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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217G5121999-10-14014 October 1999 Revised Page 285 to TS Re Allowed Containment Leakage Rate, Changing Rev 0 to Rev 1 ML20217G4341999-10-14014 October 1999 Rev C to Proposed TS Change Re Conversion to Improved Standard TSs ML20217D9961999-10-13013 October 1999 Risk-Informed ISI Program Plan for Ja Fitzpatrick ML20216J3871999-09-29029 September 1999 Proposed Tech Specs Pages,Extending LCO Allowable Out of Service Time for RHRSW Sys from 7 Days to 11 Days with Special Conditions to Allow for Installation of Mod to Division a RHRSW Strainer ML20196F6071999-06-22022 June 1999 Proposed Tech Specs Re pressure-temp Limits ML20195B8831999-06-0101 June 1999 Proposed Tech Specs,Converting to Improved Std TS ML20206U1421999-05-19019 May 1999 Proposed Tech Specs Revising AOTs for Single Inoperable EDG ML20205K1091999-04-0505 April 1999 Proposed Tech Specs,Removing Position Title of General Manager from Sections & Will State That If Site Executive Officer Is Unavailable,Responsibilities Will Be Delegated to Another Staff Member,In Writing ML20204B6321999-03-21021 March 1999 Plant Referenced Simulation Facility Four Year Performance Testing Rept ML20199H3611999-01-15015 January 1999 Proposed Tech Specs Table 4.1-2 Re Local Power Range Monitor (LPRM) Signal Calibr ML20206P0541998-12-31031 December 1998 Rev 3.2 to EDAMS/RADDOSE-V ML20198M8321998-12-30030 December 1998 Proposed Tech Specs Page 258f Re Configuration Risk Mgt Program ML20197G6181998-12-0303 December 1998 Proposed Tech Specs Reducing Size of Spent Fuel Rack Assembly N3 from 8x13 Cells to 8x12 Cells & Deleting Proposed Inclusion of Fuel Pool Water Level Inadvertent Drainage Into Amend ML20154M7181998-10-16016 October 1998 Proposed Corrected Tech Specs Section 3/4.6.C,relocating Portions of Reactor Coolant Sys - Coolant Chemistry ML20155E7831998-09-15015 September 1998 Rev 2 to Ja FitzPatrick NPP IST Program for Pumps & Valves Third Interval Plan ML20236X8041998-08-0303 August 1998 Proposed Tech Specs Section 1.1.A Re SLMCPR to Be Applicable During Cycle 14 ML20236M6231998-07-10010 July 1998 Proposed Tech Specs Pages Re Amend to Relocate TS 3/4.6.C, RCS - Coolant Chemistry, from TS to UFSAR & Applicable Plant Procedures Controlled by 10CFR50.59 Process ML20249B1631998-06-16016 June 1998 Proposed Tech Specs Re Relocation of Safety Review Committee Review & Audit Requirements ML20236L2931998-06-0707 June 1998 Proposed Tech Specs Section 3.5.b.1 Re Main Condenser Steam Jet Air Ejector & Table 3.10-1 Re Radiation Monitoring Sys That Initiates &/Or Isolates Sys ML20217K0391998-03-30030 March 1998 Proposed Tech Specs Changing Interval of Selected LSFT from Semiannually to Once Per 24 Months & Revising Definition for LSFT to Be Consistent w/NUREG-1433 B110073, Rev 1 to GE-NE-B1100732-01, FitzPatrick Reactor Pressure Vessel Surveillance Matls Testing & Analysis Rept of 120 Degree Capsule at 13.4 Efpy1998-02-28028 February 1998 Rev 1 to GE-NE-B1100732-01, FitzPatrick Reactor Pressure Vessel Surveillance Matls Testing & Analysis Rept of 120 Degree Capsule at 13.4 Efpy ML20247F7981998-02-26026 February 1998 Proposed Tech Specs Re Allowed Containment Leakage Rate ML20202G8841998-02-0606 February 1998 Revised Proposed TS Pages,Revising Allowed Outage Times for 4kV Emergency Bus Trip Functions & Replace Generic Actions for Inoperable Instrument Channels w/function-specific Actions ML20202D4021998-02-0606 February 1998 Proposed Tech Specs Revising RPS Normal Supply Electrical Protection Assembly Undervoltage Trip Setpoint as Result of Reanalysis Based on Most Limiting Min Voltage Requirements of Applied Loads ML20202D5621998-02-0606 February 1998 Proposed Tech Specs Allowing RCS Pressure Tests to Be Performed While Remaining in Cold Shutdown Mode ML20199G5921998-01-0707 January 1998 Rev 0 to JAF-ISI-0003, Third ISI Interval,Ten-Yr ISI Plan ML20199G5661998-01-0606 January 1998 Rev 0 to JAF-ISI-0002, Third ISI Interval,Isi Program. W/28 Oversize Drawings ML20203J6971997-12-12012 December 1997 Proposed Tech Specs,Revising Administrative Controls for Normal Working Hours of Plant Staff Who Perform Safety Related Functions ML20217J0021997-10-14014 October 1997 Proposed TS Pages Re Changes to Design Features Section, Including Revised Limits for Fuel Storage ML20217G3071997-10-0808 October 1997 Proposed Tech Specs Re Distribution of Inoperable Control Rods ML20217K5841997-09-30030 September 1997 Rev 1 to Ja FitzPatrick Nuclear Power Plant IST Program for Pumps & Valves,Third Interval ML20211H0801997-09-26026 September 1997 Revised Proposed TS Changes to ASME Section XI, Surveillance Testing ML20236N7061997-09-0909 September 1997 Proposed Tech Specs,Describing Licensee'S Configuration Risk Mgt Program Which Supports Rev of Allowed out-of-svc Times for Single Inoperable EDGs to Accommodate on-line Maint of EDGs ML20149G2571997-07-14014 July 1997 JAFNPP ISI Program Relief Requests for 2nd Ten-Yr Interval Closeout ML20140D8131997-04-14014 April 1997 Proposed Tech Specs Re SRC Audit Requirements & Mgt Title Change ML20198G7211997-04-0303 April 1997 Hot Rolled XM-19 Stainless Steel Core Shroud Tie-Rod Matl - Crevice Corrosion Investigation ML20136H3771997-03-11011 March 1997 Rev 0 to Power Uprate Startup Test Rept for Cycle 13 ML20135B1921996-11-26026 November 1996 Proposed Tech Specs,Requesting That Snubber Operability, Surveillance & Records Requirements in TS Be Relocated to Plant Controlled Documents ML20134M1751996-11-20020 November 1996 Proposed Tech Specs Reflecting Interposed Amend That Was Issued,Updating References to Repts on TS Pp & Changing Rev Bars on Previously Submitted Update Pp Which Were Erroneously Positioned on Pp ML20149L7191996-11-0808 November 1996 Proposed Tech Specs Re Min Critical Power Ratio Safety Limit ML20129G0091996-10-23023 October 1996 Proposed Tech Specs Re Page 134 Deleted Under Amend 236 & Remain Deleted ML20128Q7441996-10-11011 October 1996 Proposed Tech Specs Re Extension of Instrumentation & Miscellanous Surveillance Test to Accommodate 24 Month Cycles ML20135D0311996-07-31031 July 1996 Rev 4 to Radiological Effluent Controls & Offsite Dose Calculation Manual ML20115G0641996-07-12012 July 1996 Proposed Tech Specs Re Cycle 12 Min Critical Power Ratio Safety Limit ML20113B6511996-06-20020 June 1996 Proposed Tech Specs Re Option B to 10CFR50,App J for Primary Containment Leakage Rate Testing Program ML20112D1531996-05-30030 May 1996 Proposed Tech Specs,Revising Minimum Critical Power Ratio Safety Limit & Associated Basis ML20112D2721996-05-30030 May 1996 Proposed Tech Specs Re ATWS Recirculation Pump Trip Instrumentation Requirements ML20112D5711996-05-30030 May 1996 Proposed Tech Specs,Eliminating Selected Response Time Testing Requirements JPN-96-023, Proposed Tech Specs Re Deletion of Requirement for PORC to Review Fire Protection Program & Implementing Procedures. Addl Deletion of Insp & Audit Requirements of Specs 6.14.A & 6.14.B1996-05-16016 May 1996 Proposed Tech Specs Re Deletion of Requirement for PORC to Review Fire Protection Program & Implementing Procedures. Addl Deletion of Insp & Audit Requirements of Specs 6.14.A & 6.14.B ML20108D1171996-04-24024 April 1996 Proposed Tech Specs,Supporting Adoption of Primary Containment Lrt Requirements of Option B to 10CFR50,App J & Clarifying Numerical Value of Allowable Containment Leakage Rate as 1.5% Per Day 1999-09-29
[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20217D9961999-10-13013 October 1999 Risk-Informed ISI Program Plan for Ja Fitzpatrick ML20206P0541998-12-31031 December 1998 Rev 3.2 to EDAMS/RADDOSE-V ML20155E7831998-09-15015 September 1998 Rev 2 to Ja FitzPatrick NPP IST Program for Pumps & Valves Third Interval Plan ML20199G5921998-01-0707 January 1998 Rev 0 to JAF-ISI-0003, Third ISI Interval,Ten-Yr ISI Plan ML20199G5661998-01-0606 January 1998 Rev 0 to JAF-ISI-0002, Third ISI Interval,Isi Program. W/28 Oversize Drawings ML20217K5841997-09-30030 September 1997 Rev 1 to Ja FitzPatrick Nuclear Power Plant IST Program for Pumps & Valves,Third Interval ML20149G2571997-07-14014 July 1997 JAFNPP ISI Program Relief Requests for 2nd Ten-Yr Interval Closeout ML20135D0311996-07-31031 July 1996 Rev 4 to Radiological Effluent Controls & Offsite Dose Calculation Manual ML20094J2421995-09-13013 September 1995 Rev 9 to Ja Fitzpatrick Nuclear Power Plant IST Program for Pumps & Valves Second Interval ML20078A5211995-01-18018 January 1995 Rev 2 to Core Operating Limits Rept ML20063L9621993-12-28028 December 1993 Rev 0 to DVP-01.02, Radiological Effluent Controls & Odcm ML20056D0151993-04-0606 April 1993 Rev 7 of Ja FitzPatrick IST Program for Pumps & Valves ML20115J1891992-08-31031 August 1992 Startup Readiness Evaluation (Sure) for James a Fitzpatrick Nuclear Power Plant ML20099J2081992-06-30030 June 1992 Assessment of Fitzpatrick Results Improvement Program ML20101H4711992-06-0808 June 1992 JAF-RPT-MISC-00543, Analog Transmitter Trip Sys Transmitter Response Time Testing Methodology JPN-91-054, Rev 4 to Second Interval Inservice Testing Program for Pumps & Valves1991-09-27027 September 1991 Rev 4 to Second Interval Inservice Testing Program for Pumps & Valves ML20012B0331989-12-20020 December 1989 Rev 7 to Odcm. ML20148A2251988-03-15015 March 1988 Hydrogen Water Chemistry Sys for James a Fitzpatrick Nuclear Power Plant. W/Three Oversize Drawings ML20235S6001987-06-30030 June 1987 Rev 2 to Procedure PDP-3. Direct Reading Dosimeter Calibr ML20235S6141987-05-15015 May 1987 Rev 3 to Procedure PDP-7, Dosimetry Sys Calibr & QC Procedure ML20206N1771987-03-31031 March 1987 Rev 5 to Ja Fitzpatrick Nuclear Power Plant Offsite Dose Calculation Manual. Two Oversize Maps Encl ML20235S6101987-03-0404 March 1987 Rev 4 to Procedure PDP-6, Rem Sys Instructions ML20209J0981987-01-0707 January 1987 Revised Emergency Plan Implementing Procedures,Including Rev 5 to IAP-2, Classification of Emergency Conditions, Rev 11 to EAP-1.1, Offsite Notifications & Rev 7 to EAP-2, Personnel Injury ML20207T6241986-12-31031 December 1986 Rev 4 to Offsite Dose Calculation Manual ML20206L4821986-07-30030 July 1986 Public Version of Revised Emergency Plan Implementing Procedures,Including Rev 7 to EAP-17, Emergency Organization Staffing & Rev 7 to SAP-3, Emergency Communications Testing. W/Undated Release Memo ML19302A5181986-05-15015 May 1986 Advanced Technical Training Program for Ja Fitzpatrick Nuclear Power Plant. L-86-024, Installation Procedure ML-86-024, Limitorque Valve Actuator Qualification Insp/Upgrades. Result Summary of Limitorque Control Wire Insps,Per IE Info Notice 86-003,encl1986-03-0606 March 1986 Installation Procedure ML-86-024, Limitorque Valve Actuator Qualification Insp/Upgrades. Result Summary of Limitorque Control Wire Insps,Per IE Info Notice 86-003,encl ML20138A7651986-02-28028 February 1986 Revised Emergency Plan Implementing Procedures,Including Rev 3 to IAP-1, Emergency Plan Implementation Checklist, Rev 4 to IAP-2, Classification of Emergency Conditions & Rev 8 to EAP-1.1, Offsite Notifications ML20136H4721985-11-0101 November 1985 Revised Emergency Plan Implementing Procedures,Including Rev 5 to SAP-3 Re Emergency Communications Testing Rev 5 to EAP-22 Re Operation & Use of Radio Paging Device & Rev 14 to EAP-2 Re Personnel Injury ML20205C9461985-09-0606 September 1985 Rev 3 to Fitzpatrick Emergency Procedure Guidelines ML20129J7201985-06-30030 June 1985 Emergency Plan Implementing Procedures,Vols 2 & 3,including Rev 5 to EAP-4, Dose Estimates from Dose Assessment Calculator & Rev 3 to EAP-6, In-Plant Emergency Survey/Entry ML20212B1031985-06-25025 June 1985 Rev 2 to Offsite Dose Calculation Manual ML20128G9231985-06-19019 June 1985 Rev 0 to Procedure EDP-16, Procedure for Technical Review of Procurement Documents ML20116N6881985-04-30030 April 1985 Long-Term Pipe Support Insp & Evaluation Program Plan ML20205A9481985-04-17017 April 1985 Administrative Procedure AP 1.10, Process Control Program ML20205C9701985-02-0808 February 1985 Rev 5 to Administrative Procedure AP 2.2, Procedure for Emergency Operating Procedures ML20100A9571984-11-30030 November 1984 SPDS Implementation Plan for Ja Fitzpatrick Nuclear Power Plant ML20128G9091984-09-13013 September 1984 Rev 3 to Procedure PSO 28, Operating Experience Feedback ML20128G8981984-08-23023 August 1984 Rev 1 to Procedure EDP-12, Procedure for Establishing QA Category Classifications ML20094F5711984-07-18018 July 1984 Emergency Response Plan Exercise Manual for Ja Fitzpatrick Nuclear Power Plant ML20083N9001984-03-23023 March 1984 Rev 2 to Procedure RTP-34, Contamination Radiation Monitoring - Post-Accident ML20083N8961984-03-23023 March 1984 Rev 1 to Procedure RTP-46, Core Estimation Damage, Post-Accident Sampling Sys ML20087G6771984-02-29029 February 1984 Revised Proposed Disposal Procedures for Radioactively Contaminated Fuel Oil ML20092P6771984-02-0909 February 1984 Procedure 23, Post-Trip Evaluation ML20081B9441983-10-31031 October 1983 Revised Offsite Dose Calculation Manual ML20090H3041983-10-19019 October 1983 Detailed Control Room Design Review Program Plan for Ja Fitzpatrick Nuclear Power Plant ML20085K7581983-10-12012 October 1983 Emergency Response Plan Exercise Manual ML20072D3151983-06-21021 June 1983 Offsite Dose Calculation Manual ML20078J8471983-04-30030 April 1983 Rev 1 to Procedure SAP-1, Emergency Response Plan Exercise Manual ML20069E6861983-03-18018 March 1983 Change 1 to Rev 3 of Inservice Testing Program for Pumps & Valves 1999-10-13
[Table view] |
Text
_ _ -. . _ . _ ..
ENCLOSURE 2 5.
JUNE 1992 LSSESSMENT OF THE FuzrATRICK RESULTS IMPROVEMENT PROGRAM e
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Revienwed by. __f z w_
-w fa2A Robert Pommy I
Reviewed by. A 2 Adhah Appmed by: m P PDR _
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I.
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EXECUTIVE
SUMMARY
Background .
The purpose of this repost is to assess the progress and effectiveness of the aedon plans in-resolving the issues ident1 Pied in the Fitzpatrick Results Improvernent Program (RIP). 'Illis report also sets forth the 74.cdology that was used to assess the RIP.- .
In June'_1992, .during a % week period, a New York Power Authodty
. Assesament Team conducted 204 interviews,.revieweri 292 documents, collected
- 100 surveys, observed various field activities and reviewed RIP -closure documentation.
the appiusch r A~ significant portion.of the team's effort centered on developing 3 to perform an effectivences evaluation which met the intent of the James A. FitzPatrick Nuclear Power Plant's (JAF) Administrat Procedure 1.15 which states:
" Semi-annual ane*nments shall be i Liudd to ensure [ RIP]
effectiveness and to ensure communication and cooperadon exist.
These assessments shall be the responsibility of the Nucicar Leadership Team (NLT). A senior level manager shall be assigned responsibility for execution of the assessments."
Overall Evahsation -
The RIP Assessment Team hEs obsmed that the RIP t a well-conceived program that has been, r.nd will continue to be, an extenely usand tool fbr identifying and resolving issues that will, over time, help impsove the overall performance of JAF. The Ed.cdeiogy used to develop the RIP Program fostered significant cocpsidan among alte departments as well as divisions in the corporata office,
. and this teamwork is an important and solidifying elamam of the success of the-RIP Program.
i-However, the team strongly recommends that the RIP be..sii place gresect i
emphasis.on issue resoludon as opposed to action item counpletion. Presendy, individuals are held accountable only for'their andgned action items without
- sufficient consideration of the actual issue, although the Plant Leadership Team (PLT) in its review of completed action items does evale its effect on the
- issue. By focusing individual staff members on the issues, it should become apparent whether or not the actions are == Wily resolving the lasues. This recommendation, along with others noted in this report, will serve to improve and L enhance the effectiveness of the RIP in i4A-/.ug its objecsive.
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Progress on the RIP Issues All 159 issues were myiewed in this annemment. For these issues, it has been determined that:
39 issues are not yet resolved, but appropriate action is being taken 2 resolve the issure in a timely mr.nnar.
- 78 issues have action plans that the team recommends be enhanced to more effectively address the lasues.
30 issues have appropriate action plans but more timely action is requhed.
In many cases, issues are being addressed appropriately. In most cassa, for the 78 issues, additional actions att reconie to ensure that they will fully resohe W issues. In some cases, actions were not completed on a timely basis We uponsibilities for action itemos were either unclear, or certain prerequisites required for an acdon item had not yet been completed. In those cases, recomame=dans are being made to clarify the responsibilities in the action plan. :
Conclusions and, when applicable, Rooornmenderinns for each of the RIP issues are presented as an appendix to this report.
' Assessement of the RIP: Issue Ikavan=es-lAs an additional product of this manaann==w, the RIP mammanrnant team provided input on the overall psogrees of RIP isome resolution at JAF. While the team concluded that the RIP is ; 54 problemas at the plant, it also found that some
+=== would be heanaew to ensuring the psogram's errectiveness:
The focus of activity at JAF is prhner9y ahned at completion of the action items identiSed in RIP, rather then on raanhainn at the issues presented in that report. _ As _a consequenos, the team found several Issues where the action plan hasns had been cannpleend or nearly completed, but the issue had not or would not be resolved.
=
- N mm managementand communie=dans should be enhanced for RIP items, including (1) assigning reapanwihiHden for issue sesolution as well as action items, (2) dtviding long-term action items (those act due to be completed for several_ months or years) into a series of actions that include short-term % and (3) recognir.ing that certain 2-
+
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.=
s issues (such as those involving morale and management oversight) may never be permanently " closed *, and should have action items that require periodk review and follow-up on those haiw a Certain issues should be consoMatai to centralize accountability and to enable resolution of the issues in an integrated manner.
With these course conections and others noted in thli report, the RIP program will become more effective in achieving overall performance improvements at JAF.
Observations and Mndinas Several overall observations and findings emerged during the RIP ==mement process. These are:
Operations and Iwata*==ca
- Action plans spr.cific to departmentally-contained issues appear to be on target and are progressing on schedule. (See Issues 02,010, IC4, ORG1, BG1-6 and BG8.)
= Taining issues, including those internal to other departmental issue lists, are ger.:nlly progressing d%1y. (See Issues T1, T2,75, T6, T8, 'I9, M13 and 06.)
- De availability of resources appears to have improved, but more effecu% ntl1M% of these resources needs most management auention. (See Issues M3, M6, P2 and P3.) ,
- Certain isAes and action plans regire most top mrsagement integration and cocidk=h rather than relying solely on self-contained departmental plans. (See Issues P2 and IC2.)
hah
- Nuclear Generanon staff noted that the Performance and System Engineering Groups' involvement in day-kHlay wodc activities has -
improved. He Syssem Engh,siing Group which ped +11y rvviews systern problems and remmmte cancive action was noted by the team to be highly effective and has resulted in more detallad DBDs being developed. (See Issues TS1 and TS2.)
- ne Opeating F.xperience Group's activities have irnproved in that the 3
.s l
l group has a solid program improwment plan, a resource schedule, and personnel have been hiral to address the backlog issue. (See Issue TS4.)
Several support groups at JAF, such.as MBL, Drawing Update and Plant Records Management Groups trad their increasing Wuan,, on a monthly basis and plans to effect a reduction in their harHag are in place. It was noted that all supervisors in the JAP Configuration Management Group are in acting positions. Permanent supervisors should be hired as soon as possible. (See Issues CC6, CC10 and SE8) .
Design Basis Documents (DBDs) were considered a positive aspect of the Configuration Group. (See issues SB12 and SB13.)
Roles and responsib!!! der for engineering and support groups in the Nuclear Generation Department have not been clearly defined. (See Issue SEl.)
Outage delays and increased engineering workload have resulted in slippage of many engineering action items. (See Issue TS4.)
Specific tr:1ning in enginectmg for pufM development needs to be improved. (See Issues CC5 and SE14.)
Work planning, scheduling, and prioriHradan require significant improvement and managernent attention. (See Issues TS4, CCl, SE4, SE6 and SE7.)
Managaneet and orsa, L,dson First-line supervisory training at the plant has been highly effective. (See Issue MO3.)
Morale at the plant is low, but may be beyond the reach of RIP-type
" action plans" and more W upon serful plant start-up, reductions in working hours, and gmuer regulatory /public acceptance.
(See Issue MO2.)
Leadership is not presently perceived as strong but the changes in management are probably too recent to show their effect at this time.
More time will be required to drwunne the effectivmess of the leadership issue actions. (See Issue MOI.)
4
,1
- Pirnnin Ud schedullog, both departmental and plant wide, are *m the culy males of devdooment and have not yet resulted in significant impravements. (See Issues MO4, P1 and P2.)
- Communications, prdenlarly from plant middle management to staff, un perceived as weak. (See issues MO5.)
Each of these issues are M!ted in the body of this report.
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