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Category:TECHNICAL SPECIFICATIONS
MONTHYEARML20217C7961999-10-0606 October 1999 Marked-up & Type Written Proposed TS Pages,Revising TSs 1.0, 3.6,Bases 3.0,Bases 3.6 & 5.5,to Adopt Implementation Requirements of 10CFR50,App J,Option B for Performance of Type A,B & C Containment Leakage Rate Testing ML20209A7351999-06-23023 June 1999 Proposed Tech Specs Pages 3.3-4 & 3.3-6,replacing Page 3.3-6 Re Recirculation Loop Flow Transmitters & Applicable SRs Associated with Function 2.b ML20196B4741999-06-17017 June 1999 Proposed Tech Specs Bases Changes Made at Plant Subsequent to Receipt of License Amend 178,dtd 980731,for Conversion to Its,Through 990610 ML20195E9101999-06-0808 June 1999 Proposed Tech Specs,Correcting Described Method by Which SGTS Heaters Are to Be Tested ML20205H2891999-03-31031 March 1999 Proposed Tech Specs Modifying ACs for Unit Staff Qualifications for Shift Supervisor,Senior Operator,Licensed Operator,Shift Technical Advisor & Radiation Manager Positions ML20236W1141998-07-28028 July 1998 Proposed Tech Specs Re Implementation of BWR Thermal Hydraulic Stability Solution ML20151Q0621998-07-28028 July 1998 Final Version of Improved TS & Bases Re Proposed Change to Conversion to Improved Standard TS ML20236R9821998-07-16016 July 1998 Proposed Tech Specs Section 6.5.1,re Implementation of BWR Thermal Hydraulic Stability Solution ML20236Q0641998-07-13013 July 1998 Proposed Tech Specs Re Rev B to Conversion to Improved STS ML20216H0801998-04-15015 April 1998 Proposed Tech Specs Sections 2.1.A.1.d & 3.2.C,deleting Max Rated Power for APRM Rod Block Trip Setting ML20216H0571998-04-15015 April 1998 Proposed Tech Specs 4.2.C,exempting Neutron Detectors from Channel Calibr Requirements ML20216B4481998-04-0202 April 1998 Proposed Tech Specs 4.2.C,exempting Neutron Detectors from Channel Calibr Requirements ML20148G3481997-05-30030 May 1997 Proposed Tech Specs,Changing Frequency of Testing RHR Cross Tie valve,RHR-MOV-MO20,position Indication from Once Per Month to Once Per Operating Cycle ML20138J0751997-05-0505 May 1997 Proposed Tech Specs,Relocating Control of Standby Liquid Control Relief Valve Setpoint in TS 4.4.A.2.a & Associated Bases ML20148B0041997-05-0202 May 1997 Proposed Tech Specs,Deleting SLC Relief Valve Testing Described in TS Section 4.4.A.2.a & Associated Bases in Bases Section 3.4.A Since Testing Is Already Performed Under ISI Program ML20134K3771997-02-10010 February 1997 Proposed Tech Specs Re Requirements for Avoidance & Protection from Thermal Hydraulic Instabilities to Be Consistent w/NEDO-31960 & NEDO-31960,Suppl 1, BWR Owners Group Long-Term Stability Solutions.. ML20117K3291996-06-0606 June 1996 Proposed Tech Specs Revising Safety Limit MCPR from 1.06 to 1.07 for Dual Recirculation Loop Operation & from 1.07 to 1.08 for Single Recirculation Loop Operation ML20100R4431996-03-0505 March 1996 Proposed Tech Specs,Consisting of Change Request 142, Revising TS, DG Enhancements ML20086K4421995-07-14014 July 1995 Revised Proposed Tech Specs Re DG Enhancements Reflecting More Conservative Approach to Enhancing DGs ML20086B7061995-06-28028 June 1995 Proposed Tech Specs Re Increasing Required RPV Boron Concentration & Modifying Surveillance Frequency for SLC Pump Operability Testing ML20085J2631995-06-15015 June 1995 Proposed Tech Specs Re Extension of Surveillance Intervals for Logic Sys Functional Testing for ECCS ML20083A7241995-05-0505 May 1995 Proposed Tech Specs Reflecting Changes to TSs & Associated Bases for License DPR-46 ML20083A1341995-05-0202 May 1995 Proposed Tech Specs Re Temporary Rev to SR to Extend Two Year LLRT Interval Requirement ML20149H8821994-12-27027 December 1994 Proposed Tech Specs Re Control Room Emergency Filter Sys ML20078S5711994-12-22022 December 1994 Proposed Tech Specs Re Definition of Lco,Per GL 87-09 ML20073J2371994-09-26026 September 1994 Proposed TS LCOs 3.5.C.1 & 3.5.C.4,increasing Min Pressure at Which HPCI Sys Required to Be Operable from Greater than 113 Psig to Greater than 150 Psig ML20071K1541994-07-26026 July 1994 Proposed Tech Specs to Increase Flow Capacity of Control Room Emergency Filter System ML20070M6671994-04-26026 April 1994 Proposed Tech Specs Re Intermittent Operation of Hydrogen/ Oxygen Analyzers ML20065K1931994-04-12012 April 1994 Proposed Tech Specs,Reflecting Removal of Definitions 1.0.Z.B.1 Through 5,change to LCO 3.21.B.1.a (Line 5) Re Ref to 10CFR20.106 & Change to Paragraphs 1,4,5 & 6 (Lines 6,3,8 & 2 Respectively) Re Ref to 10CFR20.106 ML20058N2321993-12-10010 December 1993 Proposed Tech Specs 3/4.21, Environ/Radiological Effluents, 6.5, Station Reporting Requirements & 6.5.1.C.2 Re 10CFR50.59(b) Rept ML20058N2881993-12-10010 December 1993 Proposed Tech Specs for Pressure Vs Temp Operating Limit Curves ML20058M2591993-09-28028 September 1993 Proposed Tech Specs Modifying Organizational Structure by Removing Mgt Positions of Site Manager & Senior Manager of Operation ML20056G5971993-08-31031 August 1993 Proposed TS Re Primary Containment Isolation Valve Tables ML20056G5821993-08-31031 August 1993 Proposed TS Re Primary & Secondary Containment Integrity ML20056G2341993-08-25025 August 1993 Proposed Tech Specs Bases Section to Reflect Operational & Design Changes Made to CNS Svc Water Sys During 1993 Refueling Outage ML20056F3331993-08-23023 August 1993 Proposed Tech Specs 6.0, Administrative Controls, Reflecting Creation of Mgt Position of Vice President - Nuclear ML20045D8991993-06-23023 June 1993 Proposed TS SR 4.9.A.2 Re Determination of Particulate Concentration Level of Diesel Fuel Oil Storage Tanks ML20045C0031993-06-14014 June 1993 Proposed Tech Specs Associated W/Dc Performance Criteria ML20045C8301993-06-14014 June 1993 Proposed Tech Specs Incorporating New Requirements of 10CFR20 ML20128L5561993-02-12012 February 1993 Proposed TS Table 4.2.D, Min Test & Calibr Frequencies for Radiation Monitoring Sys & TS Pages 81 & 84 Re Notes for Tables 4.2.A Through 4.2.F ML20128E6201993-02-0101 February 1993 Proposed Tech Specs Reflecting Current NRC Positions Re Leak Detection & ISI Schedules,Methods,Personnel & Sample Expansion,Per GL 88-01 ML20127B8331993-01-0505 January 1993 Proposed TS Pages 53,55,70 & 71,removing Bus 1A & 1B Low Voltage Auxiliary Relays ML20115F8531992-10-15015 October 1992 Proposed Tech Specs Page 48,reflecting Relocation of Mechanical Vacuum Pump Isolation SRs ML20115A3481992-10-0808 October 1992 Proposed TS Section 6.1.2 Re Offsite & Onsite Organizations, Delineating Responsibilities of Site Manager & 6.2.1.A Re Min Composition of Station Operations Review Committee ML20104B2091992-09-0909 September 1992 Proposed TS 3.1.1 Re Reactor Protection Sys Instrumentation Requirements & TS Table 3.2.D Re Radiation Monitoring Sys That Initiate &/Or Isolate Sys ML20104A8691992-09-0202 September 1992 Proposed TS 3.9 & 4.9 Re Auxiliary Electrical Sys ML20099D4151992-07-28028 July 1992 Proposed TS 3.6 Re LCO for Primary Sys Boundary & 4.6 Re Surveillance Requirements for Primary Sys Boundary ML20113G8241992-05-0404 May 1992 Proposed Tech Spec Pages for Removal of Component Lists,Per Generic Ltr 91-08 ML20096D6111992-05-0404 May 1992 Proposed Tech Specs Change 100 to Eliminate Main Steam Line Radiation Monitor Scram & Isolation Functions ML20090A8061992-02-25025 February 1992 Proposed Tech Specs Re Dc Power Sys 1999-06-08
[Table view] Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML20217C7961999-10-0606 October 1999 Marked-up & Type Written Proposed TS Pages,Revising TSs 1.0, 3.6,Bases 3.0,Bases 3.6 & 5.5,to Adopt Implementation Requirements of 10CFR50,App J,Option B for Performance of Type A,B & C Containment Leakage Rate Testing ML20209A7351999-06-23023 June 1999 Proposed Tech Specs Pages 3.3-4 & 3.3-6,replacing Page 3.3-6 Re Recirculation Loop Flow Transmitters & Applicable SRs Associated with Function 2.b ML20196B4741999-06-17017 June 1999 Proposed Tech Specs Bases Changes Made at Plant Subsequent to Receipt of License Amend 178,dtd 980731,for Conversion to Its,Through 990610 ML20195E9101999-06-0808 June 1999 Proposed Tech Specs,Correcting Described Method by Which SGTS Heaters Are to Be Tested ML20207A0761999-05-14014 May 1999 Rev 3 to CNS Strategy for Achieving Engineering Excellence ML20206J2661999-04-22022 April 1999 CNS Offsite Dose Assessment Manual (Odam) ML20205H2891999-03-31031 March 1999 Proposed Tech Specs Modifying ACs for Unit Staff Qualifications for Shift Supervisor,Senior Operator,Licensed Operator,Shift Technical Advisor & Radiation Manager Positions ML20151Q0621998-07-28028 July 1998 Final Version of Improved TS & Bases Re Proposed Change to Conversion to Improved Standard TS ML20236W1141998-07-28028 July 1998 Proposed Tech Specs Re Implementation of BWR Thermal Hydraulic Stability Solution ML20236R9821998-07-16016 July 1998 Proposed Tech Specs Section 6.5.1,re Implementation of BWR Thermal Hydraulic Stability Solution ML20236Q0641998-07-13013 July 1998 Proposed Tech Specs Re Rev B to Conversion to Improved STS ML20206P9051998-07-0707 July 1998 Rev 2, Strategy for Achieving Engineering Excellence, for Cooper Nuclear Station ML20216H0571998-04-15015 April 1998 Proposed Tech Specs 4.2.C,exempting Neutron Detectors from Channel Calibr Requirements ML20216H0801998-04-15015 April 1998 Proposed Tech Specs Sections 2.1.A.1.d & 3.2.C,deleting Max Rated Power for APRM Rod Block Trip Setting ML20216D8971998-04-0808 April 1998 Rev 1 to Strategy for Achieving Engineering Excellence ML20216B4481998-04-0202 April 1998 Proposed Tech Specs 4.2.C,exempting Neutron Detectors from Channel Calibr Requirements ML20203G4271998-02-24024 February 1998 Rev 0 to First Ten-Year Interval Containment Insp Program for Cns ML20202H5311998-02-11011 February 1998 Strategy for Achieving Engineering Excellence ML20216G1571997-09-0505 September 1997 Rev 2.1 to Third 10-Yr Interval Inservice Insp Program ML20210H5641997-08-0707 August 1997 Rev 2 to NPPD CNS Third Interval Inservice Testing Program ML20148G3481997-05-30030 May 1997 Proposed Tech Specs,Changing Frequency of Testing RHR Cross Tie valve,RHR-MOV-MO20,position Indication from Once Per Month to Once Per Operating Cycle ML20148G8531997-05-0909 May 1997 Nebraska Public Power District Nuclear Power Group Phase 3 Performance Improvement Plan, Closure Rept ML20138J0751997-05-0505 May 1997 Proposed Tech Specs,Relocating Control of Standby Liquid Control Relief Valve Setpoint in TS 4.4.A.2.a & Associated Bases ML20148B0041997-05-0202 May 1997 Proposed Tech Specs,Deleting SLC Relief Valve Testing Described in TS Section 4.4.A.2.a & Associated Bases in Bases Section 3.4.A Since Testing Is Already Performed Under ISI Program ML20138H3861997-04-29029 April 1997 Rev 1.2 to CNS Third Interval IST Program ML20134K3771997-02-10010 February 1997 Proposed Tech Specs Re Requirements for Avoidance & Protection from Thermal Hydraulic Instabilities to Be Consistent w/NEDO-31960 & NEDO-31960,Suppl 1, BWR Owners Group Long-Term Stability Solutions.. ML20134E1091996-10-25025 October 1996 NPPD Cooper Nuclear Station Third Interval IST Program, Rev 1 ML20117K3291996-06-0606 June 1996 Proposed Tech Specs Revising Safety Limit MCPR from 1.06 to 1.07 for Dual Recirculation Loop Operation & from 1.07 to 1.08 for Single Recirculation Loop Operation ML20100R4431996-03-0505 March 1996 Proposed Tech Specs,Consisting of Change Request 142, Revising TS, DG Enhancements ML20101L8381995-12-31031 December 1995 Reactor Containment Bldg Integrated Leak Rate Test. W/ ML20113B0531995-12-29029 December 1995 Rev 4.1 to NPPD CNS Second Ten Yr Interval ISI Program for ASME Class 1,2 & 3 Components ML20093L1901995-10-18018 October 1995 Rev 0 to Third Ten-Yr Interval ISI Program for Cns ML20086K4421995-07-14014 July 1995 Revised Proposed Tech Specs Re DG Enhancements Reflecting More Conservative Approach to Enhancing DGs ML20086H7341995-07-14014 July 1995 Rev 7 to CNS Second Ten Yr Interval IST Program ML20086H7601995-06-30030 June 1995 Rev 4 to CNS Second Ten Yr Interval ISI Program for ASME Class 1,2 & 3 Components ML20086B7061995-06-28028 June 1995 Proposed Tech Specs Re Increasing Required RPV Boron Concentration & Modifying Surveillance Frequency for SLC Pump Operability Testing ML20085J2631995-06-15015 June 1995 Proposed Tech Specs Re Extension of Surveillance Intervals for Logic Sys Functional Testing for ECCS ML20083A7241995-05-0505 May 1995 Proposed Tech Specs Reflecting Changes to TSs & Associated Bases for License DPR-46 ML20083A1341995-05-0202 May 1995 Proposed Tech Specs Re Temporary Rev to SR to Extend Two Year LLRT Interval Requirement ML20083M0401995-01-20020 January 1995 Rev 1 to Restart Readiness Program ML20083M0901995-01-13013 January 1995 Rev 2 to Startup & Power Ascension Plan ML20149H8821994-12-27027 December 1994 Proposed Tech Specs Re Control Room Emergency Filter Sys ML20078S5711994-12-22022 December 1994 Proposed Tech Specs Re Definition of Lco,Per GL 87-09 ML20083M0141994-11-0909 November 1994 Rev 3 to Phase 1 Plan, ML20083M0321994-11-0808 November 1994 Rev 0 to Restart Readiness Program ML20073J2371994-09-26026 September 1994 Proposed TS LCOs 3.5.C.1 & 3.5.C.4,increasing Min Pressure at Which HPCI Sys Required to Be Operable from Greater than 113 Psig to Greater than 150 Psig ML20149F9921994-09-15015 September 1994 Rev 1 to CNS Startup Plan ML20071K9311994-07-27027 July 1994 Diagnostic Self Assessment (DSA) Implementation Plan ML20071K1541994-07-26026 July 1994 Proposed Tech Specs to Increase Flow Capacity of Control Room Emergency Filter System ML20070M6671994-04-26026 April 1994 Proposed Tech Specs Re Intermittent Operation of Hydrogen/ Oxygen Analyzers 1999-06-08
[Table view] |
Text
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lNLS90003101
- Attachment-Page 1 of 9?
, 1 REVISED TECHNICAL SPECIFICATION PAGES FOR-ADDITION OF THE 161 KV CFF-SITE SOURCE
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Revised Pane )
193 BACKCROUND/ DISCUSSION In 1981, . the Nebraska Public Power District. (DISTRICT) ; installed' a 101- kV r 'tchyard at Cooper Nuclear Station (CNS). This 161 kV switchyard'isidesigned in a ring bus configuration capable of handling _ three -(3) line terminals. . These-t.hree (3) line terminals consist of 1) Omaha Public Power District's :(OPPD) 161 kV transmission line to Auburn, Nebraska; 2) tie-in to the existing 345/161 kV auto-transformer located in the CNS 345 kV switchyard.and; 3)_ tie-in to the CNS startup station service transformer (this configuration can'be seen in Figure -
1). To date, the DISTRICT has not' taken credit for this 161 kV transmis'sion line 3
as an off site power source for Cooper Nuclear Station.
With the installation of the 161 kV switchyard, the DISTRICT has the capability of supplying power to the startup station service transformer f?:om one of two off-site sources; 1) the 345/161 kV auto-transformer which is fed from the 345 kV -
I switchyard and; 2) .the 161 kV switchyard -(this configuration can be seen in Figure 2). Although the 161 kV switchyard has been in operation since 1981, the-l 9010100007 900928' PDR ADOCK 05000298
'P PDC
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, N1.S9000310-
. Attachmint Page 2;of 9-.
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[ DISTRICT has never1 acknowledged or requested thtt this off-site source be it.cluded in our operating license (CNS Technical Specifications) . - In ' the - .!
y unlikely - event Cooper. Nuclear Station would have lost the' entire 345 : kV .
switchyard (resulting in the emergency buses'1F-and 1G being powered from the .;
emergency transformer orf the diesel generator),- the DISTRICT could have supplied <
-i power to the-startup transformer;through the 161 kV System. However, the CNS ;l Technical Specifications,fas currently _ written,.do not acknowledge the ability to energize the startup station service transformer from the'161 kV swit'chyard sys tem.- CNS Technical Specifications -currently state in part "both off-site '
sources (345 kV and 69 kV) are available~."-
Therefore, the DISTRICT proposes to revise CNS Technical' Specification 3.'9. A.1.a' ,
to include the OPPD 161 kV system as an off-site power source available to Cooper ; ,
1 Nuclear Station to power the auxiliary electrical' equipment. Technical Specification 3.9. A.1 a will be revised to read as follows: -(revision underlined) f "One off-site source (345 kV or 161 kV) and the emerrency off-site source (69 kV) and the startup transformer and emergency transformer are available and capable of automatically supplying power to the 4160 Volt emergency buses 1F and 1G. 1 This proposed change will allow Cooper Nuclear Station to energize the startup-station service transformer from the 161 kV switchyard, thereby increasing- the operational readiness of off-site AC power sources for Cooper Nuclear Station.
This proposed change will also establish a greater flexibility in off-site power source availability at CNS. With approval of this proposed change, the DISTRICT
NLS9000310 '
Attachmint-Page 3 of 9 will-have three-(3) separate,_ independent, and unique off site power sources L _ entering Cooper Nuclear Station: 1) 345 kV source This source currently has-t four (4) 345 kV iines entering 'the -345 kV ' switchyard which are available. to supply power to emergency buses 1F and 1G; 2) 161 kV source. - This source currently has : one (1) 161 kV line entering the 161 kV switchyard which is -
available to supply power to emergency buses IF and 1G; 3)-69 kV source This-is -
, a stand-alone source and is directly tied into the 69 kV emergency transformer-l' . . ,
and is used to supply power to emergency buses IF.and'10. !
The 161 kV transmission line discussed in this proposed change as an alternate ,
off site power source for Cooper ~ Nuclear Station, was designed and has been analyzed to show, that this line will- provide adequate rated voltage . to the 4
emergency buses under all accident scenarios -(including worst - case LOCA). In-
. addition, the voltage on this transmission line is continually monitored, with the meter readout provided in the control room for. the operator's information.
Also, procedures are in place, and annunciation is provided to declare this transmission line inoperable in the event that the transmission line voltage -
drops below the required voltage necessary to operate all loads on the emergency ,
buses.
l It should be noted that these three- (3) independent sources are' adequately separated, and that the loss of one (1) off-site source, would not disable the two (2) remaining off-site sources. Therefore, with the approval of. this proposed change, the DISTRICT will be well positioned to cope with industry concerns involving station black out and loss of off-site power due to the I
existing independence and diversity of Cooper Nuclear Stations off-site source capability / availability.
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s NLS9000310~~
Attichmentt ,
Page 4 Eof 9: 3 The DISTRICT requests an approved SER on this proposed change byl June 1991. This
- will enable the DISTRICT to proceed, as scheduled, with a planned 345 kV, -
Switchyard-Modification, - This' modification is necessary to accommodate a new. j
- line terminal enterinj; the 345' kV switchyard in association with the Missouri,' l
' Iowa, Nebraska Transmission (MINT) Project. , h t
' EVALUATION OF THIS REVISION WITH RESPECT TO 10CFR50.92 l
This license amendment proposes to add a.new 161 kV off-site power source.
I 4 The enclosed Technical Specification change is judged to involve no significant- l
. 'i hazards based on the following: '
L
- 1. Does the proposed license amendment involve a significant increaae -in' the O probability or consequence of an accident previously evaluated?
t l
Evaluation l
-i ll The proposed amendment would revise the Technical Specifications to recognize an y additional existing source of off-site power, available 'to supply the emergency- I buses. Thic additional full capacity, independent source - of off-site power '
significantly improves the reliability and flexibility of . the Cooper Nuclear-St.: tion auxiliary electrical system. The probability of a loss-of voltage:or- l.
degraded voltage to the station emergency buses is si 5 nificantly reduced. The ;
proposed amendment will require the availability of at least one off-site source ;
prior to allowing reactor criticality. In addition the 69 kV emergency line till still be required to be operational as currently specified in the existing a o.
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'NLS9000310 Atttchment Page.5lof 9;
]
, . l Therefore, = this change .has- no-. effect fon : the
-Technical Specifications.
probability of loss of off-site power or reliability of the power supply to plant emergency buses and equipment, and there.is no increase in the probability or the .i consequences of an analyzed' accident.
.1 .
- 2. -Does the propose'd licensed amendment create the possibility of a new or different kind of accident from any accident previously evaluated?. ,
Evaluation-1
-The proposed Technical Specification change deals exclusively with the off-site ,
electrical power sources for the Cooper Nuclear Station. This groposed change reflects the addition of a full -' capacity.. independent . off-sive source of .
electrical power to the plant. Cooper Nuclear: Station is designed' to respond to r
design basis accidents assuming the , coincident .' loss : of ' off-site power, and.
I analyses contained in Section XIV of the Updated Safety Analysis Report (USAR)..
~
reflect this assumption, e
l The intent of the~ additional full capacity, independent off-site source is to )
. improve the reliability of off-site power. No new or different kind of accident l.
l from any accident previously evaluated would be created since the - loss of' l
l off-site power is already assumed. 1 l
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Attachment" h
.Page-6 of 9; .j
- 3. . Does the proposed amendment involve' ~a significant reduction'in the margin
, of safety?
t Evaluation F
The proposed Technical Specification wording. change will recognize lthe addition
_to the plant of another full capacity,1 independent, source of off-site electrical power. This source wi11'significantly~ improve the reliability and availability ; -]
of off-site power sources capable of supplying power to the emergency. buses. !
However, Cooper Nuclear Station is designed to respond to design basis ' accidents assuming a coincident loss of all off-site power. Therefore,' this proposed I
change will not involve a reduction in the margin of safety. .,
i As previously described, the Technical Specification change reflects the addition.
of the 161 kV electrical source which will provide < an additional - source of ,
off site power available to the plant. The installation process for the AC power source involved standard industry practices related to transmission system l 1
equipment. The overall effect of the change is' to : improve plant safety. -
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, NLS9000310' o4 L' r 'Attachmtnt-
. FIGURE -I rog,7 or 9 161: KV J SWITCHYARD L CO NN ECTIONS- ?a i
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-TIED TO CNS 34SKV SWITCHYARD
(' 34S KV/164 KV AUTO-TRANSFORMER .
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161KV SWITCHY A R D .
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p < _;. w .I 'FIGO REL '2 ^3"'?","', ;
) CNS' OFF-SITE SOURCE CONNECTIONS:
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$ UXILtARY BREAKER C D l g. 7 igTgeg p I I EMERGENCY' 2 AU BU R N I r~ l STATION SERVICE XFMR.
' O. R R O. l L l L. _ -- _ _ _ J 161 kV -
l SWITCH YARD m 69 KV N O.R P.D. ~l l
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- ,(.G .N LIMITING-CONDITIONS FOR' OPERATION SURVEILLANCE REOUIREMENTS.
3.9 AUXILIARY ELECTRICAL SYSTEM- 4.9. AUXILIARY ELECTRICAL SYSTEM
.Aoulicability:
6EPJicabilitv: f
-1 Applies to the auxiliary electrica1H-L ' Applies to the periodic . testing power. system. requirements- of. the auxiliary ,
eleetrical. systems.
l Obiective: Obiective:
To assure - an adequate' supply of Verify the operability o'f .the electrical power for operation of auxiliary electrical' system. 'J those systems required for' safety.
~
Soecification: Soecification:
A. Auxiliarv Electrical Eculement A. Auxiliary Electrical Eautoment .
- 1. The reactor shall not be. made 1. Emergency Buses Undervoltage' Relaysi critical from a Cold Shutdown' Condition- unless 'all of the ,,
g , og voltage relays- 1 following conditions are satisfied:
- a. One off-sitei source (345 kV or once every 18 mon &s, loss of a 161 kV) and the emergency off-site voltage--on emergency buses is source (69 kV) and the' startup simulated to demonst. rate the !
transformer- and emergency load shedding fromE emergency ,
transformer are available and . buses and the automatic start capable of automatically supplying of diesel generators.
power to ' the 4160 Volt emergency buses IF and 10. 'b' . Undervoltage relays L
- b. Both diesel generators shall be' 'Once every 18 . months, low I operable and there shall be a voltage' on emergency buses is minimum of 45,000 gal. of diesel simulated- co- demonstrate fuel in the fuel oil storage tanks. disconnection.of the emergency ,
buses from the offsite power
- c. The 4160V critical buses 1F and 1G source.. The undervoltage-and the 480V critical buses IF~and relays.-shall. be calibrated 10 are energized. once,every 18 months.
- 1. The loss of voltage relays 2. Diesel Generators and their auxiliary relays I are operable, a. Each diesel-generator shall be
- 2. The undervoltage relays and- not less ' than 50% of rated-their auxiliary relays are load for no less than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> ;
operable, '
once each month to demonstrate P*#"" "" #*" "****
- d. 'The four unit 125V/250V batteries and their chargers shall be operable.
- e. The power monitoring system for the inservice RPS MG set or alternate source shall be operable.
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-193-3
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