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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARB17848, Startup Test Rept Cycle 7. with1999-09-30030 September 1999 Startup Test Rept Cycle 7. with ML20211Q3361999-09-0707 September 1999 Proposed Tech Specs Removing Current Special Exception Which Precludes Applying Eighteen Month Functional Testing Surveillance to SG Hydraulic Snubbers ML20211H6471999-08-25025 August 1999 Proposed Defueled Tech Specs,Revising Sections 5.6.1,5.7.2 & 5.7.3 & Adding Proposed Section 5.6.4 to Reflect ACs Contained in NUREG-1433 ML20210Q5211999-08-0505 August 1999 Proposed Tech Specs Sections 3.8.3.2,4.6.2.1,4.6.2.2, 4.8.1.1,4.9.12 & Bases Section B 3/4.3.2,B 3/4.6.1.2 & B 3/4.8.4,incorporating Editorial Revs ML20210C6091999-07-16016 July 1999 Proposed Tech Specs Relocating Selected TS Related to Refueling Operations & Associated Bases to Plant TRM ML20206U1041999-05-17017 May 1999 Proposed Tech Specs Section 4.4.6.2.2.e,deleting Reference to ASME Code Paragraph IWV-3472(b) Re Frequency of Leakage Rate Testing for Valves Six Inches Nominal Pipe Size & Larger ML20206M8221999-05-10010 May 1999 Restart Assessment Plan Millstone Station ML20206D1761999-04-27027 April 1999 Rev 1 to Millstone Unit 3 ISI Program Manual,Second Ten-Yr Interval ML20205R2411999-04-19019 April 1999 Rev 3 to CP2804L, Unit 2 Rx Coolant & Liquid Waste Pass ML20205R2501999-04-19019 April 1999 Rev 0 to CP2804M, Unit 2 Vent & Containment Air Pass ML20205R2751999-04-19019 April 1999 Proposed Tech Specs,Reflecting Permanently Defueled Condition of Unit ML20205S5611999-04-16016 April 1999 Rev 5 to Epop 4426, On-Site Emergency Radiological Surveys ML20205M0891999-04-0707 April 1999 Proposed Tech Specs Modifying Value for Monthly Surveillance Testing of Tdafwp ML20205E4411999-03-29029 March 1999 Rev 2 to CP 2804L, Unit 2 Rx Coolant & Liquid Waste Pass ML20196K5771999-03-24024 March 1999 Rev 1 to Chemistry Procedure CP2804L, Unit 2 Rx Coolant & Liquid Waste Pass ML20205D5321999-03-22022 March 1999 Rev 3 to RPM 2.3.5, Insp & Inventory of Respiratory Protection Equipment ML20204J1581999-03-19019 March 1999 Proposed Tech Specs Section 6, Administrative Controls, Reflecting Certified Fuel Handler License Amend Changes, Approved on 990305 ML20204J4101999-03-19019 March 1999 Proposed Tech Specs Relocating Instrumentation TSs 3.3.3.2, 3.3.3.3 & 3.3.3.4 to Mnps,Unit 2 TRM ML20204K0971999-03-19019 March 1999 Proposed Tech Specs Supporting Spent Fuel Pool Rerack to Maintain Full Core Reserve Capability Approaching End of OL ML20204F9031999-03-17017 March 1999 Proposed Tech Specs,Revising 3.5.2,3.7.1.7 & 3.7.6.1 Re ECCS Valves,Atmospheric Steam Dump Valves & CR Ventilation Sys. Associated Bases Will Be Modified as Necessary to Address Proposed Changes ML20207H9551999-03-0505 March 1999 Proposed Tech Specs Section 6.0 Re Administrative Controls ML20206K1121999-03-0505 March 1999 Proposed Tech Specs Bases Sections 3/4.7.7, CR Emergency Ventilation Sys & 3/4.7.8 CR Envelope Pressurization Sys. Changes Are Editorial in Nature ML20207F6211999-03-0303 March 1999 Rev 2,change 1 to Communications - Radiopaging & Callback Monthly Operability Test ML20207E0321999-03-0202 March 1999 Proposed Tech Specs 3/4.7.4, SW Sys, Proposing Change by Adding AOT for One SW Pump Using Duration More Line with Significance Associated with Function of Pump ML20207D4821999-02-26026 February 1999 Proposed Tech Specs Re Addl Mods Concerning Compliance Issues Number 4 ML20207J0001999-02-22022 February 1999 Rev 7 to Millstone Unit 2,IST Program for Pumps & Valves ML20206D1991999-02-11011 February 1999 Change 7 to Rev 5 to ISI-3.0, Inservice Testing Program. Pages 2 of 3 & 3 of 3 in Valve Relief Request Section 6.1 of Incoming Submittal Not Included ML20203E4051999-02-11011 February 1999 Proposed Tech Specs Re DG Surveillance Requirements ML20210D2121999-01-21021 January 1999 Proposed Tech Specs Sections 3/4.5.2 & 3/4.5.3, ECCS Subsystems for Info Only ML20199L2841999-01-20020 January 1999 Proposed Tech Specs & Final SAR Proposed Rev to Ms Line Break Analysis & Revised Radiological Consequences of Various Design Basis Accidents ML20199L0801999-01-18018 January 1999 Proposed Tech Specs Change to TS 3/4.2.2 Modifies TS to Be IAW NRC Approved W Methodologies for Heat Flux Hot Channel factor-FQ(Z).Changes to TS Section 6.9.1.6 Are Adminstrative in Nature ML20199L4561999-01-18018 January 1999 Proposed Tech Specs Revising TS Table 3.7-6, Air Temp Monitoring. Proposed FSAR Pages Describing Full Core off- Load Condition as Normal Evolution Under Unit 3 Licensing Basis,Included ML20199L3271999-01-18018 January 1999 Proposed Tech Specs 3.6.1.2, Containment Sys - Containment Leakage ML20199L0431999-01-18018 January 1999 Proposed Tech Specs Removing TS 3/4.6.4.3, Containment Systems,Hydrogen Purge Sys ML20199E0931999-01-13013 January 1999 Rev 2 to Health Physics Support Procedure RPM 2.3.4, Insp & Maint Process for Respiratory Protection Equipment ML20206P5121999-01-0404 January 1999 Proposed Tech Specs 3.5.2,3.6.2.1,3.7.1.2,3.7.3.1 & 3.7.4.1, Incorporating Changes to ESF Pump Testing B17501, 1998 - 2000 Performance Plan - Work Environ Focus Area Update1998-12-31031 December 1998 1998 - 2000 Performance Plan - Work Environ Focus Area Update ML20198K6361998-12-31031 December 1998 Proposed Tech Specs Section 6.0, Administrative Controls ML20199A7531998-12-31031 December 1998 Restart Backlog Mgt Plan Commitments ML20198P9751998-12-28028 December 1998 Proposed Tech Specs Pages Revising Loss of Normal Feedwater (Lonf) Analyses to TS 2.2.1,TS Bases Change to Floor Value for Thermal Margin Low Pressure Reactor Trip & Proposed FSAR Changes ML20196H6301998-12-0404 December 1998 Proposed Tech Specs Re Section 6.0, Administrative Controls ML20197G9831998-12-0404 December 1998 Proposed Tech Specs 4.7.10.e,eliminating Need to Cycle Plant & Components Through SD-startup Cycle by Allowing Next Snubber Surveillance Interval to Be Deferred Until End of RFO6 of 990910,whichever Date Is Earlier ML20196A2181998-11-20020 November 1998 Restart Assessment Plan Millstone Station ML20195D4041998-11-10010 November 1998 Proposed Tech Specs,Modifying Sections 3.3.1.1 & 3.3.2.1 by Restricting Time That Reactor Protection or ESF Actuation Channel Can Be in Bypass Position to 48 H,From Indefinite Period of Time ML20195D8101998-11-10010 November 1998 Revised marked-up Page of Current TS 3.8.1.1 & Revised Retyped Page Re 980717 Request to Change TS ML20195H8681998-11-0404 November 1998 Rev 4 to Millstone Unit 2 Operational Readiness Plan ML20196H5921998-10-29029 October 1998 Rev 0 to TPD-7.088, Millstone 1 Certified Fuel Handler/ Equipment Operator Continuing Training Program ML20196H5861998-10-29029 October 1998 Rev 0 to TPD-7.087, Millstone 1 Certified Fuel Handler Training Program B17548, Rev 0 to TPD-7.089, Millstone 1 Equipment Operator Training Program1998-10-29029 October 1998 Rev 0 to TPD-7.089, Millstone 1 Equipment Operator Training Program ML20155B0331998-10-22022 October 1998 Proposed Tech Specs Changing TS 3.3.2.1, Instrumentation - ESFAS Instrumentation, 3.4.9.3, RCS - Overpressure Protection Sys & ECCS - ECCS Subsystems - Tavg 300 F 1999-09-07
[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML20206M8221999-05-10010 May 1999 Restart Assessment Plan Millstone Station ML20206D1761999-04-27027 April 1999 Rev 1 to Millstone Unit 3 ISI Program Manual,Second Ten-Yr Interval ML20205R2501999-04-19019 April 1999 Rev 0 to CP2804M, Unit 2 Vent & Containment Air Pass ML20205R2411999-04-19019 April 1999 Rev 3 to CP2804L, Unit 2 Rx Coolant & Liquid Waste Pass ML20205S5611999-04-16016 April 1999 Rev 5 to Epop 4426, On-Site Emergency Radiological Surveys ML20205E4411999-03-29029 March 1999 Rev 2 to CP 2804L, Unit 2 Rx Coolant & Liquid Waste Pass ML20196K5771999-03-24024 March 1999 Rev 1 to Chemistry Procedure CP2804L, Unit 2 Rx Coolant & Liquid Waste Pass ML20205D5321999-03-22022 March 1999 Rev 3 to RPM 2.3.5, Insp & Inventory of Respiratory Protection Equipment ML20207F6211999-03-0303 March 1999 Rev 2,change 1 to Communications - Radiopaging & Callback Monthly Operability Test ML20207J0001999-02-22022 February 1999 Rev 7 to Millstone Unit 2,IST Program for Pumps & Valves ML20206D1991999-02-11011 February 1999 Change 7 to Rev 5 to ISI-3.0, Inservice Testing Program. Pages 2 of 3 & 3 of 3 in Valve Relief Request Section 6.1 of Incoming Submittal Not Included ML20199E0931999-01-13013 January 1999 Rev 2 to Health Physics Support Procedure RPM 2.3.4, Insp & Maint Process for Respiratory Protection Equipment B17501, 1998 - 2000 Performance Plan - Work Environ Focus Area Update1998-12-31031 December 1998 1998 - 2000 Performance Plan - Work Environ Focus Area Update ML20199A7531998-12-31031 December 1998 Restart Backlog Mgt Plan Commitments ML20196A2181998-11-20020 November 1998 Restart Assessment Plan Millstone Station ML20195H8681998-11-0404 November 1998 Rev 4 to Millstone Unit 2 Operational Readiness Plan ML20196H5921998-10-29029 October 1998 Rev 0 to TPD-7.088, Millstone 1 Certified Fuel Handler/ Equipment Operator Continuing Training Program B17548, Rev 0 to TPD-7.089, Millstone 1 Equipment Operator Training Program1998-10-29029 October 1998 Rev 0 to TPD-7.089, Millstone 1 Equipment Operator Training Program ML20196H5861998-10-29029 October 1998 Rev 0 to TPD-7.087, Millstone 1 Certified Fuel Handler Training Program ML20154G5311998-10-0707 October 1998 Rev 4 to Project Procedure PP-02, Accident Mitigation Sys Review ML20154G5391998-10-0606 October 1998 Rev 6 to Project Procedure PP-07, Discrepancy Repts ML20154G5351998-10-0606 October 1998 Rev 3 to Project Procedure PP-04, Regulatory Review Procedure ML20154G5521998-10-0606 October 1998 Rev 5 to Project Instruction PI-01, Svsr Implementation Checklists & Workbook ML20154G5251998-10-0505 October 1998 Rev 4 to Independent C/A Verification Program for Millstone Unit 2 Audit Plan ML20236Q9341998-06-30030 June 1998 Rev 4 to PI-01, Sys Vertical Slice Review Implementation Checklists & Workbook ML20236Q9321998-06-25025 June 1998 Rev 4 to PP-01, Sys Vertical Slice Review ML20153C6171998-06-18018 June 1998 Rev 2 to CP 3804K, PASS Rcs/Rss Sample ML20153C6221998-06-18018 June 1998 Rev 1 to CP 3804L, PASS Containment Air Sample ML20153C6291998-05-31031 May 1998 Rev 0,Change 1 to CP 3804M, PASS Ventilation Samples ML20247R7851998-05-20020 May 1998 Rev 1 to Epop 4455C, Technical Assistant ML20247Q7011998-05-20020 May 1998 Rev 1 to Epop 4490, Implementation of Recovery Operations ML20247R8081998-05-20020 May 1998 Rev 1 to Epop 4455F, Rumor & Inquiry Control ML20247Q6671998-05-20020 May 1998 Rev 1 to Epop 4422A, Thermal Hydraulic Evaluation Methods ML20247Q6901998-05-20020 May 1998 Rev 1 to Epop 4475A, External Resources Coordinator ML20247R7921998-05-20020 May 1998 Rev 1 to Epop 4455D, News Releases ML20247Q6771998-05-20020 May 1998 Rev 1 to Epop 4428I, Direction of Posl Field Sampling ML20247R7541998-05-20020 May 1998 Rev 1 to Epop 4455A, Nuclear News Manager ML20247R7491998-05-20020 May 1998 Rev 1 to Epop 4455, Manager of Public Info ML20216B1791998-05-0808 May 1998 Independent Corrective Action Verification Program for Millstone Unit 3,Interim Rept,Executive Summary ML20247H4581998-04-0909 April 1998 Rev 19 to EOP 35 E-0, Reactor Trip or Safety Injection B17159, Backlog Mgt Plan for Unit 31998-03-31031 March 1998 Backlog Mgt Plan for Unit 3 ML20216K0641998-03-20020 March 1998 Rev 2 to Oversight Plan NNECO - Millstone Site Independent Third Party Oversight Program ML20216H7101998-03-13013 March 1998 Independent Corrective Action Verification Program Status Rept ML20216H7191998-03-0303 March 1998 Independent Corrective Action Verification Program Status Rept ML20203F6931998-02-20020 February 1998 Rev 6 to PI-MP3-11, Discrepancy Rept Submittal & Closure ML20203E2131998-02-19019 February 1998 Cancelled Rev 26 to 1-OPS-10.11, Locked Valve List ML20203D4111998-02-18018 February 1998 Revised 1-OM-index Unit 1 Operations Dept OM Index & Rev 2 to OM 3.8, Millstone Unit 1 Operations Manual ML20203F6751998-02-16016 February 1998 Rev 2 to PI-MP3-07, Review of Accident Mitigation Systems ML20203F6601998-02-16016 February 1998 Rev 5 to Audit Plan for Independent Corrective Action Verification Program ML20216H7351998-02-11011 February 1998 Independent Corrective Action Verification Program Status Rept 1999-05-10
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8-25-83 E.J. Mroczka Form Approved by Station Superintendent Effective Date STATION PROCEDURE COVER SHEET A. IDENTIFICATION Number OP 340 Rev. 21 Title ~24K ELECTRICAL SYSTEM Prepared By Gregg Sauer ,
B. REVIEW I have reviewed the above procedure and have found it to be satisfactory.
TITLE SIGNATURE DATE DEPARTMENT HEAD /r' oi /o!.Ud sco WM I
Al-> En[
C. UNREVIEWED SAFETY QUESTION EVALUATION DOCUMENTATION REQUIRED:
p (Significant change in procedure method or scope C/ as described in FSAR) YES [ ] NO[g (If yes, document in PORC/SORC meeting minutes)
ENVIRONMENTAL IMPACT (Adverse environmental impact) YES [ ] NO [
(If yes, document in PORC/SORC meeting minutes)
D. PROCEDURE REQUIRES PORC/SORC REVIEW YES NO [ ]
E. OS /SORC APPROVAL
~
ORC Meeting Number k N- M2 F. APPROVAL AND IMPLEMENTATION The attached procedure is hereby approved, and effective on the date below:
h sy # // fo .7WP Station / Service / Unit W erintendent Effective Date SF-301 Rev. 6
, s J l 8510290393 851004 :
PDR ADOCK 05000245 i P PDR- '
OP 340 Pegn 53
, Rev. 21 8.32 Alternator Field Ground. '
8.32.1 Location:
8.32.1.1 CRP 907, Section A2-2 (39B), Window 6-7 8.32.2 Initiating Device:
8.32.2.1 64FA Relay 8.32.3 Setpoint:
8.32.3.1 1000 ohms to ground. ,
8.32.4 Automatic Action:
8.32.4.1 Alarm only.
8.32.5 'Immediate Operator Action:
8.32.5.1 Initiate action to have electrician determine cause of ground.
8.32.6 Subsequent Operator Action:
8.32.6.1 If ground can't be located or repaired shutdown the alternator.
8.33 Failure of 15G-5T-2 and 15G-6T-2 Breakers to Open Following Generator Lockout Relay Operation
)
NOTE: The following step should only be taken as an emergency means of generator / grid separation after it has been determined that normal lockout tripping function has not occurred.
8.33.1 Simultaneously depress both pushbuttons on CRP 907 labelled "5T and 6T Emergency Trip".
8.34 RSST Undervoltage Channel "A" 8.34.1 Location:
8.34.1.1 CRP 908, Section Al-1 (54A), Window 7-3 8.34.2 Initiating Device:
8.34.2.1 AGASTAT 62/2A 8.34.3 Setpoint:
8.34.3.1 Low primary voltage, 345 kv setpoint on RSST or CB IAC 51/52 and VAC 51/52 are open.
s t
- ~ _ _ _ . . _ _ - - . _ - _
OP 340 Page 54
, Rev. 21 8.34.4 Automatic Action:
8.34.4.1 Alarm only.
NOTE: Be aware of a possible RSST low side breakers opening if a low voltage condition is present during a plant accident (MCA).
8.34.5 Immediate Operator Action:
8.34.5.1 Call CONVEX to raise system voltage above 345 kv.
8.34.5.2 If the 345 system voltage cannot be main-tained above 345 kv, 347 kv when supplying Unit 2 with shutdown power, notify the Duty Officer.
NOTE: The reason for the preceeding
- 1) voltage limits is the possibility of long term degradation of safety related motors.
8.34.6 Subsequent Operator Action:
8.34.6.1 If the system voltage is greater than 345 kv (347 kv when supplying Unit 2) and the reactor is in cold shutdown, open the undervoltage trip disconnect on the back of CRP-9228.
8.34.6.2 If the reactor is operating and the generator is synchronized to the system and either the 345KV system voltage cannot be maintained above 345KV, (347KV when supplying Unit 2), or the generator current is greater than 17.5 kilo amps as indicated on CRP-907 then carry out the following:
OP 340 Page 55
, Rev. 21 8.34.6.2.1 Notify convex of your intention to reduce reactor power using the recirculation pesps. This will reduce the generator current to the normal cperating reading of 117.5 kilo amps as indicated on CRP-907.
8.34.6.2.2 Continue to reduce reactor power until the generator current has returned to a normal reading of 117.5 kilo amps. Normally within a 10%
power reduction the generator current will have returned to normal.
0 NOTE: If after a 10%
power reduction the 345KV system voltage hasn't returned, this is indicative of a major problem.
8.34.6.2.3 Start the gas turbine and diesel generator and let idle.
8.34.6.2.4 Monitor bus voltage on buses 14A, 14B, 14C, 14D.
If the voltage drops to 3646 volts on any two buses notify Convex that we want to open the 15G-5T-2 and'
OP 340 Paga 56
, Rev. 21 15G-6T-2 breakers. Before opening the 15G-5T-2 and 15G-6T-2 open the main steam bypass valves about 10%
using the speed load changer. With Convex permission open the.15G-5T-2 and 15G-6T-2 breakers using the Getac. Do not use the ST& 6T Emergency trip buttons on CRP-907 as this will also trip the turbine.
8.34.6.2.5 Adjust generator speed and excitations using the speed load changer and the Auto field voltage adjust switches.
8.34.6.2.6 Refer to ONP-503A for added procedural guidance.
8.35 RSST Undervoltage Channel "B" 8.35.1 Location:
8.35.1.1 CRP 908, Section Al-1 (54A), Window 7-4 8.35.2 Initiating Device:
8.35.2.1 AGASTAT 62/28 8.35.3 Setpoint:
8.35.3.1 Low primary voltage, 345 kv setpoint on l RSST or CB IAC 51/52 and VAC 51/52 are open.
8.35.4 Automatic Action:
8.35.4.1 Alarm only.
NOTE: Be aware of a possible RSST low side breakers opening if a low s
OP 340 Pag 2 57
. Rev. 21 S
voltage condition is present during a plant accident (MCA).
8.35.5 Immediate Operator Action:
8.35.5.' Call CONVEX to raise the system voltage above 345 kv.
8.35.5.2 If the 345 kv system voltage cannot.be maintained above 345 kv (347 kv when supplying Unit 2 with shutdown power) notify the Duty Officer.
NOTE: The reason for the preceeding voltage limits is the possibility of long term degradation of safety related motors.
C.35.6 Subsequent Operator Action:
8.35.6.1 If the system voltage is greater than 345 kv (347 kv when supplying Unit 2) and the reactor is in cold shutdown, open the Undervoltage Trip Disconnect on the back of CRP-922A.
8.35.6.2 If the reactor is operating and the generator is synchronized to the system and either the 345KV system voltage cannot be maintained above 345KV, (347KV when supplying Unit 2),
or the generator current is greater than 17.5 Kilo amps as indicated on CRP-907 then carry out the following:
8.35.6.2.1 Notify convex of your intention to reduce reactor power using the recirculation pumps. This s
l 9
OP 340 Paga 58 Rev. 21
'S will reduce the generator current to the normal operating reading of 117.5 Kilo amps as indicated on CRP-907.
8.35.6.2.2 Continue to reduce reactor power until the generator current has returned to a normal reading of $17.5 kilo amps. Normally within a 10%
power reduction the generator current will have returned to normal.
NOTE: If after a 10%
power reduction the 345KV system i voltage hasn't returned, this is indicative of a major problem.
8.35.6.2.3 Start the gas turbine and diesel generator and let idle.
8.35.6.2.4 Monitor bus voltage on buses 14A, 14B, 14C, 140.
If the voltage drops to 3646 volts on any two buses notify Convex that we want to open the 15G-ST-2 and 15G-6T-2 breakers. Before opening the 15G-5T-2 and 15G-6T-2 open the main steam s
1 1
OP 340 Paga 59 '
Rev. 21 3
bypass valves about 10% using the speed load changer. With Convex permission open the 15G-ST-2 and 15G-6T-2 breakers using the Getac. Do Not use the ST&6T Emergency trip buttons on CRP-907 as this will also trip the turbine.
8.35.6.2.5 Adjust generator speed and excitation using the speed load changer and the auto field voltage adjust switches.
8.35.6.2.6 Refer to ONP-503A for added procedural guidance.
8.36 Main Transformer High Temperature 8.36.1 Location: Panel 907 Sectica A2-1 (398) Window 7-2 8.36.2 Instrument: 49X and/or 26QX 8.36.3 Setpoint: Winding temp reached 120 C or Oil temp has reached 90 C 8.36.4 Automatic Action: Alarm only 8.36.5 Immediate Action 8.36.5.1 Verify temp on recorder at panel 931 and at transformer.
8.36.5.2 If verifed, back down on generation to allow transformer to cool below alarm point.
l 8.36.6 Subsequent Action 8.36.6.1 Notify Convex '
j 8.36.6.2 If not verified, call station electrician l
to troubleshoot alarm. .
8.37 Generator 345KV Bus BU Pilot Wire Failure 8.37.1 Location: Panel 907 Section A2-2 (398) Window 3-6 l
- e-APPRCNED BY DA'IE M8 Y E0EM NO, 230-704 7- 2A -O " CRP-908 Al-1 -REV. 4 -
PORC MLU NO /- 7fac r DATE F/JJ/sy 4 KV BUS 14A ,4 W BUS 14A 4 KV BUS 14A 4 KV BUS 14A GROUND FEEDER GROUND NORM. SS TRANSEMMER RES SS TRANSEVEGER (1-1) (1-2) TRIP (1-3) TRIP (1-4) 4 KV BUS 14B 4 KV BUS 14B 4 KV BUS 14B 4 KV BUS 14B GROUND FEEDER GROUND NORM. SS 'IRANSEMMER RES. SS TRANSEMMER .
(2-1) (2-2) TRIP (2-3) TRIP (2-4) 4 KV BUS 14C 4 KV BUS 14C 4 KV BUS 14C 4 KV BUS 14C GROUND FEEDER GROUND NORM. SS TRANSEU MER RES. SS TRANSEW MER (3-1) (3-2) TRIP (3-3) TRIP (3-4)
.4 KV BUS 14D 4 KV BUS 14D 4 KV BUS 14D 4 KV BUS 14D GROUND FEEDER GROUND NORM. SS TRANSEU MER RES. SS TRANSEMMER (4-1) (4-2) TRIP (4-3) TRIP (4-4) 480 V BUS 12C 480 V BUS 12C 480 V BUS 12 C A m 480 V BUS 12C GROUND (5-1) FEEDER TRIP (5-2) 12D IN PARALLEL (5-3) IOSS OF DC CW POWER (5-4)
IIEE NATER FION LUBE NATER FIOf IUBE WATER FICW IUBE NATER FICW SW FS-4-2A ID FION (6-1) SW FS-4-2B ION FIOf (6-2) SW FS-4-2C ID FION (6-3) SW FS-4-2D ID FICW (6-4)
PRI PIIDP WIRE AUITNATIC POLURIN RSST Ut0ERVOL'DGE RSST UBOERVOLTAGE IMS OF DC (7-1) M NTIOR TROUBLE (7-2) OIA MEL A (7-3) OIA M EL B (7-4)
/
BK UP PIIUP WIRE ELBCP. IPR INLET FILTER AMUNCIA'ICR SUPPLY STA. BAITERY 101A IOSS T DC (8-1) DIFF. PRESS (HI-HI) (8-2) NBGATIVE GROUfo (8-3) Ot11 bur BRKR OPDi (8-4)
BACK UP 15 PSI IOSS T DC POWER GAS 'IURBINE AWUNCIA'IOR SUPPLY GEN. CORE MENTIOR CCNTR. BM. PNL TRCUBLE POSITIVE GR0t.20 HIGH LEVEL (CC 11A-2) (9-1) .(9-2) (9-3) (9-4) e-il/CRP1 FORM No. 230-704 REV. 4
.. APPROVED BY: #/4//det. DATE: V- / 5 - S 2. PORC MTG fiO: /- 2IcSt / _
)
p
~
ANNUf1CIATOR ALARM AfiD RESPONSE .
~ ~
PANEL / SECTIO;; 908 Ai-1
. WINDOW ALARM TITLE RSS,T Undervoltage Channel A INSTRUME?iT AND SETPOINT
) 62-2A Relay - Low Primary voltage,'34,3 KV setpoint on RSST or CB IAC .
J, 51/52 and VAC.51/52 are open.
j .- . ,
j '
AUTO:'ATIC ACTICN .
. . . ~.
Alarm only - ,- ,
NOTE: Be aware of a possible RSST low s'ide breakers opening if a low t
voltatje condition is pre.sent during a plant accident (MCA).'
- 1. Call Convex to' raise system voltage above 343 KV. - -
- 2. If the 345 syster voltage cannot be maintained above 341 K'V, 347 KV when suppling Unit 2 with shutdown power, notify the duty officer.
~
NOTE: The reason for the preceeding voltage ,Iimits is the possibility of long term degradation of safety related motors.
I SUBSCOVENT ACTIGil '
OP 340 Section 8.34.6 REfERENC C 0.P. 340 TECH. SPEC. _ NA P.&.I.D.
NA C.W.D. 222 OPS FORM 230-756 PEV n
AFer8s, w s :; # / /v4/ f *C// DATE: --) s2 PORC fiiG ti3: /-2<-</
3 .
) '
- ANNUtiCIATOR ALARM AfiD RESPCNSE .
PANEL /SECTION 908 Al-1 -
WIfiD0',1 7-4 ALARM TITLE .
RSS,T Undervol'tage Channel B INSTRUMENT A:D SETPOI:T e . . .
62-2B , Relay - Low primary voltage, 345 KV setpoint on RSST or CB IAC '
! 51/52 and VAC 51/52 are open _ -
j . . -
j -
AUTOMATIC ACTICil , ,
Alann only . ,,. ,
NOTE: Be aware of a' 'possible RSST low si'de breakers opening if a low voltage condition is,present dur'ing a~~ plant accident (MCA).
))
IMMEDIATE ACTION . .
Call Convex to raise sysrtem voitage above 343 KV.
- 1. .
- 2. If the 345 system voltage cannot be maintained above 341 KY, 347 KV when supplying. Unit 2 with shutdown power, notify the duty officer.
~
.- NOTE: The reason for the prec'eeding voltage limifs is the ' possibility of long tenn degradation of safAty related motors.
SUBSECUE!!T ACTIO!!
, OP 340 Section 8.35.6 l .
R,EFE P.E!:::S
[
O.P. 340
- TECH. SPEC. NA P.& I.D. na C.W.D. 222 ___
"; FC " 230-7E7 R:V. O