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Category:MEETING MINUTES & NOTES--CORRESPONDENCE
MONTHYEARML20217M5371999-10-25025 October 1999
Summary of 990901 Meeting with Licensee in Rockville,Md Re Util Planned Conversion to Improved Sts.Attendance List & Agenda Encl
ML20211N2141999-09-0808 September 1999
Summary of 990720 Meeting with Util in Rockville MD Re Amend Currently Under Review by Staff Pertaining to Control Room Habitability at Plant Units 1 & 2.List for Attendees & Licensee Handouts Encl
ML20206Q6411999-05-12012 May 1999
Summary of 990426 Meeting with Util at NRC Headquarters Re Proposed Submittal of Amend to Implement Ists.List of Meeting Participants & Matls Presented by Licensee Encl
ML20196F6101998-12-0101 December 1998
Summary of 981029 Meeting with Northern States Power, Wisconsin Electric,Wisconsin Public Service & Alliant-IES in Rockville,Md Re Various Aspects of Potential Regulatory Issues Associated with Ongoing Cooperative Efforts
ML20210H3881997-08-0808 August 1997
Summary of 970805 Meeting W/Wepc & W in Rockville,Md to Discuss Plans to Submit Two TS Change Requests That Will Address 422V Fuel & Proposed Schedule for Review.List of Attendees & Licensee Presentation Encl
ML20135F7891997-03-0303 March 1997
Summary of 970224 Meeting W/Wisconsin Electric Power Co & Gls Enterprises,Inc in Rockville,Md Re Environ Qualified Equipment Inside Containment to Perform Function Following loss-of-coolant Accident Affected by Revised Profiles
ML20058B0031993-11-10010 November 1993
Summary of 931103 Meeting W/Util in Rockville Re Emergency Diesel Generator Addition Project.Attendance List,Discussion on Proposed Review Schedule & Licensee Summary of Emergency Diesel Generator Project Encl
ML20059B1201993-10-21021 October 1993
Summary of 931014 Meeting W/Util in Rockville,Md Re RCS Flow TS Change.List of Meeting Attendees & Handouts Encl
ML20149D6051993-09-15015 September 1993
Summary of 930708 Region III Annual Training Managers Conference in Glen Ellyn,Il.Purpose of Meeting to Provide Forum for Discussion on Rev 7 of Operator Licensing Examiner Stds & to Discuss Operator Licensing Issues
ML20056F8591993-08-16016 August 1993
Summary of 930727 Meeting W/Util in Rockville,Md Re Outstanding Licensing Issues.List of Participants Encl
ML20059P0041990-10-12012 October 1990
Summary of 900905 Meeting W/Util in Rockville,Md Re Plans for Upgrading Onsite Emergency Power Capabilities
ML20153G5481988-05-0404 May 1988
Summary of 880427 Telcon W/Utils in Region III Re Personnel Changes,Follow Up on Previous Items,Items of Interest from Sites & New Items
ML20154G9921988-04-26026 April 1988
Summary of 880331 Meeting W/Sandia Natl Lab,Numarc,Epri, Saic,Util,Westinghouse & ERC Intl Re Differences Between Industry Sponsored Analysis & Earlier Analysis of Same Plant Sponsored by NRC
ML20149K7541988-02-10010 February 1988
Summary of 880204 Meeting in Rockville,Md to Discuss Licensee Accident Reanalysis to Support Increased Allowable Core Peaking Factors at Facilities.Slides Used During Presentation & List of Meeting Attendees Encl
ML20237A9931987-12-0303 December 1987
Summary of 871104 Meeting W/Westinghouse & Utils in Bethesda,Md Re Susceptability of Facility Steam Generators to High Cycle Fatigue.Attendance List & Nonproprietary Westinghouse Handouts Encl
ML20237L1111987-08-28028 August 1987
Summary of Operating Reactors Events Meeting 87-28 on 870825 Re Events Which Occurred Since 870818 Meeting.List of Attendees & Significant Elements Encl
ML20215C8721987-06-0808 June 1987
Summary of Operating Reactors Events Meeting 87-10 on 870406 Re Events Which Occurred Since 870330 Meeting.List of Attendees,Events Discussed & Significant Elements of Events & Summary of Reactor Scrams & Significant Events Encl
ML20214W1621987-06-0505 June 1987
Summary of 870530 Meeting W/Util in Bethesda,Md Re Licensee Assessment of Flaw Indication Observed in Reactor Vessel nozzle-to-shell Weld for Safety Injection Sys.Attendees List Encl
ML20215D0631986-12-11011 December 1986
Summary of Operating Reactor Events Meeting 86-42 on 861201. List of Attendees & Viewgraphs Re Significant Elements of Events Discussed Encl
ML20215C9961986-12-11011 December 1986
Summary of Operating Reactor Events Meeting 86-41 on 861124.List of Attendees,Events Discussed & Significant Event Elements & Summary of Events That Will Be Input to NRC Performance Indicator Program Encl
NUREG-0518, Summary of ACRS 316th Meeting on 860807-09 in Washington,Dc Re Proposed Standardization Policy Statement & Review of Issues Related to Reorganization of TVA Mgt Structure & Shutdown of TVA Nuclear Power Plants1986-08-18018 August 1986
Summary of ACRS 316th Meeting on 860807-09 in Washington,Dc Re Proposed Standardization Policy Statement & Review of Issues Related to Reorganization of TVA Mgt Structure & Shutdown of TVA Nuclear Power Plants
ML20211G7781986-06-13013 June 1986
Summary of Operating Reactor Events Meeting 86-19 on 860609. List of Attendees,Events Discussed & Status of Previous Assignments Encl
ML20197F7721986-05-0808 May 1986
Summary of Operating Reactors Events Meeting 86-15 on 860505.List of Attendees,Events Discussed & Status of Previous Assignments Encl
ML20138N9841985-12-19019 December 1985
Summary of 851122 Meeting W/Licensees & Westinghouse to Present Status of Program for Developing New Upper Plenum Injection Evaluation Model.Nonproprietary Viewgraphs,List of Attendees & Agenda Encl
ML20137X5091985-11-29029 November 1985
Summary of Operator Reactor Events Meeting 85-24 on 851125 Re Briefing of Ofc Directors & Div Directors & Representatives on Events Which Occurred Since Last Meeting on 851118.List of Attendees Encl
ML20138P0081985-10-21021 October 1985
Summary of Operating Reactors Events Meeting 85-19 on 851007 W/Ofc Directors,Div Directors & Representatives on Events Which Occurred Since Last Meeting on 851007
ML20133F9941985-10-0707 October 1985
Summary of Operating Reactors Events Meeting 85-16 on 850916 Re Briefing of Director,Div Directors & Representatives on Events Occurring Since 850909 Meeting.List of Attendees & Viewgraphs Encl
ML20141E5521985-09-26026 September 1985
Summary of ACRS Subcommittee on Reactor Operations 850910 Meeting in Washington,Dc to Discuss Recent Operating Occurrences.Fr Notice,Meeting Schedule & List of Meeting Slides Encl
ML20209G6871985-09-0909 September 1985
Summary of Operating Reactor Events Meeting 85-14 on 850826 to Brief Director & Div Directors on Events Which Occurred Since 850813 Meeting.Computer Printout of 1985 Operating Reactor Events Meeting Topics to Date Encl
ML20133E0661985-07-25025 July 1985
Summary of 850628 Meeting W/Utils & Westinghouse Re Status of Development of New Upper Plenum Injection Evaluation Model.List of Attendees & Agenda Encl
ML20127N9021985-06-24024 June 1985
Summary of Operating Reactors Events Meeting 85-10 on 850612.Only 3 of 17 Items Scheduled for Completion by 850531 Remain Incomplete.List of Attendees,Summary of Events Discussed & Status of Previous Assignments Encl
ML20236Y4401981-07-0101 July 1981
Summary of Site Audit & 810609-11 Meeting W/Util Re Response to IE Bulletin 80-11 on Masonry Walls.Lists of Attendees & Action Items Resulting from Meeting Encl
ML20126L2331981-05-0101 May 1981
Summary of 810429 Meeting W/Pwr Owners Group Re Thermal Shock to Reactor Pressure Vessels.All Parties Agree That Thermal Shock W/Subsequent Repressurization Is Safety Concern Needing Prompt Evaluation
ML20196H3981978-07-0505 July 1978
Summary of 780622 Meeting W/Westinghouse Owners Group to Discuss Results of Phase a of three-phase Plan & Current Schedule for Resolution of Asymmetric LOCA Loads Isssue.List of Attendees Encl
ML20245C3211977-07-11011 July 1977
Summary of 770525 Meeting W/Westinghouse & Util Group Members Re Efforts to Prevent Reactor Vessel Overpressurization.W/O Encls
ML20196H3251976-06-29029 June 1976
Summary of 760525 Meeting W/Util & Westinghouse Re Proposed Approach to Solution of Reactor Vessel Lateral Loading Question.List of Attendees,Agenda & Viewgraphs Encl
1999-09-08
[Table view]
Category:MEETING SUMMARIES-INTERNAL (NON-TRANSCRIPT)
MONTHYEARML20217M5371999-10-25025 October 1999
Summary of 990901 Meeting with Licensee in Rockville,Md Re Util Planned Conversion to Improved Sts.Attendance List & Agenda Encl
ML20211N2141999-09-0808 September 1999
Summary of 990720 Meeting with Util in Rockville MD Re Amend Currently Under Review by Staff Pertaining to Control Room Habitability at Plant Units 1 & 2.List for Attendees & Licensee Handouts Encl
ML20206Q6411999-05-12012 May 1999
Summary of 990426 Meeting with Util at NRC Headquarters Re Proposed Submittal of Amend to Implement Ists.List of Meeting Participants & Matls Presented by Licensee Encl
ML20196F6101998-12-0101 December 1998
Summary of 981029 Meeting with Northern States Power, Wisconsin Electric,Wisconsin Public Service & Alliant-IES in Rockville,Md Re Various Aspects of Potential Regulatory Issues Associated with Ongoing Cooperative Efforts
ML20210H3881997-08-0808 August 1997
Summary of 970805 Meeting W/Wepc & W in Rockville,Md to Discuss Plans to Submit Two TS Change Requests That Will Address 422V Fuel & Proposed Schedule for Review.List of Attendees & Licensee Presentation Encl
ML20135F7891997-03-0303 March 1997
Summary of 970224 Meeting W/Wisconsin Electric Power Co & Gls Enterprises,Inc in Rockville,Md Re Environ Qualified Equipment Inside Containment to Perform Function Following loss-of-coolant Accident Affected by Revised Profiles
ML20058B0031993-11-10010 November 1993
Summary of 931103 Meeting W/Util in Rockville Re Emergency Diesel Generator Addition Project.Attendance List,Discussion on Proposed Review Schedule & Licensee Summary of Emergency Diesel Generator Project Encl
ML20059B1201993-10-21021 October 1993
Summary of 931014 Meeting W/Util in Rockville,Md Re RCS Flow TS Change.List of Meeting Attendees & Handouts Encl
ML20149D6051993-09-15015 September 1993
Summary of 930708 Region III Annual Training Managers Conference in Glen Ellyn,Il.Purpose of Meeting to Provide Forum for Discussion on Rev 7 of Operator Licensing Examiner Stds & to Discuss Operator Licensing Issues
ML20056F8591993-08-16016 August 1993
Summary of 930727 Meeting W/Util in Rockville,Md Re Outstanding Licensing Issues.List of Participants Encl
ML20059P0041990-10-12012 October 1990
Summary of 900905 Meeting W/Util in Rockville,Md Re Plans for Upgrading Onsite Emergency Power Capabilities
ML20153G5481988-05-0404 May 1988
Summary of 880427 Telcon W/Utils in Region III Re Personnel Changes,Follow Up on Previous Items,Items of Interest from Sites & New Items
ML20154G9921988-04-26026 April 1988
Summary of 880331 Meeting W/Sandia Natl Lab,Numarc,Epri, Saic,Util,Westinghouse & ERC Intl Re Differences Between Industry Sponsored Analysis & Earlier Analysis of Same Plant Sponsored by NRC
ML20149K7541988-02-10010 February 1988
Summary of 880204 Meeting in Rockville,Md to Discuss Licensee Accident Reanalysis to Support Increased Allowable Core Peaking Factors at Facilities.Slides Used During Presentation & List of Meeting Attendees Encl
ML20237A9931987-12-0303 December 1987
Summary of 871104 Meeting W/Westinghouse & Utils in Bethesda,Md Re Susceptability of Facility Steam Generators to High Cycle Fatigue.Attendance List & Nonproprietary Westinghouse Handouts Encl
ML20237L1111987-08-28028 August 1987
Summary of Operating Reactors Events Meeting 87-28 on 870825 Re Events Which Occurred Since 870818 Meeting.List of Attendees & Significant Elements Encl
ML20215C8721987-06-0808 June 1987
Summary of Operating Reactors Events Meeting 87-10 on 870406 Re Events Which Occurred Since 870330 Meeting.List of Attendees,Events Discussed & Significant Elements of Events & Summary of Reactor Scrams & Significant Events Encl
ML20214W1621987-06-0505 June 1987
Summary of 870530 Meeting W/Util in Bethesda,Md Re Licensee Assessment of Flaw Indication Observed in Reactor Vessel nozzle-to-shell Weld for Safety Injection Sys.Attendees List Encl
ML20215D0631986-12-11011 December 1986
Summary of Operating Reactor Events Meeting 86-42 on 861201. List of Attendees & Viewgraphs Re Significant Elements of Events Discussed Encl
ML20215C9961986-12-11011 December 1986
Summary of Operating Reactor Events Meeting 86-41 on 861124.List of Attendees,Events Discussed & Significant Event Elements & Summary of Events That Will Be Input to NRC Performance Indicator Program Encl
NUREG-0518, Summary of ACRS 316th Meeting on 860807-09 in Washington,Dc Re Proposed Standardization Policy Statement & Review of Issues Related to Reorganization of TVA Mgt Structure & Shutdown of TVA Nuclear Power Plants1986-08-18018 August 1986
Summary of ACRS 316th Meeting on 860807-09 in Washington,Dc Re Proposed Standardization Policy Statement & Review of Issues Related to Reorganization of TVA Mgt Structure & Shutdown of TVA Nuclear Power Plants
ML20211G7781986-06-13013 June 1986
Summary of Operating Reactor Events Meeting 86-19 on 860609. List of Attendees,Events Discussed & Status of Previous Assignments Encl
ML20197F7721986-05-0808 May 1986
Summary of Operating Reactors Events Meeting 86-15 on 860505.List of Attendees,Events Discussed & Status of Previous Assignments Encl
ML20138N9841985-12-19019 December 1985
Summary of 851122 Meeting W/Licensees & Westinghouse to Present Status of Program for Developing New Upper Plenum Injection Evaluation Model.Nonproprietary Viewgraphs,List of Attendees & Agenda Encl
ML20137X5091985-11-29029 November 1985
Summary of Operator Reactor Events Meeting 85-24 on 851125 Re Briefing of Ofc Directors & Div Directors & Representatives on Events Which Occurred Since Last Meeting on 851118.List of Attendees Encl
ML20138P0081985-10-21021 October 1985
Summary of Operating Reactors Events Meeting 85-19 on 851007 W/Ofc Directors,Div Directors & Representatives on Events Which Occurred Since Last Meeting on 851007
ML20133F9941985-10-0707 October 1985
Summary of Operating Reactors Events Meeting 85-16 on 850916 Re Briefing of Director,Div Directors & Representatives on Events Occurring Since 850909 Meeting.List of Attendees & Viewgraphs Encl
ML20141E5521985-09-26026 September 1985
Summary of ACRS Subcommittee on Reactor Operations 850910 Meeting in Washington,Dc to Discuss Recent Operating Occurrences.Fr Notice,Meeting Schedule & List of Meeting Slides Encl
ML20209G6871985-09-0909 September 1985
Summary of Operating Reactor Events Meeting 85-14 on 850826 to Brief Director & Div Directors on Events Which Occurred Since 850813 Meeting.Computer Printout of 1985 Operating Reactor Events Meeting Topics to Date Encl
ML20133E0661985-07-25025 July 1985
Summary of 850628 Meeting W/Utils & Westinghouse Re Status of Development of New Upper Plenum Injection Evaluation Model.List of Attendees & Agenda Encl
ML20127N9021985-06-24024 June 1985
Summary of Operating Reactors Events Meeting 85-10 on 850612.Only 3 of 17 Items Scheduled for Completion by 850531 Remain Incomplete.List of Attendees,Summary of Events Discussed & Status of Previous Assignments Encl
ML20126L2331981-05-0101 May 1981
Summary of 810429 Meeting W/Pwr Owners Group Re Thermal Shock to Reactor Pressure Vessels.All Parties Agree That Thermal Shock W/Subsequent Repressurization Is Safety Concern Needing Prompt Evaluation
ML20196H3981978-07-0505 July 1978
Summary of 780622 Meeting W/Westinghouse Owners Group to Discuss Results of Phase a of three-phase Plan & Current Schedule for Resolution of Asymmetric LOCA Loads Isssue.List of Attendees Encl
ML20245C3211977-07-11011 July 1977
Summary of 770525 Meeting W/Westinghouse & Util Group Members Re Efforts to Prevent Reactor Vessel Overpressurization.W/O Encls
ML20196H3251976-06-29029 June 1976
Summary of 760525 Meeting W/Util & Westinghouse Re Proposed Approach to Solution of Reactor Vessel Lateral Loading Question.List of Attendees,Agenda & Viewgraphs Encl
1999-09-08
[Table view] |
Text
' *
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/ October 12, 1990 -
Docket Nos. 50-266- DISTRIBUTION and 50-301 eacket, Filet 6 NRC & Local PDRs FMiraglia JPartlow -
LICENSEE:' Wisconsin Public Service Corporation DCrutchfield JHannon .
OGC-WF1 EJordan FACILITY:. Point Beach Nuclear Power Plant ACRS(10) BSamworth JZwolinski PDIII-3 r/f SUBJECTi PLANS FOR UPGRADING ONSITE EMERGEN",Y POWER CAPABILITIES AT POINT BEACH
-On September 5, 1990, NRR_ staff met with Wisconsin Electric Power Company.
staff at NRC headquarters in Rockville. The purpose of the meeting was for WEPCo to inform NRC of plans for upgrading onsite emergency power capabilities at the Point Beach Nuclear Plant. A list of meeting attendees is attached.
WEPCo advised NRC that they have contracted for purchase of two additional diesel generators similar in manufacture and capacity to the two emergency diesel generators installed at Point Beach. The diesels will be shared by the two Point Beach nuclear units.
The additional diesels'and associated electrical systems perform a safety-related function and will be classified as IE. WEPCo will advise NRC more specifically of the standards to which the uagrade will be designed. WEPCo will also inform.
HRC of the testing program whici will be proposed to demonstrate operability of the new diesel generators.
. Emergency electrical loads have been tabulated using nameplate ratings of emergency equipment (e.g., motors on pumps and valves). The licensee will retabulate emergency loads using measured electrical demands of this equipment.
.The licensee also reported the intended installation of an additional station
- battery.
Copies of the viewgraphs used in the licensee's presentation are attached.
- odginalsigned by Robert B. Samworth, Project Manager Project Directorate III-3 .
Division of Reactor Projects - III, IV, Y and Special Projects-Office of Nuclear Reactor Regulation Attachments:
"As' stated fcc: See next page DOCUMENT NAME: PB MEETING SUMMA Y 0ffice: LA/PDIII-3 TM/PDIII-3 PD) III-3 Surname: P3rehzer BSamworth/tg JHannon Date: - p / e, /90 /p/ g /90 p/p/90
$02 p
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r ;, ' Mr. C. W. Fay ~ Point Beach Nuclear Plant i
. Wisconsin Electric Power. Company Units 1 and 2 l
-cc:: Ernest L. Blake, Jr.
Shaw, Pittman, Potts and Trowbridge l
-2300 N Street, N.W.
Washington, DC 20037 ,
i' Mr. Gregory J. Maxfield, Manager Point Beach Nuclear Plant Wisconsin Electric Power Company 6610 Nuclear Road Two Rivers, Wisconsin 54241 Town Chairman ,
Town of Two Creeks j Route 3
'Two Rivers, Wisconsin 54241 ..
Chairman- -
3 Public Service Commission of Wisconsin ,
Hills Farms State Office Building Madison, Wisconsin 53702 Regional Administrator, Region III U.S.. Nuclear Regulatory Commission Office of Executive Director :
for Operations 799 Roosevelt Road Glen Ellyn, Illinois 60137 i
Resident Inspector's Office !
U.S. Nuclear Regulatory Commission !
L6612 Nuclear Road iTwo Rivers, Wisconsin 54241 J
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ATTENDANCE LIST 9/5/90 Nane Affiliationi Paul J. Katers ~ WE Chris_ North WE (QA)
Garry. Frieling WE Dave Butler RIII-DRS James Zach WE Bruce Sasman WE Chuck Krause WE(Licens'ing)
Bob Samworth NRC Jack Gadzala- NRC Nick Jackiw NRC-Region III Om P. Chopra NRC-SELB S. N. Saba NRC-SELB-J. N. Hannon NRC PDIII-3 Eve Fotopoulos SEP.Ct' Licensing, Bechtel
'J. H. Raval NRC/NRR/SPLB
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. AGENDA POR DIESEL GENERATOR / BATTERY J '- KEETING WITE STAFF, september 5, 1990 A. Introduction /:?urpose of Meeting B. Addition of riesel Generator Capacity
- 1. Existing Plant Configuration
- 2. Purpose of Modifications
- 3. Design Inputs
- 4. Description of Proposed Modifications
- 5. Proposed Design Standards
- 6. . Schedule
- 7. Licensing Issues C. Addition of Swing Safety Related Battery
- 1. Existing Plant Configuration
- 2. . Battery Testing Tech. Spec. Change-3.: Description of Proposed Modification
- 4. Schedule
- 5. Licensing Issues
.D . Addition of Non Safety Related Battery
- 1. Purpose of Modification
- 2. Description of Proposed Modification
- 3. Schedule -
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l) EMERGENCY DIESEL GENERATOR PROJECT l E
l EXISTING PLANT CONFIGURATION l .
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- Two Emergency Diesels - Shared Between Units i u e Located in Adjacent Rooms in Control Building f
e' A Single Diesel is Required for Design Basis ,
o Accident ;
- Normal Plant Operation Requires that Both Diesels -,
be Operable
- Removal of One Diesel from Service Places Both Units.in a Seven Day LCO
- - Required Safety Loads under Design Basis !
Conditions are Approximately 2700 KW. 2000 Hour E
Rating of Each of-the Existing Diesels is 2850 KW.
- Placement of Additional Loads on the. Diesel .
- Generators Which Enhance the Ability to Deal with Accident: Conditions,-Requires Operators to l Closely Control Diesel Generator Loading.
- - Existing'.. Station' Blackout Response Utilizes Combustion-Gas Turbine as an Alternate. AC Source
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. . EMERGENCY DIESEL GENERATOR PROJECT PURPOSE.OF MODIFICATIONS
- Increase Reliability-- Preliminary PRA Studies Have Shown That Addition of Diesel Generators Significantly Reduces the Probability of Core Damage
-* To Provide Additional Capacity - This Will Allow for Use of Additional Equipment Under Accident-Conditions. This Will in Turn Enhance Capability to Cope With Events and Will Reduce the Need for Operator Control of Diesel Generator Load.
- To Provide Additional Margin Between Required Safety' Loads and Diesel Generator Capacity.
- To. Allow for the Removal of Any One of the Diesel Generators from Service for Maintenance Without
-Entering an LCO Condition.
- To Provide a Qualified. Alternate AC Source for Each Unit to be Used Instead of-'(or in Addition to) the Existing Combustion Gas Turbine.
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EMERGENCY DIESEL GENERATOR PROJECT DESIGN INPUTS
- Additional Diesels and Associated Electrical -
, ' Systems Perform a Safety Related Function and~Will "
be Classified as Class 1E.
- Where Components:of Auxiliary Systems are Necessary to Support Safety Related Functions of .t the Diesel Generators They Will Also be Classified 3 as Safety-Related.
c L := Any Two Diesel Generators (Existing or New) Will -
3 L be Capable'ofLProviding the Necessary Power Required-to Respond to Accident Conditions, Plus L Capability for Supply.of Additional Desired .
L "
Loads.
Accident Conditions include a LOCA in One Unit and< Required Shutdown:of the Other Unit Coincident With a Lossiof All Offsite Power. In-Addition One. Diesel Generator isLAssumed to be Out of Service ( for Maintenance) and a Second Diesel L' Generator Fails.
Reduction of Operable: Diesel Generators t'o Two-
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p Will Result in:an LCO Condition.
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f.c EMERGENCY DIESEL GENERATOR PROJECT
. DESIGN INPUTS
- Fuel Oil Supply Will Be Capable.of'Providing A.
Seven Day Supply of Fuel Oil for the-Two Additional Diesels.
~
(Sharing Between Units When One Diesel is out of L Service) l L
- Each of the Diesels Must Meet the Requirements to-p Qualify;as an Alternate AC Source for. Station Blackout-Purposes. This Requires the Following as 1 o a Minimum: ,
I
- A Single Diesel Must Have Adequate Capacity:to '
Supply the Required Shutdown Loads .of Both Units. -
- The Normal Electrical-System Alignment Will .>
Require That Each Diesel be Dedicated to a. l Single Unit-and That it be isolated From the Electrical System of. the Other Unit by at Least
.Two Open Circuit Breakers.
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EMERGENCY DIESEL GENERATOR PROJECT ELECTRICAL CHANGES
- New Safety Related 4160 Volt Busses 1A06
( Unit'#.1 B- Train) and 2A05 (Ur.!t #2 A-Train) Will be:Provided in the New Diesel Generator Building.
- Each of..the Four Diesels (2 New and 2 Existing) Will be' Connected to Supply One of the Four 4160 Volt Safety Related Busses During Normal Operation.
Each Diesel Will be' Unit and Train Specific. Each-Diesel Will Start and Assume the Appropriate Loads Upon Loss of Voltage to the Associated Bus.
- Upon Removal of a Single Diesel from Service.the System Will be Manually Realigned Such That the Diesel Dedicated to the Same Train of the Other Unit Will- Automatically Supply the Loads for the Single Train of Both Units.
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EMERGENCY DIESEL GENERATOR PROJECT ELECTRICAL. CHANGES
- Removal of a Second Diesel From Service (LCO Condition) Will Result in One of Two Operating "
Arrangements. -
- 1) Each of the Two Remaining Diesels Would be i Shared Between Units, Each Diesel Supplying One- '
Safety Related Train for Both Units. In this Arrangement Neither of the Diesels-Would Qualify. ,
as an Alternate AC Source for Station Blackout ,
Purposes. -
- 2) EachLof the Two Remaining Diesels. Would Provide Supply to the Same Safety Related Train -
on Opposite Units. ( Example: One Diesel Would Supply A- Train Unit # 1 and the Second Diesel .
Would Supply A- Train on Unit # 2)' The Other 1 Train on Both Units Would be Inoperable.
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(CONTINUED) vu,c
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EMERGENCY DIESEL' GENERATOR PROJECT:
E PROPOSED MODIFICATIONS y
L' e NEW DIESELS ARE EMD MODEL 20-645-E4 i l/ BUILT IN 1976 FOR TVA-HARTSVILLE.
. EQUIPMENT INCLUDED.WITH,THE DIESEL: l
- AIR START SKIDS, FUEL OIL DAY TANKS, 1 AIR INTAKE FILTERS, INTAKE 'AND EXHAUST ,
SILENCERS AND FUEL OIL TANKS.
. NEW SWITCHGEAR IS ITE 4160v BUILT IN '
1980 FOR WPPS3.
- THE NEW DIESELS AND SWITCHGEAR WILL '
BE HOUSED IN A SAFETY RELATED CONCRETE L
STRUCTURE.
THE NEW DIESELS WILL BE COOLED USING !
RADIATORS. t
- HE N DIESELS WILL INCLUDE A NEW o
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.< l EMERGENCY DIESEL GENERATOR. PROJECT
' APPLICABLE CODES AND STANDARDS- a e THIS PROJECT IS VIEWED AS A L
MODIFICATION OR ENHANCEMENT TO AN j EXISTING SYSTEM, NOT^AN ADDITION i OF A NEW SYSTEM. 4 L
- THIS PROJECT WILL MEET ALL CODES, i STANDARDS AND REG GUIDES COMMITTED j TO IN THE POINT BEACH FSAR. .
- THIS-PROJECT WILL MEET THE APPLICABLE STANDARDS OF THE TIME WHEN THE EQUIPMENT WAS MANUFACTURED FOR THE-EQUIPMENT-PURCHASED FROM-GENERAL.PUBLIC UTILITIES. 1
- THIS PROJECT WILL REVIEW CURRENT DAY CODES, STANDARDS AND REG GUIDES TO :
L DETERMINE WHICH STANDARDS-OR PORTIONS l THEREOF CAN REASONABLY BE MET.
l CONSISTENT WITH THE ABOVE ITEMS.
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. EMERGENCY DIESEL GENERATOR PROJECT ESTIMATED SCHEDULE-
- 1. DISCUSSIONS WITH THE NRC 09/05/90
,; 2. FILE REVISED APPLICATION 10/01/90 WITH PSCW
- 3. HlRE - A- FINAL DESIGN 12/01/90 CONSULTANT 4.- REFURBISH DIESELS 06/01/91
- 5. FINISH FINAL DESIGN 11/01/91
- 6. ' START CONSTRUCTION 11/01/91
- 7. ' START- UP TESTING 06/01'/93
- 8. COMPLETION 06/30/94 l
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EMERGENCY: DIESEL-' GENERATOR PROJECT
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EMERGENCY DIESEL GENERATOR PROJECT LICENSING SUBMITTALS AND APPROVALS
- May 1991- Licensee submits Diesel Generator Design Bases- and Modification Report
- Nov 1991- NRC confirms basic acceptability of proposed design e Jul 1993- Licensee. submits License Amendment Request with proposed Technical Specification changes e Jan 1994- NRC issues License Amendments approving revised Technical Specifications subject to project completion mi
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F SAFETY RELATED BATTERY ADDITION t
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- Purpose - To Provide a Source of Emergency DC '
Power Which Can Provide for the Same Function as Any One of the Four Existing Station Batteries.
This Will Allow for Removal of Any One Station !
Battery From Service For Testing or Maintenance.
- Schedule - An Additional Battery and Racks were Purchased to Support Replacement of Original -
Plant Batteries in 1989. Present Schedule Calls ;
l for Completion of This Project in Mid 1992, i (Reference Wisconsin Electric Response to inspection Reports 50-266/90-201 and i 50-301/90-201 dated August 3,1990) 1
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NON-SAFETY RELATED BATTERY ADDITION
- Purpose - To Install a Non-Safety Related DC System including a Battery to Provide a Source for Selected Existing and Future DC Powered Equipment Which Does Not Require a Safety Related Source. This Will Allow for Removal of Several Large Loads From the Existing Safety Related Batteries, Thus Significantly increasing the Margin Between Available Capacity and Required Capacity. ,
- Schedule - Design and Equipment Specification is Expected to be Completed in Early 1991. System installation will be Completed by Mid 1992.
( Reference Wisconsin Electric Response to inspection Reports 50- 266/ 90- 201 and 50- 301/ 90- 201 dated August 3,1990)
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