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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARB17848, Startup Test Rept Cycle 7. with1999-09-30030 September 1999 Startup Test Rept Cycle 7. with ML20211Q3361999-09-0707 September 1999 Proposed Tech Specs Removing Current Special Exception Which Precludes Applying Eighteen Month Functional Testing Surveillance to SG Hydraulic Snubbers ML20211H6471999-08-25025 August 1999 Proposed Defueled Tech Specs,Revising Sections 5.6.1,5.7.2 & 5.7.3 & Adding Proposed Section 5.6.4 to Reflect ACs Contained in NUREG-1433 ML20210Q5211999-08-0505 August 1999 Proposed Tech Specs Sections 3.8.3.2,4.6.2.1,4.6.2.2, 4.8.1.1,4.9.12 & Bases Section B 3/4.3.2,B 3/4.6.1.2 & B 3/4.8.4,incorporating Editorial Revs ML20210C6091999-07-16016 July 1999 Proposed Tech Specs Relocating Selected TS Related to Refueling Operations & Associated Bases to Plant TRM ML20206U1041999-05-17017 May 1999 Proposed Tech Specs Section 4.4.6.2.2.e,deleting Reference to ASME Code Paragraph IWV-3472(b) Re Frequency of Leakage Rate Testing for Valves Six Inches Nominal Pipe Size & Larger ML20206M8221999-05-10010 May 1999 Restart Assessment Plan Millstone Station ML20206D1761999-04-27027 April 1999 Rev 1 to Millstone Unit 3 ISI Program Manual,Second Ten-Yr Interval ML20205R2411999-04-19019 April 1999 Rev 3 to CP2804L, Unit 2 Rx Coolant & Liquid Waste Pass ML20205R2751999-04-19019 April 1999 Proposed Tech Specs,Reflecting Permanently Defueled Condition of Unit ML20205R2501999-04-19019 April 1999 Rev 0 to CP2804M, Unit 2 Vent & Containment Air Pass ML20205S5611999-04-16016 April 1999 Rev 5 to Epop 4426, On-Site Emergency Radiological Surveys ML20205M0891999-04-0707 April 1999 Proposed Tech Specs Modifying Value for Monthly Surveillance Testing of Tdafwp ML20205E4411999-03-29029 March 1999 Rev 2 to CP 2804L, Unit 2 Rx Coolant & Liquid Waste Pass ML20196K5771999-03-24024 March 1999 Rev 1 to Chemistry Procedure CP2804L, Unit 2 Rx Coolant & Liquid Waste Pass ML20205D5321999-03-22022 March 1999 Rev 3 to RPM 2.3.5, Insp & Inventory of Respiratory Protection Equipment ML20204J4101999-03-19019 March 1999 Proposed Tech Specs Relocating Instrumentation TSs 3.3.3.2, 3.3.3.3 & 3.3.3.4 to Mnps,Unit 2 TRM ML20204J1581999-03-19019 March 1999 Proposed Tech Specs Section 6, Administrative Controls, Reflecting Certified Fuel Handler License Amend Changes, Approved on 990305 ML20204K0971999-03-19019 March 1999 Proposed Tech Specs Supporting Spent Fuel Pool Rerack to Maintain Full Core Reserve Capability Approaching End of OL ML20204F9031999-03-17017 March 1999 Proposed Tech Specs,Revising 3.5.2,3.7.1.7 & 3.7.6.1 Re ECCS Valves,Atmospheric Steam Dump Valves & CR Ventilation Sys. Associated Bases Will Be Modified as Necessary to Address Proposed Changes ML20207H9551999-03-0505 March 1999 Proposed Tech Specs Section 6.0 Re Administrative Controls ML20206K1121999-03-0505 March 1999 Proposed Tech Specs Bases Sections 3/4.7.7, CR Emergency Ventilation Sys & 3/4.7.8 CR Envelope Pressurization Sys. Changes Are Editorial in Nature ML20207F6211999-03-0303 March 1999 Rev 2,change 1 to Communications - Radiopaging & Callback Monthly Operability Test ML20207E0321999-03-0202 March 1999 Proposed Tech Specs 3/4.7.4, SW Sys, Proposing Change by Adding AOT for One SW Pump Using Duration More Line with Significance Associated with Function of Pump ML20207D4821999-02-26026 February 1999 Proposed Tech Specs Re Addl Mods Concerning Compliance Issues Number 4 ML20207J0001999-02-22022 February 1999 Rev 7 to Millstone Unit 2,IST Program for Pumps & Valves ML20206D1991999-02-11011 February 1999 Change 7 to Rev 5 to ISI-3.0, Inservice Testing Program. Pages 2 of 3 & 3 of 3 in Valve Relief Request Section 6.1 of Incoming Submittal Not Included ML20203E4051999-02-11011 February 1999 Proposed Tech Specs Re DG Surveillance Requirements ML20210D2121999-01-21021 January 1999 Proposed Tech Specs Sections 3/4.5.2 & 3/4.5.3, ECCS Subsystems for Info Only ML20199L2841999-01-20020 January 1999 Proposed Tech Specs & Final SAR Proposed Rev to Ms Line Break Analysis & Revised Radiological Consequences of Various Design Basis Accidents ML20199L0431999-01-18018 January 1999 Proposed Tech Specs Removing TS 3/4.6.4.3, Containment Systems,Hydrogen Purge Sys ML20199L3271999-01-18018 January 1999 Proposed Tech Specs 3.6.1.2, Containment Sys - Containment Leakage ML20199L0801999-01-18018 January 1999 Proposed Tech Specs Change to TS 3/4.2.2 Modifies TS to Be IAW NRC Approved W Methodologies for Heat Flux Hot Channel factor-FQ(Z).Changes to TS Section 6.9.1.6 Are Adminstrative in Nature ML20199L4561999-01-18018 January 1999 Proposed Tech Specs Revising TS Table 3.7-6, Air Temp Monitoring. Proposed FSAR Pages Describing Full Core off- Load Condition as Normal Evolution Under Unit 3 Licensing Basis,Included ML20199E0931999-01-13013 January 1999 Rev 2 to Health Physics Support Procedure RPM 2.3.4, Insp & Maint Process for Respiratory Protection Equipment ML20206P5121999-01-0404 January 1999 Proposed Tech Specs 3.5.2,3.6.2.1,3.7.1.2,3.7.3.1 & 3.7.4.1, Incorporating Changes to ESF Pump Testing B17501, 1998 - 2000 Performance Plan - Work Environ Focus Area Update1998-12-31031 December 1998 1998 - 2000 Performance Plan - Work Environ Focus Area Update ML20199A7531998-12-31031 December 1998 Restart Backlog Mgt Plan Commitments ML20198K6361998-12-31031 December 1998 Proposed Tech Specs Section 6.0, Administrative Controls ML20198P9751998-12-28028 December 1998 Proposed Tech Specs Pages Revising Loss of Normal Feedwater (Lonf) Analyses to TS 2.2.1,TS Bases Change to Floor Value for Thermal Margin Low Pressure Reactor Trip & Proposed FSAR Changes 05000423/LER-1998-002, Proposed Tech Specs Bases Section 3/4.5.2,clarifying SRs That Ensure That ECCS Piping Is Full of Water,As Committed to in LER 98-002-00,dtd 9802071998-12-21021 December 1998 Proposed Tech Specs Bases Section 3/4.5.2,clarifying SRs That Ensure That ECCS Piping Is Full of Water,As Committed to in LER 98-002-00,dtd 980207 ML20197G9831998-12-0404 December 1998 Proposed Tech Specs 4.7.10.e,eliminating Need to Cycle Plant & Components Through SD-startup Cycle by Allowing Next Snubber Surveillance Interval to Be Deferred Until End of RFO6 of 990910,whichever Date Is Earlier ML20196H6301998-12-0404 December 1998 Proposed Tech Specs Re Section 6.0, Administrative Controls ML20196A2181998-11-20020 November 1998 Restart Assessment Plan Millstone Station ML20195D8101998-11-10010 November 1998 Revised marked-up Page of Current TS 3.8.1.1 & Revised Retyped Page Re 980717 Request to Change TS ML20195D4041998-11-10010 November 1998 Proposed Tech Specs,Modifying Sections 3.3.1.1 & 3.3.2.1 by Restricting Time That Reactor Protection or ESF Actuation Channel Can Be in Bypass Position to 48 H,From Indefinite Period of Time ML20195H8681998-11-0404 November 1998 Rev 4 to Millstone Unit 2 Operational Readiness Plan B17548, Rev 0 to TPD-7.089, Millstone 1 Equipment Operator Training Program1998-10-29029 October 1998 Rev 0 to TPD-7.089, Millstone 1 Equipment Operator Training Program ML20196H5921998-10-29029 October 1998 Rev 0 to TPD-7.088, Millstone 1 Certified Fuel Handler/ Equipment Operator Continuing Training Program ML20196H5861998-10-29029 October 1998 Rev 0 to TPD-7.087, Millstone 1 Certified Fuel Handler Training Program 1999-09-07
[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20206M8221999-05-10010 May 1999 Restart Assessment Plan Millstone Station ML20206D1761999-04-27027 April 1999 Rev 1 to Millstone Unit 3 ISI Program Manual,Second Ten-Yr Interval ML20205R2501999-04-19019 April 1999 Rev 0 to CP2804M, Unit 2 Vent & Containment Air Pass ML20205R2411999-04-19019 April 1999 Rev 3 to CP2804L, Unit 2 Rx Coolant & Liquid Waste Pass ML20205S5611999-04-16016 April 1999 Rev 5 to Epop 4426, On-Site Emergency Radiological Surveys ML20205E4411999-03-29029 March 1999 Rev 2 to CP 2804L, Unit 2 Rx Coolant & Liquid Waste Pass ML20196K5771999-03-24024 March 1999 Rev 1 to Chemistry Procedure CP2804L, Unit 2 Rx Coolant & Liquid Waste Pass ML20205D5321999-03-22022 March 1999 Rev 3 to RPM 2.3.5, Insp & Inventory of Respiratory Protection Equipment ML20207F6211999-03-0303 March 1999 Rev 2,change 1 to Communications - Radiopaging & Callback Monthly Operability Test ML20207J0001999-02-22022 February 1999 Rev 7 to Millstone Unit 2,IST Program for Pumps & Valves ML20206D1991999-02-11011 February 1999 Change 7 to Rev 5 to ISI-3.0, Inservice Testing Program. Pages 2 of 3 & 3 of 3 in Valve Relief Request Section 6.1 of Incoming Submittal Not Included ML20199E0931999-01-13013 January 1999 Rev 2 to Health Physics Support Procedure RPM 2.3.4, Insp & Maint Process for Respiratory Protection Equipment B17501, 1998 - 2000 Performance Plan - Work Environ Focus Area Update1998-12-31031 December 1998 1998 - 2000 Performance Plan - Work Environ Focus Area Update ML20199A7531998-12-31031 December 1998 Restart Backlog Mgt Plan Commitments ML20196A2181998-11-20020 November 1998 Restart Assessment Plan Millstone Station ML20195H8681998-11-0404 November 1998 Rev 4 to Millstone Unit 2 Operational Readiness Plan ML20196H5921998-10-29029 October 1998 Rev 0 to TPD-7.088, Millstone 1 Certified Fuel Handler/ Equipment Operator Continuing Training Program B17548, Rev 0 to TPD-7.089, Millstone 1 Equipment Operator Training Program1998-10-29029 October 1998 Rev 0 to TPD-7.089, Millstone 1 Equipment Operator Training Program ML20196H5861998-10-29029 October 1998 Rev 0 to TPD-7.087, Millstone 1 Certified Fuel Handler Training Program ML20154G5311998-10-0707 October 1998 Rev 4 to Project Procedure PP-02, Accident Mitigation Sys Review ML20154G5351998-10-0606 October 1998 Rev 3 to Project Procedure PP-04, Regulatory Review Procedure ML20154G5521998-10-0606 October 1998 Rev 5 to Project Instruction PI-01, Svsr Implementation Checklists & Workbook ML20154G5391998-10-0606 October 1998 Rev 6 to Project Procedure PP-07, Discrepancy Repts ML20154G5251998-10-0505 October 1998 Rev 4 to Independent C/A Verification Program for Millstone Unit 2 Audit Plan ML20236Q9341998-06-30030 June 1998 Rev 4 to PI-01, Sys Vertical Slice Review Implementation Checklists & Workbook ML20236Q9321998-06-25025 June 1998 Rev 4 to PP-01, Sys Vertical Slice Review ML20153C6221998-06-18018 June 1998 Rev 1 to CP 3804L, PASS Containment Air Sample ML20153C6171998-06-18018 June 1998 Rev 2 to CP 3804K, PASS Rcs/Rss Sample ML20153C6291998-05-31031 May 1998 Rev 0,Change 1 to CP 3804M, PASS Ventilation Samples ML20247R7851998-05-20020 May 1998 Rev 1 to Epop 4455C, Technical Assistant ML20247Q6901998-05-20020 May 1998 Rev 1 to Epop 4475A, External Resources Coordinator ML20247R8081998-05-20020 May 1998 Rev 1 to Epop 4455F, Rumor & Inquiry Control ML20247Q7011998-05-20020 May 1998 Rev 1 to Epop 4490, Implementation of Recovery Operations ML20247Q6771998-05-20020 May 1998 Rev 1 to Epop 4428I, Direction of Posl Field Sampling ML20247R7491998-05-20020 May 1998 Rev 1 to Epop 4455, Manager of Public Info ML20247R7541998-05-20020 May 1998 Rev 1 to Epop 4455A, Nuclear News Manager ML20247R7921998-05-20020 May 1998 Rev 1 to Epop 4455D, News Releases ML20247Q6671998-05-20020 May 1998 Rev 1 to Epop 4422A, Thermal Hydraulic Evaluation Methods ML20216B1791998-05-0808 May 1998 Independent Corrective Action Verification Program for Millstone Unit 3,Interim Rept,Executive Summary ML20247H4581998-04-0909 April 1998 Rev 19 to EOP 35 E-0, Reactor Trip or Safety Injection ML20216K0641998-03-20020 March 1998 Rev 2 to Oversight Plan NNECO - Millstone Site Independent Third Party Oversight Program ML20216H7101998-03-13013 March 1998 Independent Corrective Action Verification Program Status Rept ML20216H7191998-03-0303 March 1998 Independent Corrective Action Verification Program Status Rept ML20203F6931998-02-20020 February 1998 Rev 6 to PI-MP3-11, Discrepancy Rept Submittal & Closure ML20203E2131998-02-19019 February 1998 Cancelled Rev 26 to 1-OPS-10.11, Locked Valve List ML20203D4111998-02-18018 February 1998 Revised 1-OM-index Unit 1 Operations Dept OM Index & Rev 2 to OM 3.8, Millstone Unit 1 Operations Manual ML20203F6601998-02-16016 February 1998 Rev 5 to Audit Plan for Independent Corrective Action Verification Program ML20203F6751998-02-16016 February 1998 Rev 2 to PI-MP3-07, Review of Accident Mitigation Systems ML20216H7351998-02-11011 February 1998 Independent Corrective Action Verification Program Status Rept ML20203H3271998-02-0505 February 1998 Restart Assessment Plan Millstone Station 1999-05-10
[Table view] |
Text
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Docket No. 50-336 B17596
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Millstone Nuclear Power Station Unit No. 2 Restart Backlog Management Plan r
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December 1998 9901130123 981222 PDR ADOCK 05000336)j!
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'U S Nucl:ar Regul tory Commission B17596%ttachment 2\\Page 1 p
i Millstone Unit 2 Restart Backlog Management Plan Summary i.
i Table of Contents Section Descriotion P_9.2%
t-1
' Introduction 2
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2' Characterization of the Backlog of Deferrable Work 2
3.
Backlog Management Methodology.
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4.
Measuring Unit 2 Backlog After Plant Startup 4
5 Reference List 4
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- Table 1:
Deferrable (Recovery Bccklog) Items Summary f.
Table 2:
Restart and Post Restart Performance Targets by Work
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Management Category i
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- Table 3 Millstone Acronyms l
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U.S. Nucl=r Reguliitory Commission B17596\\ Attachment 2\\Page 2 1.
INTRODUCTION 1
Purpose 4
[
The Millstone. Unit 2 Restart Backlog Management Plan provides an integrated, j
structured approach to successfully manage and disposition the backlog of identified open items at the time of Unit 2 restart. The plan considers the
. balance and integration of the " Recovery Packlog", "New Work" and the need to 4-focus on t5e safe, event-free operation of Unit 2.
Performance Obiectives 4
The Plan; has been constructed to support the following Unit 2 high level j
performance objectives:
j Reduce challenges to the operators e
i e
improve timeliness and effectiveness of maintenance and work activities, while maintaining high quality standards Maintain a high state of plant materiel condition i
e l~
Plan Structure Section 2 provides a characterization of the items that may be completed l
after restart.
Section 3 describes the backlog management method.
Section 4 describes measuring backlog after restart.
Section 5 provides the reference list.
i i
o Table 3 provides a listing of Millstone acronyms.
)
e 2.
CHARACTERIZATION OF THE BACKLOG OF DEFERRABLE WORK Work items identified Prior to Entry into Mode 2 Deferrable work items identified beforo entry into Mode 2 will be tracked as
" Recovery Backlog" " Recovery Backlog" will include Unit 1 deferred work on systems required to support the Unit 2 licensing and design hasis.
The methodology for determining deferrable work items was provided in References 3,4,and5.
Work items identified After Entry into Mode 2
. Work items identified after entry into Mode 2 will be tracked as "New Work".
"New Work" items will be prioritized in accordance with station processes (e.g.,
work control and cc.nective action).
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U.S. Nuclezr Regulatory Commission B17596\\ Attachment 2\\Page 3 Outaoe Prooress in Dispositionina Work Items Throughout this recovery outage, primary emphasis and priority has been placed on completing those items required for the safe restart of Millstone Unit 2.
However, this has not been to the exclusion of other work. Beyond those items required for restart, a significant number of deferrable. corrective action items have also been completed. These items encompass Millstone Unit 2 Condition Reports, ICAVP DRs, CMP Unresolved Item Reports (UIR), Maintenance AWOs, and engineering work products.
Daily progress is being mede in dispositioning both restart and post-restart work items.
3.
BACKLOG MANAGEMENT METHODOLOGY The Backlog Management Guidance, which reflects the following process functional requirements, will be developed and PORC approved prior to entry into Mode 2. Note that "dispositioned" is defined as establishing management direction for the course of action needed to move a backlog item towards it closure. Disposition may include scheduling an item with an implementation due date such as the next refueling outage, providing work item closure, or canceling an item.
Backlog of UIRs will be dispositioned prior to entry into mode 2 following RFO13.
Backlog of Discrepancy Reports (DRs) will be dispositioned prior to entry into mode 2 following RFO13.
Remaining " Recovery Backlog" will be dispusitioned within six months after RFO13.
Existing work control and prioritization processes will be used to disposition work items, including an option not to pursue performance enhancement items.
- Resiart Backlog Management Plan performance monitoring will be established, tracked, and monitored. KPI's for the categories of backlog will be maintained and reported quarterly.
There will be management performaace review of Key Performance Indicator (KPI) goals.
Periodic assessments will be conducted to provide added assurance that management standards are being conservatively applied.
[U'.S. Nuclur Regulatory Commission i
B17596\\ Attachment 2\\Page 4 4.
MEASURING UNIT 2 BACKLOG AFTER STARTUP The "P.ecovery Backlog" list will be finalized within the first calendar week after Unit 2 enters Mode 2. This list of assignments will be reported to the NRC within 30 days after Unit 2 enters Mode 2.
Applying the Unit 2 " Recovery Backlog" list selection logic through December 18, j
1998, generates e list of 2765 backlog assignments, in nine work management areas, as shown in Table 1.
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Restart items for eight of the work management categories are listed in Table 2.
Also shown on Table 2 are the restart and post restart performance targets for
.I i-each of the work management categories. The post restart targets apply to the summation of " Recovery Backlog" and "New Work. Progress for each work management category will be monitored by Key Performance Indicators similar j
to the KPis in use for Unit 3. *
!I i
5.
Reference List
)'
(1) NRC Letter, S. J. Collins (NRC) to N. S. Carns (NNECO), dated April 16,
-1997.
(2) NNECO Letter, B. D. Kenyon (NNECO) to U. S. Nuclear Regulatory Commission, " Millstone Nuclear Power Station, Units 1,2, and 3, Progress j
Toward Restart Readiness at Millstone Station," dated February 12,1998.
(3) NNECO Letter, M. L. Bowling to U. S. Nodear Regulatory Commission,
" Millstone Nuclear Power Station, Unit Nos.1,2, and 3, Initial Information Submittal Regarding NRC 10 CFR 50.54(f) Information Request," dated May 29,1997.
(4) NNECO Letter, M. L. Bowling to U. S. Nuclear Regulatory Commission,
" Millstone Nuclear Power Station, Unit No. 3, Update Submittal Regarding NRC 10 CFR 50.54(f) Information Request," dated January 9,1998.
(5) NNECO Letter, M. L. Bowling to U. S. Nuclear Regulatory Commission,
" Millstone Nuclear Power Station, Units 2 and 3 Supplementary Response to 10CFR 50.54(f), Information Request, item 3, Process and Rationale for Deferrable items", dated December 22,1998.
s (6) NNECO Letter, M. L. Bowling to U. S. Nuclear Regulatory Commission,
" Millstone Unit No. 3 Third Quarter Performance Report" dated November 16, 1998.
'.S. Nucirr Regulttory Commission U
B17596%ttachment 2\\Page 5
't Table 1 Deferrable (Recovery Backlog) Items Summary Work Management As of:
Category Bins 12/18/98 Corrective Action Assignments (includes Level 4 DR ARs) 1825 Corrective Maintenance Work Orders 531 Configuration Management Discovery 73 (UIRs)
Non-Conformance Reports 0
Operator Work Arounds 3
Control Room Deficiencies 2
Temporary Modifications 3
Engineering Backlog 297 Procedures in "Do Not Use" Status 31 TotalDeferrable items 2765 a
' D U.S. Nuclear Regulatory Commission B17596\\ Attachment 2\\Page 6 Table 2 Restart and Post Restart Performance Targets by Work Management Category WORX MANAGEMENT RESTART RESTART MP2 POST RESTART RFO13 RESTART
' CATEGORY ITEMS TARGET EXPECTATIONS TARGETS As of 12/18/98 (NEAR-TERM TARGETS)
Corrective Action 1443 No MID13 1st Qtr. - Total open Level 1 & 2 CRs -
. fe overdue Level 1 CRs Assignments assignments hold steady
. < 1 % overdue AITTS tied to No overdue
. Subsequent Qtrs. - Gradual Reduction Level 1&2 CRs Level 1 CR in total open.
. All Deferred Corrective Actions investigations Dispositioned 53%
. ICAVP DR corrective actions overdue completed and implemented AITTS tied to Level 1&2 CRs No MID13 Expected to rise for the first quarter 5 500 Power Block Corrective Maintenance 776 Work Orders (AWOs)-
AWOs following restart, hold steady in the 5 350 On PRA Risk Significant 5 500 Power second quai 3r, and be reduced in Systems Block subsequent quarters.
5350 On PRA Risk Significant Systems Temporary Modifications 18 510 Temp.
By the end of 1999:
510 Temp. Mods. at Restart.
Mods.
510 Temp. Mods. that can be removed
. No Temp. Mod. installed > 1 at power cycle without CNO approval (at Restart of each planned outage).
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U.S. Nuclear Regulatory Commission
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B17596\\ Attachment 2\\Page 7 -
Table 2 (Continued)
Restart and Post Restart Performance Targets by Work Management Category WORK MANAGEMENT RESTART RESTART MP2 POST RESTART RF013 RESTART CATEGORY ITEMS TARGET EXPECTATIONS TARGETS I
as of 12/1/98 (NEAR-TERM TARGETS)
Operator Work Arounds 16 510 OWAs
. By the end of 1999 510 OWAs that can 56 OWAs at Restart.
(OWAs) be addressed at power
. No OWAs open11 cycle without CNO approval (at Restart of each planned outage).
Control Room Deficiency 35 5 10 By the end of 1999, 5 5 CRDs that ccn be 5 5 CRDs at Restart.
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(CRDs) addressed during power operations.
'. No CRDs open 31 cycle without CNO approval (at Restart of each planned outage).
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Configuration 35 No Open LB/DB
. All UIRs dispositKmed.
Management Discovery items (UIR)
Procedures in "Do Not 59 31 No procedures in "Do Not Use" Status Use" status i
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U.S. Nuclear Regulatory Commission
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l B17596\\ Attachment 2\\Page 8 Table 2 (Continued)
I Restart and Post Restart Performance Targets by Work Management Category WORK MANAGEMENT BACKLOG RESTART MP2 POST RESTART RFO13 RESTART CATEGORY As of 12/1/98 TARGET EXPECTATIONS TARGETS (NEAR-TERM TARGETS)
Engineenng Backlog 67 All Restart e 3 Months followina Restart - Emphasize day-to-day
. Complete RFO13 Modifications Engineering items support of safe, event-free operations. Cor duct (includes: EWA, EWR, MMOD, dispositioned.
review of pj! open Engineering work items. Identify-DCN,DCR,PDCE,MSEE, a) Items that can be safely worked during power PDCR, PMR, RIE) operations.
t b) Items that can only be worked during plant l
shutdown.
By 6 months followina Restart c) Publish the list of modifications that will worked j
during RF013.
d) Issue PJrchase Orders for RFO13 long lead time parts and materials.
e) Identify / eliminate Engineering Bacidog items 3
that
- 1. are not required for compliance with DB/LB requirements, or
- 2. do not meeningfully contribute to safe, t
event-free operations, or
- 3. do not measurably, and significantly improve plant availability or output.
I
. By end of 1999:
f) Engineering Packages issued for > 50% of RFO13 Modifications.
g) Publish the list of modifications that will be worked during RFO13.
M Publish the list of modifications that will be worked during power operations (approved by VP Operations).
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B17596\\ Attachment 2\\Page 9 J'
Table 3 Millstone Acronyms Acronym Words that form the Acronym AITTS Action item Tracking Trending System AR Action Request AWO Automated Work Order CIA Corrective Action CR Condition Report CRD Control Room Deficiency i
DCN Design Change Notice DCR Design Change Record DR.
Discrepancy Report EWA Engineering Work Assignment EWR Engineering Work Request
' KPI Key Performance Indicator LAR License AJnendment Request LB/DB License Bases / Design Bases MR Maintenance Rule MRT Management Review Team MSEE
' Maintenance Support Engineering Evaluation NCR Non-Conformance Report NSAB Nuclear Safety Assessment Board i
OIR Open issue Report OWA Operator Work Around PDCE Plant Design Change Evaluation PDCR Plant Design Change Record PMR Plant Modification Request
- PORC Plant Operations Review Committee TMOD-Temporary Modification UIR Unresolved Issue Report