Text

Loss of Reactor Coolant/Reactor Coolant Pressure (Small Break LOCA) Causing Automatic HPI, Emergency Procedure 1202-6B.Certificate of Svc Encl
	ML20037B537
Person / Time
Site:	Crane
Issue date:	06/30/1980
From:	; METROPOLITAN EDISON CO.
To:	;
Shared Package
ML19347B808	List: ML19347B807; ML20037B537;
References
	1202-6B, NUDOCS 8010160014
	Download: ML20037B537 (76)
	v • d • e

{{#Wiki_filter:--- - ------ "~ FOR USE IN UNIT I ONLY r 1202-6B Revision 7 03/19/81 THREE MILE ISLAND NUCLEAR STATION CONI?.0"m COFY FOR UNIT NO.1 EMERGENCY PROCEDURE 1202-6B LOSS OF REACTOR COOLANT / REACTOR COOLANT PRESSURE USE IN UNIT 1 ONLY (SMALL BREAK LOCA) CAUSING AUTOMATIC HIGH PRESSURE INJECTION Table of Effective Pages Pace Revision Pace Revision Pace Revision Pace Revision '} [h 1.0 7 26.0 7 1 2.0 7 27.0 7 bgtn CONyR "1aCO3Y; 3.0 7 28.0 7 4.0 7 29.0 7 t 5.0 30.0 7 6.0 / 31.0 7 81 DEc 17 A10:11 7.0 7 8.0 7 . f,c,g ;g w ( 9.0 7 r

7. samr' 10.0 7

"hRANCH 11.0 7 12.0 7 13.0 7 14.0 7 15.0 7 16.0 7 17.0 7 18.0 7 19.0 7 20.0 7 21.0 7 22.0 7 23.0 7 24.0 7 25.0 7 Unit 1 Staff Reconinends Approval Approval A/ Date Cognizant Oept. Head Unit 1 PORC Recorrnends Approval Qhf W f ' Chairman of PORC Date J 7/ / ) pproval pSl6IBI Manager IIA 8 Date "l $l /1 v OA Modifications / Operations Mgr W Oate FO R USE L N UNIT I OMtY 4" .gsw w ' by

~ r FOR USE IN UNIT 1 ONLY 1202-6B Revision 7 THREE MILE ISLAND NUCLEAR STATION UNIT 1 EMERGENCY PROCEDURE 1202-6B LOSS OF REACTOR COOLANT / REACTOR COOLANT PRESSURE (SMALL BREAK LOCA) CAUSING AUTOMATIC HIGH PRESSURE INJECTION ! NOTE:(1) If RC pressure remains above ESAS setpoint proceed per ! 1202-6 A. (2) If OTSG tube rupture is confirmed proceed per 1202-5. (3) If loss of coolant is large enough to initiate HPI, CF and LPI flow automatically and RC pressure drops below 200 psig, proceed per 1202-6C. (4) The block diagram in Attachment 5 may be used as an aid in determining the applicable procedure and section. The block diagram does not supersede any procedure steps. 3.B.1 Symptoms 1. Decrease in reactor coolant pressure. RC Pressure Hi/Lo Alarm. 2. Reactor Trip Alarm. '~ 3. Turbine Trip Alarm. l l 4. ES Actuation A and ES Actuation B not bypassed alarm. 5. ES Actuation indicated by status lights on PCR panel. 6. ap indication on RC-RV-2 (PORV) or code safety valve dis-charge line or alarm on the acoustic monitor on RC-RV2 (PORV). 6.B.2 Immediate Action l c A. Automatic Action i 1. Reactor trip on low RCS pressure or pressure to tem-l perature. 2. Reactor trip containment isolation occurs. 3. ESAS actuation at 1600 psig. B. Manual Action I FOR USE IN UNIT I ONLY s

FOR USE IN UNIT I ONLY 1202-6B Revision 7 i I NOTE: The parameters indicated with an asterisk (*) will be reverified as the first step in Follow-Up Action. 1. Press the reactor trip push button and verify that all rods havc inserted (except Group 8). 7 2. If RCS pressure decreases to HPI setpoint: l l a.) Verify HPI automatically initiates. HPI pu=ps l start, !!U-V14A and B open and MU-Y16A, B, C and D open. l .l. b.) Trip all operating Reactor Coolant Pumps l 1 mediately following verification of HPI. ! CAUTION: Do not start any major motors such as the condensate i l i pu=p or the condensate booster pump during E.S. i block loading. i 3. Verify the Turbine is tripped and verify that the Turbine L ~ stop valves are closed. .a - 4. Close MU-Y12. 5. Close RC-Y2 (may be reopened if necessary to control a pressure increase). l

6.

Verify that EF-P-1, EF-P-2A and EF-P-2B start and dis-charge pressure increases to >1010 psig, EF-Y35A and B open and flow is indicated to increase stem generator level to 50 percent. NOTE: Control of OTSG feedrate is critical to obtaining i RCS Pressure Control (neglecting effects of LOCA I pressure transient) Monitor RCS pressure and cold leg temperatures and manually control OTSG feed i rate to prevent an overcooling event. F O R U S E I, UNIT I ONLY ~ I

FOR USE IN UNIT I ONLY 1202-6B Revision 7 7. Evaluate for a hon-LOCA overcooling event by observing the following: ! NOTE: During a loss of coolant accident, RCS conditions will 1 approach saturation. Temperature will remain fairly constant and pressure will decrease to saturation pressure. During a Non-LOCA overcooling event, pressure : 1 and temperature will both decrease rapidly. Some subcooling will be maintained unless pressurizer level is lost. a. RCS pressure, temperature, and saturation margin. b. OTSG pressure: Decrease for steam line break. c. OTSG level: Higher than required for an overfeeding event, low level for steam line break. d. Main and startup and/or Emergency feedwater flow: High flow for overfeeding event, isolated for steam e line break. If non-LOCA overcooling is indicated proceed per Attach-ment-2. 8. Take or verify manual control of EF-V-30A and B and slowly raise OTSG level to 95 percent on operate range. NOTE: Monitor RCS pressure and cold leg temperatures during 1 OTSG level changes to insure feed rate does not 1 cause significant RCS pressure transient. I I l FOR USE M UNIT I ONLY

~ FOR USE IN UNIT I ONLY 1202-6B Revision 7 9. Verify.that the reactor trip building isolation and high pressure injection systems have actuated. 10. Evaluate for OTSG tube rupture by observing the following: a. Main steam line high radiation monitors. b. Condensor air ejector high radiation monitor (RMA-5) c. Verify no increase in RC drain tank and reactor building temperature, pressure and radiation level. If a tube rupture is confirmed, proceed per EP1202-5.

11. Monitor reactor cc A nt drain tank level, pressure, and temperature for any unexpected increase. Check PORY and code safety valve discharge flow alarms in the control room, and check acoustic monitoring for PORV.

12. If ESAS has been bypassed due to heatup on cooldown, initiate HPI manually. 6.B.3 Follow-Up Action The objectives of the Small Break LOCA Emergency Procedure are to trip the reactor, determine whether a LOCA or a NON-LOCA over-cooling event has occurred, conserve RCS inventory, keep.the core covered and cooled by maintaining 50*F subcooled condition, es-tablish natural circulation and remove core heat through the steam generators, achieve a cold shutdown condition and to minimize radioactive release to the environment. 1. Reverify the parameters in Manual Action that are marked with an asterisk (*). Use redundant indication if avail-able. 2. Declare a Site Emergency (carry out EPIP 1004.3). 3. Verify the following reactor building isolation valves EGR USE y UNIT I ONLY w -r n-w---

FOR USE IN UNIT I ONLY 1202-6B Revision 7 NOTE: These valves automatically close on reactor trip. RB Sump WDL-V534 WDL-V535 RC Drain Tank WDG-V3 WDL-V303 WDG-V4 WDL-V304 RCS Sample CA-V1 CA-V3 CA-V2 CA-V13 RB Purge AH-VlA AH-ViC AH-VlB AH-VID Core Flood Tank CF-V2A CF-V2B CF-Vl9A CF-Vl9B CF-V20A CF-V20B Demin Water CA-V189 OTSG Sample CA-V4A CA-V5A CA-V4B CA-V5B Letdown Cooler MU-V3 4. Verify that both trains of HPI components are operating per table 1. If both HPI trains have not actuated, attempt to start second HPI train. FOR USE),N UNIT I ONLY

I. ~ FOR USE IN UNIT I ONLY 1202-6B Revision 7 ! CAtJTION: Do not attempt to operate ES valves to the Non ES position and do not trip any ES components until the ES signal is bypassed. The breaker anti _ pump feature will prevent reolosure of tripped breakers until the ES start signal is cleared. 5. Maintain RCS Pressure / Temperature relationship in accor-dance with the following: a) If RCP's are off with HPI flow on, maintain RCS between curves NO. 1 (Interim Brittle Facture Curve) and NO. 2 (50*F subcooled) of figure 1. NOTE: If the RCS inadvertently violates (goes above and to the left) curve NO. 1 on Figure 1, RCS pressure shall ! be decreased as soon as possible until the RCS is again back between curves NO. I and NO. 2. See Step _ 11 for HPI throttling criteria. b) If RCP's are off with no HPI flow on (MU_V-16 A/B/C/D Closed), maintain RCS between curves NO. 1 (Technical Specification NOT Curve) and NO. 2 (50*F Subcooled curve) of Fig. 2. c) If RCP's are on, maintain RCS between Curve NO. I l t and NO. 2 of Fig. 2. l t 6. If reactor building pressure reaches 4 psig, verify that l the RB-isolation valves have closed as indicated on Panel PCR (See Table II).- FOR USE iN UNIT l ONLY

FOR USE IN UNIT I O.NLY 1202-6B Revision 7 7. Verify that total HDI flow exceeds the reouired flow for RCS pressure as indicated below. RC Pressure, psig Recuired HPI flow gom O 550 -~ 600 500 1200 438 1500 4 05 1600 392 1800 365 2400 260 't ?500 216 If flow reovirements are not met verify valve positions and attempt to start another Make-Up Pump. 8. If inadeouate core cooling is indicated by one or more of the following conditions refer to Attachment 3: 'r " l Superheated conditions as indicated by the saturation a. I meter. l 6 b. Superheated conditions as indicated by the RC hot leg I RTD's and the narrow or wide range RC pressure indicators. c. Superheated conditions as indicated by the incore thermo-couples for the existing RCS pressure measured by the narrow or wide range pressure indicators. NOTE: With NO. RCP's running, the degress of subcooling shail be detemined by the saturation meter or the five highest and operable incore thermocouples, l 1 depending on the ability to establish or verify g Natural Circulation flow. (ie: no flow, use l 1 5 highest and operable incore thermocouples) FOR USE iN UNIT I ONLY l t

1 FOR USE IN UNIT I ONLY ~ 1202-6B Revision 7 9. Close or verify cicsed RC-V3, RC-V1, RC-Y35, MU-V1A, MU-VlB and RC-V25 in an attempt to isolate the leak. 10. Intemediate Closed Cooling (IC) and seal injection should be maintained to the RC Pump seals to assure long [ term availability. If NUs Service closed cooling to the RC Pump Motors is lost, monitor bearing anc stator temperatures. Each pump should not be run for more than 30 minutes without cooling water to the motor. l 11. l a. Throttle HPI after bypassing ESAS only when one of the following conditions exists: l l (1) The LPI system is in operation and flowing at a i rate in excess of 1000 gpm in each line and the l ~ situation has been stable for 20 minutes. i (2) The degree of subcooling is at least.50*F (as i determined by saturation meter or 5 highest anc i i operable incore themocouples) and the action is necessary to prevent pressurizer level from going off scale high. l l NOTE: If the degree of subcooling cannot be maintained at 150*F, full 5fPI shall be reinitiated. NOTE: The degree of subcooling beyond 50*F shall be limited by the applicable pressure-temperature restrictions of Fig.1 or 2. I NOTE: Monitor total make-wp flow to maintain >80 gpm per pump. Open MU-V-36 and MU-V-37 if Tieeded to provide bypass flow. l FOR USE A UNIT I ONLY L

~ FOR USE IN UNIT I ONLY 1202-6B Revision 7 CAUTION: Be:ause MU-V-12 is closed, monitor make-up tank level and pressure to avoid lifting the make-up tank relief valve (MU-RV-1). b. With criteria to throttle HPI met, bypass ESAS as follows: (1) Defeat 2 channels of RB isolation in Actuation A and B (recuired only if 4 psig RB isolation has occured). (2) Bypass all three channels for 1600 psig in Actuation A and B (If RCS has repressurized to greater than 1700 psig, reset the 1600 psig bir. tables rather than bypass) 12. Verify that Natural Circulation has been established by observing: a. Cold leg temperatures approach saturation temperature for secondary side pressure within l approximately 5 minutes. I b. Primary delta T(That - Tcold) becomes constant at i approximately 30*F - 50*F.

13. Monitor Source Range Nuclear instrumentation and incore thermocouple temperatures. Unexpected increase in source range indication or incore thermocouple temperatures may indicate voiding and inadeouate core cooling.

If voiding occurs assure that full High Pressure Injection is.in operation. FOR USE s.N UNIT I ONLY

FOR USE IN UNIT I ONLY 1202-6B Revision 7 14. Send an operator to the emergency feed pump area to take manual control of the EF Valves if problems occur. If neither main nor emergency f0eowater is available, maintain full high pressure injection until feedwater is restored. Open the RC-RV-2 (FORV) and RC-V2 or allow the code safety valves to open to provide a flow path. Refer to Attachment 4 for restorir:g Emergency Feedwater.

15. Reduce turbine header pressure setpoint or take manual control of the bypa:s valves to cooldown the RCS so that the degree of subcooling is at least 50*F and cocidown rate is approximately 100*F/ hour but within Tech Spec limits. When 50*F subcooling is achieved and RC pressure

~ is below 700 psig close CF-VlA and CF-VlB to isolate core flood tanks. 16. If the criteria for RC pump restart per attachment 1 is i met and if RC pumps and emergency feedwater are avail-able, bump the RC pumps in accordance with Attachment 1, ~~ and proceed to forced cooling. 17. If RC pumps are not available continue cooldown on natural circulation. I 6.B.4 Long Term { t 1. Upon a Borated Water Storage Tank Lo-Lo alarm of 36", i i shift suction of MU pumps from the Borated Water Storage l l Tank to the Reactor Building Sump by opening DH-V7A and DH-V7B, DH-V6A and 6B and closing DH-VSA and 5B and l 8 closing MU-V14A and 14B. Injection flow path is now as follows: FOR USE R4 UNIT I ONLY

FOR USE IN UNIT I ONLY 1202-6B Revision 7 Spilled coolant to R.B. sumo, R.B. sump to LPI pumps, LPI pumps to MU pumps, MU pumps to RCS via MU-V16A, B, C, D. 2. When both MU pumps are in piggy back mode of operation with >500 gpm flow per pump and RC pressure is <250 psig trip al' RC pumps (if operating). MonirJr Hot Leg RCS temperatures and incore thermocouple temperatures. 3. If RCS pressure decreases to <200 psig, and the HPI throttling criteria have been met, throttle HPI dis-charge flow by throttling MU-V16A/B/C/D. If recuired -. a open MU-V36 and MU-V37 to provide at least 80 gpm thru ~ each HPI pump. Periedically open MU-712 as necessary to control makeup tank level and pressure, e CAUTION: Because MU-V12 is closed, monitor make-up tank level and pressure to avoid lifting the makeup tank relief valve (MU-RV-1). Observe that LPI pumps deliver water to RCS via DH-V4A/B (>1000 gpm per LPI loop). 4. When LPI is verified >1000 gpm and stable for y_20 minutes l in both loops, stop the make-up pumps and close DH-V7A, 7B and MU-V16A/B/C/D. Injection flow path is now as i follows: I Spill coolant to RB sump, RB sump to LPI pumps, LPI pumps l to RCS through DH-V4A and B. l FOR USE11N UNIT.I ONLY

FOR USE IN UNIT I O.NLY 1202-6B Revision 7 5. Throttle DH-V4A and 45 as recuired to maintain LPI pump flow of >1000 <3500 gpm and when time permits, throttle manual valves DH-V19A and 19B and reopen DH-V4A and 4B. Within about 24 hours establish a long term cooling circulation mode as described in OP 1104-4 and listed below. Mode 1 - Forced circulation using decay heat drop line. Mode 2 - Gravity draining reactor coolant hot leg to the Reactor Building sump via the D.H. drop line. Mode 3 - Hot leg injection using pressurizer auxiliary spray line. Mode 4 - Reverse flow through the decay heat drop line into "B" reactor coolant loop hot leg. ' = 6. Monitor reactor building hydrogen concentration. Place the hydrogen recombiner in operation if hydrogen con-centration reaches 3 percent per OP 1104-62. ~ 7. Containment isolation valves may be opened to obtain samples in accordance with approved procedures.. The isolation valves shall be reclosed after the-sample is obtained. e e ) FOR USE IN UNIT I ONLY 12.0

FOR USE IN UNIT I ONLY 1202 6B Revision 7 8. Other containment isolation valves automatically closed shall remain closed until tha following conditions are met. a. Reactor building pressure is less than 2 psig. b. Containment radiation levels have been assessed based on radiation monitor readings or samples. c. The integrity of the system outside the reactor building has been assessed. (Stable surge tank level, visual inspection or pressure test should be considered to verify integrity). d. The Shift Supervisor or Emergency Director shall give permission to re-open containment isolation valves. e. Installed radiation monitors or portable monitors f'=' shall be available to detect any release that may result from opening the valve. l l [ FOR USE E UNIT I Ol\\'LY l

FOR USE IN UNIT I ONLY 1202-6B Revision 7 TABLE No. 1 HPI Actuation A (Left) Actuation B (Richtl Status Status Status Light Description Light Status Light Description Light Color Color BWST SUP MU-V14A Blue A. BWST SUP MU-V14B Blue R.B. SUMP DH-V6A Blue B. R.B. SUMD DH-V6B Blue DH to MU DH-V7A Blue C. DH to MU DH-V78 Blue Diesel A Running Blue D. Diesel B. Running Blue

r..

Aux. Bldg. MCC A Bkr Blue E. Aux. Bldg. MCC B Bkr Blue -F. Scrn. House MCC A Bkr Blue F. Scrn. House MCC B Bkr Blue i. LPI Line DH-V4A Blue G. LPI Line DH-V4B Blue BWST SUP DH-V5A Blue H. BWST SUP DH-V5B Blue R.B.C. Pump A RR-P1A Blue I. R.S.C. Pump B RR-PIB Blue

o..

RBC PP REC RR-V10A Blue J. RBC PP REC RR-VIOS Blue K. RB Fan A AH-E1A Blue X. RB Fan B AH-ElB Blue l L. RB Fan Mtr NS-V52A Blue L. RB Fan Mtr NS-V52B Blue M. RB Fan ~Mtr'NLV53A Blue M. RB Fan Mtr NS-V53B Blue N. DR Pump A DR-PIA Blue N. DR Pump B DR-PIB Blue 1 0. DR Pump Dis DR-V1A Blue 0. DR Pump Dis DR-V1B Blue P. NR Pump A/B NR-PIA /B Blue P. NR Pump B/C NR-PIB/C Blue l Q. NR Pump Dis NR-VIA/B Blue Q. NR Pump Dis NR-V1B/C Blue R. D.C. Pump A DC-PIA Blue R. D.C. Pump B DC-PIB Blue 5. NS Pump A/B NS-PIA /B Blue S. NS Pump B/C NS-PIB/C Blue i T. NS Deicing NR-V4A Blue T. NS Deicing NR-V4B Blue i U. Aux. BL Fan AH-E-15A Blue U. Aux. BL Fan AH-E-15B Blue i l l FOR USE 1h UNIT I ONLY 1

FOR USE IN UNIT I ONLY 1202-6B Revision 7 TABLE No. 1 HPI (Cont'd) Actuation A (Left) Actuation B (Right) Status Status Status Light Description Light Status Light Description Light Color Color V. SCR HS Fan AH-E-27A Blue V. SCR HS Fan AH-E-27B Blue W. H-P Recire MU-V36 Blue W. H-P Recire MU-V37 Blue X. RB Sample CWV-1 Blue X. RB Sample CM-V-2 Blue Y. RB Sample CNV-3 Blue Y. RB Sample CM-V4 Blue 2. MU-V-2A Blue 2 MU-V-2A Blue AA. RR-V-1A Blue AA. RR-V-1B Blue 88. RR-V-3A Blue BB. RR-V-3B Blue CL. RR-V4A Blue CC. RR-V4 B Blue DD. R B-V-7 Blue Actuation A or B (Center) a Status ,L-1 Status Light Description Light Color A. Non ESS Dump NS-V32 Blue B. RB Fan C,AH-E1C Blue C. RB Fan Mtr *IS-V52C Blue D. RB Fan Mtr NS-V53C Blue i E. Make up MU-V-18 Blue i F. RR-V-3C Blue G. RR-V-4 C Blue i H. RR-V-4D Blue l I. RB-V-2A Blue FOR USE A UNIT I ONLY

r-FOR USE IN UNIT I ONLY 1202-6B Revision 7 TABLE NO. II R.B. ISOLATION 4 PSIG Actuation A (Left Side) Actuation B (Right Sice) Status Lignt Descriot1cn Coier 5tatus L1gnt Descr1ction Coior A. S.G.B. Sample CA-V-5B Blue A. S.G.A. Sample CA-V-5A Blue B. S.G.A. Sample CA-V-4A Blue B. S.G.B. Sample CA-V-4B Blue C. R.B. Air Sam CM-V-1 Blue C. R.B. Air Sam CP V-2 Blue D. R.B. Air Sam CP V-3 Blue D. R.B. Air Sam CM-V 4 Blue E. R.B. Purge AH-V-1B Blue E. R.B. Purge AH-V-1A Blue F. R.B. Purge AH-V-ID Blue F. R.B. Purge AH-V-IC Blue G. R.B. Gas Vnt WDG-V-3 Blue G. R.B. Gas Vnt WDG-V-4 Blue H. R.C. Drn Tk WDL-V-303 Blue H. R.C. Drn Tk WDL-V-304 Blue I. R.B. Smp out WDL-V-534 Blue 1. R.B. Smp Out WDL-V-535 Blue J. CFA Sam IS CF-V-2A Blue J. CFA Sam IS CF-V-20A Blue K. CFB Sam IS CF-V-2B Blue K. CFB Sam IS CF-V-20B Blue j L. R.C. Letd IS MU-V-3 Blue L. R.C. Letd IS MU-V-2A Blue M. R.C. Sam IS CA-V-2 Blue M. R.C. Letd IS MU-V-2B Blue N. PRZ Stm SA CA-V-1 Blue O. PRZ Wtr SA CA-V-3 Blue l P. R.C. Let Sam CA-V-13 Blue Q R.B. Cooler RB-V-7 Blue FOR USE 140 UNIT I ONLY

FOR USE IN UNIT I ONLY 1202-6B Revision 7 TABLE NO. II (cont'd) Actuation "A" or "B" (center) Status Lien: Description Color A. n.c. Mec W r CA-V-lEr neue B. Nomal MU MU-V-1B Blue ~ R.B. Cooler RB-V-2A Blue CF Tk Fill CF-V-19A Blue CF Tk Fill CF-V-19B Blue l FOR USEliN UNIT I ONLY

2500 p- -Q-C l Al 1 I AIIT I (%M V -_e. =._ _-1 1. D 1I - -w ;- .= 7 CURV2 12 a-r ~--.. 2400 E_ c- -n,, _ 1=v

j

. __ m -- r= . w, 4 s am -7 ] CURVE f1, g=fg.. _ =_.__ _ _ _ _.. _a=._==r-i-g== =..= - 2300 x _u-- n =>=- N _. _ CURVE #3 _._2.....---...._ _. 2200 - = a 7 -.____;=- / CURVE #4 Iz -+- Y - - ~ ~ 2100 ~ - --

m.__7.,.__._...j=,.

= = - y_ _- _ - - - =. :. =-. .~' 2000 = ---+ w 1900 ___... ; _ _ __ r. 1800 T_ - -- : 1-- - - ~ ~-!.1 _ : - - - - ~ i--------._ _:~~ -~ 1700 1600 = =, _ 1500 t _4 -_.: N.--

?---'....---._...C_--

1400

a.. 4 q

..-..4 q r _.. _=-..= =--

r4

___..sr.__,.__ _ _. ,44.-.---.._ 1300 w - y~d~ - _.=gg = : -_ _- . :4 ;__: CURVE #1 - INTERIM--- l=i _; _ =FBRITTLE FRACTURE 1200 -__ w,3==_ CURVE #2 - 50 F g _4 :4. - 4 : =- --+ =' c wg -+3 __ __---+5i!-== SUBC00 LED MARGIN

4 M-----'-----*---

1100 ._.---g_=---* 1-iEE=== CURM #3 - T CLAD LESS m 0 E - E==f =a =-.- 4--63) =1=-3=. THAN 1400 F 1000 _ _s. 2.- - CURVE #4 T CLAD LESS 0

==fdi._.__

~ -.:.. 41T-T==i a - THAN 1800 F 900 - - 4 :, - --- ~7. 3J - r_ = = a:. ;_,=.,. _r. -e =. =r = ;.

--p - - --: == = --

=2=- ---i 5'u i-

-a = _ __. _=_n.--- =; _- =_ '15:=h -; - : =1 =_ '----

=

^ 800 .._._. l. ;}.

--..--_.---- s__,._--.._-...__.___......,=.____=_ ;

-"~~~ =# - - - - " _ ~ ~ ~ - - ~ ~ - -

-~~~

700 -1 =-s = i- -g - = ^ ' - - __-. -.'.. d:. .=i===: *f. _.;,3..."_-"_._. 4 _ -..-,_ 4._ _a _ x. 7... _. - "-=~~--'"._...."-1.__..4 600 ..-_i,_--__.___.. - =....

J-t = = =l= r 500

.-1. m_:._-_ 4C0 i-/- - =v.=i_ - _ : - _:=. : - - w =-..C. e:- w -4 4 t , iE:ET=. 300

_ --_ = _.==r -

J. _.. w-- . _,._- L.__j.__2 _ 3..,_. ...-. _ { _.==j p : _ . _ - j3=_ - _, - _ -.. _._43 ~ s r-- w _ a- ~ ' - ~ ~ ' = ~ = ~ ~ " ' ~ ~ ~ ' ~ = = - * = =* = " = * ~ 100 x-=..u.2_ - E vif"F"} -,rT-T= "i - = - -1 s ', r-i,,.. - 6a r= rw, a--- x h0M W6E 90% ddldo 1C00M$ bob 1300140015001600 I 100 200 INCORE THERMOCOUPLES (Use average of five highest) on n

PAm t 1 & f" tA1 1 1 h 0 P'T" I NNM 2500 a / al M. i _ _n. :p x = %_. _;_.%.. p.u..; g.._g. __.2..e_ _:.t.g...,.=. -.. m_ _b5. =i = _..... c.2. a;-l. _2_. : j.,. a . :..;;4::. 2 :=a - -- - ___.-.._.:=..=~ . _-.- r== r--

-f :: _. 4 __ -

--+=._

2400

h.. 4....

i.a=..-. :: : = = =__ : : r ; v - =-- - --- - : :====. - - -- --- + 1 ie=i =4 M, 243. -.=..: >. =

..l...: ; - ~;1 _. _,.==s =_.-= _.:r u =r. _- = -- -- _ _.. - _. - __ -. i - _ -.. a " Mnv o t,

v- = - - . ~~:=:.==.=_-=__ 2300 4 -g=. . _ : =: __...._=y ..m1.=;. 4 CURVE !1 g .= r CURVE #2 El 2200 .r4 : :c-T._-..---.-_.__,,,:._. __.: a _.. . _ - = - __:.!= =. :.g: :.: - i. =_._.....__:n&.=:r = __ : =- 2100

g.g.g_niggg-.__.~2====== _. - - - - - - -

l---<--- = < _.g..__ u

==.,g.._.._-- .r_---

.:=_. _=,

2000 ...._=._-__=.__==:. - ~ _-i ,-----.===.r.... r -- .__ - r = =" - 3 _ - E.__. _._... _._, - _. ; J _~.Eh._.:J_D_.i._:=_ EO=f=F -~ ":F. =- - '-TM = =_EEi - T -* - t - =:=== :J' --2:-.4..._.._. j t +

-- _ u =._.:.4. =.....--=t=.=---_.=.-- --:

._._ - _= = :. .----=.:- x =_.=._r------;d.------ _.."==4_--J.--------- -i :-.. _ _._=..E__. 30 .. r. _::.y..=--:---...- .-_v_ ..;._....__..i._...___a._ - - - - -, - _. ..:r.=]

;ib=r

== : ~ ~- ~===V.-.i -.

==. .- :. s a==.: r - =:. .1600 J..== _" : _==:.=. a' :.- _.'- 2: __:==. _._ -.-. = .::u--,-------------}. $. ___ _ _. _ _. __ _ ____. __r =] 1500 _{,. _.._ _ _. - _ _ _ _ = = - = i. _ r- _ _-- 1 1400 = =,= = _ - -, - - - - - = _ _ _ _... - i:_ .___--n.__._

-- - :.=:== -

r

3 '.

300 = =".,_ m"'='.__. .'- ~ _ _ = - - - - ' -. - - -.. _ = =. _ ',._ .. = = =. _e._q L_ -.._. _ f.=i -- .400 a 1100 -- CURVE #1 - T.S. NDT ~ .-g;.. __ _. c. _=_;., CURVE #2 - 50 F Margin' m a + g

-=-

_ _2 900 .==r===_=.-. 32 ---~~ 800 l 700 .. - - - _ -,.__ y - = .,a 600 .T _ __ ~ ~~ ---~ 500 400

S

"~~~ 300 -~ -2 200 ~ 100 ~ r N h0 !I 100 50] 700 INDICATED RC TEMP OF 19.n

~ FOR USE IN UNIT I ONLY :: 1202-6B ~' Revision-7 ATTACHMENT 1 Rt.5 TART OF REACTOR COOLANT PUMPS j i ~ i ^ FOLLOWING AUTOMATIC ESAS ACTUATIO.N 1.0 PREREQUISITES i ' j _2-NOTE: The normal limits for minimum RC pressure for RC pump operation are superseded b} these / ~ instructions. RC pump shaft' vibration may also eiceed normal limits. "If (ne vibration is- ,r I cff-scale (>40 mils) -the pumps should only be 'l run if incere Tc temper:tures are greater tbn 1 2 Curve 4 of Figure 1. 4,

l

_a ' [- o 1.1 Restart of the Rea.: tor Coolant pumps is recomended for tne l ,,.3 ~ " following conditions: r a. Feedwater flow is available and RCS repressu'rizes to greater than 1600 psig or RCS is greater than 250 fsig _'s with at least a 50*F subccoles margin. Refer lth Section - 0 p 2.1 of Attachment 1. b. Feedwater flow is available and RCS pressure exceeds 1., secondary system pressure by 600 psig, refer to,Section. 2.2 of Attacnment 1. .3 Secondary system pressure is less than 100 psig.r.nd ICS c. pressure is greater than 250 psig, ref'er to Section 2.3 of Attachment 1. d. Inadequate core cooling, refer to Attichment 3. 4 e. Non-LOCA - Overcooling Event, refer to Attachment 2. 4 i 7 l FOR USE FN) UNIT 1;ONLY r .w..

FOR USE IN UNIT l ONLY 1202-6B Revision 7 1.2 Verify the following RC pump services. a. Seal injection total flow approximately 32 gem (>22 gpm). b. Seal cooling: Intermediate Closed Cooling pump on, IC-V2, 3, and 4 open. c. RC Pump Motor Cooling, NS-V4, 15, and 35 open. 1.3 ' Start RC Pump Motor Backstop Oil Pump. 1.4 Start RC Pump Motor Oil Lift Pump. RESTART OF RC PtRP 2.1 RCS Reoressurized to >1600 psig, or >250 psig with at least a 50*F - - ;. u subcooled margin. j,/ a. Verify that emergency feedwater is available to at least J ..a one steam generator. Start one RC pump on the operable steam generator. b. ' ~ ' c' ~ Continue cooldown at approximately 100*F/ hour but within -c. Technical Specificatinn limits. / ~' a 2.2 ' RCS Pressure Ex_ceed Secondary System Pressure by 600 psig. ~ /

'[

a. Verify that emergency feedwater is available to at least ~~ one steam generator. jA 6.* Sump one RC pump on the steam generator with feedwater J* - J l/, t,/ t',/ / for 10 seconds. ) l / g NOTE: Bumping of RC pump on steam generator with low steam ! 1 generatcr level would not help condense the trapped RC vapors. I / c. Allow RCS pressure to stabilize while continuing to cool j down. l i ^ ? FOR USE kM UNIT I ONLY

FOR USE IN UNIT I ONLY 1 1202-6B s Revision 7 d. If after 15 minutes, RCS pressure exceeds secondary ~ system pressure by 600 psig bump a different pun.p on steam generator kith feedwater for 10 seconds. Bump alternate'RCpumpssojhatnopumpisbumpedmorethan ~ once in an hour. e. After, five (5) bumps allow the RC pump to continue in operation. 2.3 Secondary System Is Less Than 100 psio 2nd RCS Pressure Is Greater Than 250 psia. a. Verify that emergency feedwater is available to at least one steam generator, b. RC pressure.has been stabilized for greater than one hour. [ tc. ' Bump an RC pump on steam generator with feedwater for approximately 10 seconds. 4 d. Wait 30 minutes and start an alternate RC pump, if RC ^ flow is indicated and established, maintain OTSG cooling by adjusting turbine by pass valves for the respective x OTSG. e \\ l \\ \\ r s

~

~ g FOR USE A UNIT I ONLY

H FOR USE IN UNIT I ONLY 1202-6B Revision 7 ATTACHMENT 2 NON-LOCA OVERC00 LING TRANSIENT WITH FEEDWATER AVAILABLE 1. If a steam line break is indicated, verify the following valves closed for the affected steam generator. A Steam Generator B Steam Generator FW-V17A FW-V17B FW-V16A FW-Y16B F WV92A FWV92B FW-V5A FWV5B EF-V30A EF-Y305 MS-Y3D MS-V3A MS-V3E MS-V3B MS-V3F MS-V3C Refer to AP 1203-24 Steam Supply System Rupture. e 2. If an overfeeding event is indicated close the following valves for the affected steam generator. A Steam Generator B Steam Generator FW-V16A FW-V16B FW-V17A FW-V17B FW-V5A FW-V5B FW-V92K FW-V928 EF-V30A EF-V30B If unable to isolate main feedwater flow trip the main feedwater pumps. 3. Immediately restart one RC pump in each loop if the RCS is 50*F subcooled. FOR USE1h UNIT I ONLY

FOR USE IN UNIT I ONLY 1202-6 B Revision 7 4 Bypass ESAS and secure HPI. Restore normal make-up and letdown. NOTE: Considerable H.P.I. may have been added to the R.C.S. which could lead to going solid in the RCS. Use the turbine bypass er atmospheric dump va.lves to control and stabilize the RCS heatup rate. 5. When RCS conditions have been stabilized, use the normal heatup or cooldown procedures to establish the desired plant conditions. a b { l l l l l I l 1 l l FOR USE AN UNIT I ONLY .y , - ~, a,-- n--

FOR USE IN UNIT I ONLY 1202-6B Revision 7 ATTACHMENT 3 ACTIONS FOR INADE00 ATE CORE COOLING ! NOTE: Where instructions reouire opening the RC-RV-2 (PORV), it must be accomplished by inserting key into the RC-RV-2(PORV) manual control key switch and keeping the spring loaded switch in open position for the duration RC-RV-2 (PORV) needs to be open. IMMEDIATE STEPS FOR INADEOUATE CORE COOLING. ! NOTE: If RC pumps are running, do not trip pumps. This supersedes instructions in Section B Manual Action. 1.1 Verify HPI/LPI systems are functioning properly with maximum flow. Start third HPI pump and open MU-V217, if possible, to increase injection flow. Refer to step 6.B.3.7 for HPI Min Flow. (LPI System may only be on pump recire due to high (> 250 psig) RCS ~ pressure. 1.2 Verify steam generator level is being controlled at 95 percent on operate range. 1.3 Depressurize operative steam generator (s) to establish a 100*F/ hour decrease in secondary saturation temperature. 1.4. Ensure core flood tank isolation valves CF-V1A and B are open. 1.5 If reactor coolant. system pressure increases to 2300 psig open pressurizer RC-RV-2 (PORV) to reduce reactor coolant system pres-Reclose RC-RV-2 (PORV) when RCS falls to 100 psig above the sure. se,condary pressure. Repeat if necessary. If RC-RV-2 (PORV) is not operable, pressurizer safety valves will relieve pressure. i 1.6 When the indicated incore thermocouple temperatures or hot leg RTD temperatures are superheated for the existing RCS pressure, FOR USE h UNIT I ONLY 2

~ FO.R USE IN UNIT I ONLY 1202-6B Revision 7 l operator action shall be based on conditions determined from Figure 1, by a sample of the highest incore thermocouple temperature f l readings to determine the core exit thermocouple temperature. l l l ! NOTE: More than one thermocouple temperature reading should be m used (for example use the average of 5). r. i l _1.7 When the incore thermocouple temperature has been determined, proceed per the following guidelines. INCORE THERMOCOUPLE TEMPERATURE SECTION Incore T/C < Saturation (left of Curve 6.B.3 Follow-up 2 fig. 1) Action i Incore T/C > Saturation Curve 2 Repeat Section 1 but less than Curve 3 fig. 1 of this attachment Curve 3 i 1 ncore T/C < Curva 4 Figure 1 2 of this attachment Incore T/C y, Curve 4 Figure 1 3 of this attachment ! NOTE: The incore thermocouple temperature readings shall be continuously monitored until the indicated incore i: - thermocouple temperatures return to saturation temperature ! for the existing RCS pressure. 2.0 ACTIONS FOR CURVE 3 I 1 NCORE T/C < CURVE 4 FIGURE 1. 2.1 If RC pumps are not operating, start one pump per loop (if pos-sible). This instruction supersedes previous' instructions to trip RC pumps. ! NOTE: Do not bypass normal interlocks. Operate RC pumps until pump shaft vibrations are up to 30 mils. 2.2 Depressurize operative steam generator (s) as rapidly as possible to 400 psig or as far as necessary to achieve a 100*F decrease in secondary saturation temperature. FOR USE E UNIT I ONLY

FOR USE IN UNIT I ONLY 1202-6B Revision 7 2.3 Open the RC-RV-2 (PORV), as necessary, to maintain RCS pressure within 50 psi of steam generator secondary side pressure. ! NOTE: If steam generator depressurization was not possible, open ! RC-RV-2 (PORV) and leave open. 2.4 Immediately continue plant cooldown by maintaining 100*F/ hour. Decrease secondary saturation temperature to achieve 150 psig RCS pressure. ! CAUTION If emergency feed pump EF-Pl is supplied by main steam, do ! not decrease steam pressure below 150 psig, necessary for EF-P1 operation. 2.5 If the average incore themocouple temperature increases to Curve 4 Figure 1 proceed imediately to Section 3.0. 2.6 When RCS pressure reaches 150 psig, proceed per section 6.B.4 'Long Te.rm Cooling'. 3.0 ACTIONS FOR INJORE T/C > CURVE 4 FIGURE 1 3.1 If possible, s' tart all R.C. pumps. NOTE 1: Starting interlocks may be defeated if necessary. 1 (See GAI 208-110). In order to minimize the ~ possibility of a fire due to bypassing some interlocks, the following guidance should be observed: Do Not defeat the overload trip circuit and if Nuclear Services closed cooling is not restored to the motor within 30 minutes, trip the RC pump. Starting the RCP with neithe* inter-mediate closed cooling nor seal injection will probably fail the pump seals and may cause the pump shaft'to break. These consecuences are 1 deemed acceptable is an effort to establish adequate core cooling NOTE 2: High levels of shaft vibration should be expected. The RC pumps should not be tripped if vibration limits are exceeded. F O R U S E laWO UNIT I ONLY

~ FOR USE IN UNIT l ONLY 1202-6B Revision 7 _3.2 Depressurize the operative steam generator (s) as ouickly as pos-sible to atmospheric pressure. (150 psig if EF-P1 is in operation using main steam). ! CAUTION: If~ emergency feed pump is' supplied by main' steam, do not decrease steam pressure below 150 psig. 3.3 Open the pressurizer RC-RV-2 (PORV) and leave open. ! NOTE: The RCS will depressurize and the LPI system should I restore core cooling. 3.4 When incare thermocouple temperatures return to the saturation temperature for the existing RCS pressure - and - the LPI system is delivering flow (flow dependent on RCS pressure), proceed as follows: 3.4.1 Close the pressurizer RC-RV-2 (PORV); reopen if RCS pressure increases above 150 psig. 3.4.2 Decrease to two (2) RC pump operation (one per loop). 3.4.3 Isolate the core flood tanks. 3.4.4 Maintain steam generator pressure at atmospheric pressure (150 psig if EF-P1 is in operation using main steam). 3.4.5 HPI flow may be throttled if criteria of 6.B.3.11 is met. 3.4.6 Monitor BWST level as Lo-Lo level limits are approached, align LPI system for suction from RB sump per Section 6.B.4 Long Term. 1 NOTE: .If HPI is recuired per 6.B.3.11 align LPI and HPI in 1 piggyback mode. Close HPI suction valves to BWST. FOR USE IN UNIT 1 ONLY-

FOR USE IN UNIT I ONLY 1202-6B Revision 7 ATTACHMENT 4 f ACTIONS FOR FAILURE OF THE EMERGENCY FEEDWATER SYSTEM A. Failure of EF-P1 to Start. 1. Verify that MS-V2A and MS-V2B are open. 2. Verify that CO-V10A, CD-V10B, EF-VIA and EF-V1B are open. 3. Press the OPEN push button for MS-V13A and MS-V138. 4. If EF-P1 fails to start press the CLOSE push button for MS-V13A and MS-V13B. 5. Have an Aux. Operator check locally that EF-P1 overspeed trip is reset and that the Manual Operator for MS-V6 is in the open position. B. Failure of EF-P2A or EF-P2B To Start. ^ 1. Verify that there is voltage available at the associated bus. - I NOTE: With an ES signal present there will be a 20 second delay in pump start. 2. Verify that control power is available as indicated by the green indicator light at the control switch. 3. Manually start the pump using the control switch. NOTE: If EF-P1 and either motor driven pump have started l 1 any further investigation may be performed when plant conditions become stable. j l 4. Check locally for targets on relays located at the switchgear. i 5. Use the 69 bypass key and attempt to start the pump locally. l i FOR USE & UNIT I ONLY

FOR USE IN UNIT I ONLY 1202-6B Revision 7 C. Failure of EF-V30A or EF-V30B to open. 1. Check steam generator level to determine whether an open signal is recuired. The valves should be open if steam generator level is > 30 inches on the startup range (RC Pumps on) or > 50 percent on the operating range (RC Pumps off). 2. Verify that EF-V30A and EF-V308 Hand-Auto Stations are in AUTO. 3. If the valves have failed to open, place the Hand-Auto Station in HAND and attempt to open the valve. 4. If the valves have not opened, attempt to open using the backup Manual Control Station located in the control room. 5. If the valves are still not open, have the aux. operator establish communication with control room operator and take local handwheel control of the valves and open them as directed by the control room operator. _l D. No Indicated Flow (Low Flow) With Steam Generator Level Below Setcoint. 1. Verify that EFF discharge pressure is higher than steam generator pressure. If not Turbine Header pressure setpoint may be reduced to get additional flow. 2.- Verify that the following valves are open: EF-V2A EF-V30A EF-V2B AND CD-V10A EF-V308 CD-V10B 3. Have aux. operator check locally for pump malfunction and correct lineup of manual valves. l h FOR USE3dN UNIT I ONLY

~ l. FOR USE IN Ifc:x/C:prc=unz; tion ONLY R 1202-68 EP 1202-6A, 68 and 6C Redsion 7, ATTACHMENT 5 NO ts RCS Pmss <1600 psi

' YES Venty Reactor tna Verify HPi l

Trio RC Pumes 6A 5 -~ mmated k:200 psa i NO RCS MU, n Reacto' 1202 EC 1202-6B .am or emerg Verify RB isol ...~4 & level Verify EFW YerifY Core Food Verify RB Spray i Did RCS Press YES Verify LPI < 1600 psi is event Non LOCA YES Overcoor:ng NO l NO 1202 6B l YES OTSG Tube Ru:t YES Did RCS ~~ 1202 5 l Recmssurize 3*C OU Yarify Cont Isci is margin from N0 NO ~, saturation > E0 i l Are symptoms YES + of inadequate cara YES Inmate fuu confinq present HPl and % 1202 68 UTSG confmg l NO - Is Mat Cire NO is sat' aten s present reached with .Y.ll J, Venty. OTSG l temp mcrease YES .Cacfmg.contmue l NO Cooldown at fuff HPI Continue HPI ~100 Tlhour BWSTLoLa Until 50

margin YES Level A! arm 5

regimed om sat. av$ade Throttle HPl to c prevent sand cond Cooldown per YES j:N0 NO ' Is LPl>1000 gpm OP 110211 is RC Pp restart Bump (Start) criteria met Attach t for>20 min RC Pum:s Estab HP!ILPI I from RB Sump lYES BWST Lo la Lavel EstabEsh LPI Alarm Fiow fremRB Suma NO is LPI >1000 gaml YES f for 20 min l I Estabftsh HPl!LPI Estabrtsh LPI

- '"7t?! U SE IN U N1T I 'DKT_'t" 31.0

FOR USE IN UNIT I ONLY 1202-6C Revision 7 03/31/81 THREE MILE ISLAND NUCLEAR STATION UNIT NO. 1 EMERGENCY PROCEDURE 12C2-6C LOSS OF REACTOR COOLANT / REACTOR COOLANT PRESSURE CAUSING AUTOMATIC HIGH PRESSURE INJECTION, CORE FLOOD AND LOW PRESSURE INJECTION Table of Effective Pages Page Revision Page Re vision Page Revision Page. Revision 2. 7 TED U W d ( EC 17 A10:10 7.0 6 V 8.0 7 9.0 6 10.0 6 11.0 4 12.0 6 9 13.0 7 ,s T 14.0 7 ) + 4 Unit 1 Staff Recommen v1 Appmval D \\' a

1ept. Head

~ Cogr.ij \\ \\ J Unit 1 P0 C ~.~ nds Appmval 0 fl &,/ Date 3 3/ B/ Chaidnan of PORC Mana er TMI I Approval M. Date h 3) * $l Mgr QA Appmval NRC Appmval Date Date DOCUMENT ID:0006N FOR USE IN UNIT I ONLY

FOR USE IN UNIT I ONLY ~ 1202-6C Revision 6 THREE MILE ISLAND NUCLEAR STATION UNIT NO. 1 EMERGENCY PROCEDURE 1202-6C 1.0SS OF REACTOR COOLANT / REACTOR COOLANT PRESSURE CAUSING AUTOMATIC HIGH PRESSURE INJECTION, CORE FLOOD AND LOW PRESSURE INJE. ION ! NOTE: (1) If RC Pressure remains above ESAS Se ) _-- proceed per 1202-6A. (2) If HPI initiates automatically b pra, ure remains ! I above 200 PSIG proceed per 120 (3) If OTSG tube rupture is confi eed per 120p58. g 1.0 SYMPTOMS 1. Rapid c Higg decrease of re ctor diantpressure. QU v' 2. Rea fp) Alarm. 3. RCS r sure ES Actuati 4 ES Act tion as indic ty-t e status ligh CR panel. 5. RB Pressure Hi Al 6. Core Flood Tan 1 vel Hi/Lo Alar 7. LPI Flow i dkatdd. 2.0 IMMEDIATE ACT A. Aut ion 1. Re ctor trip on low RCS pressure. 2. Turbine trip. 3. Hi pressure and low pressure injection initiated at 1600 psig, 500 psig RCS pressure or 4 psig reactor building pressure. 4. Both core flood tanks discharge at 600 psig. FOR USE # UNIT I ONLY

~ FOR USE IN UNIT I ONLY 1202 6C Revision 7 5. Various degrees of reactor building isolation occurs on reactor trip, high pressure injection, 4 psig RB pressure, and 30 psig RB pressure. 6. Reactor building emergency cooling initiated at 4 psig reactor building pressure. 7. Reactor Building pressure mcorder transfe toxi range transmitter. S 8. Reactor building spray initiates at B. Manual Action \\ ! NOTE: T ers indicated wi hg'n terisk (*) will be as the first step ollow-Up Action. 8 _ _ _-, 7 _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ g_ _ _ _\\_f v)the reactor t 1 ress s utton and verify that all rods ve inserted exc 8.

2.

Verify that and LPI pumps ha ed and that HPI flow is <23 g per leg. sfj _______________/._ _ _I ___________________ 7 ! CAUTION: start any major mo b as the condensate ! ( the condensat e pump during block _3 _ _ _._ _ _ _ _ _ _ _ _ _ _.{.l I W 3. all operating RC pumps. 4. Close MU-V12.

5.

Verify Reactor Buf1 ding Isolation Systems have actuated as required, see Attachnent 2.

6.

Verify that Core Flood Tanks dischanjed to the reactor coolant systerr at '600 psig. 7. Verify that reactor building spray initiated at 30 psig building pressure. b 2.0

FOR USE IN UNIT i ONLY 1202-6C Revision 6 3.0 FOLLOW-UP ACTION The objectives of the LOCA Emergency Procedure are to recover and cool the core using HPI, Core Flood and LPI, to isolate and cool the reactor building, and to achieve a cold shutdown condition on long term recirculation from the Reactor Building Sump. 1. Reverify the status / parameters in Manual Actio ng re marked with an asterisk (*), using redundant indic , available. 2. Declare a Site Emergency (carry out EPIP IQ *. 3. Verify that all ES equipment is in i E ition by observing that all ghts on the PCR p e blue with the follow Q tions. Also ver.tyt containment isolation valv A.!havh closed per AttacEMnt KR- -02 b. KR-Gil-02 c. STM GN A MS ' d. STM GN A. e. STM ESlvtd s f. Si -V10 k A CF-VlA g h Tank B CF-Vl3 1. RBS Pump A BS-PlA

j. RBS Pump B BS-PlB k.

MU-V20 RBS Pump starts when RB pressure > 30 psig. RBS pumps discharge valves BS-V1A/B open at RB pressure of 4 psig. FOR USE IN UNIT I ONLY

FOR USE IN UNIT I ONLY 1202-6C Revision 6 NOTE: The breaker anti pump feature will prevent reclosure of ! tripped breakers until the E5 start signal is cleared. Should any component not operate properly, defeat 2 RB channels, bypass all three 1600 psi and 500 psi channels, and attempt to actuate the failed component using its remote switch in the control room. If it still does not operate check the control power fuses. If the component has a local "69" bypass switch, place switch from " normal" to " bypass" and again a) empt to i start. g Monitorincorethermocoupletenperaturesasee'\\ 4 ce of over heating and void formation. Verify bot 'a{opof HPI and LPI are in op nd that core floo s ve discharged. ' CAUTION: throttle HPI to n 500 gpm/ pump unless L system is in ope on and flowing at a rate : 1 ( pxcessof1000g@2jnddhlineandthesituation gV beenstablefo{ nutes. 5.NI Y e RCS repressur a. Verify Eme c edwater is in oped K and take manual control ,0A and EF-V30B a ease steam generator leve [ rcent on the g nge. b. ressurizes due u ted condition, refer to,htio for Inadecuate Core Cooling." T2 o c. the RCS is subcooled and RCS pressure is >300 psig 'efar to 1202-68, " Follow-Up Action" for guidance on pressure-temperature restrictions. FOR USE 13 UNIT I ONLY w r w-y

~ FOR USE IN UNIT I ONLY 1202-6C Revision 7 6. WitMn 10 minutes comence continuous monitoring of the following for the plant status evaluation, and monitoring. a. Liquid levels in: 1. Borated Water Storage Tank, DH-T1 (DH-3-LI 1 and 2). 2. Sodium TMosulfate Tank (BS-T1) BS-3-LI. 3. Sodium Hydroxide Tank (BS-T2) BS-5-LI,-. b. Safeguards injection flow rate in each 4 1. Two low pressure (decay beat) ttina lines. 2. Four high pressure (makeup ec. n lines, -3 1, 2, 3 and 4. j 3 ctor buildi s ection Ifnes, BS-1-FIl d 2. \\ 4. Three (each) r@ tac 11 ding emergency cooling water V inlet and dt f'nes NS-20, 21 arid 22-FI and NS-23,

4 \\

24ang specti vely. -h /> %.*]f environmental nh gh $ns: c. Reactor B'u{ a V 1. p' liquid level. 2.h eratu re. T P ressu re. Re actor Building liquid level indicator. 7. If conditions require throttling, obtain shift supervisor - permission, bypass all three Hf pressure and low pressure injection channels, and defeat 2 of the 3 RB pressure channels on Actuation A and B. FOR USE y UNIT I ONLY

FOR USE IN UNIT 1 ONLY 1202-6C Revision 7 8. Thruttle only as mquired to pmvent pump runout: a. Hi pressum injection flow (MU-V16A/B/C/D) 500 to 550 gpm/ pump. b. Lo pressum injection flow (DH-V4A/B) 2800-3500 GPM/ PUMP c. Building spray flow (BS-V1 A/B) 1500- 00 GPM/ PUMP N _____________.__.___________________________________ C _9.__ ' NOTE: Hf flow alarms should actuate as a wa Inttle q _____________ 9. If either LPI loop does not Fave 1500 p. w with RCS refer to Attactme6\\ p ressu re

10. Upon ngaBWSTLo-Loala inc hes:

tor coolant system is 'apove 200 psig or if LPI flow a. r ss than 1000 g{perh op. it [ hl. Open DH-V6 2. Close DH-VSA hile observing LP.Q A flow. 3. Ope while observing A flow and LPI J 4 DH-V6B. ose DH-V5B while(oohserg\\ing LPI Loop B flow. Open DH-V78 while observing HP1 loop B flow and LPI loop B ' low. ! NOTE: MU-V14A and B may be left open to pmvide suction to the ! HPI pump in the event the LPI pump trips. 4 FOR USE IN UNIT I ONLY 6.0

FOR USE IN UNIT I ONLY 1202-6C Revision 6 7. When RCS pressure decreases to less than 200 psig and LPI flow is >1000 gpm and has been stable for >20 minutes, trip MU-P1A, MU-PlB and MU-Plc and close the following valves: DH-V7A DH-V7B g MU-V14A MU-V14B MU-V16A a coolant q'ssu s less than 200 psig, LPI is I act h reater than 1006 3 h each loop and s been stable for 20 minutes. 1. Open(b- \\\\ v 2. e N SA while obser A)t n cop A flow. 3 N -V6B. lose DH-V5B while ng LPI loop B flow. Trip MU-P1A, MU-P1B and MU-Plc. 6. Close MU-V14A MU-V14B MU-Vl6A MU-V168 MU-V16C MU-V16D FOR USE W UNIT I ONLY

FOR USE IN. UNIT I ONLY ~ 1202-6C Revision 7 11. If the RB Spray Pumps have actuated: a. When the Sodium Thiosulphate Tank level maches 3 ft. close BS-V4A and BS-V48. b. Stop the spray pumps when RB pressure is less than 4 psig.

12. If the RB Spray pumps have not actuated and re 1 ding pmssure has decreased to less than 4 psig, W -V4A and BS-V4B.

13. Evaluate radiation levels in the Aux a

11 ding and establish ssMontmls and post ig pidiation tmas.

14. Moni 1 ding sump level detect possible LPI system 1

k ,an,d' assum that t acity in WDL-T2 for sump sta rge.

15. Whe time pennits,

]gmanual valves 19A and 198 and reopen DH-V4A and ithin 24 hours, esTIMhh one of the long-term coo [ag Jtulation modes e in OP 1104-4 and listed be Mode 2hfh ty draining m tr ant hot leg to the actor Building s the D.H. dmp line. Ho Hot leg injection using pressurizer auxiliary spray line. Mode 4 - Reverse flow thmugh the decay beat dmp line into "B" Reactor coolant loop hot leg. FOR USE IN UNIT 1 ONLY 8.0

FOR USE IN UNIT l ONLY 1202-6C Revision 6 4.0 Long Term Action 1. Secure turbine, feedwater, and steam systems when time permits. 2. When the reactor building pressure is reduced to = atmospheric, monitor for H buildup. Using OP 1104-62, place the Hydrogen 2 Recombiner in service when hydrogen concentrati % ches 3 percent. M 3. Monitor R.B. Sump for pH and add Sodium % #o ' /as required thru ire de:ay heat removal system. 4 As conditi t, evaluate plant co ions and return non-es %,gauipment to its no ) ne up. b A E:Y 3 fer to the f d structions and procedures : for additional 1on as recuired: .0P 1104-21 Pg Pressurization b. -DP 1104-20 -E k p c. OP 1104-19 Vroom Tower Vent 4&ation d. OP 1106-6 fg ncy Feedwater by 5. Containment t valves may be M obtain samples in accorda e approved procedures. e isolation valves shali' be rec Rs ' Ofter the sample obta'ned. Ot mrit inment isolation va i 6. automatically closed shall remain closed until tha following conditions are met. I a. Reactor building pressure is less than 2 psig. b. Containment radiation levels have been assessed based on radiation monitor readings or samples. l FOR USE W UNIT I ONLY r e-m,c -4 m 9 a e-

FOR USE IN UNIT i ONLY- ~ ~ 1,,,, Revision 6 c. The integrity of the system outside the reactor building has been assessed. (Stable surge tank level, visual inspection or pressure test should be considered to verify integrity). d. The Shift Supervisor or Emergency Director shall give permission to reopen containment isolation ]y s e. Installed radiation monitors or portabl n s shall be available to detect any release that req) sit from opening the valve. gf O+y -v p.. q O FOR USE l& UNIT I ONLY

1202-6 C FOR USE IN UNIT I O.NLY aevisia 4 it. - -iES, _. - - - - _; =:. _ = .--.=.=1===;- , _ _ _V._ i ~E3 ... _ -... -=1==== - m=- FIGURE 1 -~ ._..__._-r=_..._ a-t 2400 7 = f__.;-,=.;;_p- - - - - - - - - - - -50 SUSCCOLED CURVE . _ =2=T=_=_.*=2235 = sr-- _ =- .._ _ 4_ ~~ z..:: 0 O. j _,_ n=~= -. _.= =:= ^--*,-L--_-

== 2300 - -r t -.:-i ' =-.; .=. _ = - - -- .=;=

t=

-+---s

=_:==-.==.==:==s.-

.-- 2200 L=_- ;;. EE-!==Ju="_. _h==.i E TJ. __..;- .r_ J- := i- .. -- c h _ _ r-ib' _ - __ ._..=_._._._=__-_.==1_.__4-.:._;i~.~.._,.- i. ~~ ~ E.. u=.: _:.=_.=_.- -. ;. :_ s= ;==- : r = s==...: : =r=a =..-- --.

;. = r := = :-=: v -.- ~_-.. =g.: - -- t= =,,

-., -.. = ;--. _.g. - ; ;,--

g 2,,

- - * - ~ ~ ~ ~ ~ ~ ' ~ " -

m.~

._,;=, { _ -':'~~'----------'----

== r =g ;; _-J

t. ;2 ; : _7..-- q;._:t:.. r =_.. 4= :=)):::.

__.i=.J ".:7-. =-f.:_":.: --=t~="=r-":-'----='---T . =. _ = 3 00

=====.= =:.=.& =:g.. : -.-* r _,,;; - - -. - - -

==s =1

-: =- _. s: y..p== =x==.= - r E = = - =~: =c

" _=2= 2r==. = i = ;*m
==' i:

- " = ' __.m' =r'"'- I. - i-r- =....._. __E ;__3_ _=x=_-t=.":=. a :=.

_ = _- _=- : :: _ _ :.= _- ; =a===

I

== ""=F -= 2000 - . r: _=:------ . = t= _: = =_ - .-=t-- t =:== _ r= - _.e. n j 1_-,, g:_ ___ _a.=.7 --* "

E.-""!

T=--*.

T'_W-t-- -r ;_*_-- {_ g - *

{ t.__..-

* *: =g;Qg'7

~2-

]

74- ;*IT =.m.;.;=: t --- -.-p; - - - - p ;;, "==

;;...-,--.--y_.

_-.r-.n--;-

.t=== *.:.:t :. ::_r=.

- r :.T_ ___ P

. _ = = _ u,.;_.'-' ^ - -~ '... =_*=__- _- ". _ _-- -- - = :' =_- r=_ c,E- =- =~ *t= 2 = t =_ L =4 - -.f'-_.. - -i i. =_ f ;.;r.', _ r-- _.y%_==. f= t-1 _-y-r---* u_ =_-- 1800 '^*=----'=='-i-="---- - * = - ', = '-- _ i. - - - -,=_- 2 -I ] } 70 0 -- ;h _ _-- - =ti i-----1..,--- ]=.= :p=.j,; ;{.g=Q=2;[. g.%-.q -$p==- -- Q ,p_.. ---r-.- -_ ;=- t .t.=:1.. j. }-- _2.r._s.- ^-

_f_ ---+ -= : r--

-=- g- _T=-i=.-]T ' - - - + - - . - : :a: w _._%. r c. -.T:[ a 2 =..... 5 =_;T- __,_ _ g =t D :q T1 r-$.= =__:F"f=.== jr.-==:- T =~ "T.._.i._._ __ g.-- -~= r t _u~._.._...__...__.=.,.n__.._w_-w..y-.. :. r_. t==

__._ a I600r=r.._

.. ;v; g a ;,, ;, _.a.-._ -.

_-H,.

__..._;;;_...._.__.m.,-_.%._._.-_,

. :. :: _o

V+-+

-!==say - -t V. 4=.:- ~' - ~ ~ - ~' ; I - -- -* -* : -~ =i=7= i "=='4 =;#-t - =A- "- - - " 1 -'= =- 'l =2' 1500 ;i-r "x : "- % g j ---+ -

- - --- - r =- - =- -

-i i-z y .=g: s =- ).

= =

=. .,. R D K= EE = u c t __ _ = - :, _ ___._ n H 14CO E__ FC QSLE/ PRESSURE - TEMP '=rr=----:='---'-==*

=

es

iM AM =E.:PE=E ~s

-- 5=3 =3 -T".1 \\ pE-- y,==..=- e --

= m -

+-a.. ' EE GIOK T4R LOCA CONDITI " -o E = .g-1300.:. ..;--ar-r- .a o - =. F:=:= -: -W.. - _. - __,....=... _=.=. .=..==l=. r - - ~ = -.._=-T =:=;= m:--- - m. i.- a= --t:= 1 = p-a: - f3I.=:iiE =l-S, 1200 4 : __:.J= -==_...i= r-Eu=:i=.5E

==i=- t=e=i== 3 i - =- ~ - fa r..= r_I t =_=_._.__.. :-== -t = ,r.=. }_. =:_u:- - - =_== :_= =!c_ =v. _.~5L. 1- _ _ __1 _ = = - - -- A m. _ _a .c - - ta > =*="-

M>==2EE= _ _.:=- d= :==*- " y=:_va - -,-. 5===,:

=p = :. ; :.; r. 1100 f- ".=: :==- :---- : =---:.=-_.. _. __ _ s.-.=.= :u, = l.H-- 2-c= ~ n '3 -'"x~="t =_.. r/ : m= e - -~ p. ~ 2..=

~. '".. _-_ _ :- "- =":-=

=.. e. - M-. m._4 T_ ~4

)--

=. = - --

=. ~

oa QC- *. 2 = ;I =* = :. _ f.J.h Y-,1. p=- '4. L I*. ... 7:-'-h-4 T.[ ~- " - #" - .-.:--'~--=- 1060 " _=== -- "=-- ~~ - 1 '= 2-n - #= -- ~

2=---

' ~ c:: u ~=- = re -

=-

__. _ _2: =r_=r/ =h --

=2--

---s t --- + -- r-M=. 5~ -A_.. =---- 4 t -l-_ -. - -4

m-+--%~---+---+---

= =. _, S,0 =:m xxv r 4 :- ..-+-t=----,.ur=; w. ~~ . _ _ = _

4 v

2a.. 3 t t _=-- r-- -9 : r -rw -.=- ', 2 -==1= x:=:: =. 4.-,=

= r-t g: ..

r

.=.- w -~

n__..._ m ic _.

- - -. = -. - l M= -* ; x M _ --~~~" _ " E '_f F # F i=~i= 1 W ~~ 4 EE ks,_MG - - 800 . ~ 5 4., - _*Q _~

r. i--&.._.r*-

E-.{.

==*=.: POSSIBLE VOID FORMATION AREA =_2E -e.=_ = w= +- -- +---- N_== HPI (LPI) MUST NOT BE THROTTL n : = - 700 - 2= . r #.. = r _= _r__._2--- ._ f.g.i===c::. -r

__=

~r g:I. _ 600 W = 2==- -~I=== 55

== = .f.. __.:.: A.=. __v_- =_. = - -- ;_. _ _ _ _ _ = _ r= ~:* =t =': + ;r- ~~ b- - - 3

=._

- - - - 500 ;_ 7_Z_.__ _. * -7 P E i! - - :t- - - * - * = -

~

' - ~- J a=_ =_'._ 2::=t- : =4_==_ _.. ~- --~ =-- -

J= -#.4 = ::= F

=. _,P __,. _ ~:=-i.- _ :1:=- 5=r- =2 .r. -._ :.= ~ -i- .2 4 _. t- - _4 [==,-4 _ + -- M-- =;.::;; p-.-t i- - ,.4 - ; -- -+ _;- ---- - E ..j,,,,,. , ; p - --. 4. - - t 2,. ;.I "--'. g

= " -

':-

2-

, :- i - -

- 400 2 =~- - M :=- = +-" 2=

Ei =5=" =h c EfE "-iT-4E_=Er "i..i j@.".[=:!2 :esE =P="ET :" -l.=.d=_ ele.F:EFE#E4 h l

EEE .r_ ..ac.1_.___.p_... .,._.:.1.. -. F.:. r.-.._.=.a..=..- ,s- _:_= .f:4-. - c.:.= _. _...,..____....a_b..._._, ... = _ _.n...,.a. _.. -.. _. _. - 3 .T.M_.--/_ :. l;.=:;_;! n =u:= g ;:*,g ,e, -T : * ;=1..- =, = : - 4- ..... _.1 _=_......- :d _: r _. t- %: ,.1. 2t r 4 =h.__.. ;.. h=- =. r z q= : - l ;-... _ e-h :L:;. (.,.- :: t- : \\ f-t :b =.:: =1~ = H in =e: =

n

-d r._.._

====l_.=r*. - m=,-i 2 2

= 200 '

a. l E --.= C E 3 50 _ '.. _ 4'0 0 ~-__g$0 50'0. _. 5$0' ~ .. 6'00 653 _ e.-E - ~ - - ~

=-

.. :t

_= _= _.==_. : -- ~. -. : J '_.... _ = g cR..$ ids LIN*U iT I O = = ' " *........* =- *. 3 =.E=- m u =_1 ' =. - - ' ' **. p = * * ' ' y"

:.a.~

.~ - =:===b:...::..= Th (Tc) Hottest R.C. Temp. 0F 7=== / - = ' *"-" ' r l 11.0 l

~ FOR USE IN UNIT I ONLY 1202-6C Revision 6 ATTACHMENT 1 FAILURE OF ONE LPI LOOP If DH-V4A/B are open, RCS is less than 100 psig, and flow is.less than 1500 gom in one of the Decay Heat Injection Lines, proceed as follows: 1. Obtain the administrative keys for the DH cross-connect isolation valves (DH-V38A and DH-V388) and the DH injection marw'(h ow control valves (DH-Vl9A and DH-V198) from the shi t-hyisor. 2. Proceed from the control room to the north end o uxiliary building at elevation 281'0". 1; ally high radiation

g s should be per 3.

The entrance to Emergency P 004.15. 4 Remove th e strative locks th solation valves in the DH V g ine and the DH o'n manual flow control valves. cros pec 5. Open th h' cross-connect 1. ion valve (e. DH-V38A next to the line having the hi h w rate as rapidl % ossible and then crack open the second c ss-connection isolkhpplve (e.g. o \\' d <'N d ..DH-V388). - e, 4 s 6. Open the sec'M th)ation valve whi as\\ st cracked in step 5 above in ross-connect lin 7. While o the second decay heat cross-connect isolation valve, throttle either DH-Vl9A or DH-Vl98 as reoufred to achieve essentially ecual flow rates in both DH injection lines. FOR USE ]N UNIT I ONLY

FOR USE IN UNIT I ONLY ~ 1202-6C Revision 7 ATTACHMENT 2 REACTOR BUILDING ISOLATION SYSTEMS (All Val ves Close) RB Isolation f rom Reactor Trip RB Isolation f rom HPI or 4 PSIG or 4 PSIG AH-Y-1A CM-Y-1 h AH-Y-1B CM-V-Q l !~t h) AH-V-1C C V .U AH-V-ID GM-Ye *, kV-A WDL-V-534 y ,s WDL-V-535 m RB-V-7 ' k'> MU-V-28 WDG-V- \\ / MU-V-2A WDG-3 MU-t-{S 4' WDG-V-304 k\\ ) CA-Y-1 RB Isol tion /f rom 30 PSIG CA-V-2 / V4 CA-V-3 -V-15 r CA-Y 3 NS-Y-35 s-CA-V-4 IC-Y-2 CA-V-4B IC-Y-3 1 CA-V-5A IC-V-4 CA-V-58 IC-V-6 MJ-V-3 MU-Y-25 CF-V-2A 1 MU-Y-26 CF-V-28 FOR USE A UNIT I ONLY

FOR USE IN UNIT I ONLY AeJ;En7 ATTACHMENT 2 (CONT'D) RB Isolation f rom Reactor Tr CF-V-19A CF-V-19B CF-V-20A CF-V-208 g f CA-V-189 ~~4@@@v 4 FOR USE Wo UNIT I ONLY~~

1202-2 Revision 7 06/29/81 THREE MILE ISLAND NUCLEAR STATION UNIT NO. 1 EMERGENCY PROCEDURE 1202-2 CONTROLLED C00',' STATION BLACK 0UT USE IN UNIT I ONI.Y Table of Effective Pages CEN RAL 21_E Pace Revisin Page Revision Page Revision Page Revision I 1.0 6 2.0 6 M cKETED 3.0 6 uwr; 4.0 6 5.0 6 6.0 7 'M [E 7.0 7 8.0 7 9.0 7 10.0 7 11.0 7 12.0 7 13.0 7 y 14.0 7 15.0 7

/
D A Unit 1 Staff Rec Ap oval Approval e Co ah ejit. Head v v Unit 1 PORC , ends Approval 0 A AftU Date 6/29 8/ Chairman of PORG l l Manage TMI I Approval [' N / h Date I l l l QA Modifications / Operations Mgr N Date l Document ID: 0012N l
3 .v _1202-2 Revision 6 .i THREE MILE ISLAND NUCLEM ' STATION i' UNIT NO. I EMERGENCY PROCEDURE 1202-2 STATION BLACKOUT b 1.0 SYMPTOMS ~ 1. Separation from the 230 KV system and generator t 9'E indicated by: I N a. Zero volts on 230 KY bus voltmeters % b-ion panel, kghtsabove' b. Generato akers open (amber a r extens is on console 2.0 IMMEDIATE ACT g A. Aut t on 1. actor Trips beca Tass of voltage to the control rod drive system. 1, 2. Turbine tri 3. Control ghting comes o 4. Emer urbine feedwater p s due to loss of all f a or coolant pump. 5. (Integrated Contro em) maintains OTSG (Once Through Steam Generator) level at 50 percent on the operate range. 6. Atmospheric steam dump valves (MS-V4A/B) control main steam pressure at 1010 psig. 7. Main Steam relief valves open if pressure reaches 1040 psig. 8. RC-RY-2 (PORV) opens when primary system pressure reaches 2450 psig. 1.0
i 1202-2 Revision 6 9. Pressurizer code safety valves open if primary system pressure ? . -- 7 reaches'2500 psig. (
~~10. Generator DC emergency seal oil pump starts.~~
~~,j ;~~
11. DC lube oil 'pys start on the main turbi.1e and feed pump

' if' i
~~/ turbiivas. t. e l'-~~
~~12. The DC oil lift pumps for the reactor coola 7 tart.~~
f
~~13. The screenhouse and circulating water hoilk d el fire pumps 4~~
~~/- vv start because of-loss of AC power. ){ 1 / 14 The stati tteries supply powe 11 five inverters. b~~
~~15. 'e The 1A a diesel generator t.~~
~~) W ' i~~
/

16.,1D 1E 4KY busses a ene ized by the diesel e
~~thus energi , S, R and T 480V busses and I ES control cent feIcy feedwater p' M~~
17. Both motor driven tart.

18. The battery are energized b a
~~B ES motor I' l control i~~
~~19. The i e switch back to i~~
~~al 480V AC source.~~
~~20. T s~~
~~intermediate c ed ling pump starts and l et cooling water to the rmal barrier heat exchanger of the RC pumps.~~
~~21. The nuclear services closed and nuclear services river water i~~
~~standby pump starts.~~
22. The lead instrument air compressor starts (IA-PIA or B).

23. The air compressors for control tower ventilation start (AH-P8A/B and AH-P9A/B).
2.0 se
g t j. 1202-2 Revision 6
~~24. The diesel generator ventilation fans start if they were previously running (AH-E29A and B).~~
s.
25. The AC oil lift pumps start on the RC pumps. The DC lift pumps stop when the RC pumps reach zero speed.

26. If not manually started, the AC turbine lift pud will start automatically when the main turbine reache p ed.

27. The main turbine turning gear starts an nga p when the turbine reaches zero speed.
~~L B. Manual Action The parameter k'ed with an aste ig~~
~~shall be reverit !ed as the fir in follow-up ac n.~~
~~3 1. r he following: ) Reactor is t a control rods h ve inserted. 'I ~~~~
b.
Both diesel ra ors start. ~ h...__.._________. (N..____...___________ ! NOTE: If Hes ' generators fai , refer to EP ation Blackou( Les's Of Diesel Ge rs. ency feedwater s rt (EF-P1, EF-P2A, and -P2B), discharge pres comes up to >1010 psig, .EF-V304 and B open, and emergency feedwater flow is indicated to control steam generator level to 50 percent on the operating range. d. If the emergency feedsystem fails to respond, refer to. - 7
e.
Turbine is tripped and both generator breakers open. 3.0 s
1202-2 Revision 6 2. Close or check closed MU.V3. 3, Restore makeup and seal injection as follows: a. Take manual control at the hand auto station and close MU-V32 and MU-V17. b. Verify that lube pump (MU-P3A) is running, c. Open MU-V14A, close MU-V12. d. Start MU-PIA, DC-P1A and DR-P1A. e. Throttle open MU-V217 as needed t in or restore pres er level,at > 100 i$ f. If '~iT zer level con IID to decrease to less than hes, open MU-Y1 an or initiate high pressure nfhtionActuati saturation margin is > 50' F, when pressuriz s restored to 100 inches reset Manual Actua o a throttle MU-V a d MU-V16B. b.......__________ _Y____________ o'q)e pressurizer whicihopreservethe f)lotwater ! NOTE: This ac sto M 1 pwviding the mar saturation after o ressurizer eeded to keep pre level on scale, initiate PI "A" and "B". h. Slowly reopen MU-V32 to establish seal injection. 1. Adjust pressurizer level setpoint to match existing level (but > 100 inches), and place MU-V-17 in AUTO. 4. Verify the following:
a.
RC pressure stable or decreasing slowly, and RC-R-V2 and pressurizer code safety valves closed as indicated by the differential pressure indications on the discharge line. r-
1202-2 Revision 6
b.
~~Diesel generator voltage is between 4000 and 4200 volts and frequency is 59 to 61 hertz.~~
c.
Verify that the RCS is subcooled by at least 50*F as l indicated on the saturation racgin meter. If margin is < 50*F increase steam generator level to eng natural l circulation cooling until 50*F margin i d. l Increase makeup flow to maintain pr 4rlevel constant. d. Veri at reactor power i than 10 percent within one te or commence e boration. e ument air compre or ing IA-P1A or B. h_........_____________....___ a ! NOT_- If ES has been ini the instrument air compressors.wil d out. Refer o EP 1202-36. 5. If ES actuate fe o EP 1202-68. 3.0 FOLLOW-UP ACTION Objective: rocedure are t h the hot water in the The objectives s pressurizer in to saturation, ish natural circu-lation cooling with h removal through the steam generators, borate the RCS to assure the reactor remains subcritical, conmence cooldown at a rate determined by heat loss from the pressurizer and to restore power to RC pumps and pressurizer heaters as soon as possible. 1. Using the redundant indict '; ion if possible reverify the parameters in manual action that are indicated with an esterisk (*). 5.0 4 m..
1202-2 Revision 7 2. Declare an Unusual Event (carry out EPIP 1004.1). 3. Verify steam generator level is at 50 percent on the operating ~ range and that steam generator pressure is being maintained at 1010 psig. I ! NOTE: If Tave < 550* F or if RCS pressure is < 20 ig check for possible overcooling condition s s stuck open bypass valve or overfeeding cg 1 4. Dispatch an operator to the emergency f alve area with instructions to take manual co 1o FV 30A and/or B O if direc Q control room operat 5. Verif pr circulation by on 9 ore of the following m th l A NOT Indications o q ;ukeirculation ma not stabilize ! for 15 to 3 3 l w %*F l a) RCS at i to approximate 1 o 50*F and stab Th is <600*F. v b) C emperatures appr c uration temperature for \\1ywithin5 minutes). se ry side pressur no c) r fy heat removal from G's 1) Turbine bypass valve positions 2) Atmospheric dump valve positions 3) Feedwater valve position l 4) Feedwater flow l 1 NOTE: Heat removal from OTSG's may not be noticeable for low decay heat cases. 6.0 l
4_..-- 1202-2 Revision 7 d) Incore thermocouple temperatures stabilizes and is less than 600*F. ~ 6. Verify that the P, S, R and T 480V buses are energized and voltage is between 440 and 500 volts. Current indicated on I the console amp meter should be < 160 a to each us. 7. If 230 KV line voltage is available, obtain d ch concur-rence, reset any lockout relays on RBA, tation building panels and re-energize an aux i
~~nsformer, verify RCS greater than 1600 ps St one RC pump per loop pe~~
'h and place pr ssuri heater controls in D aut 1 p s not available h OP 1102-16, Natural Circu-8. ion Cooling and cont u th followup action in this ocedure. ! NOTE: Primary re'ssure will dec pYoximately 1 1 70 to ur because of r heat loss. Coo must be contro ma ntain at least a5 beooled margin (Ver6fy mar in using incore ple temperatures as hot leg tempera-9. gal of 12,250 ppm or equivalent (906 cu. ft. of 8700 ppm) to the makeup tank to assure shutdown margin is maintained during cooldown. Open MU-V12 and, if necessary, close MU-V14A to get the boric acid into the RCS, Verify baron was injected into the system by observing the decrease in Make-Up Tank level. 7.0
1202-2 Revision 7 10. Open MU-V14A and close MU-V12. Makeup for additional RCS contraction from the BWST thru MU-V14A. ! CAUTION: Do not exceed 3 MW load on the diesel generator. 11. Verify or start the following ventilation fans: a. Emergency feed pump room AH-E-24A, or AH-2 b. Decay Heat /Nuc Service Closed Pump ro A or AH-E158. c. Screen House AH-E-27A or B. d. Die e tor Fans AH-E-29 mLJH-E-29B. e. wer ventilation. D Air compressors A - 8A/ and AH-P-9A/B. 2. Chilled water 3. Standby i{ 4 AH-E-N _ 5. AH 7A B. I 6. -9'A or B. 12. Verify or s tb4 following c Nuc Services River -PIA (B)(C) b. e Nuc Service Closed Pump NC-PIA (B)(C) l l c. One Secondary River Pump SR-P1A(B)(C) l d. One Intermediate Closed Pump IC-P1A(B) l l e. One Spent Fuel Cooling Pump SF-PlA(B) f. ,0ne Penetration Cooling Fan AH-E9A(B) 8.0
1202-2 Revision 7 13. Pressurizer heater group 8 or 9 may be powered from the diesel. Refer to EP 1202-29 for procedure for transfer of the gr'oup to the ES bus. ! NOTE: a. If one diesel has failed, do not put pressurizer i heaters on the ES Bus. b. If pressurizer heaters are on ES Bus an diesel fails, take the pressurizer he o the ES Bus. c. Do not put both groups of pressur a s on ES Buses at the saa time. d. Transfer of a heater group to should take place within two hours. if needed I to p ntain saturation mar {. M eh Ul cannot be perfor D e to diesel loading, ! NOTE: oti ' the airport con 1t r that the aircraft &c. g lights are out. g gize the N bus % 1-02 breakerA 14 c Do not exc g O n either diesp hE?reUp or. ! CAUTION: 15. Start SC vide turbine lu ling. ! NOTE: M M feeder break hMusmustbetripped be rJ9the tie can be sed ^ V d 16. Ene ze the IC and IJ 480V turbine plant bus through the tie to the 1N 480V bus per OP 1107-2. The following equipment is energized without operator action when the tie is closed, a. Aircraft warning lights on cooling tower. b. Feed pung turbine turning gear 'if the feed pump has stopped. i 9.0
1202-2 Revision 7 17. Verify that the main turbine turning gear starts and engages when the main turbine coasts to a stop. 18.- If reactor building temperature exceeds 140*F, provide cooling as follows: a. Open RR-V4B and start RR-P18. b. Open RR-V1B to provide cooling water reactor building cooling units. c. Start AH-ElB. A ! NOTE: If pe d by diesel loading ifhrentreactor ~ buil ing may be selec 4.0 LONG TERM 1. samples per OP 1 to determine boron entration and ac it T els. 2. Continue cooling natural circu].a ton cooling (OP 1102-16) unti h te power is resto Ra N of cooldown may be det available con d a r emergency feed. l 3. When o( power is restored, the 4KV ES busses Auxiliarytransbdasfollows: ba t " Verify 1A(B) Dies n Voltage Control". Set at 43.0 percent. This must be done before switching exciter to manual. B. Place the exciter droop switch in PARALLEL l position. C. Place the droop knob on engine govr.nor at 70 I percent. 10.0 i
1202-2 Revision 7 D. Place Diesel Generator "lA(IB) Diesel Exciter" selector on Console CR to the " Manual" position. E. Place the synchroscope into operation by placing the switch to the imediate right of the "15B-D2 (lSA-E2) Bus lE FEEDER" control switch to the "0N" position. F. Match IE Bus voltage with systentT6%t (Read from the two voltmeters to the i e1* eft of chroscope) using the (1 lesel Man. Voltage 1". A 5 b tek,'[areconnectedtothe ! NOTE: One 15meterreads 1tage and the other DG 1 ly 1 1 ge. They automa ic breaker as th y scope. g Y G. Adjust iesel Gen. Gover br" control until th chro cope is moving sT the " Fast" ct (clockwise), g slowly and at
~~00 o' clock or 5 t o~~
he synchroscope dial, ose 158-02 (1 hift load from the Diesel to the Aux Tran per OP 1107-3. v H. Place the diesel generators in ES standby per OP 1107-3. 4. Stop the diesel driven fire pumps and place tum in standby per OP 1104-45. 5. Start one RC pump per loop per OP 1103-6 to assure boron equalization. Repeat RC samples per 1104 43. 11.0
--....a-.... 1202-2 Revision 7 6. Stabilize plant conditions, establish circulating water, draw condenser vacuum and commence feedwater cleanup per applicable operating procedure. 7. Restore pressurizer heaters power supply back to normal per i 1202-29. s 4 s 'J 9 v C g 12.0 l
~~m. _~~
1202-2 Rev: ion 7 A1TACHMENT 1 Actions for Failure of the Emergency Feedwater System A. Failure of EF-P1 to Start. 1. Verify that MS-V2A and MS-V2B are open. 2. Verify that CO-V10A, CO-V108, EF-VlA and E V Are open. 3. Press the OPEN pushbutton for MS-V13A V Vi 8. 4 If EF-P1 fails to start press the C $ button for MS-Vl3A MS-V138, and place EF-P Auto Start switches in d 5. p rgAux Operator check 1 ly that EF-P1 overspeed trip rjtetandthatthe Operator for MS-V6 is in the open position. 6. After verifyin 1 overspeed tri is reset and MS-V6 Manual Op to is pen to remove e EF-Auto Start switch EAT. B. Failure of EF-PEA -P2B to Start. h\\y t the alterna ol switch is in Pull to Lock. 1. 2. that there is vol vailable at the associated bus. ! NOTE: With an ES signal present there will be a 20 second 1 delay in pump start. 3. Verify that control power is available as indicated by the green indicator light at the control switch. 4. Manually start the ' pump using the control switch. 13.0 i
1202-2 Revision 7 ! NOTE: If EF-P1 and either motor driven pump have started any i further investigation may be performed when plant conditions become stable. 5. Check locally for targets on relays located at the switchgear. I 6. Use the 69 bypass key and attempt to start the pump locally. C. Failure of EF-V30A or EF-V30B to Open. 1. Check steam generator level to determine w e pen signal is required. The valves should b h ,f steam generator level is <30 inches on th range (RC Pumps on) or < he operating rang umps off). 2. Veri
~~aQ-V30A and EF-V3~~
$n Auto Stations are in AUTO. 3. If e valves have failed h ope place the Hand-Auto Station \\[ w HAND and attempt to p valve. 4. the valves have e d, attempt to en using the backup Manual nt tation located ontrol room. 5. If the valv ar till not open, h +h ux operator take local h ee ontrol of the 1 s no open them as dire he control ro o. M h 0. No Indicate,d No ow Flow) with staas ge ator level below setooint. V V y that EFP discharge pressure is higher than steam 1. V 1 generator pressure.. If not turbine header pressure setpoint may be reduced to get additional flow. 14.0
a 1202-2 Revision 7 2. Verify that the following valves are open: EF-V2A EF-V2B CO-V10A CO-V108 Have Aux Operator check locally for pump malf nc ignjand 3. correct lineup of Manual Valves. p 4 0+@e o <t 4 v 4' O g 15.0
E"f2&VE =aE.NEoUNIT I ORY str'iiftin'13 08/11/81 THREE MILE ISLAND NUCLEAR STATION C T. ~ tr3,@ g g. #0'.% >' UNIT NO.1 DTRGENCY PROCEDURE 1202-5 OTSC TUBE LEAX/ RUPTURE ~ Table of Effective Pages {Q f R T L [, Page Revi sion Page Revision Page Revision Page Revis ori 1.0 12 2.0 13 3.0 12 4.0 12 5.0 12 6.0 13 7.0 13 s 8.0 13 9.0 13 10.0 13 11.0 13 1 N %'9 @J c.sN a %a x 2 b [ ,d\\ Unit 1 Staff Approval \\ Approval ( ) s C 06pt. Head \\' Unit 1 PORC Rec cpends Approval o P () /M Date 2 kJ Chairman of PORC Manager I Approval Dateb-fl~Sl /) ~ V QA Modifications / Operations Mgr .$h Date Document ID: 0029H FOR USE IN UNIT I ON Y
l 1 l
~~OR USE IN UNIT I ONLY 12$;5 n 1, THREE MILE ISLAND NUCLEAR STATION UNIT NO. 1 EMERGENCY PROCEDURE 1202-5 OTSG TUBE LEAX/ RUPTURE Section I: A'utomatic Reactor Trip Has NOT Occurred.~~
~~1.0 SYMPTOMS A. Decreasing reactor coolant pressure. B. Decrease in pressurizer level. \\\\ C. Make-up tank level decreasing. v I D. Make-up flow increasing. y~~
E.
~~RM-A5 off-gas monitor alam/ alert /increa d cong; rate. (~~
r.
~~Secondary sam (nWsis indicates act vit n the secondary side. Possible increashf water level in da G. OTSG. 4,% '. \\$~~
H.
~~Increase 'nunthateonSteamLi Radiation Monitors. 2~~
~~Unique symp(4fbf the Tube Rupture, d~~
d m N') 2.0 IMMEDIATE AClH NS [\\ s' %'" k A. Automatic Action N -y. h 1. MU-V-17 will ,P ~ egen *g compensate for reduced,' pressurizer level, f gQ Qs 'v 2. PZR heatersjyty energize to maintii?FRCppressure. B. Manual Acti'ao C b 19 k Tn~dicates a key parametey hich requires (An as r1 s N/ V reverifi hon as a follow-up action.) 1. If an automatic reactor trip occurs while in Section I, proceed to Section II of this procedure inriediately.
2.
If any one of the below conditions exist, imediately begin reducing load at 10 percent per minute.: 1 a. Make-up tank level is decreasing at greater than 10 gpn (1 inch /3 minutes). 1.0 FOR USE IN UNIT I ONLY
FOR USE IN UNIT I ONLY H$;5,n 33 b. RM-A-5 and/or Steam Line Radiation Detectors have confirmed alams and pressurizer level cannot be maintained at 220" by MU-V-17. NOTE: If only RM-A_5 and/or the Steam Line Radiation l l detectors are in alam, an evaluation must be made to ' determine tube leak rate and radioactiv release rates. Unit shutdown may not be required tube i leak rates less than 1 gpm.
3.
Close MU V-3 and start an additional make-g and open Mevelgreater MU-V 217 as necessary to maintain pre u than100ih. (o NOTE: . _V-3 closed, MU-V-14 ust be opened as , up tank level detYeasep to below 55". 1 \\ C. Follbw-Action Objective: A b w c This procedure is d .d ttr expeditiously geol dawi and h Joutliftingsteam depressurize the n tmospheric pre sq s-relief valves t necessarily steamin a ected OTSG in order to minimizeT ( e releases outs' e containment. This is accomp e6-isolating the affes OTSG when RCS temperature is below 540' and minimizing saturation margin to reduce the primary to secondary aP. Affected OTSG 1evel is to be maintained < 95 percent on the operate range to prevent water carry over to steam lines until primary pressure can be lowered such that the secondary pressure is controllable below the steam relief valve setpoints. 2.0 FOR USE IN UNIT I ONLY
l FOR USE IN UNIT I ONLY g;s,, 1, 1. Re-verify those immediate manual actions marked by an asterisk using alternative instruments if available. .._______..._________..________________________________m.. NOTE: If primary to secondary leakage is > 1 gpn an Alert shall be declared in accordance with EPIP 1104.2. I NOTE: If primary to secondary leakage is > 50-~fp. a ite Emergency shall be declared in accor WYnEPIP 1004.3. 2. Centinue to reduce power to les percent at 10 pere g minute. l __.._________.4 %._____.__________....____ '(faetWen choving the first $'am fed from the affected trThed pump, remove the NOTE: i pump that is being ste 4G if known. Remdve'the" feed pump per OP 1102-10. __.,,..______. _____ m ~.__.. ________ ________.___... By sampling OT eying steam lines, observation of (\\ OTSG 1evels a / rates,etc.de affected 0TSG. _____..._____.... A __.s._______..._______ NOTE: Affeck 'd should indicat Q M erlA qvel,24lower nd CS g r higher Be k Ga ma', HJ, fe9@r n Na I sampleresy ~)th turbine bypass valve 4 Op oximately 0 MWe N anual, controlling ste(m pressure, trip the turbine n generator. Verify generator breakers open and turbine stop valves closed. CAUTION: Adjust turbine bypass valves as necessary to pick up ! additional steam flow from turbine and not challenge ! main steam safeties. 3.0 FOR USE IN UNIT I ONLY
FOR USE IN UNIT I ONLY g;5,, 1, 5. Verify turbine bypass valves in manual and' manually trip the reactor. l 6. Reduce RCP's to one pump per loop. NOTE: Keep RC.P.1A on for PZR spray. 7. Turn off PZR heaters and manually start pr er spray to depressurize RCS and reduce subb ed kCSpressure margin to 20* F as soon as possibl wh is greater than 1600. Maintai[0* rMbcooling below 1607 [\\h (h \\ 8. trbo Jupction with above step anually control turbide bypass valve th opin a 100* F/hr. cooldown ggN*Fsubcooledmarginwhen /' rate while maintain r. above1600psj tain RCS conditions within ~t pressure tectperatype curve. 'M) { f.: ___________________._ m__,_f._...... _____. g__ _\\ e,.____ NOTE: Step bbdfSG's to reduce 3S3o Y ss than 540' F. s.______..__________,.______4__________..__ 9. W temperature les h F, isolate the facted OTSG by closink ' v -V-1A and B or C and D NOTE: Assure MFP is being fed from unaffected OTSG or Auxiliary Steam. FW-V-17 A or B FW-V-5 A or B FW-V-16 A or B 4.0 FOR USE IN UNIT I ON _.Y
~~OR USE IN UNIT l ONLY~~
$2;5,, 12 FW-V-92 A or B FW-V-85 A or B ~ EF-Y-30 A or B t15-Y-85 A and B or C and D MS-V-13 A or B (close manual hand wheel) l b MS-V-10 A or B y MS-V-3 D/E/F or A/B/C K ______________-_______________________________ q _ %.__.___________ NOTE: Affected OTSG must be steamed t . in less than l 3 i 1000psigandlessthan95pegentonoperaterange. i ...______-_____-__-sp
~~10. Maihai~~
~~F/hr.cooldepi1Ke.~~
\\9,N 11. S pressure is being cont, rolled, bypass ESAS at mal bypass pres et tpo'nts. At 1600 psig, rge yfssurizer spray 3to obtain a 50' F saturationmik ( Terminat %m & ~; 13. charge from IWTS a K WFSsuntil monitoring U \\N i r e and ptihtro reestablishedA owdance with HPP Open breakers fo d lowing sump pumps to @ 01 discharge to t (IWFS): Unit MCC Turbine Bldg. Sump Pumps SD-P5 10E ID Turb. SD-P2 A IC IC Turb. SD-P2 B 1E ID Turb. Powdex Sump Pumps SD-P1 A 4D 1A Turb. SD-P1 B 4D 1R Turb. 5.0 FOR USE IN UNIT I ON _Y
FOR USE IN UNIT I ONLY g;5,, 13
~~14. Notify Health Physics to begin survey of the Intennediate and Turbine Buildings to determine the need for controlled areas.~~
~~Initiate Emergency Flan if required, as a result of the surveys.~~
15. Notify Unit II Control Room to isolate auxiliary steam cross connect by closing AS-Y-23 and its g S-V-209.

16. The affected OTSG must be steamed on1 e ssary to 3
maintain level < 95 percent on thee- ' rat range and OTSG pressure below 1000 psig. Aftprkthe mary pressure is low [wg that the secondah h sure can be <x centrollpd and maintained beTow4000 psig, it is i A \\h ge9 table to secure stea%ng the affected OTSG and completely fillMthe es up to the applicable MS-V-1 g {-. (\\ valves. _______________________p.l__%),,_____________.__ _ _______________ NOTE: Under ptse?gency situations, blac' ling / pining of MS i hangers @twhenjflooding the applihble,MS lines is not i i ne sa If the MS lines _ase iW ed without i b g/ pinning of the M5 h , an engineering i i v ion of the struc,tutah egrity of the MS ust be perfonn d r 'to resumi ig normal i V 17. oldown at 100* F per hour on the unaffected OTSG using CP 1102-11 (taking exceptions for only one OTSG).
18. When on DH Removal, depressurize RCS to vent header pressure per GP 1104-4.

19. If OTSG tube leakage exceeded the limits of Tech. Spec.
3.1.6.3, an unscheduled inservice inspection of the affected OTSG must be conducted prior to startup pursuant to Tech. Spec. 4.19.3.C.1. 6.0 FOR USE IN UNIT I ONLY
9
~~OR USE IN UNIT I ONLY g2;5,,,,~~
~~Section II: Automatic Reactor Trip Has Occurred. 1.0 SYMPTOMS A. Dec'reasing RCS pressure. B. Decreasing pressurizer level. C. Decreasing Make-Up Tank level. D. Increasing Make-Up flow.~~
E.
~~RM-A-5 off-gas monitor alarm, increasing count r F. Possible increasing water level in damaged 0~~
G.
~~Increase count rate on Steam Line Radiati Mon 1 hrs. H. Reactor trip - r trip. \\~~
~~Unique symptoms of _~~
l leak. V V, \\\\ IMMEDIATEACTIOkQJ h s 2.0 // v yy A. Autoca Actions. w 1. R or trip isolat 202-4. 2. MU-V-17 opens n ) PZR level. to maintain pre,ssu(N s re -// 3. PZR heaters e e A jN V 4. Possible (SA,SSif pressure decreasas to 1J00 psig. ManualActioh\\ B. QfpKgetor trip and turb(gt)p. t
1.
Ve
2.
Veri U-V.3 is closed, and start additional make-up pump; open MU-V-217 as necessary to maintain pressurizer level greater than 100 inches. l l 1 NOTE: With MU-V-3 closed, MU-V-14 A/B must be opened as make-up tank level decreases to below 55 inches.
3.
i If ESAS auto actuates at 1600 psig: i a. Immadiately trip RC pumps. 7.0 FOR USE IN UNIT I ONLY
FOR USE IN UNIT I ONLY g;5,, 13 b. Verify that EF-P-1, EF.P.2A and EF-P-23 start and discharge pressure increase to > 1010 psig and flow (as required) is indicated to each OTSG. c. Take manual control of EF-V-30A/B on affected OTSG and maintain 30" on s/u range. d. Take manual control of EF-Y-30A/B on una e TSG and manually raise level to 95 percent. C. Follow-Up Action hbM' Objective: b The objectivek% %2 procedure is te oldown and depressurize RCS to atmosp lm(q]h \\ D ressure (on forced fT it possible) as quickly as ak possitAe
~~f imize radioactive r ses outside of containment.~~
// t% Thi bit accomplished by is a he affected OTSG when RCS y A temperature is below 5 $ minimizing the_Jaturation margin to C Affec y GT50'N reduce the primary on ary aP. Tevel is to be D.O 8 maintained < 9 g o prevent wate.ca,rry pver to the steam lines until trdypressurecanbelo. -such that the secondary pressure o'dtrollable below t steam relief valve setpoints. D 1 Rhferify those imedia ual actions marked by an sterisk using alternate instruments if available. i NOTE: If primary to secondary leakage is > 1 gpa but i < 50 gpm an Alert shall be declared in accordance with EPIP 1004.2. NOTE: If primary to secondary leakage is > 50 gpm a Site i i Emergency shall be declared in accordance with EPIP i i 1004.3. i 8.0 FOR USE IN UNIT I ONLY \\
~~OR USE IN UNIT I ONLY s202 5 Revision 13 2.~~
Reduce RCP's, if running, to one RCP per loop. NOTE: Leave RCP 1A in operation to provide spray. 3. If RCP's had been tripped, verify Natural Circulation. 4 De-energize pressurizer heaters. 5. If ESAS actuated, verify HPI injection. r 1 HPI and start one RCP per loop as soon as RCS p control is 7 established with at least a 50' F ma rgi n. / O NOTE: Moni total make-up flow whafntain >80 gpm per i t i push a MU V.36 and MU-V 37 ff'needed to provide i s \\s / N CAU7fd.. \\ ..______________r Be[ause MU-V-12 ig't+dsed/ monitor make-up tank level ' l i t(: i sV and pressure to avMdQffting the make-up tank relief ' valve (MU V _________________________-RV , g g i N m s 6. Taking manv % son 1 by turbine bypass vahes, establish F q \\ ( \\ and mai tatnjl00* F per hour rao.l'dc'wrNate (steaming j V ds both s),toanRCStempkatucahf<540*F. m \\ )do,1 rate, depressurize 7. .c e with establi 4)ctol ( TCS using spray, if 'R, 'a)re running, or open the PORY. Depressurize the RCS as rapidly as possible, maintaining at least at 50' F saturation margin. 8. Confinn affected OTSG [i.e. sampling (refer to Attachment 1, to override containment isolation), surveying steam lines, observation of OTSG 1evel and feed rates]. 1 NOTE: AffectedOTSGshouldindicatehigherwaterlgvel, logrfeedrate,angrhigherBeta-Gamma,H, 1 1 nag, I-133 and CS-sample results. i FOR USE IN'0 NIT I ONLY
FOR USE IN UNIT I ONLY g;s,, 13 9. With RCS less than 540' F, isolate affected OTSG by closing: MS-V-1 A and B or C and D 1 NOTE: Assure MFP is being fed from unaffected 0TSG or i i Auxiliary Steam as necessary. i _u...__.__.. FW.V-17 A or B FW.V.5 A or.B ( FW.V-16 A or B p Na FW-V-97 7 r B (j I' ) FW-V o B N\\ \\8 30 A or B @ RS A and B or ) MS-V-3 D/E/F or C 7 f.4\\ ........ ___..__________.__.,_ p _..____....___ _ q._____________ l NOTE: MS-V-3 D a'rejrem A OTSG. ".....Q___.___...__.__.! s -dtclose manual hh ee.1) MS-Y mss I or B V 10. a_fhetedOTSGmust ayed only as necessary to ain level < 95 perce t4n operate range and OTSG at pressure below 1000 psig. After the primary pressure is lowered such that the secondary pressure can be 10.0 FOR USE IN UNIT I ON _Y
FOR USE IN UNIT I ONLY 5;L, a controlled and maintained below 1000 psig, it is acceptable to secure steaming the affected OTSG and ~ completely fill the MS lines up to the applicable l MS-V-1 valves. 1 NOTE: Under emergency situations blocking /pinnik f MS i hangers when flooding the applicable M .es s not i i nece ssary. If the MS lines are fille t u 1 blocking / pinning of the MS hangers .gMeeri ng i evaluation of the structural integkty,f) the MS i 1 lines must be perfomed prior t \\gg nomal cperations. \\ (N D t.2d 0TSG. \\g s s .6fRCP'srunningkn Pl throttled, follow CP 1102-11 takin ons for only one OTSG. p nd RCS pressure f less than b. HPI unth secondary sure follow EP If52WBj
~~12. Termina 4 arge from IWTS/%F t0 monitoring and y~~
N N/ cont are established ingcMance with HPP 16f!B. kers for the f qt g ump pumps to control argetotheIWTS! d4 Unit MCC Turbine Bldg. Sump Pumps SD-P5 10E 1D Turb. 50-P2 A IC 1C Turb. SD P2 B IE ID Turb. Powdex Sump Pumps SD-P1 A 40 1A Turb. SD-P1 B 4D 1B Turb. 11.0 FOR USE IN UNIT I ONLY ~
OR USE IN UNIT I ONLY 1202-s Revision 13

13. Notify Health Physics to begin survey of the Intermediate and Turbine Buildings to determine the need for controlled areas.
~~Initiate Emergency Plan if required, as a result of the surveys. 14 Notify Unit II Control Room to isolate auxi ry steam cross connect by closing AS-V-23 and its [ AS-V-209. ^~~
~~15. When on DH Removal, depressurize t vent header pressu er CP 1104-4.~~
16. If leakage exceede mits of Tech. Spec. 5 'N n unscheduled inserv <e inspection of the 7 Mected OTSG must be etnahted prior to startup My pursuant to Tech. pectw.19.3.C.1. (s dc ts %g .h 'h /P 4 ? N di s> c 12.0 FOR USE IN UNIT ! ONLY
FOR USE IN UNIT I ONLY 1202-s Revision 1; ATTACHMENT 1 Criteria to override Containment Isolation Signals 1. Containment isolation valves may be opened to obtain samples in accordance with approved procedures. The isolation valves shall be reclosed after the sample is obtained. 2. Other containment isolation valves automatically closed s ain closed until the following conditions are met. a. Reactor building pressure is less than 2 ps b. Containment radiaMon levels have been sedYasedon 4 v radiationmonder ngs or samples > s,f t e system outside the).; reactor building has been '\\ \\Q c. The integp oj) "N v ed.k,flesurgetank ethisualinspectionor asse J test should be codd'erep to verify integrity). pres (n L.' Director shao d. The Shift Supervisor or(. ency permission to re-open containckisol't/ tion valves. V ) Installee raetat,5oOytors or portabg ccs sha11 de e. available to tek any release that ni Iqstrlt from opening the <Q, d val ve. &.e- - N .) g'> b FOR USE IN' UNIT I ONLY J}}

ML20037B537

Contents

Text

;ib=r

==s =1

_ = _- _=- : :: _ _ :.= _- ; =a===

= =

~. '".. _-_ _ :- "- =":-=

r

':-

n

Navigation menu

ML20037B537

Text

;ib=r

==s =1

_ = _- _=- : :: _ _ :.= _- ; =a===

= =

~. '".. _-_ _ :- "- =":-=

r

':-

n

Navigation menu

Search