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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217K9011999-10-18018 October 1999
Proposed Tech Specs 3.6.2.2 Loc,Allowing Plant to Operate with Two Independent Trains of Containment Cooling, Consisting of One Fan Cooler Per Train,Operable During Modes 1,2,3 & 4
ML20211F5501999-08-24024 August 1999
Proposed Tech Specs Page Xviii, Index Administrative Controls, Originally Submitted with TS Change Request NPF-38-220
ML20211F3701999-08-24024 August 1999
Proposed Tech Specs,Revising Efas,Originally Submitted on 980702 as TS Change Request NPF-38-207
ML20210M9681999-08-0404 August 1999
Existing & Proposed marked-up TS Pages Modifying TS 3.5.2 by Extending AOT to Seven Days for One LPSI Train Inoperable & AOT of 72 Hours Imposed for Other Conditions
ML20210M9861999-08-0404 August 1999
Existing & Proposed TS Pages Modifying TS 3.5.2 by Extending AOT to Seven Days for One HPSI Train Inoperable & TS 3.5.3, Changing end-state to Hot Shutdown with at Least One Operable Shutdown
ML20210H1771999-07-29029 July 1999
Proposed Tech Specs 3.8.1.1 Re EDG AOT Increase from 72 H to Ten Days
ML20210H2371999-07-29029 July 1999
Proposed Tech Specs 3.6.2.1 Extending Allowable Outage Time to Seven Days for One Containment Spray Sys Train Inoperable
ML20210B3411999-07-19019 July 1999
Proposed Tech Specs 4.5.2.f.2,increasing Performance Requirement for LPSI Pumps
ML20210D0521999-07-15015 July 1999
Proposed Tech Specs Creating New TS for Feedwater Isolation Valves
ML20210D1071999-07-15015 July 1999
Proposed Tech Specs Adding TS Bases Control Program to TS Administrative Controls Section & Correcting Editorial Error Identified in TS Following Issuance of Amend 146,dtd 981019
ML20209H3191999-07-15015 July 1999
Proposed Tech Specs Pages Modifying TS 3/4.4.8.1,Figures 3.4-2 & 3.4-3 to Extend RCS Pressure Temperature Curves to 20 EFPY
ML20209D4091999-07-0707 July 1999
Proposed Tech Specs,Revising Actions 19 & 20 for Table 3.3-3 for Functional Unit 7 Emergency Feedwater, Items B & C,Per 980702 TS Change Request NPF-38-207
ML20196E9971999-05-24024 May 1999
Rev 3 to NTP-203, Emergency Plan Training
ML20195B1811999-05-20020 May 1999
Proposed Tech Specs Changes to Bases B 3/4.3.1 & 3/4.3.2, B 3/4.6.3,B 3/4.7.1.2 & B 3/4.7.12
ML20204H2591999-03-16016 March 1999
Rev 0 to STD-100-237, Procedure for Modification of RCS Pressure Boundary for Installation of Mechanical Nozzle Seal Assemblies (Mnsa) for Waterford Nuclear Generating Station Unit 3
ML20204H2511999-03-16016 March 1999
Rev 1 to C-NOME-EP-0189, Engineering Procedure for Installation of Mechanical Nozzle Seal Assemblies for Waterford 3
ML20203C4891999-02-0505 February 1999
Proposed Revised Tech Specs Pages 3/4 3-12a & B 3/4 3-1a Re Reactor Trip Circuit Breaker Surveillance Interval Extension
ML20199D9851999-01-12012 January 1999
Proposed Tech Specs,Adding Requirement That CR Intake Monitors Be Operable & SRs Be Applicable During Movement of Irradiated Fuel
ML20199E0861999-01-12012 January 1999
Proposed Tech Specs Re Rev 1 for TS Change Request NPF-38-174
ML20198G2401998-12-23023 December 1998
Proposed Tech Specs,Modifying LCO for 3.3.3.7.1 for Chlorine Detection Sys by Changing Alarm/Trip Setpoint from 3 Ppm to 2 Ppm
ML20196D2181998-11-30030 November 1998
Proposed Tech Specs Pages 3/4 8-8,3/4 9-8,3/4 9-9 & B 3/4 9-2,revised for Consistency Between Action Statements & NUREG-1432,Rev 1, Std Tech Specs for CE Plants
ML20154E4171998-10-0606 October 1998
Proposed Tech Specs Pages Re TS Change Request NPF-38-212, Modifying Requirement to Perform Mtc Test Near End of Each Cycle
ML20154E1141998-10-0101 October 1998
Proposed Tech Specs Modifying TS 3.3.3.7.3 & SR 4.3.3.7.3 for Broad Range Gas Sys
ML20153D5771998-09-23023 September 1998
Proposed Tech Specs Revising Description Re Reactor Power Input Used by Operating Bypass Permissive & Trip Enable of 10-4% Bistable
ML20153B4441998-09-18018 September 1998
Proposed Tech Specs Modifying Notes in Tables 2.2-1 & 3.3-1 Re Reactor Protective Instrumentation
ML20151W5971998-09-11011 September 1998
Proposed Tech Specs Re Notes in Table 2.2-1 Re Reactor Protective Instrumentation Trip Setpoints Limits & Table 3.3-1 Re Reactor Protective Instrumentation
ML20237A7921998-08-12012 August 1998
Proposed Tech Specs,Increasing Max Boron Concentration in SITs & Rwsp from 2300 Ppm to 2900 Ppm
ML20236U7361998-07-29029 July 1998
Proposed Tech Specs Pages Revising TS 6.9.1.11.1 to Replace Ref to Abb Combustion Engineering SBLOCA ECCS Performance Evaluation Model
ML20236H1501998-07-0202 July 1998
Proposed Tech Specs Section 3/4.3.2,adding Restriction on Period of Time Channel of Efas Instrumentation Can Remain in Tripped Condition
ML20249C8321998-06-29029 June 1998
Proposed Tech Specs 3.7.6.1,3.7.6.2,3.7.6.3,3.7.6.4 & 3.7.6.5,revising Control Room Ventilation to Be Consistent w/NUREG-1432
ML20249C7901998-06-29029 June 1998
Proposed Tech Specs Adding Footnote to Action Statements to Allow CR Ventilation Sys to Be Unisolated Periodically Under Administrative Controls
ML20249A3101998-06-12012 June 1998
Proposed Tech Specs Pages,Adding Footnote to TS Refueling Operations,Surveillance Requirements 4.9.7.2,to Effect Limited Deviation to Allow Crane Main Hook Electrical Interlocks to Be Replaced W/Administrative Controls
ML20248B7611998-05-28028 May 1998
Proposed TS Pages Supporting Change to TS 3.7.1.2, Surveillance Requirement 4.7.1.2 & Bases for Emergency Feedwater Sys
ML20248H7871998-05-25025 May 1998
Rev 1 to Waterford Unit 3 Second Interval ISI Plan
ML20247P2431998-05-21021 May 1998
Proposed Tech Specs Re Design Feature Suppl
ML20217P8411998-05-0101 May 1998
Rev TS Pages Changing Actions Required Should Channel of Recirculation Actuation Signal (RAS) Be Placed in Tripped Condition,Replacing TS Pages Submitted in 970603 Submittal
ML20217L9971998-04-30030 April 1998
Small Break LOCA ECCS Performance Analysis Using Abb/Ce Suppl 2 Model
ML20217D5181998-03-25025 March 1998
Proposed TS 3.9.8.1,3.9.8.2,TS Action 3.9.8.2a,3.8.1.2 & Bases 3/4.9.8
ML20198R3081998-01-21021 January 1998
Errata to Proposed TS Change Request NPF-38-196 Which Changed TS 3.1.1.1,3.1.1.2,3.10.1 & Figure 3.1.-1 by Removing Cycle Dependent B Concentration & Boration Flow Rate from Action Statements
ML20198R1251998-01-21021 January 1998
Corrections to Proposed Tech Spec 3/4.1 Re Reactivity Control Sys
ML20197C6431997-12-22022 December 1997
Proposed Tech Specs Page Supplementing TS Change Request NPF-38-186,by Retaining Operations Superintendent in Paragraph 6.2.2.f of Administrative Controls Section
ML20202C2911997-12-0101 December 1997
Rev 0 to Pump & Valve Inservice Test Plan for Second 10-Yr Interval. Page 23 of Incoming Submittal Not Included
ML20199A0011997-11-13013 November 1997
Errata to Proposed Tech Specs Change Request NPF-38-193, Replacing Pages 13 Through 21
ML20199A1101997-11-13013 November 1997
Proposed Tech Specs,Modifying 6.8.4.a, Primary Coolant Sources Outside Containment to Add Portions of Containment Vacuum Relief Sys & Primary Sampling Sys to Program
ML20217M0221997-10-28028 October 1997
Rev 8 to RW-001-210, Process Control Program
ML20217H5931997-10-14014 October 1997
Revised Page of App B of FOL, Environ Protection Plan (Nonradiological)
ML20217G2421997-10-0707 October 1997
Proposed Tech Specs Modifying 3.3.3.7.3 & Surveillance Requirement 4.3.3.7.3 for Broad Range Gas Detection Sys
ML20211F8141997-09-25025 September 1997
Proposed Tech Specs Pages Modifying LCO 3.6.1.2, Containment Leakage, Associated Action & SR 4.6.1.2
ML20141G7131997-07-0707 July 1997
Proposed Tech Specs Expanding Applicability of TS 3.7.1.3 to Include Mode 4 Operational Requirements & Maintains 91 Percent Minimum Condensate Storage Pool Level Previously Requested for Modes 1,2 & 3
ML20141D8551997-06-26026 June 1997
Proposed Tech Specs Revising TS Tables 3.7-1 & 3.7-2 by Changing MSSVs Orifice Size from 26 Inches to 28.27 Inches & Relocating Orifice Size from TS to TS Bases
1999-08-04
[Table view]
Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20196E9971999-05-24024 May 1999
Rev 3 to NTP-203, Emergency Plan Training
ML20204H2591999-03-16016 March 1999
Rev 0 to STD-100-237, Procedure for Modification of RCS Pressure Boundary for Installation of Mechanical Nozzle Seal Assemblies (Mnsa) for Waterford Nuclear Generating Station Unit 3
ML20204H2511999-03-16016 March 1999
Rev 1 to C-NOME-EP-0189, Engineering Procedure for Installation of Mechanical Nozzle Seal Assemblies for Waterford 3
ML20248H7871998-05-25025 May 1998
Rev 1 to Waterford Unit 3 Second Interval ISI Plan
ML20202C2911997-12-0101 December 1997
Rev 0 to Pump & Valve Inservice Test Plan for Second 10-Yr Interval. Page 23 of Incoming Submittal Not Included
ML20217M0221997-10-28028 October 1997
Rev 8 to RW-001-210, Process Control Program
ML20217H5931997-10-14014 October 1997
Revised Page of App B of FOL, Environ Protection Plan (Nonradiological)
ML20141B0441997-05-0808 May 1997
Performance Improvement Plan
ML20138D8951996-10-0606 October 1996
Rev 5 to Odcm
ML20117A5681996-07-28028 July 1996
Ldcr 97-0047-Location of Cabinets C-3A(B) & C-4 Outside Cvas Boundary - Rev 1
ML20116B1441996-04-17017 April 1996
Rev 6 to Procedure NTC-216, Emergency Plan Training Initial
ML20116B1531996-04-17017 April 1996
Training Course Description Emergency Plan Continuing Training
ML20138D8891996-01-11011 January 1996
Rev 7 to RW-001-210, Process Control Program
ML20086C0191995-05-31031 May 1995
Basement Monitoring Program Rept 6
ML20070P8701994-02-17017 February 1994
Rev 7,change 5 to Waterford III Pump & Valve IST Plan
ML20056F2061993-08-19019 August 1993
Rev 7,Change 4 of Waterford Unit 3 IST Plan for Pumps & Valves
ML20118A7181992-09-16016 September 1992
Rev 5 to Waterford 3 Steam Electric Station 10-Yr Inservice Insp Program,First Interval
ML20114C7711992-06-12012 June 1992
Rev 2 to Administrative Procedure UNT-005-014, Odcm
ML20101B8321992-05-29029 May 1992
EDG Reliability Program Description & Comparison W/Nrc Reg Guide 1.155,Section 1.2
ML20141M4281991-06-21021 June 1991
Rev 1 to Technical Procedure UNT-005-021, Safety-Related Radioactive Matl & Radioactive Sources Purchase,Receiving, Surveying,Opening & Disposal
ML20058P1191991-06-14014 June 1991
Mgt Manual Vol IV to Site Policy W1.501, Quality Reporting
ML20141M4271991-05-25025 May 1991
Rev 4 to Administrative Procedure UNT-005-001, Safety- Related Waste Mgt & Control
ML20141M4251991-04-25025 April 1991
Rev 7 to Technical Procedure HP-001-152, Safety-Related Marking,Handling & Storage of Radioactive Matl
ML20141M4241991-01-0404 January 1991
Rev 1 to Technical Procedure HP-002-223, Waste Monitoring
ML20065N7561990-08-24024 August 1990
Rev 4 to Administrative Procedure RW-001-210, Process Control Program
ML20059A5631990-08-13013 August 1990
Rev 4 to 10-Yr Inservice Insp Program First Interval 1985-1995
ML20065N7481990-08-0303 August 1990
Rev 0 to UNT-005-014, Odcm
ML20116B1221989-12-11011 December 1989
Rev 2 to Nuclear Training Procedure NTP-203, Emergency Plan Training
ML19325E4681989-10-31031 October 1989
Summary of Change 2 to Rev 6 to Pump & Valve Inservice Test Plan.
ML20246E0171989-08-0404 August 1989
Change 1 to Rev 6 of Pump & Valve Inservice Test Plan
ML20245D0161989-06-19019 June 1989
Change 1 to Rev 5 of Pump & Valve Inservice Test Plan
ML20082M2781989-05-0909 May 1989
Rev 3 to Administrative Procedure RW-1-210, Process Control Program
ML20195H9271988-11-18018 November 1988
Rev 0 to UNT-5-013, Administrative Procedure Fire Protection Program
ML20154S1941988-09-22022 September 1988
Rev 6 to Pump & Valve Inservice Test Plan
ML20154B3761988-05-11011 May 1988
Rev 0 to Procedure OP-100-012, Post-Trip Review
ML20238D0091987-12-0707 December 1987
Rev 2.1 to Nuclear Operations Procedure NOP-003, Records Mgt Sys
ML20195G9331987-12-0101 December 1987
NSID-TB-87-11, Westinghouse Circuit Breakers Type Ds/Dsl: Welds on Breaker Pole Shaft
ML20236L3341987-10-15015 October 1987
Rev 3 to 10-Yr Inservice Insp Program Waterford Steam Electric Station Unit 3
ML20082M2731987-07-10010 July 1987
Rev 2 to Administrative Procedure RW-1-210, Process Control Program
ML20147D7981987-07-0707 July 1987
Rev 6 to Surveillance Procedure HP-1-230, Offsite Dose Calculation Manual
ML20235G6051987-06-30030 June 1987
Functional Design Spec for SPDS Enhancement Program
ML20238D0271987-06-26026 June 1987
Rev 1 to Radwaste Dept Administrative Procedure RW-1-200, Record Preparation,Filing & Storage
ML20234B0171987-06-26026 June 1987
Rev 1 to Nuclear Plant Island Structure Basemat Surveillance Program
ML20238D0251987-06-24024 June 1987
Rev 0 to Maint Departmental Procedure MD-1-008, Collection & Transmittal of Maint Records & Documents
ML20216E8321987-06-12012 June 1987
Public Version of Emergency Plan Implementing Procedures, Including Rev 7 to EP-2-052, Protective Action Guidelines & Rev 10 to EP-2-060, Radiological Field Monitoring
ML20238D0151987-01-14014 January 1987
Rev 2 to QA Procedure QAP-010, QA Records
ML20114B7241986-09-20020 September 1986
Rev 5 to Technical Procedure RW-2-200, Packaging Radioactive Solid Waste (DAW) for Dispsosal
ML20206D4681986-06-16016 June 1986
Rev 2 to 10-Yr Inservice Insp Program
ML20151Z0521986-01-31031 January 1986
Rev 3 to CEN-39(A)-NP, CPC Protection Algorithm Software Change Procedure
ML20151Z0641986-01-31031 January 1986
Rev 0 to CEN-323-NP Reload Data Block Constant Installation Guidelines
1999-05-24
[Table view] |
Text
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1.0 INTRODUCTION
This procedure outlines specific requirements of the Customer and governing Code, as contractually established for additional work on a previously tested and code stamped Class MC Containment Vessel.
2.0 REFERENCES
2.1 Nuclear Quality Assurance Manual for Repairs and Alternations to ASME Code Stamped Components, Issue No. 4.
2.2 Nuclear Quality Assurance Manual (QAM) for ASME Section III Products, Issue No. 6.
2.3 1971 ASME Code,Section III, Division 1, Subsections NA & NE, with Su=mer 1971 Addenda. ,
2.4 ESASCO Design Specification No. LOU 1564.717.
2.5 71-2426 0.A. Handbook 2.6 National Board Rules l
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REPAIR PROCEDURE .Aac ~o. 2 or 3
'"0 DUCT NUCLEAR CONTAINMENT VESSEL
3.0 SCOPE
All work to be accomplished in accordance with the reference documents given in Para. 2.0.
3.1 Install 6'E roof cutout and Equipment Hatch Cover. ,
3.2 Remove miscellaneous temporary clips, bracket straps and lugs. ,
3.3 Provide permanent pads and clips as requ' ired by customer. .
4.0 PROCEDURE
4.1 Installation of 6'E roof cutouts (See Detailed Field Procedure for Detail C on Contract Dwg. 12).
, 4.1.1 Clean edges of cutout and opening by brushing or grinding.
4.1.2 Fit cutout in opening, gouge and weld in accordance with WPS-E7018/71-2426 and Special Procedure Instructions on approved contract Drawing .1.2.
(See GWPS-SMA for correction of wide gaps.)
4.1.3 100% radiograph the weld in accordance with RTP-71-2426-9B and approved contract drawings.
4.2 Installation of Equipment Hatch Cover. (See Detailed Field Procedure for Joint G on Contract Dwg. 26.)
4.2.1 Clean edges of Cover and Barrel by brushing or grinding.
4.2.2 Fit Cover to Barrel, gouge and weld in accordance with WPS-E7018/71-2'26 and Field Procedure Instruc-tions on approved contract drawing 26. .-
4.2.3 100% radiograph the weld in accordance with RTP-71-2426-9B and approved contract drawings.
4.3 Removal of miscellaneous clips, bracket straps, and lugs.
4.3.1 Gouge and remove.
-- 4.3.2 Grind remaining weld relatively smooth.
I secutiricatio" RP
$ a r v. no. 2 commacT 71-2426 REPAIR PROCEDURE
,,,,,,,,3 ,, 3 NUCLEAR CONTAINMENT VESSEL 4.3 Removal of Miscellaneous clips, bracket straps, and lugs (cont.)
4.3.3 Visually inspect per VIP-13.
4.3.4 If questionable indications are found by visual ex="ination, MT indications in accordance with MTP-(71-2426)-13B. #
4.3.5 Unacceptable indications may be' repaired by grinding (not to exceed .01 inches below thickness shown on contract drawings) or by welding.
- 4.3.6 After repairing by grinding or welding, MT ,
examine the completed repair in accordance with MTP-(71-2426)-13B 4.4 Provide permanent pads and clips as required by customer.
[> 4.4.1 Fabricate and install the pads and clips in accordance with approved contract drawings, the appropriate cus-tomer approved welding procedure (WPS-E7018/71-2426, WPS-E308L/71-2426 and/or WPS-E309A/71-2426), and the QA Manual.
)> 4.4.2 MT or PT all welds in accordance with MTP-(71-2426)-13B ,
or PTP-12B as specified on contract drawings.
5.O CLARIFICATION OF QAM REQUIREMENTS:
Authorized Inspection for the shop and field shall be provided by CBI. (Refer to Paragraph i.1 of the Repair and Alteration O. A. Manual) ,
6.0 DOCUMENTATION
6.1 Document the work in accordance with the OAM for the contract.
6.2 The " Manufacturer's Report of Welded Repairs" (Page 4 l of Repairs and Alterations Q.A. Manual) shall be provided in lieu of any ASME Data Reports described in QAM.'
6.3 A " Manufacturer's Report of Welded Repairs" may be provided to cover all repair work or several
" Manufacturer's Report's of Welded Repairs" may be provided to document individual or groups of repair work covered by this procedure.
l Sol 68 A REV JaN 77
