|
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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
'
doirrm. Ms.-
( / /L f INSUKATION,INC. OMo PROCEDURE FOR: PROCEDURE NUMBER:
INSTALLATION OF INSULC0/HEMYC CABLE TRAY PROTECTION SYSTEM - CURVED SECTI0N 8400.102 PROCEDURE ISSUE
SUMMARY
ISSUE /DATE PREPARER APPROVED CO+ENTS A DRAFT #
11/15/82 R.L. Meadows K.R. Ha is Issued for Review and Comment
/ L.C. a e' -
( B ISSUE 11/29/82 R.L. Meadows N
K.R. Har is vVN Add Insulco Foreword; Revise 1.0 to define testing; Add ANI ref-erence to3.2; Revise 3.4; Add
" clamp" to 4.0; Revise 5.1, 5.2,
. . ri g 5.3, 5.4, 6.1, 6.2.1, 6.2.2, 6.2.3, 6.2.4, 6.2.5; Add 6.2.7; Revise 6.3.1, and 6.3.2.
Section 2.0 revised also.
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1 S302230353 830214 PDR ADOCK 07,000382 F PDR r- <f 5 06/01/82 superceces previcus P O. BOX 2531 . HOUSTON. TEXAS 77001 . (713) 688-8971
(
INStiLCO INSULCO INCORPORATED Novettber 1, 1982 FOREWORD This Procedure has been developed by B&B Insulation, Inc.,
an affiliate cowpany of INSULCO, INC. and is intended for use in the installation of the HEMYC CABLE TRAY PROTECTION SYSTEM into nuclear facilities.
( This Procedure may be utilized by an affiliate cortpany of INSULCO, INC. or by any organization granted written author-ization by INSULCO, INC. Refer to Section 5.4 within this Procedure for certification of the installed system requirements.
INSULCO, INCORPORATED
/sd L. Charles S 1, Quality Assurance Manager Post Office Box 2531 - Houston, Texas 77001 - 713-688-8971
- \*$ug 'O & D INSULATION, INC, N 8400.102 11/29/82 PNZ: 2 of 7 --
t B INSTALLATION PROCEDURE FOR INSULCO/HEMYC CABLE TRAY PROTECTION SYSTEM CURVED SECTION -
B 1.0 PURPOSE The purpose of this Procedure is to assure that the installation of the INSULC0/HEMYC Cable Tray Protection System is consistent with system as tested on the various qualification tests. The Fire Qualification Test, referenced as B&B CTP-1026, consisted of a One (1) Hour Fire Exposure, g per ASTM E-119 criteria, including hose stream test in accordance with g the AMERICAN NUCLEAR INSURERS Information Bulletin No. 5(79) entitled, o "ANI/MAERP STANDARD FIRE ENDURANCE TEST METHOD TO QUALIFY A PROTECTIVE 15 ENVELOPE FOR CLASS IE ELECTRICAL CIRCUITS".
W 5B 2.0 SCOPE This Procedure provides the methods and guidelines to be utilized for y the installation of INSULCO/HEMYC Cable Tray Protection systems.
A g
3.0 REFERENCES
.l Ef 3.1 10CFR50, Appendix R 10 E B 3.2 ANI Bulletin No. 5(79)
E g 3.3 HEMYC Test, CTP-1026
~
gB 3.4 B&B Installation Procedure No. 8400.101 g INSTALLATICN PROCEDURE FOR INSULCO/HEMYC CABLE TRAY PROTECTION SYSTEM o - STRAICHT SECTI0tts E
m 4.0 DEFINITIONS FLAT BRACKET - galvanized plate used to connect strut sections.
L-BRACKET - galvanized "L" shaped connection used to support and connect strut in areas where clamp is not needed or cannot be used.
B CLANP - stainless steel hose type clamp.
B 5.0 RESPONSIBILITY 5.1 The authorized installer's ENGINEERING DEPARTMENT shall be respon-sible to define the scope of work as preccribed on the applicable contract documents cnd provide the appropriate drawings, specifice-tions, requirements, instructions, etc. to the departnient respons2ble for installation.
This department shall also be recponcible to provide liason with ,
applicable client personnel and other internal departments to assure I smooth flow of ecmmunication. ]
For CC-5.1 N /01/P?
- B400.102
' p1 S]sug 'B & B INSULATION, INC, 11/29/82 PACE: 3 of 7
(.
5.2 The authorized insta11er's PRODUCTION DEPARTMENT shall be responsible for the identification and scheduling of work to be performed as defined on the documents furnished by ENGINEERING.
5.3 The authorized insta11er's PRODUCTION DEPARTMENT shall be responsible for the performance of installation activities herein prescribed.
5.4 INSULCO, INC. QUALITY ASSURANCE DEPARTMENT shall be responsible that appropr' me inspection, documentation and monitoring is provided as established in the applicable INSULCO and/or B&B Insulation Quality Control Procedures.
b The quality activities may be performed by the Quality Control i Department of any affiliate company of INSULCO, INC. or by any 0 organization granted written authorization by the INSULCO QUALITY
$ ASSURANCE DEPARTMENT utilizing the established INSULCD QC Procedures.
" If this is the case, INSULCO QA maintains the responsibility for b the QA/QC of the system installation and shall certify that the 0 installed system is consister. with the qualification tested system
@ design.
5
= 6.0 PROCEDURE F
(' @B O
6.1 For basic framework installation refer to B&B Procedure No. 8400.10:
INSTALLATION PROCEDURE FOR INSULCO/HEMYC CABLE TRAY PROTECTION SYSTEM - STRAICHT
$ SECTIONS.
E E 6.2 Horizontal Curves E
C B 6.2.1 A prototype framework may be developed for each cable tray
$ size and type. These will be used to establish the D; dimensions for fabrication of rails as required.
8 g B 6.2.2 Rail shall be assembled, using flat brackets, spring nuts, g bolts and 1cokwashers, as shown in Figure 1, to allow for curvature of rails.
B 6.2.3 Curved sections require adoitional supports as shown in Figure 2. Supports are attached as illustrated in Details 1 and 2 of Figure 2. Further support requirements, if any,
. will be determined by the Insta11er's Site Engineer.
B 6.2.4 Locking clamps shall be used in at leact one location on curved section. Rails shall extend onto adjoinino e ~
cable tray section and be securely attached using acw._,.
clamps. (Reference Ficure 2 and Finure 5). !
C 6.2.5 Studc that cannot be pre-stinen 1 ;c curved rail section, must be attached as shown in Figures 3 and 4.
6.2.6 Flat brackets riust be used to connect adjoining rail sections and curved rails to streight rn11c at intersections. Re ference Figurc 5, Detail /!1.
F0 00-5.1 rr,, m,
l 1gsysgUE B & B INSULATION, INC,
- B400 '02 11/29/82 Pts: 4 of 7 8 6.2.7 Additional supports or studs may be necessary as determined by the Insta11er's Site Engineer.
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- (lyug 'B & B INSULATION, INC.
- B400 102 11/29/82 PACE: 7 of 7-(
6.3 Vertical Curves B 6.3.1 Vertical curves, up or down, do not require cutting or welding. The rails are bent on a roller to a radius to be determined by Insta11er's Site Engineer.
B 6.3.2 Additional supports or studs may be necessary as determined by the Insta11er's Site Engineer.
6.3.3 Clamp installation and attachment are the same as for horizontal curves. (Reference Figure 5).
u E 6.4 Blanket Installation o
$ 6.4.1 Refer to Section 6.3 of B&B Procedure No. 8400.101 for blanket installation procedure.
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