 Rev 13 to AR-703, Ssf R Annunciator Response 1999-03-09
[Table view] |
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yq Fk>rida gd Power ACTION PLAN DEPARTMEhrf/DVIDION CR 3 Operations NUCLEAR OPERATONS GOAL Emergency Operating Procedures (EOPs) Task Force PREPAND BY: D E APPFC D BY. DATE
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Paul V. Fleming Senior Nuclear Licensing Engineer f fg g g
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PROJECT DEFINmON (what is to be done?)
Restore EOP process documentation to regulatory and industry standards.
OBJECTIVE (Why will it be done?)
!!is imperative that actions be taken to reinforce the adequacy of the EOPs and restore process control documentation. Ensure applicable elements of the following regulatory guidance is complied with:
= NUREG/CRG99 Ouidelines for the Preparation of Emergency Operating Procedures a NUREG/CR-1875 Evaluation for Emergency Operating Procedures for Nuclear Power Plants
. NUREG/CR-1977 Guidelines for Preparing Emergency Procedures
- NUREG/CR-1999 Human Engineering Guidelines for use in Preparing Emergency Operating Procedures for Nuclear Power Plants
. NUREG-1358 Lessons Learned form the Special Inspection Program for Emergency Operating Procedures (includes Tl 2515/92)
. NUREG-1358 S1 Lessons Learned form the Specialinspection Program for Emergency Operating Procedures (includes NRC Inspection Manual 42001)
. NUREG 600 Standard Review Plan 13.5.2: Operating and Maintenance Procedures.
. NUREG 800 Standard Review Plan 13 5 2 Appendix-A: Review Procedures for the Evaluation of Procedures Generation Packages.
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9401310022 940114 7 l PDR ADOCK 05000302 e )
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'I
- . a ACTION PLAN'- Continued 1
. METHOD OF IMPLEMENTATION (How will it be done?)
e Assemble an interdisciplinary team to effect restoration.
Individuals have been selected from the following departments:
- Licensing [
c - Operations ,
L, . Training
- Quality Programs Engineering ;
Using a team approach will provide independence and timely completion. .;
i
. . Establish appropriato management to ensure the team functions in accordance with expectations. This is accomplished by using a -
2 Project Maneger (PM) reporting directly to the Operations Manager. Frequent status reports will be communicated to senior management and resident NRC inspectors. >
e Define management expectations of each team member in terms of accountabilities and responsibilities relating to EOP process ?l documentation, j SCHEDULE, WITH BENCHMARKS (when will it be done?)
e Assemble team to discuss milestones, responsibilities, accountabilities Snd logistics.1/24/94
. Update, Review and Approve the Deviation Document using revision 7 of the GTG: .
Update - 2/25,94 ;
. Review - 3/11/94 'E
. Approve - 3/25/94
}
. ' Revise and approve EOP Writer's Guide (Al-402A): ,
Revise - 2/25,94 Approve - 3/4/94 -
= Revise and approve EOP Verification and Validation Plan: ,
Revise 2/25/94 l Approve - 3/4/94 !
e Revise Abnormal Procedures (APs) to correct valid deficiencies identified in IR 9316. lf Revise -2/18/94 ,
Approve 2/25/94 {
e Perform safety evaluations (50.59) on all existing EOPs and safety significant GTO deviations.
Deviations 3/11/94 AllEOPs - 3/25/94
= Perform verification on all EOPs:
Complete - 3/31/94 ' f
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T^4
-PageE- g b
I i
p ACTION PLAN - Continued e Perform validation as needed on EOPs:
r 1st run-Week of 4/4/94 2nd run - Week of 4/18/94 Complete 4/29/94
= Revise EOPs to correct valid deficiencies:
Revise 4/8/94 Approve - 4/15/94
. Perform end of task quality programs evaluation:
Complete - 5/6/94 RESPONSIBluTY (Who will do it?)
. The PM, a Senior Nuclear Licensing Engineer, is responsible for ensuring all elements of the restoration plan, as described below, are r completed:
- Operations will update the Plant Specific Technical Guideline (PSTG). This is 3ccomplished by developing a cross-step document comparing the Generic Technical Guideline (GTG) to FPC EOPS. Es ch safety significant deviation will be justified. The PM will be the first level of review. Engineering will provide a sNond level of review. The Operations Manger will provide approval. Establish the deviation document as quality and co',4 trolled.
- Quality Programs will revise the EOP Writer's Guide.
- The Training Department will revise the Verification and Validation Plan.
- Engineering wal review all safety significant GTG deviations.
The Training Department will manage verification and validation efforts with Operations support.
- Operations will revise EOPs to correct actual deficiencies.
Quality Programs will conduct an end of task evaluation.
PROGRAM COST (How much? What resources are required?)
With the exception of performing quality evaluations, all other activities ident:fied in this action plan will be accomplished using intradepartmental personnel and therefore should not result in additional expenses.
There may be a modest expense for the use of personnel (on loan from other utilities) outside the company to help perform quality evaluations.
RESULTS (How will results be measured 7)
Updating the GTG to EOP cross-step and deviation document provides the basis for evaluating EOPs. Ensuring all process documentation is accurate provides the necessary controls for future EOP revisions and evaluations. e IF NECESSARY, ATTACH SUPPORilNG DOCUMENTS Page 3
\
i E0P TASK FORCE Proiect Management:
Paul Flemina (Licensing) reporting to G. H. Halnon, Operations Manager. ,
i Responsibilities and Accountabilities: :
= Restore E0P support documentation to an acceptable status, reverify and revalidate all E0Ps, and produce new 50.59 evaluations on all E0Ps.
= Provide first level of review for all E0P deviations from the GTG. ;
I a Provide a level of management that ensures all elements of this project l are accomplished in accordance with the established plan, which includes !
updating senior management.
Pro.iect Participants Ron Tvrie (Operations)
Responsibilities and Accountabilities:
= Develop cross-step document GTG to E0P and E0P to GTG.
= Develop deviation document using revision 7 of the GTG, a Ensure project manager review (concurrence) of deviations from GTG.
= Ensure Engineering review (concurrence) of safety significant deviations '
from GTG. l l
= Provide input to revising AI-402A (Writer's Guide for Emergency Operating Procedures) and AI-402C (EOP Verification & Validation Plan).
Joe Baumgardner (Quality Programs)
Responsibilities and Accountabilities:
a Review E0P development requirements.
- Revise AI-402A (Writer's Guide for Emergency Operating Procedures).
= Coordinate and manage end of project QA evaluation.
I i
R. C. Zareck (Training)
Responsibilities and Accountabilities:
= Review E0P V&V requirements.
a Revise AI-402C (E0P Verification & Validation Plan).
R. D. deMontfort (Training) ;
Responsibilities and Accountabilities:
= Coordinate and manage the verification and validation of all E0Ps. ,
= Ensure any problems encountered and documented during the V&V process are resolved.
R. Rawls (Operations)
Responsibilities and Accountabilities: ,
a Develop 50.59 for all E0Ps post verification and validation.
= Provide a technical review of safety significant deviations from the GTG.
= Provide a 50.59 type review for all safety significant deviations from the GTG.
M. Fitzgerald (Engineering) ,
Responsibilities and Accountabilities:
= Provide assistance for technical evaluations of safety significant deviations from the GTG.
= Provide qualified reviewers as needed to support any E0P revisions.
Operations Responsibilities and Accountabilities:
= Ross Bremer - SRO to aid in developing the E0P/GTG deviation document.
= E. Gallion - Provide and manage operators (R0 and SRO) to perform verification and validation of E0Ps. [ Coordinate with D. deMontfort] 4
D E0P Task Force Organization .
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B. J. Hickle Director, Nuclear. Plant Operations i
Greg Halnon Manager, Nuclear Plant Operations Paul Fleming Senior Licensing Engineer Project Manager Ron Tyrie Joe Baumgardner Ron Zareck Dave DeMontfort Mike Fitzgerald EOP Coordinator, SRO Quality Programs SRO~ Cert /Lic. Op Train SRO/Sim Trainer Engineering Writer's Guide EOP~V&V Plan -Manager Perf. Tech. Review'of QA Evaluation of V&V Act. Deviations Qualif. Review of Revisions Ross Bremer SRO Ricky Rawls SRO/STA Deviation Document Cross Step _ Document Writer's. Guide 50.59 Development
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