|
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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
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i 9903050328 990224 i PDR ADOCK 05000373 l P PM k
LaSaNo County Station Unit 2 Restart Plan REVISION 4
.Page1
! 1. PLAN PURPOSE ,
L I
- Revision 4 of the restart plan is being issued to reflect th'e review, oversight and approval process necessary to restart Unit 2. In addition to the verification of restart
! readiness, the review and affirmation process will focus on the station's capability to i
support safe dual unit operations. The process provided in this revision to the restart l.
. plan is comparable to that conducted for the restart of Unit 1, but incorporates the
. lessons learned and process enhancements noted during performance of the Unit 1 l restart. -
l
> 2. ROLES AND RESPONSIBILITIES l i'
LaSalle managers and supervisors are responsible for ensuring that Unit 2 is ready for l restart and is capable of supporting safe dual unit operations. There are restart-related j roles and responsibilities that will augment existing functions and warrant specific
- attention in this plan. In that light, the following discussion summarizes primary roles j and responsibilities of key management personnel involved in ensuring Unit 2 restart j readiness.
l
- 2.1. BWR Vice President and Site Vice President I
! The BWR Vice President is responsible for the day-to-day corporate oversight of all .
{ Comed BWRs, including LaSalle, and is also responsible for coordinating activities l 1 with the Site Vice President, LaSalle Station. The Site Vice President has overall I
responsibility for LaSalle Station, Units 1 and 2, and as a result, is accountable for i j successful implementation of the Unit 2 Restart Plan. l l l l- The Site Vice President, in conjuncbon with the BWR Vice President, is responsible for '
l recommending restart of LaSalle Unit 2 to the Chief Nuclear Officer (CNO). They will i
[ make this startup recommendation primarily based on the overall recommendation of j the Unit 2 Restart issue Review Committee (RIRC), and will certify to the CNO that l' LaSalle Unit 2 is ready for restart and that the station organization is capable of j supporting dual unit operations.
I 2.2. Station Manaaer i
l ,
The Station Manager maintains respons"oility for overall unit safe operation and shall j have control over those onsite activities necessary for safe operation and maintenance 1
of the plant. The Station Manager is responsible and accountable for ensuring that i
. 'LaSalle Unit 2 material condition and process / program readiness activities are 2
satisfactorily completed prior to certification to the Site Vice President that Unit 2 is
{ ready for restart and that the station is capable of supporting dual unit operations.
l
)
l js #
l I
- LaSalle County Ctation j Unit 2 Restart Plan
- REVISION 4 ,
1 . Page 2 j 1
i I
2.3. Restart issue Review Committee (RlRC) .
- The ' RlRC is a management review committee chaired by the Station Manager. l T - Members include the Operations Manager, Maintenance Manager, and Engineering )
l Manager. This Committee has primary responsibility for determining what activities are i required to be completed prior to restart, and to verify satisfactory implementation. The
- reviews are accomplished by the use of sub-committees,'each chaired by an RIRC j member. The sub-committee chair presents the results to the RlRC for approval.
The RIRC ensures that: (1) Unit 2 activities do not have an adverse impact on Unit 1; j (2) the Unit 2 startup activities will employ the same level of safety and rigor i implemented during the Unit i restart; and (3) that station personnel and hardware are
- capable of safely supporting dual unit operations. When it is determined by the RIRC l that all required restart activities have been satisfactorily implemented (along with
{ satisfaction of licensing and or other performance measures) the Station Manager, who :
j is the RIRC chairman, will provide his restart recommendation to the Site Vice j Presidtent. The Plant Operations Review Committee will continue to perform its j required functions in accordance with station procedures.
1.
I 2.4.- Nuclear Safety Review Board (NSRB)
[ The NSRB is an offsite committee that provides senior level oversight of the Comed :
< nuclear program with respect to nuclear safety. The NSRB consists of a number of
- external nuclear safety experts and Comed corporate and station senior management. .
l The NSRB provides an independent assessment of the Unit 2 restart readiness, I j . including the capability of the station to support dual unit operations. The NSRB will j provide the results of their assessment to the Chief Nuclear Officer,
[
4
- 3. Restart Proaram and Reauired Actions l Revision 3 of Rostart Program provided several key attributes including Restart issue Identification and Screening, Work Completion, Restart and Operational Readiness .
. - Evaluation, Restert Testing and Restart and Power Ascension. Each of these activities i i remain unchanged from Revision 3, therefore are not included in this revision of the i restart plan. For details related to these activities refer to the letter to the NRC, dated September 24,1908. l
]
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__ _ ___ _ ____c _ _____.___.___ _ _ _ ___ __ _- _ _ . -~ - -
LaSalle, County Station l Unit 2 Restart Plan l REVISION 4 )
Page 3 j
4.0 REVIEW, OVERSIGHT AND APPROVAL PROCESS 4.1 Site Review and Oversiaht Process ,
The RIRC will assess the plant readiness for restart, including the stations ability to safely conduct dual unit operations, and provide this input to the Station Manager. The Station Manager after being satisfied with restart readiness and the capability for the station to support dual unit operations, will recommend Unit 2 re' start to the Site Vice- ;
President. l Nuclear Oversight will perform an independent assessment of restart readiness and certify plant restart readiness to the Manager of Nuclear Oversight. The Manager of Nuclear Oversight will report the results of this review to the NSRB.
1 4.2 Nuclear Safety Review Board (NSRB) Assessrnent !
The NRSS will conduct an independent assessment of readiness to restart Unit 2. The scope and extent will be similar to that conducted for Unit 1 and will specifically i address the capability to support dual unit operations. The review will encompass the RIRC reviews, focusing on the system readiness and departmental readiness elements, and assessments conducted by Nuclear Oversight. Since the NRSB consists of a i I
number of external nuclear safety experts and Comed Corporate and station senior management the boards review will provide an outside perspective related to the restart readiness and the ability to support dual unit operations. The senior corporate !
- membership (Senior Vice President - Nuclear Generation Group, the BWR Vice President, the Nuclear Oversight Vice President, and the Vice President-Regulatory Services) will provide equally effective corporate oversight. The NSRB will provide the Chief Nuclear Officer (CNO) with a recommendation related to the restart readiness of Unit 2 and the capability of the station to safely conduct dual unit operations.
4.3 Chief Nuclear Officer (CNO) Restart Authorization When the Site Vice President, in conjunction with the BWR Vice President concludes that the plant is ready for restart, they will provide a recommendation for restart to the CNO. The CNO considers their recommendation along with the results of the independent assessment conducted by the NSRB to reach a conclusion regarding restart readiness. Once a determination has been made that restart is appropriate, the CNO and/or Site Vice President will inform the NRC of the intent to restart Unit 2.
4