|
|---|
Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20212F9221999-09-23023 September 1999
Rev 2.3 to Chapters 10,11,12 & App F of LaSalle Annex Odcm
ML20211L2871999-09-0202 September 1999
Revs to ODCM, for LaSalle Annex Including Rev 2.2 for Chapters 10,11,12 & App F
ML20210R3581999-08-13013 August 1999
Proposed Tech Specs Allowing Performance of CRDM & Ni Instrumentation Replacement to Not Be Considered Core Alterations During Operational Condition 5,Refueling,while Fuel Is in Reactor Vessel
ML20210Q4101999-08-0606 August 1999
Proposed Tech Specs Section 3/4.6.4, Vacuum Relief, Removing Specific Operability Requirements Related to Position Indication for Suppression chamber-drywell Vacuum Breakers & Revising Action Statements & Srs,Per NUREG-1433
ML20209G3581999-07-14014 July 1999
Proposed Tech Specs Pages Re Amend to Licenses NPF-11 & NPF-18,revising TS Allowing LCS Units 1 & 2 to Operate at Uprated Power Level of 3489 Mwt
ML20209D3231999-07-0707 July 1999
Proposed Tech Specs,Revising MCPR Safety Limits & Adding Approved Siemens Power Corp Methodology List of TRs for COLR
ML20209D3931999-07-0707 July 1999
Proposed Tech Specs,Changing Proposed Degraded Voltage Low Limit Setpoint & Adding High Limit Setpoint & Allowable Value
ML20206T1401999-05-19019 May 1999
Proposed Tech Specs Section 3/4.4.4, Chemistry, Relocating to UFSAR
ML20211C3311999-04-30030 April 1999
Rev 2.0 to Generic ODCM for Dresden,Quad Cities,Zion, Lasalle,Byron & Braidwood
ML20207A9491999-02-23023 February 1999
Rev 4 to LaSalle County Station Restart Plan for Unit 2
ML20195E0101998-11-0909 November 1998
Proposed Tech Specs Re Application for Amends to Licenses NPF-11 & NPF-18,adding Automatic Primary Containment Isolation on Ambient & Differential Temperature to High for RWCU Sys Pump,Pump Valve,Holdup Pipe & Filter/Demineralizer
ML20195E0541998-11-0909 November 1998
Proposed Tech Specs Pages Re Application for Amends to Licenses NPF-11 & NPF-18,to Modify Degraded Voltage Second Level Undervoltage Relay Setpoint & Allowable Value to TS 3/4.3.3 & TS Table 3.3.3-2
ML20154M4641998-10-16016 October 1998
Proposed Tech Specs,Lowering Power Level Below Which TCV & TSV Closure Scram Signals & EOC-RPT Signal Are Not in Effect
ML20151Y5991998-09-14014 September 1998
Rev 3 to LaSalle County Station Restart Plan, for Unit 2 Only
ML20236U5511998-07-24024 July 1998
NRC Manual Chapter 0350 Restart Action Plan,For LaSalle County Station
ML20217M6671998-05-0101 May 1998
Proposed Tech Specs Adding Ventilation Filter Testing Program
ML20217N9541998-04-30030 April 1998
Rev 1.9 to Chapter 10,rev 2 to Chapter 11 & Rev 1.9 to Chapter 12 of LaSalle Odcm
ML20217P2511998-04-28028 April 1998
Rev 2 to LaSalle County Station Unit 1/Unit 2 Restart Plan
ML20216E3221998-04-0707 April 1998
Proposed Tech Specs Pages Re Addition of Ventilation Filter Testing Program
ML20217J2981998-03-24024 March 1998
Proposed Tech Specs Deleting Unit 1 License Condition 2.C.(30)(a) in Entirety
ML20202C8971998-02-0202 February 1998
Proposed Tech Specs Re Changes to Relocate Fire Protection Requirements
ML20203G5051997-12-12012 December 1997
Proposed Tech Specs,Modifying Bypass Logic for Msli Valve Isolation Acuation Instrumentation on Condenser Low Vacuum
ML20199K5481997-11-24024 November 1997
Proposed Ts,Adding Automatic Primary Containment Isolation on Ambient & Differential Temp High for Rwcs Pump,Pump Valve,Holdup Pipe & F/D Valve Rooms & Eliminating RHR Sys Steam Condensing Mode Isolation Actuation Instrumentation
ML20211P9331997-10-15015 October 1997
Proposed Tech Specs Eliminating Unnecessary Detail from Accident Monitoring Instrumentation Surveillance Requirements
ML20217C3771997-09-26026 September 1997
Proposed Tech Specs Adding Ventilation Filter Testing Program
ML20216H7711997-09-0404 September 1997
Corrected TS Bases Sections B 3/4.2.1 & B 3/4.2.3 Re Thermal Limits
ML20216C6381997-08-29029 August 1997
Proposed Tech Specs,Incorporating New Siemens' Methodologies That Will Enhance Operational Flexibility & Reducing Likelihood of Future Plant Derates
ML20217Q7981997-08-26026 August 1997
Rev 1a to LaSalle County Station Unit 1/Unit 2 Restart Plan
ML20141J5671997-08-12012 August 1997
Proposed Tech Specs Surveillance Requirement 4.7.1.3.c Re Ultimate Heat Sink by Deletion of Sediment Deposition Insp in Lake Screen House
ML20151K9551997-08-0101 August 1997
Proposed Tech Specs Changing Title of Site Quality Verification Director to Manager of Quality & Safety Assessment
ML20148U2591997-07-0101 July 1997
Proposed Tech Specs to Change Definition of Channel Calibration & Correcting Miscellaneous Errors in TS & Bases. TS Affected Are TS Definition 1.4,TS Tables 3/4.3.2-1 & 3/4.3.6-1 & Bases for TS 3/4.3.1
ML20148Q4301997-07-0101 July 1997
Proposed Tech Specs Reflecting Improvements Made to Control Room Ventilation Air Intake Radiation Monitoring Sys Logic to Reduce Spurious Actuation of Emergency Filtration Mode of Operation & Unnecessary Challenges to ESF
ML20148N0201997-06-19019 June 1997
Proposed Tech Specs,Relocating Fire Protection Requirements
ML20141L0371997-05-27027 May 1997
Proposed Tech Specs,Incorporating Restructured Station Organization,Change to Submittal Frequency of Radiological Effluent Release Rept & Other Administrative Changes
ML20148D9561997-05-16016 May 1997
LSCS Unit 1/Unit 2 Restart Plan
ML20137W5131997-04-14014 April 1997
Proposed Tech Specs Re Feedwater/Main Turbine Trip Sys Actuation Instrumentation Design Change
ML20140C9231997-03-31031 March 1997
Rev 1.9 to Chapter 11, Radiological Environ Monitoring Program & LaSalle Annex Index
ML20216H8691997-03-31031 March 1997
Revs to OCDM for LaSalle Station,Including Rev 1.8 to Chapter 10,rev 1.9 to Chapter 11,rev 1.8 to Chapter 12 & Rev 1.7 to App F
ML20134A1931997-01-20020 January 1997
Proposed Tech Specs 3/4.1.3.5 Re Control Rod Scram accumulators,3/4.4.4.3.2 Re Reactor Coolant Sys Operational leakage,3/4.5.1 Re ECCS - operating,3/4.5.3 Re ECCS, Suppression Chamber & 3/4.6.2.1 Re Suppression Chamber
ML20135E6841996-12-0202 December 1996
Proposed Tech Specs,Requesting Amend to Section 3.4.2 to Revise SRV Configuration to Include Only 13 of Current 18 SRVs
ML20134L0221996-11-30030 November 1996
Rev 1.8 to ODCM, Annex,Chapters 10,11 & 12
ML20129J4491996-10-31031 October 1996
Proposed Tech Specs Re Elimination of Seismic Monitoring Instrumentation Requirements
ML20129B7981996-10-14014 October 1996
Proposed Tech Specs 2.1.2 Re Thermal Power,High Pressure & High flow,5.3 Re Reactor core,4.0 Re Design features,3/4.1.3 Re Control Rods & 3/4.2.4 Re Linear Heat Generation Rate
ML20116A9601996-07-15015 July 1996
Proposed Tech Specs Re Revision of App A,Ts for Licenses NPF-11 & NPF-18,relocating Fire Protection Requirements of Listed TS Sections
ML20115D8781996-07-0808 July 1996
Cycle 8 Startup Test Rept
ML20113C8641996-06-21021 June 1996
Proposed Tech Specs,Including Extension of 18 Month Surveillance Interval & One Time Change to TS to Extend AOT for Each Subsystem of CR & Auxiliary Electric Equipment Room Emergency Filtration Sys
ML20107F0641996-04-16016 April 1996
Proposed Tech Specs,Eliminating Selected Response Time Testing Requirements
ML20107A8641996-04-0808 April 1996
Proposed Tech Specs for Siemens Power Corp Fuel Transition
ML20097C9051996-02-0202 February 1996
Rev 1 to ISI Plan for Comm Ed LaSalle County Station Units 1 & 2 Second Ten-Yr Interval Insp Program
ML20096G3411996-01-18018 January 1996
Proposed Tech Specs,Changing Setpoints for Automatic Primary Containment Isolation on MSL Tunnel Differential Temp High & Deleting Automatic Isolation Function on MSL Tunnel Temp High
1999-09-23
[Table view]
Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20212F9221999-09-23023 September 1999
Rev 2.3 to Chapters 10,11,12 & App F of LaSalle Annex Odcm
ML20211L2871999-09-0202 September 1999
Revs to ODCM, for LaSalle Annex Including Rev 2.2 for Chapters 10,11,12 & App F
ML20211C3311999-04-30030 April 1999
Rev 2.0 to Generic ODCM for Dresden,Quad Cities,Zion, Lasalle,Byron & Braidwood
ML20207A9491999-02-23023 February 1999
Rev 4 to LaSalle County Station Restart Plan for Unit 2
ML20151Y5991998-09-14014 September 1998
Rev 3 to LaSalle County Station Restart Plan, for Unit 2 Only
ML20236U5511998-07-24024 July 1998
NRC Manual Chapter 0350 Restart Action Plan,For LaSalle County Station
ML20217N9541998-04-30030 April 1998
Rev 1.9 to Chapter 10,rev 2 to Chapter 11 & Rev 1.9 to Chapter 12 of LaSalle Odcm
ML20217P2511998-04-28028 April 1998
Rev 2 to LaSalle County Station Unit 1/Unit 2 Restart Plan
ML20217Q7981997-08-26026 August 1997
Rev 1a to LaSalle County Station Unit 1/Unit 2 Restart Plan
ML20148D9561997-05-16016 May 1997
LSCS Unit 1/Unit 2 Restart Plan
ML20216H8691997-03-31031 March 1997
Revs to OCDM for LaSalle Station,Including Rev 1.8 to Chapter 10,rev 1.9 to Chapter 11,rev 1.8 to Chapter 12 & Rev 1.7 to App F
ML20140C9231997-03-31031 March 1997
Rev 1.9 to Chapter 11, Radiological Environ Monitoring Program & LaSalle Annex Index
ML20134L0221996-11-30030 November 1996
Rev 1.8 to ODCM, Annex,Chapters 10,11 & 12
ML20097C9051996-02-0202 February 1996
Rev 1 to ISI Plan for Comm Ed LaSalle County Station Units 1 & 2 Second Ten-Yr Interval Insp Program
ML20095F4041995-12-0202 December 1995
Rev 1 to Procedure LZP-1250-1, A-Model Operation
ML20093H1791995-10-10010 October 1995
Rev 1 to Pump & Valve Inservice Testing Program Plan,2nd Ten Year Interval for LaSalle County Station Units 1 & 2
ML20094D9271995-09-30030 September 1995
Rev 1.7 to ODCM Chapters 10,11,12 & App F for LaSalle Station
ML20077Q5601994-12-30030 December 1994
Offsite Dose Calculation Manual Revisions to Chapters 10-12 & Appendix F for Lasalle Station
ML20149G2551994-10-17017 October 1994
Rev 0 to ISI Plan for LaSalle County Nuclear Station Units 1 & 2 Second Ten-Year ISI Interval
ML20149G2591994-10-17017 October 1994
Rev 0 to LaSalle County Station Units 1 & 2 Pump & Valve IST Program Plan 2nd Ten-Yr Interval
ML20065G5401994-03-23023 March 1994
Rev 1 to Test Procedure TR-213, One Hour Fire Test of Darmatt KM1 Sys for Protecting Cable Tray,Conduit,Supports & Junction Boxes in LaSalle Nuclear Power Station Units 1 & 2 DG Corridors
ML20063F8921994-01-31031 January 1994
Rev 1.0 to Chapters 10,11,12 & App F to Odcm,Lasalle County Station
ML20059M9671993-10-27027 October 1993
Rev 1 to LZP-1130-2, Core Damage Assessment
ML20045B5921993-05-28028 May 1993
Rev 1 to Procedure LZP-1210-4, Reporting of Transportation Accident.
ML20127D0691992-12-30030 December 1992
Corporate Emergency Response Organization Required Reading Package 92-11
ML20114C7321992-08-20020 August 1992
Revised Annex to Chapter 11 to ODCM Re Exposure Pathway &/Or Sample
ML20101M3611992-06-25025 June 1992
Offsite Procedures,Including Rev 16 to LZP-1110-01,Rev 2 to LZP-1110-2,Rev 4 to LZP-1120-2,Rev 4 to LZP-1210,Rev 0 to LZP-1210-3 & Rev 0 to LZP-1210-4
ML20079C0351991-05-0303 May 1991
Rev 2 to Procedure LZP-1330-30, Transfer of Wastes from Hrss Waste Tank & Waste Sump
ML20043G4791990-05-18018 May 1990
Offsite Procedures,Including Rev 1 to LZP-1330-12,Rev 2 to LPZ-1330-13,Rev 1 to LZP-1330-14 & Rev 6 to LPZ-1330-14
ML19327A7521989-08-16016 August 1989
Rev 2 to Combined Units 1 & 2 Inservice Testing Program for Pumps & Valves.
ML20245L7651989-08-0707 August 1989
Rev 0 to Offsite Dose Calculation Manual
ML20236G5971987-07-0101 July 1987
Rev 0 to Units 1 & 2 Combined Inservice Testing Program for Pumps & Valves,Lasalle County Station,Comm Ed
ML20212B2791986-07-28028 July 1986
Revised Std Radiological Monitoring Program,Lasalle County Station
ML20214P6431986-06-18018 June 1986
Rev 1 to Procedure 8601-009, Model 103 Long-Term Test Plan
ML20205F5721986-05-31031 May 1986
Rev 12 to Offsite Dose Calculation Manual List of Tables for La Salle Section 8.0
ML20203L3551986-04-30030 April 1986
Rev 0 to Comm Ed Training Program Description for Station Control Room Engineer/Shift Technical Advisor
ML20155F4541986-04-18018 April 1986
Snubber Reduction Program for Nuclear Piping Sys,Lasalle County Nuclear Station Units 1 & 2
ML20138Q1261985-11-30030 November 1985
Rev 11 to site-specific Sections 7.2 & 8.0 to Offsite Dose Calculations Manual
ML20138B2711985-11-22022 November 1985
Rev 0 to LaSalle Station Proactive Mgt Plan
ML20116C9751985-04-0909 April 1985
NUREG-0737,Suppl 1,Detailed Control Room Design Review Program Plan Suppl 3
ML20127J3041985-03-11011 March 1985
Rev 0 to LAP-100-15, Control of Vendor Equipment Technical Info
ML20086J8191984-10-17017 October 1984
Public Version of Revised Emergency Plan Implementing Procedures,Including Procedures LZP-1200-5 Re Generating Station Emergency Procedure Guidelines for Offsite Protective Actions & LZP-1310-1 Re Notifications
ML20087J2501984-03-15015 March 1984
Rev 0 to Procedure LTS-1000-35, Fire Damper Operability Test
ML20087H1501984-03-0505 March 1984
Rev 1 to Procedure LTS-1000-36, Fire Damper Visual Insp
ML20079L7441983-12-29029 December 1983
Public Version of Rev 3 to Emergency Plan Implementing Procedure LZP-1210-1, Hazardous Matl Incidents Reporting
ML20079P0331983-11-21021 November 1983
Public Version of Revised Emergency Procedures LZP-1330-21, Determination of Reactor Coolant Chloride... Sampling Sys & LZP-1330-25, Sampling of Reactor Coolant at High Radiation Sample Sys
ML20083H8761983-11-17017 November 1983
Public Version of Rev 2 to Emergency Plan Implementing Procedure LZP-1360-2, Use of Potassium Iodide (Ki) as Thyroid Blocking Agent & Revised Index
ML20083G5071983-11-0404 November 1983
Public Version of Rev 2 to Emergency Plan Implementing Procedure LZP-1200-4, Classification of Liquid Release. Revised Index Encl
ML20090L6481983-10-31031 October 1983
Rev 6 to Procedure Lts 300-4, Unit 1/2 Integrated Primary Containment Leak Rate Test
ML20085K4251983-10-0303 October 1983
Public Version of Rev 5 to Emergency Plan Implementing Procedure LZP-1110-1, Station Director (Acting Station Director),Receipt Form & 10CFR50.59 Format for Safety Evaluation
1999-09-23
[Table view] |
Text
..
+ J, n b
"', 2 ^
Page 1 of 6 Commonwealth Edison r~N U
@ LaSalle County Nuclear Stauon Unit I AUGHENTED INSERVICE INSPECTIONS 7',,
' o Augmented Inservice Inspections (AISI) are not ASME Section XI Code requirements but are 1) additional examination area requirements, or 2) increased inspection frequency requirements or combinations of both which are requested by the Nuclear Regulatory Commission. When components fall into the scheduled testing of both ISI and AISI, credit for both requirements is taken (no double testing).
There are presently 4 types of Augmented Inservice Inspections required at LaSalle County Nuclear Stations:
Type Description 1A The ASME Category B-F and B-J welds of the high energy line break exclusion regions as identified in the FSAR and requested by the NRC.
See response to FSAR Q111.72.
O IB Examinations of the Feedwater Nozzle Inner Radli, Nozzles Bores, O Nozzle Safe Ends, and Spargers, as requested by the NRC in NUREG-0619.
1C Examinations of the High and Low Pressure Core Spray Spargers and the associated piping inside the RPV each refueling outage, as requested by the NRC in IE Bulletin No. 80-13, 2A Examinations of the Reactor Core Isol.ation Coolant lines that are exempted by ASME Section XI, IWC-1220(b), but are examined due to the NRC requesting this system be treated as an essential system.
l l
i
(
1 Ov 1 ~ " ~
l '~ 8211090305 '821103 '
PDR ADOCK 05000373 l l
O PDR
CommonwealthEdison Page 2 of 6 LaSalle County Nuclear Station Unit 1 k) Augmented Inservice Inspection Type 1A The following ASME Category B-F and B-J welds receive 100% volumetric examination each inspection interval, except as noted. Those welds marked by asterisk (s) receive alternate examinations as follows:
- See RI-05 for alternate examination.
- See RI-11 for alternate examination.
For further information on a component, such as configuration, material, cal.
std., etc., see Tab 11 "ASME Category B-F", or Tab 15 "ASME Category B-J".
Feedwater Low Pressure Core Spray Main Steam IFW-1001-10 ILP-1001-2 IMS-1054-18 IFW-1001-10LD ILP-1001-2A IMS-1054-18LD IFW-1001-13 ILP-1001-8 IMS-1054-19*
IFW-1001-13LD ILP-1001-9 IMS-1054-19LU*
IFW-1001-13LU ILP-1001-12 IMS-1054-21 IFW-1001-16 ILP-1001-14 IMS-1054-21LD IFW-1001-16LU ILP-1001-15 IMS-1054-26 IFW-1001-18* ILP-1001-16 IMS-1054-25LU IFW-1001-18LD* ILP-1001-17 IFW-1001-20 ILP-1001-18 IMS-0014A-13 IFW-1001-20LU ILP-1001-19 IMS-0014A-14 ILP-1001-21
(])
IFW-1002-10 Main Steam Residual Heat Removal IFW-1002-10LD IFW-1002-12 IMS-1051-15 IRH-1001-2 IFW-1002-12LD IMS-1051-15LD IRH-1001-7 IFW-1002-12LU IMS-1051-16* IRH-1001-10 IFW-1002-15 IMS-1051-16Ll? IRH-1001-12 IFW-1002-15LU IMS-1051-18 IRH-1001-13 IFW-1002-17* IMS-1051-18LD IRH-1001-14 IFW-1002-17LD* IMS-1051-26 IRH-1001-17 IFW-1002-20 IMS-1051-26LU IRH-1001-18 IFW-1002-20LU IRH-1001-19 IMS-1052-17 IRH-1001-20 High Pressure Core Spray IMS-1052-17LD IRH-1001-21 IMS-1052-18* IRH-1001-24 IHf-1001-2 IMS-1052-18LU*
IHP-1001-8 IMS-1052-20 IRH-1002-2 IHP-1001-10 IMS-1052-22LD IRH-1002-5 IHP-1001-13 IMS-1052-28 IRH-1002-6 IHP-1001-15 IMS-1052-26LU IRH-1002-12 IHP-1001-16 IRH-1002-14 IHP-1001-17 IMS-1053-15 IRH-1002-15 IHP-1001-19 IMS-1053-15LD IRH-1002-19 IHP-1001-20 IMS-1053-16* IRH-1002-20 IHP-1001-21 IMS-1053-16LU* IRH-1002-22
(~/)
N_ rHP-1001-22 IMS-1053-18 IRH-1002-23 IHP-1001-28 IMS-1053-19LO IMS-1053-26 IMS-1053-26LU
Commonwealth Edison Page 3 of 6
(~')
\/
@ LaSalle County Nuclear Station Unit 1 Augmented Inservice Inspection Type 1A (Cont'd)
Residual Heat Residual Heat Reactor Core Removal (Cont'd) Removal (Cont'd) Isolation Coolant IRH-1003-2 IRH-1031-20ALD IRI-1002-1 IRH-1003-9 IRH-1031-20BLD IRI-1002-3 IRH-1003-10 IRH-1031-25 IRI-1002-4 IRH-1003-12 IRH-1031-25ALU IRI-1002-5 IRH-1003-13 IRH-1031-25BLU IRI-1002-6 IRH-1003-15 IRH-1031-27 IRI-1002-8 IRH-1003-16 IRH-1031-29 IRI-1002-9 IRH-1003-19 IRH-1031-31 IRH-1003-20 IRH-1031-31ALD IRI-1003-9 IRH-1003-21 IRH-1031-31BLD IRI-1003-10 IRH-1003-22 IRH-1031-32 IRI-1003-11 IRH-1003-24' IRH-1031-32ALU IRI-1003-13C IRH-1003-26 IRH-1031-32BLU IRI-1003-14 IRH-1031-40 IRI-1003-15 IRH-1004-2 IRH-1031-43 IRI-1003-17 IRH-1004-3 IRI-1003-18 IRH-1004-9 Reactor Core IRI-1003-19 IRH-1004-11 Isolation Coolant IRI-1003-20 IRH-1004-12 IRI-1003-22 fs IRH-1004-16 IRI-1001-1 IRI-1003-23
!s ,) IRH-1004-17 IRI-1001-2 IRI-1003-24 IRH-1004-19 IRI-1001-3 IRI-1003-25 IRH-1004-20 IRI-1001-4 IRI-1003-27 IRI-1001-5 IRI-1003-28 IRH-1005-2 IRI-1001-6 IRI-1003-29 IRH-1005-8 IRI-1001-7 IRI-1003-30 IRH-1005-10 IRI-1001-7A IRI-1003-31 IRH-1005-13 IRI-1001-8 IRI-1003-32 IRH-1005-15 IRI-1001-9 IRH-1005-16 IRI-1001-9A** Reactor Water Clean-Up IRH-1005-17 IRI-1001-15 IRH-1005-18 IRI-1001-16 IRT-1001-24 IRH-1005-20 IRI-1001-16A IRT-1001-25 IRI-1001-18 IRT-1001-26 IRH-1031-9 IRI-1001-19 IRT-1001-27 IRH-1031-12 IRI-1001-20 IRT-1001-28 IRH-1031-12ALD IRI-1001-21 IRT-1001-29 IRH-1031-12BLO IRI-1001-24 IRT-1001-30 IRH-1031-17 IRI-1001-25 IRT-1001-31 IRH-1031-17ALU IRI-1001-26 IRT-1001-32 IRH-1031-178LU IRI-1001-27 IRT-1001-33 IRH-1031-20 IRI-1001-28 IRT-1001-37 IRT-1001-38 v
l l
CommonwealthEdison Page 4 of 6 I
@ LaSaHe County Nuclear Station Unit 1 Augmented Inservice Inspection Type 18 The feedwater components listed in Table 1 receive examination per Section 4.3.2.3 of NUREG-0619 and Table 2. As required by Section 4.4.3.1 of NUREG-0619, within 6 months of completing an outage at which an inspection was performed in accordance with Table 2, the licensee must submit a detailed report discussing the inspection (s) performed. Information required includes:
(a) Number of startup/ shutdown cycles since the previous inspection, and the total number of cycles. This will include cycles accumulated during the initial startup and testing of the plant.
(b) Summary of methods used and results of previous inspections, including maximum crack depth and number of cracks found in previous PT-and-grind operations, and number of startup/ shutdown cylces between such inspections.
(c) Description of any additional system changes or changes in operating procedures that will affect feedwater flow or temperature and that should be considered in predicting future cracking tendencies based on past history.
(d) A detailed discussion of the inspection results, including a complete description of cracking location, dimensions, and profile, if cracking
(]. was found. Drawings and photographs, if available, are requested.
(e) Information regarding the results of leakage monitoring. However, the staff must be informed imediately if on-line leakage monitoring during operation discloses any leakage on welded spargers or leakage on the order of 0.3 gpm through single-sleeve / single-piston-ring spargers or triple-sleeve spargers.
(f) Information regarding all UT crack-like indications and any subsequent PT indications. Information regarding UT techniques should be as precise and as extensive as possible in order that it may be of benefit in future inspections.
(g) The above information is to be submitted to the Regional Director, IE, with copies to Director, IE, and Director, NRR.
(vD
e CommonwealthEdison Page 5 of 6 V'
@ LaSalle County Nuclear Station Unit 1 Table 1 Components Receiving Examination
_ Exam./ Component I.D. No. For Further Information See:
1 - NIR - 4A (and Nozzle Bore) Tab 9 "ASME Category B-D" 1 - NIR - 4B (and Nozzle Bore) Tab 9 "ASME Category B-D" 1 - NIR - 4C (and Nozzle Bore) Tab 9 "ASME Category B-D" 1 - NIR - 4D (and Nozzle Bore) Tab 9 "ASME Category B-D" 1 - NIR - 4E (and Nozzle Bore) Tab 9 "ASME Category B-D" 1 - NIR - 4F (and Nozzle Bore) Tab 9 "ASME Category B-D" 1 - Feedwater Spargers Tab 21 "ASME Category B-N-1" IFW-1001-71A Tab 11 "ASME Category B-F" IFW-1001-81A Tab 11 "ASME Category B-F" IFW-1001-89A Tab 11 "ASME Category B-F" IFW-1002-53A Tab 11 "ASME Category B-F" IFW-1002-63A Tab 11 "ASME Category B-F" IFW-1002-72A Tab 11 "ASME Category B-F" 1Further information such as: examination type, material specification, calibration standard, etc.
Table 2 c Routine Inspection Intervals Inspection Interval-Refueling Cycles (or Startup/ shutdown Cycles)
Visual Inspection Configuration UT of Sparger l Routine PT2 ,3 Triple-sleeve spargers 2 4 9 (or 135) with two piston-ring seals, clad removed.
1 Visual inspection of flow holes and welds in sparger arms and sparger tees.
2 To be performed even if the UT and leak test results are satisf actory.
3 The routine PT consists of removal of a sparger from one nozzle followed by flapper wheel grinding of the nozzle and PT examination of both the nozzle and the accessible portions of the other feedwater nozzles.
4The UT examination consists of external UT examination of all feedwater nozzle safe ends, nozzles bores, and nozzle blend radii.
S If UT recordable indications are interpreted to be cracks in any nozzle (s),
{s~} remove the sparger(s) from the nozzle (s), perform PT examination on the nozzle bore and nozzle blend radius, and repair. Also, perform PT examination on the accessible portions of the remaining nozzles.
1 CommonwealthEdison Page 6 of 6 ry b'
@ LaSalle County Nuclear Station Unit 1 Augmented Inservice Inspection Type IC Visual examination of the High and Low Pressure Core Spray Spargers and the associated piping inside the RPV is performed each refueling outage, as requested by the NRC in IE Bulletin No. 80-13. The visual examination is performed using LaSalle County Station Procedure LTS 600-8.
Augmented Inservice Inspection Type 2A The components of the Reactor Core Isolation Coolant piping lines listed in Table 3 are exempt from examination by ASME Section XI, IWC-1220(b). Due to the NRC requesting this system be treated as an essential system, the components are scheduled for examination using ASME Section XI selection criteria. For further information, see Tab 5 " Component and Piping Line Number Table: CPLN". The type and number of components requiring examination are listed in the CPLN.
Table 3 RCIC System AISI Piping Lines 1RIO2A 1RIO2B 1RIO2C
- 1RIl2A L, IRI16A 1RI16B 1RI17A 1RI24A 1RI408 1RI43B O
.. . ]
CommonwealthEdison jE <f ' --
LaSalle County Nuclear Station Unit 1 O @
NDE PROCEDURES The NDE procedures used to perform the Inservice Inspection examinations are listed in Table 1. The NDE procedures are contained in the LaSalle County Station Inservice Inspection Nondestructive Examination Procedures Manual and are available for review at the LaSalle County Station.
O The NDe procedures ere written in eccordence ith the aSxE 80iier end eressure Vessel Cod _e,1980 Edition thru Winter 1980 Addenda. The ISI examinations are performed tising the revision of the NDE procedure in effect at the time of the examination, n
U
}
CommonwealthEdison m
@ LaSailo County Nuclear Stauon Unit 1 TABLE 1 NDE Procedure No. Title APUN-W801 Automated Ultrasonic Testing of Nozzle to Vessel Welds APUV-W801 Automated Ultrasonic Testing of RPV Welds and Base Material MPUB-W801 Ultrasonic Inspection of Pressure Retaining Greater Than Two Inches in Diameter MPUD-W801 Manual UT Examination of Full Penetration Piping Welds (Half-Vee Technique)
MPUL-W801 Manual UT Examination of Flange Ligaments MPUP-W801 Manual UT Examination of Full Penetration Piping Welds MPURHX-W801 Manual Ultrasonic Testing of RHR Heat Exchanger Welds O
k> MPUV-W801 Manual Ultrasonic Testing of RPV Welds NIRRHX-W801 Ultrasonic Examination of RHR Heat Exchanger Nozzle Inner Radius NIRZ1-W801 Procedure for Nozzle Inner Radius Zone 1 Ult.rasonic Examination NIRZ2-W801 Procedure for Nozzle Inner Radius Zone 2 Ultrasonic Examination NIRZ2-N9-W801 Ultrasonic Examination for Nozzle Inner i Radius Zone 2 on LaSalle Unit 1 Jet Pump l Instrumentation Nozzles PP-W801 Liquid Penetrant Examination of Nuclear Power Plant Components PV1-W801 Visual Examination VT-1 !
l PV2-W801 Visual Examination VT-2 j PV3-W801 Visual Examination VT-3 s PV4-W801 Visual Examination VT-4 l
1 l
1
J MS6 War 9xsjxdis f htu Se/if
!$Mef//
