ML20038C542
| ML20038C542 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 11/13/1981 |
| From: | FLORIDA POWER & LIGHT CO. |
| To: | |
| Shared Package | |
| ML17212B193 | List: |
| References | |
| PROC-811113-01, NUDOCS 8112110204 | |
| Download: ML20038C542 (87) | |
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1.0 Title
Charging and Letdown - Off Norr.:_1 Operation 2.0 Review and Approval: Reviewed 19 # Approved by byPyl 7d.W)'Gclear Safety Committee
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devision J xeirieved,by FRG h '2- / 19k Approved by O e /w t a . M d iant Mandger ,. ~1 7 19 p Revision 6 reviewed by FRG Alnua ku- [. 1981. Approved by $ J /2 //>F % - Plant Manager A4y. // - 1981. M 3.0 Purpose or Discussion: 3.1 This procedure provides instructions for re-establishing charging and letdown flow or isolating affected components following a malfunction in the charging or letdown systems. 4.0 Sv=ptons: > 4.1 Charging pumps low flow (M-14) 4.2 Charging, pumps low header pressure (M-15 4.3 Letdown high flow (M-13) 4.4 Letdown high-low pressure (M-5) 4.5 Volume cor. trol tank high temperature (M-19) 4.6 Boronometer and process radiation monitor Lcw Flow (M-17) 4.7 Ion exchanger bypass high te=perature (M-10) 4.8 7CT outlet valve V2501 indicates not open 4.9 Charging pu=ps not running (M-22, M-23, M-24, M-30, M-31, M-32, M-46, M-47 and M-48) 4.10 Pressurizer level deviation (H-19, H-20, R-25, and H-26) i
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P-OPERATING ?ROCEDURE NO. 0210030, REV. 6 j CHARGING AND LETDOWN - 0FF NORMAL OPERATING j
5.0 Instructions
im, 5.1 Immediate automatic operations 5.1.1 Regenerative heat exchanger high outlet temperature of 470 F closes letdown isolation valve V2515. 5.1.2 Hi AP across the regenerative Ex of 275 psi closes letdown isolation valve V2516. 5.1.3 Charging pumps trip on low suction pressure of 10 psia. 5.1.4 Letdown heat exchanber high outlet temperature of 145 F isolates flow to the baronometer and process radiation: monitor and diverts letdown flow past the purification ion exchangers. . 5.2 Immediate Operator Actions 5.2.1 Verify any automatic actions have occurred if called upon to do so. 5.2.2 Immediately secure charging (letdown) if letdown (charging) is lost.
. 5.2.3 On any abnormal condition involving loss of letdown or charging flow, hold power constant to sinimize pressurizer level deviations.
5.2.4 Investigate cause of problem. 5.3 Subsequent actions 5.3.1 Notify plant supervisor-nuclear of any abnor=al conditions. 5.3.2 Re-establish charging and letdown flow iy as follows:- 5.3.2.1 The VCT should be within its nor=al operating , level band. 5.3.2.2 Start one charging pu=p per procedure 0210020 Charging and Letdown - Normal Operation and observe 44 G7M flow on FI 2212. 5.3.2.3 Check that the letdown level control valve selector switch HSil10-1 and the letdown pressure control valve selector switch HS 2201 are selected to the level / pressure control valves in service.
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s a Paga 3 cf 4 ) I OPERATING PROCEDURE NO. 0210030, REV.6 i , CHARGING AND LETDOWN - 0FF NORMAL OPERATING l
5.0 Instructions
(Cont.) I n=== 5.3 (Cont.) 5.3.2. (Cont.) 5.3.2.4 Mar.ch the auto-manual output c we letdown level controller, shift to manual, .nd close. 5.3.2.5 Check the letdown pressure controller in Auto and set to =aintain 340 psig. /R6 5.3.2.6 Place ficw limited bypass switch in the bypass position. 5.3.2.7 Check that regenerative heat exchanger high temp. alarm, SIAS, or CIS alar =s are not present and open letdown isolation valves V2515 and V2516. 5.3.2.8 Open letdown control valve and establish 5 GFM letdown flow. 5.3.2.9 When letdown temperature stabill:es increase letdown flew until letdown and charging flows are matched. CAUTION: Increase letdown flow at a rate not to exceed 5-10 GPM in any one minute. Insurecharggngtemperaturedoesnot increase more than 60 F per minute. 5.3.2.10 Insure the letdown pressure controller maintains letdown pressure at 340 PSIG. 5.3.2.11 Balance the letdown level control auto-manual cutputs and shift to auto. 5.3.2.12 Take flow li=ited by-pass switch out of by-pass. 5.3.2.13 If a loss of charging occurs secure letdown i=cediately. The above steps should then be followed to return the system to nor=al operation. 5.3.3 Transferring letdown level control to the alternate control valve. 5.3.3.1 Unisolate alternate control valve by opening: V2342 and V2341 (LCV,-2110P) or V2344 and V2343 (LCV-2110Q) 5.3.3.1 Place letdown level controller (RIC 1110) in manual and adjust for mini =um letdown flow. 5.3.3.3 Select Position on HS 1110.1 letdown level valves selector switch. .
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OPERATING PROCEDURE NO. 0210030, REV. 6 CHARGING AND LiTDOWN - 0FF NORMAL OPERATING 5.0 Instructions:- (Coat.' ; ama 5.3 (Cont.) 5.3.3 (Cont.) 5.3.3.4 Select desired valve. 5.3.3.5 Place letdown level controller (HIC 1110) in automatic. 5.3.3.6 Isolate letdown valve not in service by closing: V2342 and V2341 (LCV-2110P) # - V2344 and V2343 (LCV-2110Q) 5.3.4 Transferring letdown pressure control to the alternate
. control valve.
, 5.3.4.1 Unisolate alternate control valve by opening: V2350 and V2348 (PCV-1201P) # V2349 and V2347 (PCV-2201Q) 5.3.4.2 Place letdown level controller (HIC 1110) in manual and adjust for minimum letdown flow. 5.3.4.3 Select positionor.HS-2201 ' letdown pressure control valve selector switch. 5.3.4.4 Select desired valve. 5.3.4.5 Place letdown level controller (Hic 1110) in
- automatic.
I i 5.3.4.6 Isolate pressure control valve not in service by closing: 72350 and V2341 (PCV-2201P) # V2349 and 72347 (PCV-2201Q) l 6.0
References:
6.1 PSAR, Chapter 9 6.2 C.E. ? & I Diagrams E-193630210-120 and E-19367-210-121 7.0 Records Recuired:
- 7.1 Nornal log entries.
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i . Page 1 of 35 m FLORIDA POWER & LIGHT COMPANY ST. LUCIE PLANT UNIT NO. 1 0FF-NORMAL OPERATING PROCEDURE NO. 0960030 REVISION 7
1.0 Title
DC Ground Isolation 2.0 Review and Approval: Reviewed by Facility Review Group February 25, 19H Approved by K. N. Harris Plant Manager February 26 19H Revision 7 Reviewed by F R G SE/ r. 3 19 B i Approved by ,8 8 [// d Plant Manager ge, /. 2. e - 19g C/
3.0 Purpose
3.1 ' Prov4de instructions for isolating a DC system ground without affecting plant operation.
3.2 Discussion
This procedure shall be used as a guideline for DC ground location and isolation. The Nuclear Plant Supervisor and the Nuclear Watch Engineer shall use any section, in any order, as they deem necessary to naintain the plant stability and to insure that no limiting condition for operation from the Standard Technical Specification is violated. 4.0 Precautions and Limits: Maintain two-way radio ccarsunic.stion between control center and operating point. Verify control center og erator is observing ground light on RTG3-101 when isolating circuits to ::unimize time each circuit is switched off. 5.0 Related System Status: pa%}9N yQ3 k UI , gled. 0*I " None T s docum.nt is no, ,,ngrelled documenh
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i . Pcgo 2 of 35 FLORIDA POWER & LIGHT COMPANY UNIT NO. 1 0FF-NORMAL OPERATING PROCEDURE NO. 0960030 ,l REVISION 7 . 6.0
References:
I s 6.1 Ebasco Power Distribution Motor Data 8770-B-335 series drawings ( 6.2 Ebasco Control Wiring Diagrams 8770-B-327 series drawings 7.0 Records Required: Plant Work Order for the grounded circuits } 9
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Paga 3 af 35 r FLORIDA POWER & LIGHT COMPANY UNIT NO. I ! 0FF-NORMAL OPERATING PROCEDURE NO. 0960030 REVISION 7
8.0 Instructions
8.1 If the ground appears on a bus which is tied to the A, B, or C D/C iw bus, then proceed to Step 8.1.1. If the ground is on a separato isolated bus, then proceed to Step 8.1.5. 8.1.1 Energize the standby battery charger and verify that all the 125 V DC buses are being supplied from their respective chargers. 8.1.2 Open or verify open the following breakers: 8.1.2.1 Bkr. 60311, 125 V DC bus IC. 8.1.2.2 Ekr. 60315, tie to DC svgr. lA. 8.1.2.3 Bkr. 60316, tie to DC svgr. 1B. 8.1.3 The 1AB 125 V DC bus is now isolated from the 1A & IB 125 V DC buses, and the IC 125 V DC bus is isolated from the 1AB 125 V DC bus. Determine which DC bus is grounded. 8.1.4 Return the 125 V DC system to its original line up. 8.1.5 Proceed to the appropriate section as follows:
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- 125 V DC bus IA ground: ,
Section 8.2 , 125 V DC bus IB ground: Section 8.3 125 V DC bus IAB ground: Section 8.4 125 V DC bus IC ground: Settion 8.5 8.2 Isolat.e a ground on 125 V DC bus IA as follows: 8.2.1 The following breakers can be momentarily opened and closed without affecting plant operation: 8.2.1.1 Bkr. 60110, aux. transformer 1A Note: Annunciator window C-48 will alarm. 8.2.1.2 Bkr. 60112, startup transformer IA Note: Annunciator window B-21 will alarm. 8.2.1.3 Bkr. 60114, main transformer 1 A Note: Annunciator window C-36 will alarm. 8.2.1.4 Bkr. 60120, DC lighting panel 1127 8.2.1.5 Bkr. 60129, Battery charger IA
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Pcgo 4 of 35 FLORIDA POWER & LIGHT COMPANT UNIT NO. 1 0FF-NORMAL OPERATING PROCEDURE NO. 0960030 REVISION 7
8.0 Instructions
(continued) ; 6' 8.2 (continued) 8.2.2 Operate breaker 60101, 480V switchgear 1A2. Note: Annunciator window B-29 will alarm. If the grcund does not clear, proceed to section 8.2.3. If the ground does momentarily clear, proceed to 480V switchgear 1A2 and perform the following: 8.2.2.1 Open compartment 6A (instrumentation) and momentarily remove and replace the IA2 swgr. UV relay fuses. Note: Annunciator window B-29 will alarm. Close compartment 6A. 8.2.2.2 At the rear of each compartment listed below, momentarily remove and replace the close and trip circuit fuses for the listed breakers: Compt. 21r.r . Equipment IA 402.'8 MCC 1A 6 1B 4021) MCC 1A 7 2A 40214 MCC 1A 5 2B 40215 MCC 1A 8 4A 40209 Fire Pump 1A , 4B 40210 Charging Pump 1A 4C 40211 CEDM Cool. Fan (HVE-21A) SA 40205 Containment Cooler 1A SB 40206 Containment Cooler IB SC 40207 CEA Drive MG Set 1A
, 5D 40208 Aux. Bldg. Main. Ex. Fan (HVE-10A) 63 40203 Main Feed } 6C 40204 480V Load Center 1AB 8.2.3 Momentarily open and reclose breaker #60103, 480 switchgear IA1. If ground does not clear, proceed to section 8.2.4. If the ground did clear, proceed to 480V switchgear IAI and perform the following:
8.2.3.1 At the rear of each compartment listed below, l momentarily remove and replace the close and trip i circuit fuses for the listed breakers: I l Compt. Bkr. Equipment 7B 40119 MCC IC 1 7C 40120 Serv. Bldg. Feed l 7D 40121 MCC IA 2 1 6B 40115 MCC 1A 1 6C 40116 MCC 1A 3 ! 6D 40117 Swyd. Norm. Feed 6A 40114 Main Trans. IB Clg. Equip. Source 2 5B 40111 Turb. Bldg. crane SC 40112 Main Trans. lA C1g. Equip. Source 1 SD 40113 MCC -1A 4 , 3C 40107 Air conpressor 2B 40103 Main feed
Pego 5 of 35 FLORIDA POWER & LIGHT COMPANT UNIT NO. 1 0 FF-NORMAL OPE RATING PROCEDURE NO. 0960030 REVISION 7 8.0 Instruc tion _s_: (continued) 8.2 (continued) 8.2.4 Momentarily open and reclose bkr. 60106, 4.16 KV swgr. lA2. Note: Annunciator window B4 & B12 will alarm. If the ground did not clear, proceed to section 8.2.5. If the ground did clear, proceed to 4.16 KV switchgear IA2 and perform the following: 8.2.4.1 Open cubicle 1 and momentarily remove and replace the close and trip circuit fuses for bkr. 20101. If the ground did not clear, momentarily remove and replace the 4.16 KV 1A2 undervoltage fuses. Close cubicle 1. 8.2.4.2 Open cubicle 2 and :nomentarily remove and replace the close and trip circuit fuses for breaker 1 20132. If the ground did not clear, momentarily remove and replace the Startup Standby transformer IA lockout relay fuses. Note: Annunciator window B12 will annunciate. Close cubicle 2. 8.2.4.3 Open cubicle 10 and momentarily remove and replace
- the close and trip circuit fuses for bkr. 20110. If the ground did not clear, momentarily remove and replace the 4.16 KV swgr. lA2 differential relay fuses.
Note: Annunciator window B4 will alarm.
. 8.2.4.4 Open the cubicles listed below and momentarily remove and replace the close and trip circuit fuses for the listed breakers:
Cubicle Breaker Equipment 03 20103 Cire. water pump 1A1 04 20104 Cire. water pump 1B1 06 20106 Turb. Plant Cool. Wtr. Pump 1A 07 20107 Condensate pump 1A 08 20108 Her. drain pump 1A 09 20109 Feed to 4.16 KV svgr. lA3 Note: Cubicle 5 is a spare 8.2.5 Momentarily open ana reclose bkr. 60107 D/G 1A control panel. Note: Annunciator window B36 on RTGB 101 and B24 on D/G 1A annunciator will alarm. If the ground did not
' clear, proceed to step 8.2.6. If the ground did
, i clear, proceed to D/G 1A control panel and perform the following:
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8.0 Instructions
(continued) 8.2 (continued) 8.2.5.1 Momentarily remove and replace start circuit fuses F1 & F2. Note: Annunciator windows B36 on RTGB 101 and B24 on D/G 1A annunciator will alarm. 8.2.5.2 Momentar . ly remove and replace the fuses listed below: F3 & F4 D/G 1A lockout relay
- Fil & F14 D/G 1A governor control FIS & F16 D/G 1A voltage adjusts F17 & F18 D/G 1A annuna.lator FS & F6 Fuel Prime pump 1A1 motor B1/a F7 & F8 Fuel Prime pump 1A2 motor 31/b F9 & F10 Emerg. Oil Cire. pump 1A1 motor B2/a F11 & F12 Emerg. Otl Cire. pump 1A2 motor B2/b i
8.2.6 Momentarily open and reclose bkr. 60108, 4.16 KV swgr. lA3. Note: Annunciator windows B4, 15, 52, 54, 56, 57 & 59; E-46; G-44, R-51, 55, 58 & S-51 will alarm. If the ground did not clear, proceed to sectio. 8.2.7. If the ground did clear, proceed to 4.16 kv svgr. lA3
. and perform the following: ,
8.2.6.1 Open cubicle 6 and momentarily remove and replace l the close and trip circuit fuses for bkr. 20207, component cooling water pump 1A. Note: Annunciator window S-51 will alarm. If , the ground did not clear, momentarily remove and replace the 4.16 KV swgr. lA3 differential relay fuses. Note: i Annunciator window B4 will alarm. 8.2.6.2 Open cubicle 11 and momentarily remove and replace the close and trip circuit fuses for bkr. 20211 diesel generator IA. Note: Annunciator window B56 will alarm. If the ground does not momentarily clear,
; momentarily remove and replace the 4.16
, KV svgr. lid load shedding relays fuses. Note: Annunciator window BIS will alarm.
f
. 8.2.6.3 Open the cubicles listed below and momentarily
' remove and replac.e the close and trip circuit fuses
, for the listed breakers.
Note: Listed annunciator windows will alarm.
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P: ga 7 of 35 FLORIDA POWER & LIGHT COMPANY UNIT NO. 1 0FF-NORMAL OPEP.ATING PROCEDURE NO. 0960030 REVISION 7
8.0 Instructions
(continued) W 8.2 (continued) Cubicle Breaker Ann. Window Equipment 1 20201 R-55 IrSI Pump 1A 2 20202 R-58 LPSI Pump 1A 3 20203 R-51 Cont. Spray Pump 1A 4 20204 B-59 Feed t o 480V Press. Her. Ioad Ctr. lA3 6 20206 CCW Prms 1A 7 '20207 E-46 ICW Pm 4 1A 8 20208 E-54 Feed t' i.16KV Swgr. LAB 9 20209 B-52 Supply trom 4.16KV Swgr.1A2 10 20210 B-47 Feed to 480V Load Ctr.1A2 12 20211 G-44 Aux. Feedwater Pump 1A Note: Ccmpt. 5 is a spare. 8.2.7 Verify all reactor trip '.reakers are closed, then inform the controi room that TCB-1 and TCB-5 will be tripped. Momentarily opeu and reclose breaker 60109, reactor trip svgr. (Ncte: Annunciator windows K-7 & K-8 will alarm) If the ground did not clear,
- reset TCB-1 and TCB-5 and proceed to ,section 8.2.8. If the ground did momentarily clear, proceed to reactor trip switchgear, unit 001 and perform the following:
8.2.7.'. Momentarily re=ove and replace the close and trip circuit fuses for ICB-1. 8.2.7.2 Momentarily remove and replace the close and trip circuit fuses for TCB-5. 8.2.7.3 Reset the ungrounded breaker as datermir.ed from steps 8.2.7.1 and 8.2.7.2. 8.2.8 Verify all reactor trip breakers are closed, then inform the control room that TCB-3 and TCB-7 will be tripped. Momentarily open and reclose breaker 60111 reactor trip swgr. Note: Annunciator windows K4 & K5 will alarm. If the ground did not clear, reset TCB-3 and TB-7 and proceed to stap 8.2.9. If the ground did /R7 momentarily clear, proceed to reactor trip swgr. unit 004 and perform tbe following: 3.2.8.1 At compt. V004A momentarily remove and replace the close and trip circuit fuses for bkr. TCB-3. 8.2.8.2 At compt. 7004C mooentarily remove and replace the close and trip circuit fuses for breaker TCB-7. ....a..e.. . - - . . . ..-.-------% . .- -~, - -
. . i Pego 8 cf 35 FLORIDA POWER & LIGHT COMPANY UNIT NO. 1 0FF-NORMAL OPERATING PROCEDURE NO. 0960030 RFVISION 7
8.0 Instructions
(continued)
<w 8.2 (continued) 8.2.8.3 Reset the ungrounded breaker as determined from 8.2.8.1 & 8.2.8.2 8.2.9 Remove static inverter 1C from service by performicg sections 8.3.1 thru 8.3.8 of Operating Procedure #0970020.
8.2.10 If the ground did not clear, perform sections 8.1.1 thru 8.1.9 of Operating Procedure #0970020 to return static inverter 1C to service. 8.2.11 Remove static inverter 1A from service by performing sections 8.3.1 thru 8.3.8 of Operating Procedure #0970020. 8.2.12 If the ground did not clear, perform section 8.1.1 thru 8.1.9 of Operating Procedure 0970020 to return static inverter 1A to service. 8.2.13 Momentarily open & reclose breaker #60115 component cooling water surge tank. Note: LCV-14-1 (CCW surge tank inlet) fails closed; RSE-14-1 (CCW aurge tank vent) fails open. 8.2.14 7erify SS/189-1, SS/158, SS-3/603, SS-1/603, SS/130, and SS-1/157 in isolation panel IA are in "nor=al" position. Momentarily open and close Bkr. 60116, isolation panel 1A. 8.2.15 Momentarily open & reclose breaker #60117, RTGB-103 (Fuses RR-1-10'. See Appendix A for load list. 8.2.16 Momentarily open & reclose breaker #60118, Aux. spray valve ISE-02-3. Note: Valve fails closed, loses indication. 8.2.17 Check circuit by removing individual fuses, RTCB-106 (fuses CCC-1-36) See Appendix C for load list. Certain fuses will be ested: "D0 NOT REMOVE" 8.2.17.1 CAUTION: Before removing fuses 27 to 30 (HCV 1,2), ensure that the air-supply solenoid valves HSE 14-1, 2 are mechanically jumpered to prevent closure of HCV-14-1,
- 2. After checking for a ground, install fuses 27 to 30 and reset HCV-14-1, 2 control switches in the Control Room.
/ 8.2.17.2 Remove mechanical jumpers on I.V. HSE-14-1, 2.
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Pcgo 9 ef 35 FLORIDA POWER & LIGHT COMPANY UNIT NO. 1 0FF-NORMAL OPERATING PROCEDURE NO. 0960030 REVISION 7
8.0 Instructions
(continued) 8.2 (continued) 8.2.18 Momentarily open & reclose breaker #60123, RIGB-106 (fuses CCC 4I-69). See Appendix D for load list. 8.2.19 Momentarily open & reclose breaker #60124, DC PP-118. See Appendix E for load list. 8.2.20 Momentarily remove & replace the DC bus 1A undervoltage relay fuses in DC bus 1A. 8.2.21 Momentarily remove & replace the DC bus 1A ground relay fuses in DC bus IA. CADTION: Performance of Step #8.2.22 will cause an autostart of "A" and "C" auxiliary feed water pumps and the feeding of "A" steam generator. 8.2.22 Momentarily open and reclose breaker #60119. RTGB-105 (fuses HH 19-63). See Appendix B for load list. 8.3 Isolate a ground on 125V DC bus 1B as follows: 8.3.1 The following breakers can be momentarily opened and reclosed
, without affecting plant operations: Unless otherwise noted.
8.3.1.1 Bkr. 60210, Aux. transformer IB 8.3.1.2 Bkr. 60202, Start-up transformer 1B 8.3.1.3 Bkr. 60214, Main transformer 13 8.3.1.4 Bkr. 60226, DC ltg. panel LP-128 8.3.1.5 Bkr. 60229, Battery Charger 1B output 8.3.2 Open and reclose breaker 60201, H2 control panel. Note: The annunciator horn at the H2 control panel must be reset locally. 8.3.3 open and reclose breaker 60203, line repeat panel. Note: The line repeat panel annunciator must be reset at the panel. 8.3.4 Momentarily open and reclose breaker 60205, 4807 svgr. 132. If the ground did not clear, proceed to section 8.3.5. If the ground did momentarily clear, proceed to 480V svgr.1B2 and perform the following: 8.3.4.1 Open compt. 2A (instrumentation) and momentarily I remove and replace the 1B2 swgr. undervoltage relay fuses. Close compt. 2A.
- e m emme s.ne= = m s=
- e, e, . * * - . , . - em +.--e . . . . e-. am..m%.w w . m w % y . . - . g . . , . . , . .
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.- --.g&m.-im-,r-- . -. -.= - , .
Page 10 o f 3 5 I FLORIDA POWER & LIGHT COMPANY UNIT NO. 1 0FF-NORMAL OPERATING PROCEDURE NO. 0960030 REVISION 7
8.0 Instructions
(continued) 8.3 (continued) 8.3.4.2 At the rear of each compartment listed below '" momentarily remove and replace the close and trip circuit fuses for the listed breakers. Compt. Bkr. Equipment 23 40503 Main feed 2C 40504 480V Ld. Cen. LAB 3A 40505 Cont. Cooler HVS-1C 3B 40506 Cont. Cooler HVS-ID 3C 40507 CEA Drive MG 1B ID 40508 Aux. Bldg. Main Exh. HVE-10B 4A 40509 Fire Pump 1B 4B 40510 Charging Pump 1B 4D 40512 CEDM Clg. fan HVE-21B ' 6A 40514 MCC IB5 6B 40515 MCC IB8 6C 40516 Rx. Bldg. Crane #1 7A 40518 MCC 136 7B 40519 MCC 137 i 8.3.5 Momentarily open and reclose breaker 60206, 4.16 KV swgr.
- 1B2. -
, Note: Annunciator windows A4 & A16 will alam. If the ground does not clear, proce'ed to section 8.3.6. If the ground did clear, proceed to 4.16 KV svgr. IB2 and perfom the following:
Open cubicle 10 and momentarily re=ove and replace 8.3.5.1 the close and trip fuses for breaker 20301. If the ground did not clear, momentarily remove and replace 4.16 KV svgr. IB2 undervoltage fuses. Close cubicle 10. 8.3.5.2 open cubicle 9 and mom 2ntarily remove and replace close and trip fuses for breaker 20302. If the i ground did not clear, momentarily remove and replace the startup standby transformer IB lockout relay fuses. Note: Annunciator window A15 will alarm. Close cubicle 9. 8.3.5.3 Open cu' c . a 1 and momentarily remove and replace the close and trip fuses for breaker 20310. If the e ground did not clear, momentarily remove and replace
; the 4.16 KV swgr. 132 differential relay fuses.
Note: Annunciator window A4 will alarm. 8.3.5.4 Open the cubicle doors listed below and momentarily remove and replace the close and trip circuit fuses for the listed breakers:
- . .,.-- ----- - - - . -.....-.. -.. ~- ;-. . - .. --.~- .._.. -...-....
.Page 11Lof 35 FLORIDA POWER & LICHT . COMPANY UNIT NO. 1 i 0FF-NORMAL OPERATING PROCEDURE NO. 0960030 REVISION 7
8.0 Instructions
(continued) 8.3 (continued) s= 8.3.5.4 (continued) Bkr.# Cubicle # Equipment 20303 08 Cire. Water Pump 1A2 20304 07 Cire. Water Pump 1B2 20305 06 Spare 20306 05 Turb. Plt. Cool. Water pump 1B 20307 04 condensate pump IB Heater Drain pump 1B
~
20308 03 20309 02 Feed to 4.16KV vital swgr. IB3 8.3.6 Momentarily open and reclose breaker 60207, 480V swgr. 1Bl. If the ground does not clear proceed to section 8.3.7. If the ground did clear, proceed to the 480V svgr. 1B1 and perform the following: 8.3.6.1 At the rear of each compartment listed below, momentarily remove and replace the close and trip fuses for the listed breakers: Bkr.# Cubicle # Equipment 40403 6B Main Feed (4.16KV svgr. IB2)
. 40404 6C Bus tie to 480V* load center 1A 40410 3A MCC IC (turbine) 40411 3B MCC IB1 (turbine) 40412 3C' MCC IB3 (intake) 40413 3D MCC 134 (wtr. treatment plant) 40415 2B Serv. Bldg. Feed (PP-3B) 40416 2C Mn. Trans. 1B cool. equip. source 1 40417 2D Switchyard Feed (Alt.)
40418 1A Service Bldg. water heater 40419 1B Mn.Trans. lA Cool. equip. source 2 i 40420 IC Aux. boiler MCC IB10 40421 1D MCC IB2 (rad. waste) ! 8.3.7 Momentarily open and reclose breaker 60208, 4.16KV svgr. 1B3. Note: Annunciator windows A4, A15, A52, AS4, A56, A57, A59, E47, G45, RS2, RS6, R59, and SS2 will alarm. , If the ground did not clear proceed to section 8.3.8. If the ground did clear, proceed to 4.16KV swgr. IB3 and perfor:a the following: 8.3. 7.1 Open cubicle 4 and momentarily remove and replace , the close and trip fuses for breaker 20404 Note: Annunciator window S-52 will alarm. If the ground did not clear, momentarily remove and replace the 4.16KV swgr. 183 i differential relay fuses.
- Note
- Annunciator window A4 will alarm.
1
v Page 12 of 35 l FLORIDA POWER & LIGHT COMPANY UNIT NO. 1 , OFF-NORMAL OPERATING PROCEDURE NO. 0960030 ' REVISION 7 ,
8.0 Instructions
(continued) ] mammi 8.3.7.2 Open cubicle 1 and momentarily remove and replace the close and trip fuses for breaker 20401. Note: Annunciator window A-56 will alarm. If the ground did not clear, momentarily remove and replace the 4.16KV swgr. 133 load shedding relay fuses. Note: Annunciator window A4 will alarm. 8.3.7.3 Open the cubicles listed below and momentarily remove and replace the close and trip fuses for the listed breakers. Note: Listed annunciators will alarm. Cubicle Breaker Ann. Window Equipment 02 20402 A-57 Feed to 480V Vital Load ctr. 132 03 20403 A-59 Feed to 480V Press. herld. cent. IB3 04 20404 CCW pump 1B 05 20405 R-56 H.P. Safety Injection pump 1B 06 20406 R-59 L.P. Safety Injection pump 1B 07 20407 R-52 Containment Spray pump 1B 08 20408 Spare 09 20409 A-54 Feed to 416KV Vital swgr.1AB , 10 - 20410 E-47 Intake cool. water pump 13 11 20411 A-52 Supply from 4.16KV swgr. I AB 12 20412 G-45 Aux. Feedwater pump 1B 8.3.8 Mo=entarily open and reclose breaker 60213, D/G IB control panel. Note: Annunciator window A-36 on RIGB 101 and 24 on DG/DP annun:1ator will alarm. If ground did not clear, pror ni to section 8.3.9. If the ground did clear, proc _ d to D/G 1B control panel and perform the following: 8.3.8.1 Momentarily remove and replace start circuit fuses F1 & F2. Note: Annunciator windows A-36 on RTGB-101 and 24 on DG 1B annunciator will alarm. 8.3.8.2 Momentarily remove and replace the fuse listed below: Fuse # Equipment 73 & F4 D/G 1B lockout relay F13 & F14 D/G 1B governor control FIS & F16 D/G 1B voltage adjust F17 & F18 D/G 1B annunciator FS & F6 Fuel Prime pump 1B1 motor 31/a F7 & F8 Fuel Prime pump 132 motor B1/b F9 & F10 Er. erg.011 Circ. Pump 1B1 motor B2/a Fil & F12 - Emerg.0il.Cire. Pump 132 motor B2/b . l
Pcgo 13 of 35 ' t FLORIDA POWER & LIGHT COMPANY UNIT NO. 1 0FF-NORMAL OPERAfING PROCEDURE NO. 0960030 REVISION 7
8.0 Instructions
(continued) 8.3.9 Remove static inverter ID from service by performing section 8.3.1 thru 8.3.8 of operating procedure #0970020. 8.3.10 If the ground did not elect, perform section 8.1.1 to 8.1.9 of operating procedure #0970020 to return static inverter ID to service. 8.3.11 Verify the reactor trip breakers TCB-1 thru 8 are closed. CADTION: Completing Step 8.3.12 will place plant in an unstable condition. TCB-9, TCB-2 & TCB-6 will open, resulting in one MG set supplying load to CEA's. Since synchronizing across trip breakers is impossible, the unloaded MG set output breaker must be opened, TC3-9 closed, and unloaded MG set resynchronized to grid. Ground should be checked by completing Steps 8.3.12.1 through 8.3.12.2. 8.3.12 Inform the costrol room the TC3-2 and TC3-6 & TCB-9 will be tripped. womentarily open & reclose breaker 60220. Note: Annunciator windows K-1, K-2 & K-3 will alarm. If the ground did not clear, reset TCB-2 & TCB-6 & TCB-
, 9 per caution statement above and proceed to section 8.3.13. If the ground did clear, proceed to reactor trip svgr. unit 002 and perform the following:
8.3.12.1 Momentarily remove and replace the close'& trip fuses for TCB-2. 8.3.12.2 Mcmentarily remove and replace the close & trip fuses for TCB-6. 8.3.12.3 Reset the ungrounded breakers as determined from 8.3.12.1 & 8.3.12.2. 8.3.13 verify all reactor trip breakers are closed, then inform the control room the TCB-4 & 8 will be tripped. Momentarily open and reclose breaker 60222. Note: Annunciator window K-10 and K-11 will alarm. If the ground did not clear, reset TCB-4 and 8 and proceed to section 8.3.14. If the ground did clear, proceed /R7 to reactor trip swgr. unit 005 and perform the following:
, 8.3.13.1 Fomentarily remove and replace the close and trip fuses for TC3-4.
8.3.13.2 Momentarily remove and replace the close and trip fuses for TCB-8.
- - . - . . . _ - . . . - ~ - . . . . _ _ _ _ _ . . - - . .- ~ _. -
I Pago 14 of 35 '
! l FLORIDA POWER & LIGHT COMPANY UNIT NO. I l 0FF-NORMAL OPERATING PROCEDURE NO. 0960030 REVISION 7
8.0 Instructions
(continued) m-m 8.3 (continued) 8.3.13.3 Reset the ungrounded breakers as determined from steps 8.3.13.1 and 8.3.13.2. 8.3.14 Remove static inverter 1B from service by performing steps 8.3.1 to 8.3.8 of operating procedure #0970020. 8.3.15 If the ground did not clear, return static inverter 1B to service by performing steps 8.1.1 to 8.1.9 of operating procedure 10970020. 8.3.16 Momentarily open and reclose breaker 50202 relief valve V-1404. Note: Valve fail closed, lose indication, annunciator window D-30 alarms. 8.3.17 Momentarily open and reclose breaker 60217, RTGB-103, -104 (fuses QQ-1 to 10, - 104 fuses 13 & 14. See Appendix F for load list. 8.3.18 Momentarily open and reclose breaker 60215, RTGB-106 (-106 buses GG 41-70) See Appendix I for load list.
- 8.3.19 Momentarily open and reclose breaker 60218 Letdown stop valve V-2515.
Note: Valve fails closed, loses indication, and must be opened and reclosed quickly to prevent loss of letdown. 8.3.20 Check circuit by removing individual fuses, RTGB-106 (fuses CG-1 to 40). See Appendix H for load list. Certain fuses will be noted: DO NOT REMOVE. 8.3.20.1 CAUTION: Before removing fuses 27 to 30 (HCV-14-6, 7), ensure that the air-supply solenoid valves HSE-14-6, 7 are mechanically jumpered to prevent closure of HCV-14-6, 7. After checking for a ground, install fuses 27 to 30 and reset HCV-14-6, 7 control switches in the Control Room.
/ 8.3.20.2 Remove mechanical jumpers on I.V. HSE-14-6,7.
8.3.21 Momentarily open and reclose breaker 60223, DC PP-119. See Appendix J for load list. i 8.3.22 Momentarily open and reclose breaker 60228 Aux. spray valve ISWE-02-A. Note: Valve fails closed, loses indication.
. ._ . --. ~.~ _ _. .
I Pcga 15 of 35 FLORIDA POWER & LIGHT COMPANY UNIT NO. 1 0FF-NORMAL OPERATING PROCEDURE NO. 0960030 REVISION 7
8.0 Instructions
(continued) 8.3 (continued) 6 8.3.23 Momentarily remove and replace the DC bus IB undervoltage relay fuses in DC, Bus 13. 8.3.24 Momentarily remove and replace the DC Bus IB ground relay fuses in DC Bus IB. 8.3.25 Momentarily open and.reclose Breaker 60219, RTGB-105 (fuses EE-19 to 54). See Appendix G for load list. CAUTION: Performance of Step 8.3.25 will result in an autostart of "B" and "C" auxiliary feed water pumps and the feeding of "B" steam generator. 8.3.26 If the ground has not cleared at this point, notify Electrical Maintenance that the ground is apparently in the generator excitation switchgear. DO NOT operate breaker 60209 (main generator will trip on loss of DC). 8.4 Isolate a ground on the IAB 125V DC Bus as follows: 8.4.1 The following breakers can be momentarily opened and reclo' sed without affecting plant operation: Bkr. Equipment 60304 4.16 KV Swgr. IA3 & IB3 Test Stand 60305 6.9 KV Swgr. Test Stand 60306 2TGB 101 & 102 Annunciator Power Supply Cont. Hi Press. CIS pretrip Cont. El Rad. CIS pretrip Pr:r Lo Press. pretrip 60307 4.16 KV Swgr. lA2 & IB2 Test Stand 60309 4.16 KV Swgr. 1AB Test Stand 8.4.2 Momentarily open and reclose breaker 60301, 4.16KV svgr. LAB. Note: Annunciator windows A5, AS4, 354, E91, S53 & R57 will alarm. If the ground did not clear, proceed to section 8.4.3. If the ground did clear, proceed to 4.16KV svgr. IAB and perform the following: 8.4.2.1 Open cubicle 1 and momentarily remove and replace the close and trip fuses for breaker 20501. Note: Annunciator window S-53 will alarm. If the ground did not clear, remove and replace the 4.16KV svgr. LAB differential lockout relay fuses.
_ _ _ . . _ . _ . . ._. .. _ __ ~ _. _ .__...._ .__.....__. . . _ . . . _ . _ . _ _ _ _ . . . - . . _ _ . I Pago 16 of 35 FLORIDA POWER & LIGHT COMPANY UNIT NO. 1 ! 0FF-NORMAL OPERATING PROCEDURE NO. 0960030 REVISION 7
8.0 Instructions
(continued)
=
8.4 (continued) 8.4.2.2 Open cubicle 4 and momentarily remove and replace the close and trip fuses for breaker 20504. Note: Annunciator window AS4 will alarm. If the ground did not clear, remove and replace the 4.16KV swgr. LAB load shedding relay fuses. Note: Annunciator window A5 will alarm. 8.4.2.3 Open the cubicles listed below and momentarily remove and replace the close & crip fuses for the listed breakers. Note: Listed annunciators will alarm. 20502 02 R-57 Component Cooling water pump IS 20503 03 E-51 Intake Cooling water pump IS 20505 05 B-54 Supply from 4.16KV svgr. lA3. 8.4.3 Momentarily open and reclose breaker 60302, 480V svgr. LAB. If the ground did not clear, proceed to sectf an 8.4.4. If the ground did clear, proceed to 480V swgr. LAB and perform the following: 8.4.3.1 Opencobpt. 2A (instrumentation) and momentarily , remove and replace the 480V svgr. LAB undervoltage relay fuses. Close compt. 2A. 8.4.3.2 At the rear of each component listed below, momentarily remove and replace the close and trip fuses for the listed breakers: 40702 13 Supply from 480V Vital Load Ctr. lA2 40703 1C MCC 1AB (reactor) 40704 ID Spare 40706 23 Supply from 480V Vital Load Ctr.132 40707 2C Charging pump IS 40708 2D Spare 8.4.4 Momentarily open and reclose breaker 60303. Reset annunciators on RTGB-103,104,105 and 106. 8.4.5 Verify that aux. feedwater pump IC is not running and open and reclose the following breakers: 3kr. 60308 Skr. 60310 8.4.6 Remove the Vital AC Static Inverter from service by performing steps 8.4.1 thru 8.4.12 of operating procedure
#0970021.
6 Page 17 of 35 l FLORIDA POWER & LIGHT COMPANY UNIT NO. 1 0FF-NORMAL OPERATING PROCEDURE NO. 0960030 g REVISION 7 l
8.0 Instructions
(continued) 8.4 * (continued) 8.4.7 If the ground did not clear, perform, steps 8.5.1 thru 8.5.11 of operating procedure #0970021 to return Vital AC Static Inverter to service. 8.4.8 Momentarily remove and replace the DC Bus 1AB undervoltage relay fuses in DC bus 1AB. 8.4.9 Momentarily remove and replace the DC Bus 1AB ground relay fuses in DC Bus IAB. 8.5 Isolate a ground on 125V DC bus 1C as follows: 8.5.1 The following breakers can be uomentarily opened and reclosed: 8.5.1.1 Battery charger 1C output 8.5.1.2 Load Test 8.5.2 The emergency oil punp is not normally in use. Verify with the Control Room that the emergency oil pump is not running, then open and reclose breaker 60711. Note: Annunciator window C-56 will a'larm., 8.5.3 Verify that the air side seal oil pump (25 RP) is not running, then open and reclose breaker 60231. i l 1 1 l l l 1
Page Ift of 35 OPERATING PROCEDURE NO. 0960030, D.C. CROUND ISOLATION, REVISION 7 APPENDIX A PP DC 1 A_, CKT 17 RTCB 103 TB RR CWD 394 Rev. 9 Ref. 8.2.18 hkr. #60117 GE EBASCO FilSE NO. I.INE NO. 1.0AD CONDITIONS REQUIRED TO DE-ENERGIZE j CWD TAG TITI.E i 1 PIA 121 V-1400 Quench Tank Vent Valve Fall closed, lose indication 2 N!A . l l 3 P2A 97 63x/PIC- Backup & prop. heaters energize (all bankaa) 1100 . If in auto. Lose indication of spray valve
. 4 N2A 130 PCV-1100 Pressurizer Press. position i
5 ) P3A 117 63x/P-1102 6 N3A 74-3 Power Oper. ' Relief Valves Annunc. at 11-22. Valve fail closed
> 7 P4A 139 L-ll10-2 Backup prop. heaters de-energize-must be 8 N4A reset af ter return to normal. Annunc. at 11-4 19,20,25,26,31,32. Backup chg. pumps start if in " auto".
9 P5A 138 63x/LC- Pzr. Level Control Backup & prop. heaters de-evergize if 11S-1110-IlOOXL 2/139 selected to "X" or "BOTil". Both backup 10 NSA 63x/LA- chg. pumps start if in " auto" and control 1100XL selected to "X" 8 I l t 5 I
P ga H of 35 I OPERATING PROCED11RE NO. 0960030, D.C. CRollND ISOLATION, REVISION 7 - APPENDIX B PP DC IA CKT 19 RTCB 105 TB lill CWD 645 Rev. 7 9 i CE EBASCO !
, FilSE No. LINE NO. LOAD CONDITIONS REQtJIRED TO DE-ENERGIZE ,
j 8
! CWD TAG TITLE 19 PIA 159 V-2205 RCP controlled bleedoff rail closed; lose indication.
20 NIA isolation f 21 P2A 159 V-2516 Letdown isolation Fall closed, lose indication. 22 N2A 157 , 23 P3A 159 V-2510 B.A. tank IA recirc. Fall closed, lose indication. 24 N3A i 25 P4A 563 V-6301 Reactor drain tank 1801. Fall closed, lose indication. , 26) N4A l 27 PSA 564 V-6554 Waste gas isolation Fall closed, lose indication. , 28 NSA , 29 P6A 159 V-2511 B.A. tank IB recirc. Fall closed, lose indication j 30, N6A 31 P7A 576 LCV-07-IIA Cont. aump 1s01. Fall closed, lose indication. 32 N7A 33 F8A 176 FCV-2161 B.A. pump disch. to VCT Fall closed, Jose indication. 34 N8A 35 P9A 158 LCV-2110P Letdown throttle valves Lose indication, scay as is. 36 N9A LCV-2110Q 37 P10A 160 V-2507 NCP controlled bleedof f Fall open, lose indication. 38 N10A relief stop . 39 Pila 160 V-2513 VCT vent Fail closed, lose indication. ! 40 NilA l 41 P12A 189 ISE-02-3 Auxiliary Spray Fail closed, lose indication. 42 N12A l
l, Pago 20 of 35 OPERATING PROCEDURE NO. 0960030, D.C. GROUND ISOI.ATION, REVISION 7 . APPENDIX 11 PP DC 1A CKT 19 RTGB 105 Til IIII CWD 645 Rev. 7 I t i EllASCO GE FilSE No. I.INE NO. I.OAD CONDITIONS REQUIRED TO DE-ENERCIZE % l (ND TAG TITI.E 43 P13A 176 ISE-02-1 till Charging line Fall open, lose indication. 44 N13A 45 Pl4A 176 ISE-02-2 IA2 charging line Fall open, lose indication. - 46 N14A 47 PI5A 562 V-6307 Flash tank diverter valve Diverts to hold-up tank, lose indication. ' All NI5A 49 P16A 562 V-6308 Flash tank N2 stop valve Fall closed, lose indication. 50 ) N16A 51 Pl7A 562 !.CV-6604 Flash tank level control I.ose indication, stay as is. 52 N17A 53 P18A 565 FCV-6627X 1.iquid waste flow control Fall closed, lose indication 54 , N18A FCV-6627Y valves j 55 P19A 151 PCV-220lP 1.etdown pressure control lose indication, stay as is. 56 N19A PCV-2201Q valves 62 "A" and "C" "A" and "C" AFW pumps will start and 63 AISI pumps and valves feed "A" steam generator. I O
- ?
Prgs 21 of 35 OPERATING PROCEDURE NO. 0960030, D.C. CROUND ISOLATION, REVISION 7 AP1lENDIX C FP DC IA CKT 21 RTGB 106 TB CCC CWD 647 Rev. 5 GE EBASCO , i
! FilSE NO. LINE NO. LOAD CONDITIONS REQUIRED TO DE-ENERGIZE j 6
CWD TAG TITLE . 1 PIA 211 IICV-14-3A CCW f rom S/D lit. exch. lA Fails open ! 2 NIA i 3 P2A 242 V-3621 SI tank 1A1 fill & drain Fall closed, lights i 4 N2A i 5 P3A 242 V-3641 SI tank IB2 fill & drain Fall closed, lights j 6 N3A , 7 P4A 243 V-3623 SI tank lAl vent Fall closed, lights , 8 ) N4A ; 4 9 PSA 243 V-3643 SI tank 1B2 vent Fail closed, lights , 10 NSA 11 P6A 274 FCV-3306 S/D cool, return flow Fall open, lights 12 , N6A 13 P7A 536 IICV-2 5-1 RAB Sump drain valves Fall closed, lose indication 14 N7A thru 7 l i 15 P8A 1000 BTIA-IAs 125V DC transfer control 16 N8A 17 P9A 289 FCV-07-1A Containment spray Fall open, lights j 18 N9A 19 P10A 312 IICV-08-1A Main steam 1801. valve Valve will open when control circuit is de-20 NIDA energized if supply air is available. (Check Plant Condition) l 21 Pila 578 V-5200 Prim. sampling sample valve Falla closed, lights out-lose sampling [ 22 NilA capability ; i I l i I
.I f
P gs 22 of 35 , OPERATING PROCEDURE No. 0960030,1).C. CROUNI) IS01.ATION, REVISION 7 ' APPENDIX C PP DC IA CKT 21 HTCB 106 TB CCC CUD 647 Rev. 5 j I GE EBASCO I FilSE NO. I.INE No. LOAD CONDITIONS REQUIRED To DE-ENERGIZE , i CWD TAG T ITI.E 23 P12A 579 V-5201 Prim. sampling sample Fails closed, lights out-lose sampling 24 N12A valve capability 25 P13A 580 V-5202 Primary sampling sample Fails closed, lights out-lose sampling 26 N13A valve capability 27 P14A 212 IICV-14-1 CCW to RCP Pails closed 28 N14A , I 29 , PI5A 212 IICV-14-2 CCW from RCP Fails closed i 30 NISA 31 P16A 32 N16A 6 33 Pl7A 281 IICV-3628 Check valve leakage drain Lose lights 34
- N17A to RWT 35 P18A 283 IICV-3648 Check valve leakage drain Lose lights
^36 N18A to RWT 37 P19A Spare 33 N19A Spare ,
llCV-08-1A 39 P20A 312 (4YA) Main Steam Isol. Valve Valve Closes 40 N20A 312 (4YAl) IICV-08-1 A Opening & Closing ilCV-08-1B (D0 NOT REMOVE FUSE) (Trips Plant) 6 l i e
P:gn j[1 of 35 OPERATING PROCEDURE No. 0960030, D.C. CROUND ISOLATION, REVISION 7 . APPENDIX D " i PP DC IA CKT 23 RTCB 106 TB CCC CWD 648 Rev. 5 l, CE EBASCO l l FUSE PM. LINE NO. LOAD CONDITIONS REQUIRED TO DE-ENERGIZE l l CWD TAG TITLE ,,J 41 P21A 283 V-3661 S1 check valve return to Fall closed, lose lights
; 42 N21A reactor drain tank l 43 P22A 274 V-3661 S1 check valve return to Fall closed, lose lights 44 N22A reactor drain tank 4
45 P23A 202 liCV-14-8A CCW Normal supply hdr. Fall closed, lose lights 46 N23A isolation f 47 P24A 202 IICV-14-9 CCW normal return hdr. Fall closed, lose lights l
! 48 ) N24A isolation {
t 49 P25A l l 50 N25A l 51 P26A 511 FCV-25-1, Cont. Purge Isol. valves Fall closed lose indication i , 3, 5 Refueling dampers ., 52 N26A SE-25-5 53 P27A 529 FCV-25-6 Vacuum relief valve Fall closed lose indication 54 N27A 55 P28A 320 FCV-26-2, Cont. Monitor sample valvee Fall closed lose indication 56 N28A 4, 6 57 P29A 461 FCV-23-7 S/G IA & IB blowdown Fall closed lose indication' 58 N29A 9 sample isolation 59 P30A 319 FCV-23-3 S/G IA blowdown isol. Fall closed lose lights 60 N30A i i* 61 P31A 319 FCV-23-5 S/G IB blowdown isol. Fail closed lose lights 62 N32A l .
I P gs 2]L of 35 OPERATING PROCEDtJRE NO. 0960030 D.C. CROUND ISOLATION, REVISION 7 APPENDIX D PP DC IA CKT 23 RTGB 106 TB CCC CWD 648 Rev. 5 CE EBASCO l FtlSE PK). LINE NO. LOAD CONDITIONS REQtJIRED TO DE-ENERGIZE { CWD TAG TITLE b""
, 63 P32A 256 V-3622 SI tank 1A1 N2 supply Fall closed lose lights 64 N32A 65 P33A 256 V-3642 SI tank IB2 N2 supply Fall closed lose lights 66 N33A 67 P34A 281 IICV-3623 SI tank 1A1 check valve Fall closed lose lights 68 N34A leakage to RWT t
i a i i I ' e
- . i
) 2
.j i i Piga 25 of 35
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i OPERATING PROCEDURE No. 0960030, D.C. CROUND ISOLATION, HEVISIO1 7 .
- APPENDIX E f .
} PP 118 CKT 24 RTGB TB CWD Rev. ! l ! CE EBASCO I { LINE No. IAAD CONDITIONS REQli1 RED TO DE-ENERGIZE ~ j lFilSENO. CWD TAG T ITI,E . j j Ckt. 2 799/2 RTCB 101 ZZ Fuse 1-6 ; , Ckt. 3 587/4 Annunciator "W" Out of service, no remote alarm. ! I i Ckt. 4 1191/1 RTGB-103 Annunciators Will be changed with re-flash i ,e Ckt. 5 117/4 V-1402 Pzr. relief valve Lose indication, prevent valve from opening,
- l '
actuate ann. H do not do concurrent with , i DC 1A Ckt. 2 .- j Ckt. 6 1191/1 RTCB-104 Annunciators Will be changed with re-flash l i I ( I
; . i f
[ i . ;
?
s t lt 4 ! i I 4 j e
I P;ge 26 of 35 OPERATING l'ROCEDURE No. 0960030, D.C. GROUND ISOLATION, REVISION 7 APPENDIX E PP 118 CKT 2 RTGB 101 TB ZZ CWD 799 Rev. 6 GE EBASCO FUSE NO. LINE NO. LOAD CONDITIONS REQUIRED TO DE-ENERGIZE CWD TAG TITLE
""d I PIA 710 20/AST Turbine auto stop trip 1. IL-710 (by trip ph) goes out 2 NIA 2. Lose elec. turbine trips other than man. 86 GP, 86cB, and 63-2/AST.
- 3. Prevents high exh. temp trip of 86CB 3 P2A 883 86/GP Prim. gen. lockout 1. Lose light actuate ann. C-31 4 N2A -
- 2. Prevent associated trips
- 3. Give bkr. open signal to Dell, field bkr.
telemetry E0P, speed / valve position recorder will shift to speed (most also require i signal f rom 86 GB bkr. position. Do not energize when PP-il9 ckt. 3 is down. 5 P3A 720 86/LFT Eli pump low low level 1. Lose light, actuate ann. D-58 6 N3A lockout 2. Prevent low low level trip 4
. Page 27 of 35 OPERATING PROCEDURE NO. 0960030, D.C. CROUND ISOLATION, REVISION 7 i l i APPENDIX F { PP DC IB CKT 17 RTCB 103 TB QQ CWD 394 Rev. 9 i
! CE EBASCO f FUSE NO. LINE NO. LOAD CONDITIONS REQUIRED TO DE-ENERGIZE _
CWD TAG TITLE ! 1 PIB 121 V-1401 Quench tank drain valve Fall closed, lose indication
=
2 NIB ,, ! l 3 P2 B 138 63Y/LC- Pzr. level control Backup & proportional htra. de-energize if HS-j l lil0YL 1110-2/139 is selected to "Y" or both. Both
;) 4 N2B 63X/LA- backup charging pumps start if in auto &
1
- I!!OYL control selected to "Y".
5 P3B 187 ISE-02-4 Aux. spray valve Fail closed, lose indication
- 6) N3B (normal supply) 7 P4B 855 112 seal oil fire prot.
i 8 N4B 9 P5B 855 Lube oil fire prot. 10, - NSB TB DD RTCB 104 13 NSB 749 Steam Dump to Cond. Fall closed 14 P58 749 Valves PCV-8802 & 8803
, i 4
i 4 i I ii - e 4
Pzg 2 28 of 35 OPERATING PROCEDURE NO. 0960030, D.C. CROUND ISOLATION, REVISION 7 i , APPENDIX G 1 l PP DC IB CKT 19 RTGB 105 TB EE CWD 645 Rev. 7 I GE EBASCO t FUSE NO. LINE NO. LOAD CONDITIONS REQtJIRED TO DE-ENERGIZE ~ CWD TAG TITLE 19 PIB 159 V-2515 Letdown stop valve Fall closed " * " 20 NIB 21 P2B 159 ISE-01-1 RCP controlled bleedoff Fall closed 22 N2B 1801. 23 P3B 163 V-2512 Hakeup stop Fall closed 24 N3B 25 P4B 565 V-6739 Spent resin to drumming closed 26 ? N4B station 27 PSB 576 LCV-07-IIB Cont. sump 18o1. valve Fail closed, lose indication 28 NSB 29 P6B 563 V-h302 RDT Cont, 1801. valve Closed 30 , N6B 31 P7B 564 V-6555 Waste gas co.t. 1s01. Closed 32 N7B valve 33 P8B 566 V-6741 N2 hdr. cont. isql. valve Closed 34 N8B 35 P9B 163 FCV-2210Y Boric acid flow Fall closed 36 N9B 37 P10B 160 V-2507 RCP controlled bleedof f Fail open 38 N10B relief stop 39 PilB 160 V-2513 Volume control' tank vent Fall closed 40 NilB 41 P12B 160 V-2500 volume control tank inlet De-energized to volume control tank 42 N12B i i
l . i - P:ge 29 of 35
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OPERATING PROCEDURE No. 0960030 D.C. CROUPD ISOIATION, REVISION 7 ,. APPENDIX G PP DC IB CKT 19 RTGB 105 TB EE CWD 645 Rev. 7
}
GE EBASCO . f FUSE NO. LINE NO. LOAD CONDITIONS REQUIRED TO DE-ENERGIZE CWD TAG TITLE i 43 P138 174 PS-2206 Boric acid P!A disch. press. i 44 N138 PS-2208 Boric acid P1,B disch. press. Ann. N 39 45 P14B 563 V-6300 RDT vent stop valve Closed j 46 N14B 47 P15B 564 V-6565 Waste gas stop valve Closed 48 NISB l 49 P168 566 V-6728 Resin disch. stop valve Closed l 50 i N16B 51 Pl?B 163 FCV-2210Y Reactor makeup water flow Falls closed 52 N17B 53 "B" and "C" "B" and "C" AFW pumps will start and 54 , AFW pumps and valves feed "B" steam generator I i t 4 t-
. l i
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i Pzge 30 of 35
~~~ l y OPERATING PROCEDURE NO. 0960030, D.C. CROUND ISOLATION, REVISION 7 !
APPENDIX 11 i P P_ DC IB CKT 21 RTGB 106 TB GG CWD 647 Rev. 5 f I
- GE EBASCO
! L FUSE NO. LINE NO. IDAD CONDITIONS REQUIRED TO DE-ENERGlZE CWD TAG TITLE m 1 PIB 211 IICV-14-3B CCW from S/D ht. exch. 18 Fails open 2 NIB
' 3 P2B 242 V-3611 Si tank IA2 fill & drain Fail closed, lose lights j 4 N2B ;
. 1 ! ,! 5 P3B 242 V-3631 SI tank 1B1, fill & drain Fail closed, lose lights i 6 N3B ' + 7 P4B 243 V-3613 Si tank 1A2 vent Fall closed, lose lights 8 i N4B I e 9 P5B 243 V-3633 SI tank 181 vent Fall closed, lose lights 10 NSB l !! P6B 274 IICV-3657 S/D cooling heat exch. Fall closed, lose lights , 12 , N6B i 13 P7B 14 N7B , 15 P88 1000 BT-lB-IAB 125V DC bus transfer 16 N8B control V 17 P98 289 FCV-07-B Containment spray Fail open, lose lights 18 N9B 19 P10B 315 IICV-08-1 B Hain steam isol. valve Valve will open and remain open when control 20 N10B circuit is de-energized if supply air is
~
available. (Check Plant Condition) > 21 PilB 578 V-5203 Prim. sampling sample Falls closed, lights out - lose sampling l l 22 NilB valve capability
?
I
Pega 31 of 35 OPERATING PROCEDURE No. 0960030, D.C. CR0llND ISOLATION, REVISION 7 APPENDIX II PP DC IB CKT 21 RTCB 106 TB CG CWD 647 Rev. 5 h GE EBASCO -
==* '
FilSE NO. LINK NO. LOAD CONDITIONS REQUIRED TO DE-ENERCIZE CWD TAG TITLE 23 P128 579 V-5204 Prim. sampling sample Falla closed, lights out - lose sampling 24 N12B valve capability
; j 25 P13B 580 V-5205 Prim. sampling sample Fails closed, lights out - lose sampling l
- 26 N138 valve capability l 1 27 P14B 212 IICV-14-7 CCW to RCP Falla closed l 28 N14B l
! 29 P158 212 IICV-14-6 CCW from RCP Fails closed 30 I N15B 31 P16B 32 N16B 33 P!7B 280 IICV-3618 Check valve leakage Fail closed, lose lights drain to RWT 34 N17B 35 PISB 282 IICV-3638 Check valve leakage Fall closed, lose lights 36 NIBB drain to RWT 37 P19B 315 IICV-08-I A Main steam Isol Valve Valve closes i 38 N198 315 (4YB) IICV-08-18 Opening HCV-08-IA (D0 NOT REMOVE' FUSE)
(4YBI) & Closing (Trips Plant) 39 P20B Spare 40 N20B Spare J I i
! i i :
6
P ge 32 of 35 OPERATING PROCEDURE NO. 09/0030, D.C. CROUND ISol.ATION, REVISION 7 APPENDIX I , ! PP DC IB CKT 15 RTGB 106 TB CC CWD 698 Rev. 5 j GE EBASCO
- FUSE NO. l.INE NO. 10AD CONDITIONS REQlllRED TO DE-ENERGIZE CWD TAG T ITI.E -
41 P21B 282 IICV-3638 181 Si check valve leakage Valve will fall closed '* l 42 N21B to RVr 43 P22B 202 IICV-14-8B CCW normal supply hdr. 1801. Fall closed, stop CCW , 44 N22B . l 45 P23B 202 IICV-14-10 CCW normal return lair. 1801. Fall closed, stop CCW l 46 N23B i 47 P24B ,
. 48 ) N24B l 49 P258 50 N25B l 51 P268 512 FCV-25-2, Cont. purge 1801.. valves Fall closed, lose indication, stop fans i 52 N26B 4, 6 53 P278 529 FCV-25-8 Vacuum relief valve Fail closed, lose indication 54 N278 i
55 P28B 320 FCV-26-1, Cont. sample isol. Cont. sample pumps should be secured by 56 N28B 3, 5 de-energizing 57 P29B 58 N29B
$9 P30B 319 FCV-23-4 S/G 1A blowdown 1801. Fail closed 60 N10B 61 P31B 319 FCV-23-6 S/C IB blowdown isol. Fall closed 62 N31B
, 63 P32B 256 V-3612 1A2 SI tank N2 valve Fall closed, lose indication 64 N12B
_ _ . _ _ . . ~_ Page 33 of 35
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OPERATING PROCEDURE NO. 0960030, D.C. GROUND ISOI.ATION, HEVISION 7 . APPENDIX I PP DC IB CKT 15 RTCB 106 TB CG CWD 698 Rev. 5 l
- GE EBASCO ,
7"JSE NO. I.INE NO. LOAD CONDITIONS REQUIRED TO DE-ENERGIZE { CWD TAG TITLE . l 65 P33B 256 V-3632 181 SI tank N2 valve Fail closed, lose indication l 66 N338 .l i I 67 P34B 280 llCV-3618 IA2 SI check valve leakage lose indication, stays as is l' ! 68 N34B to RWT _f~ i 69 P35B ! 70 N35B , t i ) I i s-l t
. 1, i
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{ Page 3j! of 35 i OPERATING PROCEDURE NO. 0960030, D.C. CROUND ISOLATION, REVISION 7 l $ I APPENDIX J i i PP 119 CKT RTGB TB CWD Rev. j i ! l GE EBAS00 FUSE NO. LINE No. LOAD CONDITIONS REQUIRED TO DE-ENERGIZE ;
- CWD TAG TITLE
- Ckt. 1 438/5 Radiation monitor Annun. """ ',
- Actuate ann. Q-36 .i i
Ckt. 3 799/6 RTGB-102 XX Fuse 7-12, 43 i i & 44 ' i Ckt. 4 1192/1 RTGB-105 Annunciators Will be changed with reflash
- Ckt. 5 740/3 SC-10-3A, 3B, 4A, 4E Vent air off operator, spring will tend to i
(Reverse current valve) close t
- Ckt. 6 1192/1 RTGB-106 annunciators Will be changed with reflash j
Ckt 7 740/3 SC-10-5A Vent air off operator, spring will tend to , (Reverse current valve) closa j Ckt. 10 740/3 SC-10-5B Vent air off operator, spring will tend to (Reverse current valve) close i e t b I i i b e 1. t - t
I Paga 35, of 35 OPERATING PROCEDURE No. 0960030, D.C. CROUND ISOLATION, REVISION 7 p APPENDIX K *
' PP 119 CKT 3 RTGB 101 TB ZZ CWD 799 Rev. 6
{ CE EBASCO FUSE NO. LINE NO. LOAD CONDITIONS REQUIRED TO DE-ENERCIZE CWD TAG TITI.E 1 PIB 711 20/ET Emergency turbine trip 1. Lose IL710, actuate ann. D-17 2 NIB 2. Prevent backup electrical trips 8 3 P25 885 86/CB Backup generator lockout 1. Lose light, actuate ann. C-31 4 N2B . 2. Prevent trips, prevent closing unit aux. bkr. i
- 3. May ptevent start of trans. coolers. l
. 4. Civa bkr. open signal to Dell, E0P, isophase I cooler alarms, field bkr. (also require g signal from 86/GP). Do not de-energize when i 118 ekt. 2 is down.
5 P3B 882 86/UF Underfrequency lockout 1. Lose light, actuate ann. C-39 6 N3B 2. Prevent underfrequency trip of switchyard 7 P4B 888 CAB /SA Synchro acceptor, Cannot use auto-sync. 8, N4B i 1 I
. i i,
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' FLORIDA POWER & LIGHI COMPANY i ST. LUCIE UNIT NO. 1 .l OFF NORMAL OPERATING PROCEDURE 0440030 REVISION 4 $
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1.0 Title
2OO b- b b This docerunt is no) contro: led. Before uso, SDC/LPSI - 0FF NORRU., OPERATION ,,7;gy;nre. .ation with a ::. icl led docununt.
2.0 Approval
Reviewed by P a N clear Safety Committee M'853 ,"24 19 Approved by A.) (4 Plant Manager [JA#u#se /0 19 Revision 4 Reviewed by Facility Review Group //cwwAe a 3 19 / Approved by # . *///lida_Flant Ein~ager ~
~7/_. //W- 19[7 j
- G 3.0 Purpose and Discussion:
Purpose:
This procedure provides instructions to be followed in the event of a component malfunction which could degrade the systems ability to provide shutdown cooling or safety injection flow. Discussion: No single active component failure will prevent the system from performing its design functions. However, manual action may be required to maintain maximum system effectiveness. Operation with a partial system means only that the cooldown process will take a longer period of time. 4.0 Symo to_ms_: 4.1 The following are indications of SDC/LPSI leakage. 4.1.1 Safe guards room sump high level alarms. 4.1.2 Local visual leakage indications. 4.2 The following are indications of a loss of shutdown cooling capacity 4.2.1 LPSI pump trip 4.2.2 SDC low flov as indicated by FI-3312', 3322, 3332, 3342, or l FIC-3306 - - 4.2.3 Increasing temperature on SDCHI outlets as indicated on TI-3303I, 3303Y or TR 3351. 4.2.4 LPSI pu=p-low discharge pressure as-indicated on PI-3307. i 4.2.5 SDC high pressure alarn _ _~ _ _ _ __ _ _ _ _ - _ 4.2.6'~ FC7-33C6' Failed Cpen~
~ ~
m- -- - 4.2.7 FCV-3657 Failed Closed 1 - . 5.0 Instructions. 5.1 I:m:tediate autematic actions: 5.1.1 SDC loop suction valves' trip closed on high pressure *
"* ' -- ',,,,W q- %
. Pcg2 2 cf 5 OFF NORMAL OPERATING PROCEDURE 0440030, REVISION 4 ,
SDC/LPSI - 0FF NORMAL OPERATION 6 5.2 Immediate Operator Actions h 5.2.1 If leakage is indicated: l 5.2.1.1 Isolate affected portion'of system. h; 5.2.1.2 Re-establish flow to core using remaining $ 3 portion of system. , . . . ... . . . .
,W 5.2.1.3 If leak cannot be isolated proceed to step 5.3.
5.2.2 If a loss of SDC capacity has occurred: -- 5.2.2.1 Check LPSI pumps operating and restart if necessary.
~
5.2.2.2 Check CCW flow to SDC BX. Start additional CCW yumps as required. , _ , _ _ , , _, 5.2.2.3 Check for Intake Cooling Water flow to be.. nor: sal _. and if necessary increase flow thru Heat - Exchangers, 5.2.2.4 Check.ICW strainer for High AP. l 5.2.2.5 Verify prope[ valve' lineup foTSDC oWraition as
- follows: --
MV-3481 SDC suction from loop 1A Open MV-3480 SDC suction from loop 1A Open MV-3651 SDC suction from loop 13 Open MV-3652 SDC. suction from loop 1B . Open
, MV.3615 LPSI header. discharge to loop 1A2 Open MV-3625 LPSI header discharge to loop 1A1 Open MV-3635 LPSI header discharge to icop 1A2 Open MV-3645 LPSI header discharge to loop 132 Open V-3658 LPSI pump discharge to SDC EX Open
. FCV-3306 SDC HX bypass flow control Throttled HCV-3657 SDC HX flow control Throtried
- 5. 2.2.6 : If SDC loop suction valves MV-3651, MV-3652, i MV-3480, or MV-3481 have tripped closed due to high pressure, perform the following:
- 1. Stop both LPSI pumps
- 2. Reduce system pressure to < 26S psig. ,
- 3. Open MV-3651, MV-3652, MV-3480, MV-3481.
- 4. Close HCV-3657 SDC EX Flow Control
- 5. Throttle FCV-3306, SDC HI Bypass Flow Control to 5% open.
- 6. Start LPSI pumps and. slowly re-open FCV-3306 to its original position and return to auto control.
Slowly open HCV-3657 to obtain desired heat- -
- 7.
F ~~
- exchanger flow. -
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OFF NORMAL OPERATING PROCEDURE # 0440030, REV. 4 SDC/LPSI - OFF NORMAL OPERATION , 1
$ 7 i
' ij 5.3 Subsequent Act. ion 5.3.1 If a plant m1down is in progress and shutdown cooling capability cannot be restored, perform the following:
5.3.1.1 Isolate the shutdown cooling system by closing the following valves:
-- - - - - - - - -- - MV-3481 SDC suction from loop 1A ' ~ ' ' ~
-" ~~
'~~
MV-3480 SIic suction from loop 1A
.- . MV-3651 .SDC suction from loop 1B _ _ _
~
MV-3652 SDC suction from loop 1B MV-3615 LPSI header discharge to loop 1A2 MV-3625 LPSI header discharge to loop 1A1 MV-3635 LPSI header discharge to loop 131 MV-3645 LPSI header discharge to loop 1B2 5.3.1.2 If the PRZ bubble is still established, increase RCS pressure to 400 psig and start at least one RCP in the "B" loop. NOTE: If the RCS is solid, rely on natural convection cfrculation, and do not start RCP's. 5.3.1.3 Establish feedwater flow to each steam generator using the auxiliary feedwater pumps. 5.3.1.4 Re-establish cooldown using the atmospheric steam dumps and proceed to cold shutdown. 5.3.2 l If refueling operations are in progress and shutdown cooling ( capability cannot be restored, perform the following: 5.3.2.1 Secure refueling operations and restore containment integrity. - 5.3.2.2 Verify the fuel pool cooling system is in operation per 0P_-0350020. _
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. . P ga 6 cf 5 OFF NORMAL OPERATING PROCEDURE p 0440030, REV.'4 ! l i SDC/LPSI - 0FF NORMAL OPERATION 5.3 Subsequent Action (Cont'd) i 5.3.2.3 (Cont'd) ; ,,, 5.3.2.3 Line up to recirculate the refueling cavity with the fuel pool purification pump as follows:
- 1. Verify that the purification pump is stopped.
- 2. Position the following valves:
V-4221 Fuel Pool skimmer suction ' Closed V-4220 Purification pump low suction Open V-4222 Purification pump suction Open V-4226 Purification pump discharge Open V-4228 Purification filter inlet Closed V-4229 Purification filter bypass Open V-4236 Fuel Pool ion exch. inlet Closec V-4251 Fuel Pool ion exch. bypass Open V-4252 Purification loop to fuel pool closed V-7206 Purification loop to refueling Open cavity (OC) V07189 Purification loop to refueling Open cavity (IC)
- 3. Start the purification pump and verify flow from fuel pool to the refueling cavity. Return flow will be via the fuel transfer tube.
4 Continue..this mode of operation until the shutdown cooling system can be returned to service. 5.3.3 Loss of Power to FCV3306, HCV 3657, or FIC 3306. 5.3.3.1 FCV 3306 fails open 5.3.3.1.1 Throttle valve manually to =aintain 3,000 GEM flow to RCS. 5.3.3.2 HCV 3657 fails closed . 5.3.3.2.1 Throttle valve manually to maintain RCS temperature as required on TR3351. 5.3.3.3 FIC 3306 fails resulting in loss of flow indication and full opening of FCV 3306. 5.3.3.3.1 Throttle FCV 3306 manually. 5.3.3.3.2 Observe individual header flow instru-ments to maintain > 3000 GPM 1A1 - FI3322 132 - FI3342 LA2 - FI3312 131 - FI3332
Pago 5 cf 5 0FF I;0RMAL OPERATING PROCEDURE #0440030, REV. 4 SDC/LPSI - 0FF NORMAL OPERATION 5.0 Instructions (cont'd) 5.3 Subsequent Action (cont'd)
=
5.3.4 If shutdown cooling capability is lost and the RCS , level has dropped below the hot leg suction and/or j the RCS has heated up excessively, reestablish shut- , dcwn cooling as follows-i 5.3.4.1 Open the associated war =up valve for the LPSI pu=p to be started (I-MV-03-LA or R/4 I-MV-03-13) (CRAC) 5.3.4.2 Crack open the LPSI pump suction valve and insure the appropriate RUT outlet valve is open. 5.3.4.3 Throttle the LPSI headervalves HCV3615, 3625, 3635, and 3645. 5.3.4.4 Start the LPSI pump. If the pu=p cavitates severely, open the suction valve further or secure the pump as necessary. NOTE: Several start attempts (with several minutes between starts) =ay be required. 5.3.4.5 When the pu=p is running satisfactorily, slowly close the LPSI suction valve and insure suction from the hot leg is adequate. Slewly close the war =up valve and open the LPSI header valves as desired. NOTE: Rx vessel level shculd be nonitored closely during this evolution. 6.0
References:
6.1 CE E=ergency Procedure Guideline F-EP-13. 6.2 FSAR Section 6 and Section 9. 7.0 Records Required: 7.1 Nor=al log entry. l
CCCUMEth" REVISION DISTRI3UTICIT SEEET - 0F M0mfAL & D'ERCETCT CPER. PT4CEDUE
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Page 1 of 18 . 5 ET0RIDA POWER & LIGHT COMPANY 4 4 ST. LUCIE ?.U.NT UNIT NO. 1 . OFF-NORMAL OPERATING PROCEDURE NO. 0110030 ' REVISION _ 6. i r 0; g3]-
.- {...;'t j ' -G ~... ~ 4W. U R:$G' . ~ me,: ,
l.0
Title:
end u 3 dxumant h no c hoh d dC C"**"f* m _armdermation wo FLCEA 0FF-NORMAL OPERATICN AND REAL y -m
2.0 Approval
Reviewed by Plan
- Nucip e Safety Committee June 25 19 75 Approved by d /bN d Plant Manager :'Julv 9 19 75
~
~~~-~~~~# Rev. 3 RevieNdby FRG Approved by Q-M/4h m/
C f t , f-c o C.8_ ___1977 _ [
# M ant Manager rC.cTa / 1977 Revision 6 reviewed by FRG MCd. S, 1981 Apyoved by 8M//M &Mr- , -
Plant Manager ///oi.,. y z 1981
~
3 . 0 Purpose ~anE Dishudsion: -
3.1 Purpose
To provide instructions for operator action during abnor=al operation and realignment of CEA's.
3.1 Discussion
During normal operacion all full length CEA's s' hall be operable with each CEA of a. given group positioned within 7.5 inches of all other CEA's in its group. In the case of a nisaligned CIA existing, this procedure implemented to ensure: L A.:ceptable: power distribution limits are m=4"rn4"edh 1 Mind n -shutdown =argin is.naintained. 3 Potential effects of. a CIA ejection accident ara 1' 4 ted co-acceptable levels. For small misalignments, a. one hour ti=e limit is provided to restore- CEA alig= ment due to small effects on peaking factors, linear heat rate, and shutdown nargin. For large nisalignments, however, distortion of core- power distribution, resulting in de-gradation- 1:: radial peaking- factors would nor be detected. by the 32S',. ao a. reductiott in thermal power prior to attempting realign-sent is necessary.. For azr immovable or untrippable CEA, or a large nisalignment of two' or more CEA's requires prompt shutdown of the reactor due to possible loss of meckm
- al functional capability of the CEA!s or loss. of shutdatm margin.
. . . . ..e . . = = . -
_. . . , ~ _ .
Page 2 of 18 OPF-NORMAL OPERATING PROCEDURE NO. 0110030 REVISION _6_ FLCEA 0FF-NORMAL OPERATION AND REALIGNMENT
4.0 Symptoms
4.1 Upon observation from metrascope, digital position indicators or data processor, one or more CIA's are misaligned, dropped, stuck,. or untrippable; 4.1 CEA position deviation.ilarm; 4.3 CEA motion inhibit alarm; 4.4 NI <hannel deviation alarm; 4.5 Dropped CEA. alarm;
'i.61 AWP alarm;.
4.Tl PDII. alarm; 4.8i Group- out of sequence alarm; 4.9- lShort term,. steady state insertion alarm. O f n e e _._....w n. nm - -~ _.
Page 3 of 18 0FF-NORMAL OPERATING PROCEDURE NO. 0110030. Rev. j _. FLCIA 0FF-NORMAL OPERATION AND REALIGNMENI
5.0 Instructions
~ ~ - ~ ~ ~
, 5.1 REGULATfiG GRO'~UP 00f0F SfqUENCE, 0R MISALlGNMENI'0F 14' INCHES ~ <. BUT LESS THAN +7J!NCHES. 5.1.1 Tamadhte automatic action 5.1.1.1 CEA motion inhibit on rog. group out of sequence. 5.1.1 I:mmediate operator action 5.1. 2.1 Place CEDS control panel on off. 5.1.2.2. Detershe if any mismatch exists between reactor power and turbine power. If a mismatch exists, adjust turbina power to equal reactor power. 5.1.3 Subsequent. operator action: 5.1.3.1 Determine from symptoms and CIA position indications the cause of the inoperability or if the CEA is operable but misaligned, in accordance with Appendix "B". 5.1.3.1 Insure automatic functions have initiated. , Determine shutdown margin within one hour af ter 5.1.3.3 , detection of an inoperable CEA to be greater than 3.3% Ak/k. (Tech. Specs 3/41-1) 5.I 3.4. If excessive friction or mechanical interference prevents movement of the CEA, or the CEA is un-trippable,. berata- the worth of the effected CEA(s) above tha 54 4 -a = shutdown margia of 3.3% ak/k. See OP #0030125, Turbine Shutdown Full Load to Zero Load. (Tech Specs 3/41-20) . 5.1.3.5 If one CIA. is inoperable due to ocher reasons than stated in Section 5.1.3.4, operation in modes 1 and 1 may continue for up to 7 days per occurrence with
- a. total accumulated time of <14 days per calendar year (Tech Specs 3/4 1-20).
5.I..T 6 If CEL is functioning properly realign the rod with its group 12 accordance with Appendir "A". A 8 9 p--3-a gy - --ge w-,..c-e- ----g .e-- p--- . , , ,- -
Page 4 of 18 0FF-NORMAL OPERATING PROCEDURE NO. 0110030 Rev. _6 FLCEA 0FF-NCRMAL OPERATION AND REALIGN 1 6 5.0 Instructions (ccat.): l === 5.2 r,,rra
- cNE OR MoRE czA's vrorT51n_n h q 7.s fN5iEs 3UT rw n THAN 15, 5.2.1 7 ==df ate- automatic action
- 5. 2.1.1 CEA. motion inhibit 5.2.2 I:mnediate operator action 5.2.2.1 Place CEDS control panel on off 5.2.2.2 Determine if any mismatch exists between reactor power and turbine power. If a mismatch exists, adjust turbine power to equal reactor power.
5.2.3 Subsequent operator action:
- 5. 2.3.1 Determine from symptoms and CEA position indicacious the cause of the inoperability or if the CEA is operable but misa11gned,. in accordance with Appendiz."B".
5.2.3.2 Insura auto =atic functions have initiated.
~
5.2'.3.3 Decernine shutdown margin within ene hour af'ter detectica of an inoperable CEA to be greater than 33% ak/lc (Tech Specs 3/41-1). 5.2.3'.4- If excessive friction or mechenical interference prevents movement of the- CIA, or the CEA is un-trippable,. borate the worth of the effected. CEA(s) above the m1 4- shutdown =argin of . 3.3% ak/k and. be in het standby in six hours. See OPf 0030125, Turbine Shutdown Full Load To Zero Load (Tech Specs 3 /4- 1-20) . 5'.2.3.5 If one or more CEA(s) are inoperable due to other reasons. than stated in Section 5.2.3.4 declare in-
. operabia within ona hour and if above 70% thermal power,
; borate car not greater than 70% thermal power within jone hour and. realign remn91 der of operable CEA!s in
; grou;> within 7.5 inches of inoperable CEA's, without jviolating,CEA.sequenceand. insertion 1Prfts,within 8
. one hour._ Operating time in MODES 1 and 2 =ay continue
; for upp to- 7 days. per occurrence with a. tr.tal accumulated ,
time of 4_t4, days- per calendar year (Tech- Specs 3/4 1-21).! do-- 4 3
- . ~ . ,
.-m._._ _- - ~ . _ _ . - . . _ _ - . .- m.___ _ - - _ . .
Page 5 of 18 0FF-NORMAL OPERAIDIG PROCEDURE No. 0110030,Rev._6]. } FLCIA 0FF-NORMAL OPERATION AND REALIGNMENI 5.0 Instructions (cont.): 5.2 (cont.) 5.2.3.6 If CIA's ara functioning properly, realign CEA(s) within ona bour, in accordance with , Appendix "A". (Tech Specs 3/41-20). CAUTION: If CEA(s) become misaligned by 13 inches or more, but does not drop while performing the above instruction, proceed to instruction 5.3.2.2. If CEA(s) drop while performing the above instruction, proceed to instruction 5.4 l
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Page 6 of 13 0FF-NORMAL OPERATING PROCEDURE NO. 0110030, Rev._6 ' FLCEA 0FF-NORMAL OPERATION AND REALIGA W 5.0 Instructions (cont. ): num 5.3 WITH ONE"CTEWALwaw BY ~15' INCHES ~0lf MORE SUT'NOT' A' DROPPED mL ..
- 5. 3.1 7- M4ata automatic. action 5.3.1.1 CEA motion inhibit.
6 5.3.1 T-M4 aee operator action 5.3.2.1 Place CEDS control panel on off. 5.3.2.1 Determine if any sis =atch exists between reactor power and turbine power. If a mismatch exists, adjust turbine power to equal reactor power. 5.3. 3 Subsequent actions 5.3.3.1 Determine from synptoms and CIA position indications the cause of the inoperability or if the CEA is operable but misaligned, in accordance with Appendix n3n,, 5'.3.3.1 Insure.autenatic functions have initiated. 5.3.3.3. Deterrdne shutdesu. nargin withis one hour after detection of an inoperable CEA to be greater than J.3% ak/k. (Tech. Specs 3/4 1-1). 5.3.3.4 If excessive friction or =echanical interference prevents. 4ve=ennn of the CEA, or the CEA is un-trippable, borate- the worth of the effected CEA(s) above:the in4 r shutdown =argia of 3.3% ak/k and be in hot standby in six hours. See OPf0030125, Turbine Shutdown Full Load To Zero Load.(Tech. Specs 3/4 1-20), t i i e-- # g
.. _ . - - - - . _ _ , . . - - . . _ ~ ___ . . . - _. _ . - . ..
Page _7 of 18 0FF-NORMAL OPERATING PROCEDURE NO. 0110030, Rev.- F FLCEA 0FF-NORMAL OPERATION AND REALIGNMENT 5.0 Instructions (cont.): ,m f 5.3 (cont.) : 5.3.3.5 If one; CEA is inoperable due to other reasons than stated.in Section 5.3.3.4 and if above 70% thermal power, borata to not greater than 70% thermal pcwer-within one hour. The controlled boration should be done in a :nanner which will insure that the reactor power is reduced to a level of less than or equal to 70% within 10 to 30 minutes.. Declare the CEA inoperable, and raalip the remainder of operable CIA's in group within 7.5 inches of inoperable CEA without violating CIA sequence and insertion limits within one hour. After declaring the CEL inoperable, POWER OPERATION may continue for
'^
up- co- 7 days per occurrence with a total accumulated tinw of <14 days per calendar year. With more: than one full length CEA inoperable or mis-a1f pad from any other CEA in its group by 15 inches (indicated position) or nore, be in HOI STANDBY within 6 hours. (Tech Specs 3/41-21 and 3/41-22). 5.3.3.6 If CEA is functioning properly and if above 70% cher:p).
. power, borate to not greater than 70% thermal power within one hour. The controlled boration should be 3
done. in a manner which will insure that. the reactor power is reduced to a level of less than or equal cc:70% within 10 to.30 minutes. R==lign CEA within one hour after reducing ther=al power as. required.in accordance- wi*h Appendix "A". gech, Specs. 3 /4.1-21) . 4 e no- a p i l . _ _ . - .-
- . .- -- .. -.~ -- -. - .. .- ---
Page 3 of 18 0FF-NORMAL OPERATING PROCEDURE NO. 0110030, Rev."6~ FLCEA 0FF-NORMAL OPERATION AND REALIGNMENT 5.0 Instructions (cont. ): 5.4 -DRdPPED ROD Dropping of a CEA during power operation is considered to occur in one of two circumstances:
- 1. Reactor operating at a power level of 70% or less of the
=r4== allowable THERMAL POWER for the existing reactor coolant. pump combination.
- 2. Reactor operating at a power level of greater than 70% of the mrime allowable THERMAL POWER for the existing reactor coolant. pump combination.
5.4.L , DROPPED ROIL CASE.1 5.4.1.1 T=w ate automatic action 5.4.1.1.1 CEA motion inhibit 5.4.1.2' Immediate operator action 5.4.1.2.1 Immediately reduce turbine load to match the reactor power and to return the plant conditions to within LCO's.
- 5. 4.1. 3 Subsequent operator action:
5.4.1.3.1 Determine from symptoms and CEA positica indications- the cause of the inoperability or if the CEA is operable but misaligned, izr accordance. with- Append 1r "B". During. 1 - the- determination of the cause of the i dropped CEA. the reactor power shall not be; increased above the value present at the time the dropped CEA occurred. (Tech Spec- 3/4 1-21) (CE letter F-SF-917).
- 5. 4.1. J. 2. Insure automatic functions have initiated.
F.4.1.3.3 Determine shutdowtr nargin within. one hour after detection; of an inoperable - CEA. cor be greater than . 3.3% Ak/k. (Tech. Specs. 3/4- L-1) .
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i i Page 9 of l lI - 0FF-NORMAL OPERAIDIG PROCEDURE NO. 0110030, Rev.' 6 PLCEA 0FF-NORMAL' OPERATION AND REALIGMENT I l 5.0 Instructions (cont.):- 1 , m 5.4 (cont.): 5.4.1.3.4- If excessive friction or mechanical interference prevents movement of the CIA, or the CIA is untrippeble, borate the worth of the effected CEA(s) above the mini == shutdown margin of
'3.3% ak/k and be in hot standby in six hours. See OPf0030125,. Turbine Shutdown Full Load To Zero Load (Tech Specs 3/4 1-20).
I
; 5.4.1.3.5 If one CEA is inoperable due to other reasons than stated in Section 5.4.1.3.4, declare the CIA in- '
operable After declaring the CEA inoperable, POWER OPERATION may con-tinua for up to 7 days per occurrence
. with a total acetamalated time of <14 days per calendar year provided the
. ra==inder of the CEAs in the group with
. the inoperable CEA are aligned to within 7.5 inches of the inoperable CEA while-maintaining the allowable 4
CEA sequence and insertion limits
- shown. on Figura 3.1-2' of the Tech j Specs ?dSTWRRMAT. POWER level shall be restricted pursuant to Specification 3/41-28 3.1.3.6 during subsequent operation.
j (Tech Specs 3/41-21) (Tech Specs 3/4 1-28). 5~.4.1.4 With mora than. one full length CEA inoperabla or 4 =4 ==14=ned from any other CEA in its group by 15 l inches (indicated position) or more, be in HOT STANJBY within 6 hours (Tech Specs 3/41-22). , 5.4.1.5 RECOVERY: I Upon ascertaining and correcting the cause for the dropped. CEA,. recovery of the CEA may be made. That CEA should be recovered by a slow, smooth l , withdrawal using small increments of movement. Preferably,. the movement increments should be threecsteps or less. The period of time for
- recovering the CEA should be at lease 10 minutes.
Appropriata changes in reactor coolant system boren concentration should be.mada during the withdrawal of the CEA m- --%*- -g-ege--pe--g -E.--*m--^++*w- gy -^-~-r-N-~ ~ - - - " -
~~ -
l l Page 10 of 18 0FF-NORMAL OPERATING PROCEDURE NO. 0010030, Rev. 6 FLCEA 0FF-NORMAL OFERATICN AND RFALIGNMENT ~~ 5.0 Instructions (cont. ): i . 5.4 (cont.) : 5.4.1.5 RECOVERI (cont.) Reactor power should be maintained for the remainder of the recovery procedure at or below the level which resulted after natching the turbine load to the post drop steady state reactor power if at all possible. Following the return of the CEA to its group, operation should be saintained at the existing power level for at least one hour in order to allow assessment of resultant power dis-tributions and/or a:1=uchal tilts.* Upon ascertain 4rg that a. nornal power distribution is present.and that the plant conditions are normal,. power nay then be raised to the desired operating power..
- Notify Reactor- Engineering Supervisor NOTE:, It say be necessary to ' operate 'at this *
, reduced. power level for as long as 24 to 36 hours in order to reduce the az1=uthal osgillatics and the resulting values of Fr*, T g, Ety,. and ASI resulting froct a dropped CIA.
( 1 1 l l y a a
I Page 11 of 18 , OFF-NORMAL OPERATING PROCEDURE NO. 0010030, Rev. 6 FLCEA 0F7-NORMAL OPERATION AND REALIGA M i 5.0 Instructions (cont.): i. 5.4. i=
- 5. 4.1 DROPPED ROD CASE II 5.4.2.1 h aA4=ta autonatic action J
5.4.2.1. I CEA motion inhibic 5.4.2.1. I=nediate operator action 4 I' 5.4.2.2.r In accordance with the present. Technien1 Specifications, the operator shall i= mediately begin to reduce power and, within one hour, be less than 70% of the
*n*m allowable THERMAL P0k'ER level ming hornr4en d# nentire reactivit r
,is re. quired.
It is intended that this caration.shall be a. controlled boration and not an e=ergency boration. The controlled boration should be done in a nanner which will insure that the reactor power is reduced to a. level of less than or equal to 70% within 10 to
/ 30 fainutes after the CEA is dropped.
(CE letter and Tech Specs 3/4.1-21). 5.4.1.3 Subsequent operator action 5.4.2'.3.L Determine from. symptoms and CEA positiotr indications the cause of the inoperability or if the CIA 1s operable but sisaligned in accordanca with Appendix "3". During the determination of the cause of the dropped CIA the reactor power shall not be- increased above the value present at the ti=e- the dropped CEA occurred. ~-~ --, - - - . . -.-n .
Page 12 ' A8 0FF-N010fAL OPERATING PROCEDURE NO. 0010030, Rev. 6^ FLCEA 0FF-NOEMAL OPERATION AND REALIGNMENT ; i
- 5. 0 Instructions (cout.): )
5.4 (cont.) 5.4.2.3.2 Insure automatic functions have initiated. 5.4.2.3.3 Determine shutdown margin within one hour after detection of an in-operable CEA to be greater than 3.3% ak/k. (Tech Specs 3/4 1-1). 5.4.2.3.4 If excessive friction or mechanical interference prevents movement of the CEA,. or the CEA is untrippable, borata the worth of the effected CEA(s) above the nin4 == shutdown margin of 3.3% ak/k and be in hot standby in six hours. See OPf0030125, Turbine Shutdown Full Load to Zero Lead (Tech Specs 3/4 1-20). 5.4.2.3.5 If one CEA is inoperable due to other reasons than stated in Section 5.4.2.3.4, declare the CEA inoperable. After declaring the CIA inoperable, POWER OPERATION may continue for up to 7 days per occurrence with a total acetumilmtad time of <14 days per calendar year provided the remainder of the CEas in the grcup with the in-- operable CEA are aligned to within 7.5 inches of the. inoperable CEA while maintain 4,g the allowable CEA sequence and. 't.sertion limits shown on. Figure of Tech Specs 3/4 1-28 the N AL ! 3.1-2. l POWER level shall be restricted pursuant to Specifications 3.1.3.6 during subsequent operation. (Tech Specs 3/41-21) (Tech Specs 3/4 1-28). l l [
~ . ,
Page 13 of 18 0FF-NORMAT- CSERATUG PROCEDURE NO. 0010030, Rev. [5 - FLCEA On-NORMAL OPERATION AND REAT.TGNMENI d-5.0 Instructions (Cont.): 5.4 (cont.) , , 5.4.2.4 With more..than one full length C u inoperable or =4 ==14L med from any other CEA in its group by 15 inches (indicated position) or more, be izr BOT STANDBT within 6 hours (Tech Specs 3/4 1-28). 5.4.1.5 RECOVERT Upon ascertmi,ing and correcting the cause for the dropped CIA, recovery of the CEA may be made. Tha CZL should be recovered by a slow, smooth ' withdrawal using ==m11 increments of movement . Preferably, the mov-t increments should be three steps or less The period of time for recovering the CEA should be at least 10 minutes. Appropriate changes in reactor coolant system baron concentration.should be made during the withdrawal of the CEA. Reactor power should be maintained for the remmimier of the recovery procedure at or below the. level which. resulted after macching the turbine load to the-post drop steady state res.stor power if at all possible. Following the return of the CEA to its group, operation should be maintained at the existing power level for at least one hour in order to ' allow assessment of resultant power distributions and/or azimuthal tiles.* Upon ascertaining that
- a. normal power distribution is present and that the plant conditions are normal, power may then-be raised. to the desired operating power..
N09: It may be necessary to operate at this reduced power level for as long as 24 to 36 hours in order to reduce the azimuchal oscillation.and the resulting values- of F;C, F, q Fir, and ASI. resulting from a: dropped CEA.. ,
- Notif7 Keactor Engineering- Supervisor
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Page 14 of 18 t ,h, v 0FT-NORMAL OPERATING PROCEDURE No. 0010030, Rev. -6
. i FLCZA 0FF-NORMAL OPERATION AND RZALIGNMENT I I i 9
6.0
References:
6 6.1 Combustion Engineering NSSS lecture series. 6.1 Se=ndard Technis=1_ Specifications, Section 3/4.1.3. 6.3 FSAR, St. Lucie Plant Uni: No. 1, Chapter 15, Accident Analysis, Section 15.2.3. 6.4 C.E. Letter F-SF-917 6/22/76 7.0 Records Recuired: 7.L Normal Log entries. O I f e ' ' " =' --,,a. *-=FT F "
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0FF-NORMAL OPERATING PROCEDURE NO 0110030 REV [ Pag 315 of 18 FLCEA 0FF-NORMAL OPERATION AND REALIGNMENT J APPYNDIX A - CEA REALIGNMENT h 1.0 Limits and Precautions: ,3 1.1 Regulating CZAs should be withdrawn in sequence and overlap between groups shall not exceed 40 percent. 1.2 Do not exceed a sustained SUR of 1.4 DPM (alarm.1.3 DPM) . M L.3 Criticality shall be anticipated. any time CZAs are being withdrawn.
- 1. 4. If deviation between CEAs in any group approaches 3 inches stop group withdrawal and realign CIAs.
1.5 inM vidual CEA positions within the group shall be determined at least once per 12 hours except when the rod position deviation circuit is our of service, then verify CEA positions at least once ever7 four hours (Tech Specs. 3/41-22) 1.6 CEAa shall be limited. in physical insertion as shown by the insertion limit curves
2.0 Instructions
2.1. Al f o.-m*"C of a CEA which, iS below its group, prior to Criticality: 2.1 L Ut4T4 ?ing manual sequential control insert the misaligned ~ group a.=4n4 " of'.4 inches. 2.1. 2. UM T**4ng manual individual control,. withdraw the low CEA to the group position. 2~.I.3.~ Monitor the:-position of all CZAs in the group for proper
. . , . *T + L===a t.
i L 2. hT'* -- .c of 'a CEA whicir is above its gronpr prior tor criticality:
. . _ _ . .. '.n.v .
12.L UM T4 *e manual' individual cuuuul and. insert _ the high CIA te to the. group position. 2.2.2 Monitor the position of all CEas in the group for proper al 4 g -ant. I.3' A14P"C of an. above or below CEA with the reactor critical: Z.J.E Ut111:e. ,,umi individual control to retur:r the misaligned CIA _
- = the group, positiotr ZiJ.2' If~ necessary,. alternate between. =anual individual control of
, ther misa11gned. CEA. and manual sequential control of its acco- , ciated; group to maintai:r the: desired reactor power level.
8
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Pag 316 cf.18 OFF-NORMAL OPERATING PROCEDURE NO. 0110030REV] FLCEA 0FF-NORMAL OPERATION AND REALIGNMENT t~ - APPEND 12 A - CEA REALIGNMENT (cont.)
2.0 Instructions
(cont.) 2.3 (ennt.) 2.3. Monitor the position of all CEAs in the group for proper alignment. 2.3. Utiliza manual group control as required to readjust the group positions for proper automatic sequencing.
/
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Page 17 of 18 0FF-NORMAL OPERATING PROCEDURE NO. 0110030,REV.[6 l FLCEA 0FF-NORMAL OPERATION AND REALIGNMFNT ; a APPENDII B - DROPPED CIA INVESTIGATION l 1.0 Ascertain the cause of the dropped rod by selecting manual individual ;" on the mode selection push. buttons, selecting the individual rod on the individiini CEA selection push buttons, selecting the motion inhibit push button under the group tha rod is in, selecting the group the rod fs in on the group selection push buttons, and while holding down the motion in11 bit push. button under the group selection push buttons, , insert and withdraw the rod, Reactor power shall not be increased above the valua present at the time the dropped rod occurred. If the rod moves smoothly and all indications appear normal, re-align the rod per the dropped rod procedure. 2.0 Guidelines for Investigating Dropped CEDM'S (Taken from CE Letter F-SF-0935) Dropped CEDM's have occurred from: (1) Shorted. SCR's in. the. CPP- Power Switch Module (2) Loss. of 12. Volts Control Power in the CPP Timer Module (3) Loss. of 15 Volt Power Supply (4) Failure of the Interval Timer Symptoms (1) Shorted.SCR's (a) Line fuse (s) blown in Power Supply Circuit (5) Circuit breaker closed. lamp out. Applicable dependent otr which, line fuse (s) blow. (2) Loss. of 12' Tolts (a) Indicator lamp on CPP Timer Module dim or out. (3) Loss of 15 Volt Power Supply (a) No- output or reduced output to CPP Timer Module. Tndication. lamp on CPP Timer Module din or out.. e O W h
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l I Page 18 of 18 .. 1 Il 0FF-NORMAL OPERATING PROCEDURE NO. 0110030, REV. 6' FLCEA 0FF-NORMAL OPERAI!2i AND RRAT.TGNMENT APPENDII 3 - DROPPED CEA LTESTIGATION (cont.) 2.0 (cont.) Trouble Shooting Call Digital Sps =14 =t in. (1) Check lina fuses. If blown, have Digital Spec 4=11at check SCR's for shorts, opens. DO NOT replace fuses or reclose circuit breaker and re-energize before checking for failed SC1's. (2) Check. fuses in 15 volt d-c Power Supply Transformer input. If Slova. detemina causie before replacing. Check outpuc. i 1 l l t O f y
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1.0 Titis
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?RESSURIZEL PRESSURE & Lc.c.a.- CFF-NCRMAL CPERA!!CN
1.0 Aporeval
Reviewed.by Plant Nuclear Safety Ccusittee @e */ _T o 19 '7If App cved I byl h . a_ vtN' - . la=_ _ _ _ . Manager d< ,,._ J 197[ Revisien 5 reviewed by FRG /Vo,) s 1981. App cved by /9M///AesG- - Plan s-ager 1981. -
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To provide i=strue:1cus for operater actica in the event of mifunctics of pressu 1:er pressure and level con::cl systems, or pressure ::ansient caused by inadve:: ant opera: ice of anv'142:7 spray valves. 1.0 Sv=etens: 4.1 Pressuri:er High-Lov Pressure Ala=,. =-1 = I or T 4.1 Pressuri:er- High-Lev Level Ala n, &=-- els I or Y 4.3 Pressurizer I.m.r-Lcw Level Ala=, Channels I or T l 4.1 Pressurizer ? cper:1ccal Heaters L::V Lavel !:1p - Cen:rol Switch. Isolated. A12= 4.5 Pressurizer Backup Heaters Lev Level :1p - Cen::cl Svi:ch Isolated Ala=.
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I t Page 2 of 5 OFF-NORMAL OPERATIM PROCEDURE 0120035, REV. 5. ! PRESSURIZER PRESSURE's LEVEL OFF-NORMAL OPERATION ! i
5.0 Instructions
[ maa - 5.1 Inunediate Automatic Actions 5.1.1 Abnormal Pressurizer Pressure Condition 5.1.1.1 SIAS initiates at 1600 PSIA in the pressurizar 5.1.1.2 1M/LP reactor trip initiates at 1887 PSIA minimum pressure. 5.1.1.3 Low pressure alarm actuates at 2100 PSIA 5.1.1.4 Backup heaters energize at <2200 PSIA and and denergize at >2220 PSIA. 5.1.1.5 Spray valves cycle from full closed at 50 PSI.above. setpoint, to full open 75 PSI above setpoint. 5.1.1.6 Proportional heaters cycle from minimum output at 25 PSI above setpoint, to mnv4= = output at 25 PSI below setpoint. 5.1.1.7 High pressure alarm actuates at 2340 PSIA. 5.1.1.8 High pressure react.or trip initiates and power operated reliefs open at 2400 PSIA. 5.1.1.9 Pressurizer safety valves open at 2500 PSIA. 5.1.2 Abnormal Pressurizer Level Condition 5.1.2.1 All pressurizer heaters denergize at 26.9% indicated level. l 5.1.2.2 Low level alarm actuates and all charging pumps receive backup signal to start at 5.0% below RRS setpoint. 5.1.2.3 Second backup charging pump receives signal to start 4.2% below selected setpoint. 5.1.2.4 First backup charging pump receives signal to start 2.5% below selected setpoint. l _w.-- -- - - - - - = - . - - * - -
.. . _ . . _ . . _ . . . . _ . _ , __- _ _ .a . . 2_.__.. ._; _.
P g2 3 cf 5' { I e OFF-NORMAL OPERATING PROCEDURE 0120035, REV. 5 PRESSURIZER PRESSURE & LEVEL OFF-NORMAL OPERATION i
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i 5.0 Instructions (cont.): I I 5.1 (cont.)5.1.2,5 Second backup charging pump receives signal to stop 1 C at 1.9% below selected setpoint. 5.1.2.6 Mh4-= letdown of 29 gpa. and first backup charging pump receives signal to stop at 1.1% below . elected setpoint. 5.1.2.7 All backup heaters energize and all but one charging pump receives signal to stop at 3.6% above RRS setpoint. 5.1.2.8 614 - = letdown is 12 8 spa at 9.2% above selected ./RS. setpoint. 5.1.2.9 High level alarm actuates at 10% above RRS setpoint. 5.2 Immediate Operator Actions: , 5.2.1 Abnormal Pressurizer Pressure Condition 5.2.1.1 Insure pressurizer spray, proportional and backup heaters are operating properly in automatic, if i hot, shift spray valve controller to manual, energize or denergize heaters whichever is applicable. 5.2.1.2 Insure power operated reliefs closed, if open, isolate by closing V1403, V1405, power operated relief isolation valves. Refer to OP #0120036, pressurizer relief / safety valve-off normal operation. 5.2.1.3 Insure SE-02-03, SE-02-04 auxiliary spray valves closed if open, attempt to close using key switch. If still open, stop all charging pumps, isolate letdown. Refer to OP #0210030, charging and letdown l off normal operation. 5.2.1.4 Insure pressure anomally is not caused by large rate of change of Tave-5.2.2 Abnormal Pressurizer Level Condition 5.2.2.1 Insure selected RRS channel is operating properly, l ; if not, shift to operable channel.
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Page 4 of 5 0FF-NORMAL' OPERATING PROCEDURE. 0120035, RE7. 5 PRESSURT M PRESSURE & LE7EL OFF-NORMAL OPERATION 5.0 Instructions (cont.): mmm 5.2 (cont.) 5.2.1.1 Insure backup charging pumps starr, letdown decreasing, or backup charging pumps off, letdown increasing, whichever is applicable. 5.2.2.3 Insure level anomally is not caused by large rata of change in Tave.- 5.3 Subsequent Operator Actions: 5.3.1 Check that pressurizer safeties are not 1=alting or have actuated by downstream header temperature indication and quench tank. indications. 5.3.1 Insure A07-2515, A0V-2516, letdown isolation valves open. 5.3.3 Insure SE-02-01, SE-02-02, charging isolation valves open. 5.3.4 Insure LC7-2110P, LVC-2110Q, pressuri=er level control valves are operating properly. 5.3.5 Insure PC7-220lP, PCV-2201Q Lecdown pressure control valves are operating pr'perly. o . 5.3.6 Place. second. backup charging pump control switch in auto if thraa charging pumps are necessary. 5.3.7 Insure; letdown valve limiter bypass switch and pressuri=er level bypass control switch are in the normal positions. 5.3.8 Compara letdown flow, charging flow, charging pump header pressure and VCT levels for inrHr ations of leaks or lif ting relief valves in the C7CS system. Refer to OP #0210030, chargi:ur and letdown-off nornal operation. 5.3.9 r Insure char power operated relief valve V-1402 and V-1404 I hand switches are in proper mode for existing plant conditions. l- Noter (1). SW in "Norn Range" _ RCS Pressure > 435 psia RCS Teoli t 27907~ (2)- S'i in "Iow Range" RCS Pressure < 415 psia-RCS:Teoli 5,275 F 5.3.10 If pressurizer lev s1 decrease cannot be immediately explained, refer to CP 10120031, Excessive Reactor Coolant Systen Leakage.
Page-5 of 5 b
.t 0FF-NORMAL OPERATING PROCEDURE 0120035, REY.5 . i PRESSURIZER PRESSURE & LEVEL OFF-NORMAL OPERATION 6.0
References:
6.1 FSAR, Section 7.7, Control Systems 6.2 CE P&ID 19367-210-100 6.3 CE Set Point Guidelines 7.0 Records Required 7.1 Normal log entries 7.2 If pressure transient was caused by inadvertant auxiliary spray valve actuation, document transient per OP # , Component Cyclic and Transient Limits Records. S 1 1 l i i I t t l
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Page 1 of 14
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FLORIDA POWER & LIGHI CCMPANY ST. LUCIE UNIT f1_ _, EMERGENCY OPERATING PRJCEDURE NO. 0030140 RE7ISION 22' Can
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1.0 Title
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This docum:..t i: o.' c: . -ed. We a: , v.wrnUT OPERATION . vonfy .mforrnat. :c. , w...r... a ecc.r eff-d dacur.1 -- g . .- Reviewed by Plan clear Safety Conamittee h[ 19d Approved by Asgm> Plant Manager-/h'/N Tf
- .. .. u _ . _
19g _ Revision 22 reviewed by IL < ' 1981. Aceroved by '/8 M'S// Afi- . Plant Manager
- W i i 7d * ' - ~ 1981.
p 3.0 ' Purpose ArIDiscussioti:'~~~' ~
-Y'.
p- . . 3.1 This procedura provides the action to be taken in the event of s
- _. a.completa loss of off site electrical power concurrent with a
~ - - " ~ ~ - - ' - - - ' * -
turbine trip. 3.2 Discussion 3.2.1 A loss of power to the 4160 7 buses, results in a loss of
~
power to all 480 7 load centers and motor control centers. and to all instrunentation not fed directly or indirectly from the station battery. A reactor trip will occur from a low reactor coolant flow race signal due to the loss of power to the 6900 7 buses supplying the reactor coolant pumps and will be accompanied by a turbine trip and generator lockout. 3 . 2' . 2 Steast dump to atmosphere : mast be used to remove reactor decay-heat. IniMally, steam generator safety valves may actuate to augment the steam flow and to help control steast generator pressure 1::mmediately after the trip. 3.2.3 On site power will be supplied by- Emergency Generators. 3.3 A rapid reduction in steam generator water levels will occur due to the reduction of the steam. generator void fraction on the secondary side and also because steam flow will continue after normal feedvater flow stops. Auxiliary feedvater flow lv11.L auccmatica.u.y ini:1sta .! ninutes af ter the first staan generar.ar Aevea. reacnes >+. (./4 .o gicj . 3.4 Core decay heat removal is- accomplished by natural circulation in the: reactor coolant loops. I 3.5 Core damage is not expected as a result of a loss of power condition as the steam generators are maintained as a heat sink and no loss of water occurs from the pressurizar.
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Page 2 of 14
-- EMERCENCT OPERATING PROCIDURE NO. 0030140, REY 22 BLACKOUT OPEIULTION I a
's I
i 3.0 Puroese or Discussion: (cent) a 3.6 If operating under blackout conditions and an engineered safety features actuation signal occurs, any non emergency loads that are rmning will be automatically t' ripped and the. required emargency loads will be. automatically started. 4.0 .. Synotems: - - - - -
~-
4.1 Alarms associated with the ' loss of operating plant components. 4.2 Loss of normal control room lighting and DC lighting energized. 4.3 Reactor and turbine trip. 4.4 Esmergency diesel generators start. 4.5 Reactor coolant pump trip and steam generator feed pump trip.
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Page 3 of 14 DERGENCY CPERATING PROCEDURE NO. 0030140, RE7 22 at ArvrTT OPERATION I
5.0 Instructions
5.1 Immediate auto action 5.1.1 Reactor and turbine trip, generator lockout ,I 5.1.2 Generator breakers open. 5.1.3 7" - 4ng feeder breakers open to 4160 V and 6900 V buses. 5.1.A Tie br==1rars between Nor:nal 4160 buses (IA2 and 132) and the emergency 4160 V buses (113 and 133) open. 5.1.5 Ties between essential and non-essential sections of emergency 480 V MCC's open. 5.1.6 Breakers open for the following non-safety related loads which are nor:nally fed from emergency buses. NOTE:. These leads can be =""=117 reconnected to the ' emergency buses as needed. 5.1.6.L Pressurirer heater transforners lA and 13. 5.1.6.2. Fire pump 1A and 13. 5.1.6.3 CEA Drive M.G. lA & 13. 5.1. 6.4 - Fuel #="A14 ng 480 7 MCC 1AS , 138 / 5.1.6.5 Reactor cavity sump pump 1A
- 5.1.6.6, Reactor building elevator 5.1.6.7 Electrical equipment room hoist 5.1.6.8 120/208 power panel 121 transfor=er 5.1.6.9 Lighting panel transforners 110, 112, 114, 117, 125, 126 5.1.6.10 Inceming feeder from 1A1 & 132 41607 buses 5.1.6.1L RCP oil lif t pumps (8 pumps only - A pumps ""-4"g) 5.1.6.12 Airborne radioactivity removal fans E7E-l&2 5.1.6 13 Pressurizer relief isol valves 1403 & 1405 /R22 5.1.6.14 C7C3 heat tracing transforner lA & 13 l 5.1.6.15 480V Lighting panel 2A, 23 & 2C 5.1.6.16 Waste management heat tracing transforners 2A &.23 5.1.6.17 Air conditioner HVA-4, ACC-4.
5.1.6.18 Power panel 120 5.1.6.19 Lighting panels 113, 116, 109, 115, 130 5.1.6.20 Refueling equipment 5.1.6.21 Refueling water to charging pu=ps 7-2504 5.1.6.22. Boric Acid batching tank heaters 5.1.6.23 Fire siren ( t l l 1 - - , I l
Page 4 of 14 NRf:ENCY Ori.'.Al*ING PROCEDURE NO. 0030140, RE7 22 BTarrnUT OPERATION
5.0 Instructions
(cont) 5.1 (cont) 5.1.7 All loads on amargency buses are tripped except the following: I-5.1.7.1 Boric Acid makeup pumps 5.1.7.2 Charging pumps 5.1.7.3 Emergency lighting 5.1.7.4 Class I power panels 5.1.7.5 RCP oil lift pumps (A pumps only - B pumps off) 5.1.7.6 Diesel fuel transfer pump. 5.1.8 Diesel-generators A & B start and energiza 4160 7 emergency buses 1A3,133, and 1AB and loads listed in .' step 5.1.7. 5.1. 9 - Subsequent leads are started at 3 second intervals. See Table 1, Emergency Diesel Generator Loading Sequence.
.5.L.10 wn=-7 PiidiiaYef ' Histo star'n seFqshnE& fdftfiftes when the
~ -
fD'it stemiFTehurator'reveMeereases" t'o Ju. NOTE.F Puiip stafFadd-~ frow initiatibii is delayed for 3 minutes. Pumps may be started by the operator .
-AT ANT TIME. .
5.2 7 nadiate operator Actions 5.2.1 Trip turbine and reactor manually. 5.2.2 Check.all full length CEA's are fully inserred and reactor trip breakers are open. 5 . 2. 3' Check. turbina valves are closed. 5 . 2. 4- Check. generator fieli and 240 K7 breakers are open.
- 5. 2. 5 Place reheater control system in manual, close IC7's.
5.2.6 Check that diesel generators havs started and are feeding only emergency buses. 5.2.T Open. start-up transformer breakers, f 5.2'.8. reduce T' avg. tot reference see poine by--umuur operation of than steam; dumpr valvest to- at=os_ph_ere. _ _ . i 5.2.9 Isolate steam generator blowdown. l - i
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Page 5 of 14 i EMERGENCY OPERATING PROCEDURE NO. 0030140, REV. 22 3LACKOUT OPERATION
5.0 Instruction
(Cont'd) 5.2 Immediate Operation Action (Cont'd) l-
' ~-
5.2.lG- Starr stesa driven aux.~fesd pump and establish flow to S.G.'s. If aux. feed pumps have started due to the auto ~)
-----stirt feature,- tKa-~notor- driven pumps may be secured 30 --~~~ '
seconds after eney start, if desired ~. a.4.n u any or cne automauc acucas uscen in 2.4.4 caru ., a.4.s co not occur automaucany, caen :sanuauy initiate that action. 5.3 Subsequent Action .
5.3.1 Ensure
adequate riatural circulation flow by ensuring that hot and cold leg temperatures, pressurizer pressura and. level stabill:e within minutes. The cara AT should be less than % 44 F (AT for full power). 5.3.1.1 If the above conditions are not established: 5.3.1.1.1 Check RCS te:iperature and pressure to ensure that the RCS is subcooled. 1 J 5.3.L.l.1 Ensure amH14ary feed flow to the steant generators has been initiated
, and the. steam dumps to atmosphere i ,
are in operation. 5.3.I .2. Return at least one RCP in each loop to operation as soon as offsite power is available 5 .3.2. Start _ equipment in; Table L if required. j .. . .
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t pig 3 6 cf 14 DERGENCY OPERATING PROCIDURE NO. 0030140, REVISION .27 BLACKDUT OPERATION
5.0 Instruction
(Cent'd) 5.3 (cont'd) 5.3.3 If one diesel fails to start, attempt a manual start. 5.3.3.1 If manual start attempt is unsuccessful, an operator should be sent to the diesel local control station to inspect status of local alarm panel. 5.3.3.2 If no alarms are present on the local alarm panel, an inspection of the overspeed trip lever should be made to insure it has not tripped. 5.3.3.3 If the overspeed trip levers are latched, the normal isolate switches on the local control panel should be placed in the isolate / position and a local start attempt should be made. 5.3.3.4 Refer to Operating Procedure 2200020, 2200050 Emergency Diesel Standby Line up and Periodic Test. 5.3.4 Locally open condenser vacuum b.reakers MV10-1A and MV10-13. Locally close MSR main steam block valves MV08-4, MV08-6, MV08-8, and MV08-10. . 5.3.5 Check.MSR. warm-up valves MV08-5, MV08-7, MV-9, and MV08-11 to be closed or close manually. 5.3.6 Send. an operator to align and start emergency cooling water- to the instrument air compressor, then reset local handswitch and manually start. the instrument air compressor.. CAUTION:. Do not overload the diesel generators when starting additional equipment. (3500 ICJ max continuous rating). , 5.3.7 When diesel generator power is available energize - equipment as may be required for plant safety and to achieve. an orderly shutdown vii:hin the diesel gener-ator load limitations by: 5.3'.7.1. Verify one set of cavity and supporr cooling fans, operating. If not, start one set. 5.3. 7. 2' Locking out automatic starting equipment that is. not in service.
- 5. 3. 7. 3 Manually opening all breakers on any non-vital
' bus or motor control center that is to be re-energized.
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Page 7 of 14 EMERGENCY OPERATING PROCEDURE NO. 0030140, REVISION 22 31ACKOUT OPERATION
5.0 Instructions
(Cont) 5.3 (Cont) 5.3.7 (Cont) 5.3.7.4 3asetting lockout relays for.each required bus to allow closing of feeder breakers. 5.3.8 Energize 4160 V buses IA2,132, 480 7 load centers 1A1, 131 and 480 MCC's 1A1, 131, IA4, 134, and 1C as follows: ACTION LOCATION 5.3.8.1 Strip non-vital 4.16 KV busses 1A2 132 (All should be opened automatically) 5.3.8.2 Insert sync plug, close 4.16 K7 1A2-20109 132-20309 non-vital breaker and hold control J
.._., __ __ svitch closed.while closing.4.16 KV vital breaker.
1A3-20209 133-20411 . 5.3.3.3 Strip ncn-vital load center 1A1 131
- 5.3.6.4 Close 4.16KV feed breaker to- - -- -
non-vital load centers IA2-20110 132-20310
~
5.38.5 Strip 480V MCC 1A1 131 1A4 134 1C 5.3.5.6 Close 480V load center feed breaker to MCC 1A1 & 131 1Al-40115 131-40411 5.3.8.7 Close 480V load center feed breaker to MCC 1A4 & 134 1Al-40113 131-40413
~
5.3.5.8 Close 480V load center feed breaker to MCC 1C 1Al-40119 131-40410 5.3.9 At MCC 1C, close breakers for turning gear, bearing i oil pump, air side seal oil pump and hydrogen seal oil pump. l l 5.3.IO Place turbine plant cooling water pump in operation. {- 5.3.11 Alig:r turbine cooling water system to the instrument j a1= compressor back to normal alignment. { 5.J.11.1 Open all Cit's on ??-104 except Ckt's 21 & 23. I~ ~ ~~ ~ ~ ~ ~ ~ 5.3.11.2 Close 3reaker 40851 on MCC'. lAl 5.3.11.3 Open all Ck:'s on ??-146 except Ckt 1. i . n . -
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e >~ Page 4 of 14 r EMERGENCT OPER$CNG PROCEDURE NO 0030140,- RE7ISION 22 RT.Af'KOUT OPERATION -
5.0 Instructions
(Cont) 5.3'.11.3.1 Open all Cke's on PP -150 except Ckt's 7,9 and 11. num - NOTE:- PP-146 is located on the wall '.' of the new cold lab just vest >
~
of MCC 1P.L. PP-150 is located in the new cold lab closet. 5.3.11.4 Close Breaker 41634 on MCO 131.
~
5.3.12 Place turbine drain valve switch in the open position -
/
5.3.13 Scare bearing oil pump before turbing bearing oil pressure reaches 11 psig. decreasing. Pump starts , automatically r.t 12 psig decreasing turbine bearing ' oil pressure. NOTE:. If bearing oil pump fails ,to _ start, the: emergency DC cil pump will start at 10 - psig. decreasing bearing oil pressure. Operator should start pump before 10 psig is reached. Stop the DC - oil pump if it is running in addition to the bearing ' oil pump. 5.3.14 Remove the following components from service: , 5.3.14.1 Steam jet air ejectors 5.3.14.2 Prd n%g ejector 5.3.14.3 An*14=ry priming ej ector' 5.3.14.4 Attr414 =7 steam to R.A.3. 5.3.14.5 Gland seal system 5.3.15-Star CEDM cooling fans A & 3. 5.3.16. Start reactor support cooling fans A & B. CAUTION: Consider equipment starting requirements. Alternate operation of equipment say be , required to avoid overloading the. diesel generators. (35001G Max. continuous rating). 5.3.17 Manually close breakars- for pressurizer heater buses , on 4150 V buses IA3 and 133. b
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Page 9 of 14 . DERGEICT OPERATING PROCEDURE NO. 0030140, REV 22 BI.ACKOUT OPERATION
5.0 Instructions
(cont) 5.3 (cont) im 5.3.13 Check. that the bearing oil lif t pump starts automatically when turbine speed decreases to approximately 600 rpm. ,' . 5.3.19 Starr turbine lube oil vapor extractor and generator oil vapor extractor. 5.3.20 Check that the turning gear engages and starts auto-matically when turbine speed decreases to zero rpm, or manually engage it. 5.3.21 Reduce the flow of cooling water to maintain the temperature of the oil leaving the turbine lube oil , and the air side and hydrogen side oil coolers be-tween 95 - 100 f. 5.3.22; Isolate cooling water supply to the generator hydrogen coolers. 5.3.23' If additional condensate storage tank water is required and sufficient power is available from the diesel generators, place che, water treatment plant in service. 5.3.21 Place the spent fuel pit cooling pump in operation as necessary. NOTE: 'Jith spent fuel elements from 3-1/3 cores present,. the spent fuel pic can safel7 withstand 5 hours without cooling before reaching the' boiling point. 5.3.25 Periodically check fuel oil levels in the diesel generator day tanks to confirn proper operatics of the fuel oil tranafer systen and to ensure uninter-rupted diesel generator operation. 5.3.26' Sample and analyze the reactor coolant to determine 11 fuel element clad failure has occurred.
.; 5.3.17 Determine expected duration of power outage. If unable ' to der so or if outage is to be prolonged, borate RCS c:r cold shutdown concentration.
5.3.28 If the outage will exceed 4.houro and the R7f is available, proceed to cold shutdown conditions utilizing thernal circu.lation, atmospheric steam dump and f eedwater ' addition. Place shutdown cooling in service when appropriate tenperatures and pressures are reached. Proceed to step 5.3.32. l
. . . - ~ _ - - _ - - _ _ _ . _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ - _ _ _ - _ _ -
Page 10 of 14 DERGENCY OPERATING PROCEDURE NO. 0030140, REV 22 BIACKOUI OPERATION
5.0 Instructions
(cont) 5.3 (cont) 5.3.28 (cont) NOTEt Do not begin plant cooldown until cold shutdown boron concentration is verified. 5.3.29 If the outage will exceed 4 hours and the RWT is not available, the Safety Injection tanks should be used for makeup to the RCS, if other sources are not avai?shle.. F.3.30 Maka the following preparations: 5.3.10.1 Close either or both non-essential c1e ' breakers for MCC 1A5 and MCC 135 , 1A5 - 41230
~
135 --42027
, . This will provide power to the containment instrument air ccupressors.
5.3.15.1 If rmuing of centainment instrument air
~
. compressors is not desirable, insure that .
a turbine building instrument air compressor _is rtmning and containment instrument air . pressure is normal.
,. , 5.3.30.3 Open the 480 7 AC breakers for M07-2501
- s. 4 s
and. M07-2504.
~
MOV-2501. - 42021 N07-2504. - 42017 5.3.30.4 Open and icek the following valves:
. 7-07009 SIT test line return to RWT penetration #41 l ' 7-3463 SIT test line return to RWT ~
i . penetration #41 l 7-03920 SIT test line tie to VCT inlet 5.3.30.5 Borate the RCS to cold shutdown boren
. Concentration.
CADTION:. Insure that one 3AMI tank r= mins in service to usa as a source of borated water while in node 5. W M
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Page 11 of 14 Of*JLGENCT OPERATING PROCEDURE NO. 0030140, REV 22 . BLACK 0Ur OPERATION
5.0 Instructions
(cont) 5.3 (cont) 5.3.31 Proceed to cold shutdown conditions uc41tring thermal I, circulation, atmospheric steam dump and feedwater addition. 5.3.31.1 When makeup to VCT is necessary, select a S.I.T. to use as makeup source. Open the appropriate tanks, fill and drain valve. IAl - A0V-3621 1A2 - A0V-3611 131 - A07-3631 132 - A0V-3641 5.3.31.1 C1csa the appropriate fill and drain valve when VCT is restored to normal level. - CAUTION: Use one SIT tank at a time. Insure RCS is 1750 psia before the second SIT tank is used. 5.3.31.3 Place shutdown cooling in service when
. appropriate temperatures and pressures are reached.
5.3.32 If pressuriser cooldown cannot be accomplished in a timely wrmar from the addition of cooler liquid (Aux. Spray) from the charging pump via the pressurizer spray line,, proceed with the alternate positive means of depressurization as follows: 5.3.32.1. Place the switches for the power operated relief valves. V1401 and V1404 in the override position. 5.3.31.2. Initiate a high pressurizar pressure trip , signal on two RPS charmel trip units. 5.3.32.3 Place the switch for either power operated l relief valve; (v1401 or V1404) in the nornal j range position and vent the pressuriser to the quench tank. Return the switch to override to close valve. 5.3.3b.4 Control the rate of cooldown and depressurization by selective operation of the power operated relief valves in this. mode until cooldown via l the A=414m7 Spray valves can be initiated.
, Page 12 of 14 T ERGENCY OPERATING PROCEDURE NO. 0030140, REV 22
5.0 Instructions
(cont) 5.3 (cont) 5.3.33.When nomal AC power is available: 5.3.33.1 Restore bus sections to their normal supplies. 5.3.33.2 Place the diesel generator system in standby' lineup as per OP 2200020. 5.3.33.3 Restore all plant systems to normal. s 5 0 m f W & q
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Page 13 of 14 EMERGENGT OPERATING PROCEDURE NO. 0030140, REY 22 BLACKOUT OPERATION 6.0
References:
6.1 FSAR, Section 15 8
! J 6.2 FSAR, Section 8 l, 6.3 Operating Procedure #0030130, Shutdown Resulting From Reactor / Turbine Trip 6.4 Operating Procedure #0210020, Charging and Letdown 6.5. Operating Procedure #0330020, Turbine Cooling Water Operation 6.6 Operating Procedure #0250031, Baron Concentration Control, Off-Normal 6.7 Operating Procedura #1010040, Loss of Instrument Air
- 6.8 Operating Procedure #1540020, Water Plant Startup and Shutdown .
6.9 Operating Procedure #2200020, Emergency Diesels - Standby Lineup 6.10 Operating Procedure #0700022, Aux. Feedwater System Operation 7.0 Records / Notification: 7.I Normal Log Entries. ,
- 7. 2 Notify Duty Call Supervisor.
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g4 ,p g4 l EHERGENCY DIESEI. CENERATOR LOADING SEQUENCE Loss of Coolant Accident 5.oss of and Loss of Off-Site Pouer Off-Site Power Nomip4} Running Timing
- Running
, Service h J.oad - Ea Load - Ku StartinR Running Load - Ku
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1 IIPSI pump } ' 400, IIP 330 'From 0.2 Sdc - Cont - l36 i Boric acle) pakeup ppsp 1 25 llP 22 From o Sec - 4 hrs ist 22 i t Charging pump 1 10Q llP 80 From 0 Sec - 4 hrs Block 80
- !!ator operatei) ya}ypq 500 60 l(p 40 from 0 Sec - 1 min -
Emergency liglit tag Lot 50 KW 50 from 0 Sec - Cont 50 Class I power panels 4 45KVA 40 40 From 0 Sec - Cont f
. Fuel Transfer )wmp } 5 Itr 5 from 0 Sec - Cong 5 c, l I:PS1 pump 1 400 ItP 330 from 3 Sec - 90 min -2nd 330 Co'ntainanet fan coolerts ? 15Q llP 245 From 3 Sec - Cont plock 167 i .
Component coolant pump 1 450 IIP 376 From 6 Sec - Cont 376 , 'l Shield hld yent fan 1 60 IIP $4 From 6 Sec - Cont 3rd - 1U
- Shield Bld Vent Sys Elec lltr 1 30Kl; 30 From 6 Sec - Cont Block -
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- 1 From 6 Sec - Cont I l r Intake; cooling pump 1 , 600 llP 492 Froin 9 Sec - Cont 4th Block 492
'y Contaipment spray pump 1 500 llP 400 From 12 Sec - Cont 5th Block - Auxili(ryfeedwaterppmp 1 350 llP 305 From 15 Sec - 4 hrs 6th Block 305 Bor{c d:Id Iwatt9g 1 1.op 5},75 KW 51.75 From 18 Sec - 4 hrs 51.75 Aux {liary bid supply [an 1 60 llP 54 From 18 Sec - Cont 54 , , ECM Area exhaust system 1 50 IIP 44 from 18 Sec - Cont 7th 44 I Coiltrol Room AC Outdoor linit 1 50 llP 44 From 18 Sec - Cont Block 44 Cont.,rol room AC Tudoor Unit } 7.5 llp 8 from 18 Sec - Cont 8 I control room booster fan 1 3 IIP 3 From 18 Sec - Cont 3
. Reactor Support CLG Fan 1 40 llP 37 From 18 Sec - Cont 37
Reactor Cavity ClG Fan 1 20 llP 19 From 18 Sec - Cont 19 -
l - Battery Charger 1 68 KVA 68 From 30 Sec - Cont 8th 68 : Plant Security Invertpr 20 From 30 Sec - Cont Block 20
. 1 20 KVA UPS Inverter 1 15 KVA '
15 From 30 Sec - Cont 15 250 li 198 lb.FlE*:Enmp 1 Totals: p'll6'i.75 ku___
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t, w mw s, we; 30. ,1A1 (FCa I lilFORI.:1AT10N OllLY C;py i 7 This document is not centro!!ed. Before use, t verify information with a controlled documen . OFF-NORMAL /EERGENCY OPERATING PROCEDURES LNDEX NUMBER REV. # PROCEDURE TITLE 0030130 19 SHUTDOWN RESULTING FROM REACTOR TRIP OR
,. TURBINE TRIP 0030131 - 1M PLANT ANNUNCIATOR
SUMMARY
0030140 21 BLACKOUT OPERATION 0030141 7 CONTROL ROOM INACCESSIBILITY 0030142 5 RCS COOLDOWN DURING BLACKOUT 0110030 5
- FLCEA 0FF-NORMAL OPERATION AND RE- ALIGNMENT 0120031 6~ EXCESSIVE REACTOR COOLANT SYSTEM LEAKAGE 0120032 2 EXCESSIVE REACTOR COOLANT SYSTEM ACTIVITY 0120034 10' REACTOR COOLANT PUMP - 0FF-NORMAL OPERATION 0120035 4 PRESSURIZER PRESSURE & LEVEL -OFF-NORMAL
' OPERATION 0120036 3 FRESSURIZER RELIEF / SAFETY VALVE-OFF-NORMAL OPERATION 0120040 7" LOSS OF REACTOR COOLANT FLOW 0120041 e- STEAM GENERATOR TUBE LEAK FAILURE 0120042 17 ' LOSS OF REACTOR COOLANT 0210030 5 CHARGING AND LETDOWN - 0FF-NORMAL OPERATION 0250030 ,
2 EMERGENCY BORATION 0250031 2 BORON CONCENTRATION CONZROL OFF-NORMAL 0310030 11 COMPONENT COOLING WATER - 0FF-NORMAL OPERATION 0310031 [ C. C. W. - EXCESSIVE ACTIVITY 0330030 2 TUR3INE COOLING WATER SYSTEM - 0FF-NORMAL OPERATION Page 1 of 4
3_ - _ _m, _[Oct. 30, 1981 C;py # 1 0FF-NORMAL / EMERGENCY OPERATING PROCEDURES INDEX NUMBER REV. # PROCEDURE TITLE 0350030 1 FUEL POOL COOLING SYSTDi - 0FF-NORMAL OPERATION
' '0360040 2 OPERATIONAL REQUIREMENTS FOR INTERIM ULTIMATE HEAT SINK 0410030 3 HPSI-- 0FF-NORMAL OPERATION 0440030 3 SDC/LPSI - 0FF-NORMAL OPERATION 0510030 5: UNCONTROLLED RELEASE OF RADIOACTIVE LIQUIDS 0530030 3' WASTE GAS SYSTEM - 0FF-NORMAL OPERATIONS 0530031 1 UNCONTROLLED RELEASE OF RADIOACTIVE CAS 0610030 5-' CONDENSER TUBE LEAK 0610031 2. LOSS OF CONDENSER VACUUM 0620030 3 CIRCULATING WATER SYSTEM - HIGH AT AND HIGH DISCHARGE TEMPERATURE f
4 0630040 3 CHLORINE LEAK 0640030 L- - ICW SYSTEM - 0FF NORMAL OPERATION 0700040 8- 2 LOSS OF FEEDWATER OR STEAM GENERATOR LEVEL 4d,
~
0810040 MAIN STEAM LINE 3REAK 0910030 2* START-UP TRANSFORMER OFF-NORMAL OPERATION 0910031 2 MAIN TRANSFORMER OFF-NORMAL OPERATION 0910032 0 AUXILIARY TRANSFORMER OFF-NORMAL OPERATION 0950030 BORIC ACID HEAT TRACING SYSTEM OFF-NORMAL OPERATION 0960030 T D.C. GROUND ISOLATION 1010030 3 LOSS OF INSTRUMENT AIR 1110030 1 0FF-NORMAL OPERATION OF THE LETDOWN MONITOR j Page 2 of 4
. ne t. 30, 1931 C ;py f, OFF-NORMAL /DERGENCY OPERATING PROCEDURES INDEX NUMBER REV. # PROCEDURE TITLE 1110031 1 0FF-NORMAL OPERATION OF THE CONDENSER
, AIR EJECTOR MONITOR 111C032 0' 0FF-NORMAL OPERATION OF THE LIQUID WASTE MONITOR 1110033 0 0FF-NORMAL. OPERATION OF THE GASEOUS WASTE.MONITCR - 1110034 1 0FF-NORMAL OPERATION OF THE PLANT VENT PROCESS MONITOR 1110035 1 0FF-NORMAL OPERATION OF THE CONTAINMENT PROCESS MONITOR 1110036 1 0FF-NORMAL OPERATION OF THE COMPONENT COOLING WATER PROCESS MONITORS A AND B 1110037 0 0FF-NORMAL OPERATION OF THE STEAM GENERATOR BLOWDOWN PROCESS MONITORS A AND B 1110038 0 0FF-NORMAL OPERATION OF THE FUEL BUILDING EFFLUENT MONITOR 1120030 0 AREA RADIATION MONITORING SYSTEM (ARMS) 0FF-NORMAL CONDITION OPERATION 1210030 1 WIDE RANGE NUCLEAR INSTRU iD.TATION CHANNEL MALFUNCTION 1220030 3 LINEAR POWER RANGE CHANNEL MAI. FUNCTION 1300030 1 LOSS OF CONTAINMENT INTEGRITY - 0FF-NORMAL OPERATION 1300031 3 AIRLOCKS - 0FF-NORMAL OPERATION 1560030 0 PRIMARY WATER SYSTEM - 0FF-NORMAL OPERATICN 1600030 1 ACCIDENTS INVOLVING NEW OR SPENT FUEL 1900030 -1 AUXILIARY AND CONTROL BUILDING VEhIILATION OFF-NORMAL OPERATION Page 3 of 4
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Oct._3G 4 4R L_ Copy # OFF-NORMAL / EMERGENCY OPERATING PROCEDURES INDEX, NUMBER REV. # PROCEDURE TITLE 2000030 1 LOSS OF ONE FAN IN EITHER REACIOR CAVITY COOLING SYSTEM HVS2A OR 23 REACTOR SUPPORT COOLING SYSTEM HVE3A OR 3B 210003d 0 OIL, SPILL _ EMERGENCIES _. _._ ___ . _ . Page 4 of 4
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