|
---|
Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
MONTHYEARML17309A9961999-06-30030 June 1999 Rev 35 to HP-90, Emergency Equipment. ML17309A9941999-06-17017 June 1999 Rev 1 to COP-06.06, Guidelines for Collecting Post Accident Samples. ML17241A3541999-06-0101 June 1999 Proposed Tech Specs Section 3.5.2,allowing Up to 7 Days to Restore Inoperable LPSI Train to Operable Status ML17309A9951999-05-27027 May 1999 Rev 0 to COP-06.11, Establishing Remote Lab for Analyses of Accident Samples. ML17241A3451999-05-24024 May 1999 Proposed Tech Specs 3/4.5.1 Re Safety Injection Tanks ML17229B0711999-03-19019 March 1999 Proposed Tech Specs Pages Requested by NRC for Use in Issuance of Proposed License Amend Re SFP Storage Capacity, Per Soluble Boron Credit ML17229B0441999-03-0202 March 1999 Cycle 11 Reactor Startup Physics Testing Rept. with 990304 Ltr ML17229B0201999-02-23023 February 1999 Proposed Tech Specs 3/4.1.2.9 Re Reactivity Control sys- Boron Dilution ML17229B0361998-12-22022 December 1998 Rev 20 to Procedure C-200, Odcm. ML17229A9551998-12-16016 December 1998 Proposed Tech Specs Pages Revising Administrative Controls & Incorporating Specific Staff Qualifications for Multi- Discipline Supervisor Position ML17229A9161998-11-25025 November 1998 Proposed Tech Specs Pages,Replacing Insert-A,attachment to 971231 Submittal & Revises LCO 3.4.9.11 & Associated Bases ML17229A9251998-11-22022 November 1998 Proposed Tech Specs Revising Thermal Margin SL Lines of TS Figure 2.1-1 to Reflect Increase in Value of Design Min RCS Flow from 345,000 Gpm to 365,000 Gpm & Change Flow Rates Stated in Tables 2.2-1 & 3.2-1 ML17229A9131998-11-19019 November 1998 Proposed Tech Specs,Revising Administrative Contols TS 6.3, Unit Staff Qualifications & Incorporating Specific Staff Qualifications for Multi-Discipline Supervisor (MDS) Position ML20155C3061998-10-29029 October 1998 Proposed Tech Specs Pages Revising Terminology Used in Notation of TS Tables 2.2-1 & 3.3-1 Re Implementation & Automatic Removal of Certain Reactor Protection Sys Trip Bypasses ML20153G0781998-08-26026 August 1998 Rev 19 to Plstqp, Guard Training & Qualification Plan ML17229A8441998-08-24024 August 1998 Proposed Tech Specs Removing Obsolete License Conditions & Incorporating Revs Which Clarify Component Operations That Must Be Verified in Response to Containment Sump Recirculation Actuation Signal ML17229A7731998-06-15015 June 1998 Proposed Tech Specs Pages 6-20,6-20a & 6-20c,correcting Info Supplied by Fuel Vendor Relative to Titles of Approved TRs That Are Referenced in Proposed TS 6.9.1.11.b ML17229A7601998-06-0303 June 1998 Proposed Marked Up TS Pages Modifying Explosive Gas Mixture Surveillance Requirement 4.11.2.5.1 to Provide for Use of Lab Gas Partitioner to Periodically Analyze Concentration of Oxygen in Svc Waste Gas Decay Tank ML17229A7441998-05-27027 May 1998 Proposed Tech Specs Providing for More Efficient Use of on- Site Mgt Personnel in Review & Approval Process for Plant Procedures ML17229A7481998-05-27027 May 1998 Proposed Tech Specs Section 3.5.1,removing Requirement for SITs to Be Operable in Mode 4,which Will Minimize Potential for Inadvertent SIT Discharge During RCS Cooldown/ Depressurization Evolutions ML17229A7511998-05-27027 May 1998 Proposed Tech Specs Section 6.2.2.f,revised to Allow for Use of Longer Operating Shifts of Up to Twelve Hours Duration by Plant'S Operating Crews ML17229A6751998-03-27027 March 1998 Cycle 15 Reactor Startup Physics & Replacement SG Testing Rept. W/980402 Ltr ML17229A6501998-03-0303 March 1998 Proposed Tech Specs 3.4.7 Re RCS Chemistry/Design Features/ Administrative Controls ML17229A6381998-02-12012 February 1998 Rev 19 to C-200, Offsite Dose Calculation Manual. ML17229A6151998-01-12012 January 1998 Rev 0 to ISI-PSL-1, St Lucie Nuclear Plant Unit 1 ISI Plan. ML17229A6141998-01-12012 January 1998 Rev 0 to ISI-PSL-1, Third Interval ISI Program for St Lucie Nuclear Power Plant,Unit 1. ML17229A5691997-12-31031 December 1997 Proposed Tech Specs Pages Modifying TS 5.6.1 & Associated Figure 5.6-1 & TS 5.6.3 to Accomodate Increase in Allowed SFP Storage Capacity ML17309A9131997-12-29029 December 1997 Proposed Tech Specs Modifying Specifications for Selected cycle-specific Reactor Physics Parameters to Provide Reference to St Lucie Unit 2 COLR for Limiting Values ML17229A5851997-12-12012 December 1997 Rev 0 to ADM-29.01, IST Program for Pumps & Valves. ML17229A5491997-12-0101 December 1997 Proposed Tech Specs Revising Units 1 & 2 EPP Section 4, Environ Conditions & Section 5, Administrative Procedures to Incorporate Proposed Terms & Conditions of Incidental Take Statement Included in Biological Opinion ML17309A9171997-11-26026 November 1997 Rev 0 to PSL-ENG-SENS-97-068, Spent Fuel Pool Dilution Analysis. ML17229A5931997-09-26026 September 1997 Rev 4 to Procedure QI-5-PSL-1, Preparation,Rev,Review/ Approval of Procedures. ML17229A5921997-09-18018 September 1997 Rev 0 to Procedure ADM-17.11, 10CFR500.59 Screening. ML20211Q5841997-09-10010 September 1997 Rev 18 to Training & Qualification Plan ML17229A4621997-08-22022 August 1997 Proposed Tech Specs Pages,Revising Specification 4.0.5 Surveillance Requirements for ISI & Testing of ASME Code Class 1,2 & 3 Components,To Relocate IST Program Requirements to Administrative Control Section 6.8 ML17229A4341997-08-0101 August 1997 Proposed Tech Specs,Extending semi-annual Surveillance Interval Specified in Table 4.3-2 for Testing ESFAS Subgroup Relays to Interval Consistent W/Ceog Rept CEN-403,Rev 1-A for March 1996 & Associated SE ML17309A8951997-06-11011 June 1997 Rev 0 to PL-CNSI-97-004, Transportation & Emergency Response Plan for St Lucie Unit 1 SG Project. ML17229A3601997-05-29029 May 1997 Proposed Tech Specs Incorporating Administrative Changes That Improve Consistency Throughout TSs & Related Bases ML17229A2981997-03-0606 March 1997 Final Analysis of Radiological Consequences of Main Steam Line Break Outside Containment for St Lucie Unit 1 NPP Using NUREG-0800 Std Review Plan 15.1.5 App A. ML17229A1831996-12-20020 December 1996 Proposed Tech Specs Re Safety Limits & Limiting Safety Sys Settings ML17229A1611996-12-0909 December 1996 Proposed Tech Specs 1.9a Re Core Operating Limits Rept ML17229A1191996-10-31031 October 1996 Proposed Tech Specs 6.0 Re Administrative Controls ML17229A1111996-10-30030 October 1996 Proposed Tech Specs 3/4.9.9 Re Containment Isolation Sys & 3/4.9.10 Re Water level-reactor Vessel ML17229A1061996-10-28028 October 1996 Proposed Tech Specs 1.6 Re Channel Functional test,1.7 Re Containment Vessel integrity,1.8 Re Controlled leakage,1.9 Re Core alteration,3/4.6 Re Containment Systems & 3/4.6.1 Re Containment Vessel ML17229A1091996-10-28028 October 1996 Proposed Tech Specs Rev to Allow Type A,B & C Containment Leakage Tests to Be Conducted at Extended Intervals Determined by performance-based Criteria ML17229A0951996-10-24024 October 1996 Rev 0 to 00000-OSW-16, In-Situ Pressure Test Results for St Lucie Unit 1 Spring 1996 Outage. ML17229A0861996-10-18018 October 1996 Startup Physics Testing Rept. W/961018 Ltr ML17229A2441996-09-23023 September 1996 Rev 18 to Offsite Dose Calculation Manual (Odcm). ML17228B5641996-07-15015 July 1996 Revised Tech Specs Re Core Alteration Definition ML17229A0961996-06-12012 June 1996 Rev 0 to TR-9419-CSE96-1101, Test Rept - SG Tube In-Situ Hydrostatic Pressure Test Tool Hydro Chamber Pressure Determination. 1999-06-30
[Table view] Category:TEST/INSPECTION/OPERATING PROCEDURES
MONTHYEARML17309A9961999-06-30030 June 1999 Rev 35 to HP-90, Emergency Equipment. ML17309A9941999-06-17017 June 1999 Rev 1 to COP-06.06, Guidelines for Collecting Post Accident Samples. ML17309A9951999-05-27027 May 1999 Rev 0 to COP-06.11, Establishing Remote Lab for Analyses of Accident Samples. ML17229B0361998-12-22022 December 1998 Rev 20 to Procedure C-200, Odcm. ML20153G0781998-08-26026 August 1998 Rev 19 to Plstqp, Guard Training & Qualification Plan ML17229A6381998-02-12012 February 1998 Rev 19 to C-200, Offsite Dose Calculation Manual. ML17229A6151998-01-12012 January 1998 Rev 0 to ISI-PSL-1, St Lucie Nuclear Plant Unit 1 ISI Plan. ML17229A6141998-01-12012 January 1998 Rev 0 to ISI-PSL-1, Third Interval ISI Program for St Lucie Nuclear Power Plant,Unit 1. ML17229A5851997-12-12012 December 1997 Rev 0 to ADM-29.01, IST Program for Pumps & Valves. ML17229A5931997-09-26026 September 1997 Rev 4 to Procedure QI-5-PSL-1, Preparation,Rev,Review/ Approval of Procedures. ML17229A5921997-09-18018 September 1997 Rev 0 to Procedure ADM-17.11, 10CFR500.59 Screening. ML20211Q5841997-09-10010 September 1997 Rev 18 to Training & Qualification Plan ML17309A8951997-06-11011 June 1997 Rev 0 to PL-CNSI-97-004, Transportation & Emergency Response Plan for St Lucie Unit 1 SG Project. ML17229A2981997-03-0606 March 1997 Final Analysis of Radiological Consequences of Main Steam Line Break Outside Containment for St Lucie Unit 1 NPP Using NUREG-0800 Std Review Plan 15.1.5 App A. ML17229A2441996-09-23023 September 1996 Rev 18 to Offsite Dose Calculation Manual (Odcm). ML17229A0971996-06-10010 June 1996 Rev 0 to TP-9419-CSE96-2104, Steam Generator Tube In-Situ Hydrostatic Pressure Test Tool Hydro Chamber Pressure Determination. ML20137P3651996-05-20020 May 1996 Rev 5 to Procedure 1-1220055, Calibration of Area Radiation Monitoring Sys (Arms) ML17228B4921996-04-22022 April 1996 FPL St Lucie Unit 1 SG Program. ML20137P3381996-03-0404 March 1996 Rev 0 to Procedure 1-1400207, Calibr of Containment Process Monitor ML20137K6111995-12-0707 December 1995 Auxiliary Feedwater Pump 1C Disassembly Insp & Reassembly Mechanical Maint Procedure for St Lucie Plant,Unit 1 ML17228B3461995-11-16016 November 1995 Rev 0 to Plant Administrative Procedure 2-0010024, Inservice Testing Program for Pumps & Valves. ML20137P3061995-08-31031 August 1995 Rev 2 to Procedure 2-1220057, Functional Testing of RM-80 Power Supply Assemblies ML17228B0491995-02-0303 February 1995 Rev 0 to Subsequent Inservice Exam Plan for Pressurizer Instrument Nozzles. ML17228B0171995-01-0606 January 1995 Rev 5 to Second 10-Yr ISI Interval IST Program for Pumps & Valves St Lucie Nuclear Power Plant Unit 1. ML17228A8811994-09-28028 September 1994 Rev 0 to PSL-200-AOA-94-1, St Lucie Nuclear Plant,Unit 2 ISI Interval Request for Authorization of Alternative Exam. W/Attachment Re Implementation of Reg Guide 1.150 ML20137M1611994-09-15015 September 1994 Rev 2 to Procedure 1-1220053, Calibr of Control Room Outside Air Intake Monitors ML20080M4881994-06-14014 June 1994 Rev 15 to Chemistry Procedure C-200, Odcm ML20080M4791994-01-14014 January 1994 Rev 14 to Chemistry Procedure C-200, Odcm ML17228A4621994-01-14014 January 1994 Rev 4 to Second Ten-Yr ISI Interval IST Program. ML17228A2471993-07-24024 July 1993 Rev 0 of PSL-201, St Lucie Nuclear Power Plant,Unit 2 Second ISI Interval ISI Selected Component Schedule. ML17228A2461993-07-24024 July 1993 Rev 0 of PSL-200, St Lucie Nuclear Power Plant,Unit 2 Second ISI Interval Program Plan & Schedule from 930808- 200808 ML20137P3551993-03-0808 March 1993 Rev 1 to Procedure 1-1220055, Calibration of Area Radiation Monitoring Sys (Arms) ML17227A6011992-08-11011 August 1992 Rev 2 to JNS-PSL-204, First Ten-Year Inservice Inspection Interval Inservice Testing Program for Pumps & Valves, St Lucie Nuclear Power Plant,Unit 2. ML20141M4901992-07-30030 July 1992 Rev 14 to Training & Qualification Plan ML20137P3431992-04-10010 April 1992 Rev 1 to Procedure 1-1220053, Calibration of Control Room Putside Air Intake Monitors ML17223B2931991-10-10010 October 1991 Rev 3 to JNS-PSL-203, Second 10-Yr Inservice Insp Interval Inservice Testing Program for Pumps & Valves,St Lucie Nuclear Power Plant,Unit 1. ML20137P2971991-07-0303 July 1991 Rev 1 to Procedure 2-1120070, Containment High Range Radiation Monitor Calibration ML20070T9761991-03-12012 March 1991 Rev 10 to Training & Qualification Plan ML17223A5771990-03-0707 March 1990 Rev 10 to Emergency Procedure 1-0030143, Total Loss of Ac Power. ML17223A4501989-12-15015 December 1989 Rev 2 to JNS-PSL-203, Second 10-Yr Inservice Insp Interval Inservice Testing Program for Pumps & Valves. ML17308A1901988-08-24024 August 1988 Vols 1 & 2 to Rev 0 to JNS-PSL-100, St Lucie Plant Unit 1 Second 10-Yr Insp Plan. ML17221A7041988-04-0404 April 1988 Rev 0 to Pump & Valve Inservice Test Program. ML17342B0641987-12-30030 December 1987 Rev 1 to Independent Mgt Appraisal Program Plan for Florida Power & Light Co. ML17308A1831987-09-0202 September 1987 Rev 0 to Inservice Insp Second 10-yr Summary Program. ML17221A3781987-08-11011 August 1987 Inservice Testing Program,Section I,Valve Test Program & Section Ii,Pump Test Program. ML17221A3961987-01-28028 January 1987 Rev 1 to St Lucie Unit 1,Extraction Steam Piping Insp Program Guidelines. ML17347A2241986-12-22022 December 1986 Emergency Plan Implementing Procedures,Including Procedure 1101, Duties of Emergency Control Officer,Offsite Emergency Organization & Procedure 1102, Duties of Recovery Officer,Offsite Emergency.... W/861222 Ltr ML17216A6651986-06-17017 June 1986 Rev 4 to Maint Procedure 2-0910053, 12-Month Test of Automatic Load Sequence Relays. ML17216A6661986-03-26026 March 1986 Rev 5 to Maint Procedure 2-2200063, 2B Emergency Diesel Electrical Insp. ML17216A6671986-03-26026 March 1986 Rev 4 to Maint Procedure 2-2200062, 2A Emergency Diesel Electrical Insp. 1999-06-30
[Table view] |
Text
FLORIDA POWER & LIGHT COMPANY ST. LUCIE UNIT NO. 1 EMERGENCY OPERATING PROCEDURE NUMBER 1-0030143 REVISION 0
1.0 TITLE
TOTAL LOSS OF AC POWER
2.0 APPROVAL
Reviewed by Facility Review Group 19 Approved by Plant Manager 8 -+ 199 ~
Revision Reviewed by FRG 19 Approved by Plant Manager 19 3.0 PURPOSE AND DISCUSSION:
3.1 See Appendix A.
4.0 SYMPTOMS
4.1 Loss of powe to 1A1, 1B1 6.9KV Bus.
4.2 Lo'ss of power to 1A2, 1A3, 1B2, 1B3 and 1AB 4 '16KV Bus.
5.0 INSTRUCTIONS
5.1 Automatic Actions 5.1.1 Reactor Trip.
4 Turbine Trip/Generator Lockout.
5.1.3 Auxiliary Feedwater Auto Actuation.
5 '.4 PORV's Operate.
8209i40i50 820907 PDR ADOCK 05000335 P PDR
Page 2 of STo LUCIE UNIT NO ~ 1 EMERGENCY OPERATXNG PROCEDURE ABBER 0030143, REVISION 0 TOTAL LOSS OF AC POWER
5.0 INSTRUCTIONS
(Cont.)
5.2 Immediate 0 erator Actions 5.2.1 Insure all CEA's on bottom, and reactor trip breakers open.
5.2.2 Insure Auxiliary Feedwater Pump'C is restoring Steam Generator level.
5.2.3 Place Reheat Control System in MANUAL and close TCY's.
5.2.4 Insure PORU's reseat if actuated. If not; close appropriate block valve(s).
page 3 of 9 ST. LUCZE UNIT NO. 1 EMERGENCY OPERATING PROCEDURE NUMBER 0030143, REVISION 0 TOTAL LOSS OF AC POVER
5.0 ZiVSTRUCTIONS
(Cont.)
5.3 Subse uent Actions 5.3.1 Insure generator OCB's and field breaker open.
5.3.2 Open 30102 (S.U. Transformer to 1A1 6.9KV bus).
Open 30202 (S.U. Transformer to 1B1 6.9KV bus).
Open 20102 (S.U. Transformer to lA2 4 .16KV bus).
Open 20302 (S.U. Transformer to 1B2 4.16KV bus) .
5.3.3 Insure D/G breakers open (lA-20211 and 1B-20401) ~
5.3.4 Insure lAB 4.16KV bus feeders are open:
20208, 20505 (1A3 4.16KV to 1AB 4.1'6KV bus).
204'09, 20504, (1B3 4.16KV to 1AB 4.16KV bus),
5.3.5 Open 40103 ( lA2 4. 16KV feed to 1AI L.C.-Hi side).
Open 20110 (1A2 4.16KV feed to 1A1 L.C.-Lo side).
Open 40203 (1A3 4.16KV feed to lA2 L.C.-Hi side).
Open 20210 (1A3 4.16KV feed to lA2 L.C.-Lo side).
5.3.6 Open 40403 (1B2 4.16KV feed to lBl L.C.-Hi side).
Open 20310 (1B2 4.16KV feed to 1B1 L.C.-Lo side) .
Open 40503 (1B3 4.16KV feed to 1B2 L.C.-Hi side).
Open 20402 (1B3 4.16KV feed to 1B2 L.C.-Lo side) .
5.3.7 Insure 1AB 480V Load Center Feeder's are open:
40204, 40702 (lA2 480V L.C. to lAB).
40706, 40504 (182 480V L.C. to 1AB).
5.3.8 Close HCV&8-1A (1A S/G MSIV).
Close MV-08-1A (lA S/G MSIV bypass).
Close HCV-08-1B (1B S/G MSIV) ~
Close MV-08-1B (1B S/GMSIV bypass).
5.3.9 Open lA and 1B Atmospheric Dump Valves to reduce Steam Generator pressure below safety lift pressure.'
~ Zf instrument air pressure has decayed, local operation is necessary.
- 2. Maintain communication .with local operator.
5.3.10 Close AOV-2515 and AOV-2516 (CVCS Letdown Isolation) ..
5.3 ~ 11 Close FCV 23-3, 4, 5 and 6'1A and 1B S/G Blowdown Isolations) .
Page 4 of 9 ST. LUCIE UNIT NO. 1 EMERGENCY OPERATING PROCEDURE NUMBER 0030143, REVISION 0 TOTAL LOSS OF AC POWER
5.0 INSTRUCTIONS
(Cont.)
5.3 (Cont.)
5.3 ~ 12 Close FCV-23-7 and FCV-23"9 (1A and 1B S/G Blowdown Sample Isolations).
5.3 ~ 13 Close AOV-5200, 5201, 5202, 5203, 5204 and 5205 (RCS Sample Isolations).
5.3'14 Implement the Emergency Plan as necessary in accordance with EP 3100021E, "Duties of the Emergency Coordinator."
5.3 ~ 15 'Minimize atmospheric steam dump use thereby insuring minimum RCS heat loss; however,
- 1. Maintain S/G pressure less than S/G safety setpoint.
- 2. With decreasing RCS pressure, maintain hot leg tern'perature (Th) at least 20 F below the saturation temperature corresponding to the RCS pressure.
5.3 ~ 16 Verify by the following indications that natural circulation flow has been established within approximately 15 minutes after RCP's were stopped.
- 1. Loop Delta T less than normal full power Delta T
((46 F).
- 2. Cold leg (Tc) constant or decreasing.
- 3. Hot leg (Th) stable (i.e., not steadily increasing).
5.3 ~ 17 If RCS pressure decreases to 1700 psia, verify receipt R-6 and block SIAS.
of block permissive annunciator 5.3.18 Notify system dispatcher of plant conditions and request most urgent priority in restoring off-site power.
5.3 ~ 19 If 1C Auxiliary Feedwater Pump is stopped or flow is lost, and Steam Generator level is less than 42X, then:
- 1. Reinitiate auxiliary feed flow as soon as possible; however, do not exceed a flow rate of 150 GPM per affected Steam Generator.
- 2. Limit feed flow rate to 150 GPM per affected Steam Generator until continuous feed flow to the affected Steam Generator has been maintained for five minutes.
Page 5 of 9 ST. LUCIE UNIT NO. 1 EMERGENCY OPERATING PROCEDURE NUMBER 0030143, REVISION 0
'OTAL LOSS OF AC POWER
5.0 INSTRUCTIONS
(Cont.)
5.3 (Cont.)
5.3.20 Use all available resources to restore one emergency diesel generator to operable status.
- l. (Insert techniques later) following restoration sequence assumes "A" train power 5.3.21 The supply is restored first.
- 1. Strip all vital and non-vital load center breakers in preparation for a systematic power restoration.
2,. Energize lA3 4.16KV bus by either:
- a. Starting 1A D/G and closing D/G breaker. Adjust and maintain voltage and frequency at 4.16KV/60 HERTZ.
or
- b. Close 20102 (S.U. Transformer to lA2 4.16KV bus).
Close 20109 (1A2 4.16KV to 1A3 4 16KV bus).
~
Insert sync plug and close 20209 (1A2 4.16KV to lA3 4.16KV bus).
- 3. Energize 1A2 480V Load Center as follows:
- a. Close 40203 (1A3 4.16KV feed to lA2 L.C.-Hi side).
- b. Close 20210 (lA3 4.16KV feed to 1A2 L.C.-Lo side).
4, Energize lAB 480V Load Center by closing 40204 and 40702 (lA2 480V L.C. feed to lAB L,C.).
- 5. Energize 1A5, lA6, 1A7 and lA8 480V MCC's as follows:
- a. Close 40214 (1A2 480V L.C. feed to lA5 MCC).
- b. Close 40218 (1A2 480V L.C. feed to lA6 HCC).
- c. Close 40219 (lA2 480V L.C. feed to lA7 MCC).
- d. Close 40215 (1A2 480V L.C. feed to lA8 MCC).
e ~ Open 41230 (lA5 MCC supply to 1A containment instrument ai r compressor) .
page 6 of 9 ST. l UCIE UNIT NO. 1 EMERGENCY OPERATING PROCEDURE NUMBER 0030143, REVISION 0 TOTAl LOSS OF AC POWER
5.0 INSTRUCTIONS
(Cont.)
5.3 (Cont.)
5.3.21 (Cont.)
- 6. Energize non-essential sections of lA5, 1A6 and lA8 MCC's as follows:
- a. Close 41230 (MCC lA5 non-essential breaker).
- b. Close 41325 {MCC lA6 non-essential breaker).
- c. Close 41513 (MCC lA8 non-esseneial breaker).
- 7. Insure lA battery charger is "ON LINE" supplying the lA DC bus by observing 1A DC bus voltage on RTGB 101 to be greater than 120V DC.
- 8. Align and start emergency cooling water to, the instrument air compressor. Start the IA instrument air compressor and observe restoration 'of instrument air pressure.
- 9. Start 1A Charging Pump and 1A HPSI pump, if necessary, to reestablish pressurizer level.
- a. Evaluate RCS temperature, pressure, and level.
instrumentation to determine if a bubble exists other than in the Pressurizer.
- b. If evaluation confirms, then continue charging to increase RCS pressure.
- c. When greater than 20 F subcooled, operate Charging and/or HPSZ pumps to maintain Pressurizer level greater than 30K level.
- 10. Insure closed 20204 (Pressurizer heater transformer 1A 4.16KV feed).
ll. When pressurizer level indicates greater than 30K, energize pressurizer heaters B-l, B-2, B-3, and P-l.
- 12. Reestablish CVCS letdown to maintain pressurizer level at normal operating level.
- 13. Cogence boration to Co! d Shutdown boron concentration.
Page 7 of STo LUCIE UNIT NO. 1 EHERGENCY OPERATING PROCEDURE NUMBER 0030143, REVISION 0 TOTAL LOSS OF AC POWER
5.0 INSTRUCTIONS
(Cont.)
5.3 (Cont.)
5.3.21 (Cont.)
14 . Start one set of cavity and support cooling fans.
- 15. If power was restored via 1A emergency 'D/G, proceed to step 16; otherwise:
- a. Energize )Al 480V Load Center by closing 20110 (1A2 4.16KV feed to 1A1 480V L.C.).
- b. Start lA Domestic Water Pump to supply water for Intake Cooling Water Pump start. Go to step 17.
- 16. Energize lA1 480V Load Center as follows:
- a. Insert sync plug, close 20109, and hold control switch closed while closing 20209.
- b. Close 20209 and release 20109 hand switch.
- c. Close 20110 (1A2 4.16KV'eed to 1A1 480V load center) .
- d. While loading secondary plant equipment, insure diesel loading remains le'ss than 3500 KW.
- 17. Start lA Domestic Mater Pump to supply water for Intake Cooling Mater Pump start.
- 18. Reestablish "A" train Intake Cooling Mater System as follows:
- a. Establish seal water.
- b. Throttle 1A I.C.W. pump dishcarge valve.
- c. Start 1A I.C.M. pu p; pressurize and vent "A" I.C.M. header.
- d. After venting, open 1A I.C.M. pump discharge valve.
Page 8 of 9 ST. LUCIE UNIT NO. 1 EMERGENCY 'OPERATING PROCEDURE NUMBER 0030143, REVISION 0 TOTAL LOSS OF AC POWER
5.0 INSTRUCTIONS
(Cont.)
5.3 (Cont.)
5.3.21 (Cont.)
- 19. Reestablish "A" train Component Cooling Water System as follows:
- a. Isolate CCW to RCP's by closing HCV-14-1, 2, 6 and 7 (to prevent thermal shocking RCP seals)
- b. Throttle 1A CCW pump discharge valve.
- c. Insure surge tank at normal level.
- d. Start 1A CCW pump; pressurize and slowly open 1A CCW pump discharge valve.
- 20. Proceed to EOP 0120040, "Natural Circulation/Cooldown,"
step 5.3.9, and perform in con)unction with the balance of this procedure.
- 21. Restore balance of secondary plant in accordance with EOP 0030140, "Blackout Operation."
page 9 of ST. LUCIE PLAHT EMERGENCY OPERATIHG PROCEDURE NUMBER 0030143, REVISION 0
'TOTAL LOSS OP AC POWER APPENDIX A DISCUSSION The "Total Loss of AC Power" event consists of a loss of off-site power in conjunction with failure of the Emergency Diesel Generators to provide ~
emergency .power. This results in a loss of all AC electrical power except thar provided by inverters powered from the vital DC busses. The termination.
. of AC power causes a loss of forced reactor coolant flow, main feedwater flow, steam .flow to the turbine and pressurizer pressure control. The reactor trips on either low reactor coolant flow, high reactor coolant system (RCS) pressure or low steam generator level depending on initial conditions.
The "Total Loss of AC Power" event also causes a loss of all reactor coolant system makeup capability which includes charging and safety injection flow.
Inventory losses through leakage, reactor coolant pump controlled bleedoff, and primary relief valve releases are the major contributors to the degradation of pressure and level control during the event. The other contributor to coolant system shrinkage and pressure reduction is system heat loss, primarily through the pressurizer walls.
Core heat removal is accomplished through natural circulation. Reactor coolant system heat removal is accomplished using atmospheric dump valves and the steam driven auxiliary feedwater pump.
I Procedure 0 0030143 Rev. 0 ADDENDUM INSTRUCTION SHEET FOR PROCEDURE COMPLETION TO BE DONE BY TECHNICAL STAFF VERTICAL LINES must be added as follows:
CHARTS AND GRAPHS must be added as follows:
HORIZONTAL LINES must be added as follows:
OTHER SYMBOLS must be added as follows:
Verified by Vault Custodian
4 I:-
~