ML20064G653
| ML20064G653 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 12/07/1978 |
| From: | Gilleland J TENNESSEE VALLEY AUTHORITY |
| To: | Varga S Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7812120158 | |
| Download: ML20064G653 (10) | |
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330 Power Suilding Director of ';uclear Reac:: Regula:icas attention:
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)50-32S Encl 0:!ed is 5equoyah Suclear Plant Abnormal Operating Instruction (AGI) a01-1 for reactor trip which was requested by Dr. Eencrova, Branch Laie:. c:. :ne a.ux1Aiary Systats aranen, euring the i.a/,.RC neering 2
of Cctooer,.
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i n:.s av. 22 cresses tuue use o:. tne auxillary
.u feedwater systes, icur representative is invited to observe the preoperational hot functienal :est of the auxiliary feedwater sy.2:en which is scheduled for January 11, 1979.
If this date changes, we will info n :i. Silter af ycur s:aff.
'lery trul:, ycurs,
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AOI-l Punchlist Page 1 of 1 Rev. 3 Reactor Irip Report Charts, etc., to be attached to trip report has not been determined ye:.
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I A01-1 "ni:s 1&2
? age 1 of 5 1
Rev. 3 REACTCR TRIP I.
SYMPTCMS 4
l A.
The reac:or say be tripped by ane or more of the following:
5 1.
Source range hign flux (10 CPS, 1/2). Manual block above P-6.
i 2.
Inter:edia:e range high flux (25 percent power, 1/2). Manual block.
above F-10.
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Power range high f _ tx, low se: point (25 percent, 2/4). Mancal block i
above F-10.
4 Power range high flux, high se: point (109 percent, 2/4).
5.
Power range high neutron flux rate:
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Positive rate (5 percent of full power in 2 seconds, 2/4).
b.
Negative rate (5 percen: of full power in 2 seconds, 2/4).
6.
Ov.trte=pera:ure A T.
(2/4) 7.
Overpcwer aT.
(2/4) i S.
Low coolant flow, < 90 percent (1/4 l' cops when above P-3 se:poin:
of 35 percent pcwer.
2/4 loops when < 35 percent power but above P-7).
9.
Underv.oltage on 69CCV unit RC? busses (4S30 volts, 2/4) above P-7.
10.
Underfrequency on 6900V uni: RCP busses (So H2, 2/4) above P-7 11.
High pressuri:er pressure (23S5 psig, 2/4) a 12.
Low pressurizer pressure (13c5 psig, 2/4), above P-7.
13.
Pressurizer x'.g-I-vel (92 percent, 2/3), above F-7.
14 Stes: Flow /Teedwater Flow mis =2:ch coin.cident with low S/G level (Stes: Flow > Feedwater Flow 2 33% SG rated seca: ficw, 1/2 on one P'
S/G and <_ 25 percen: level, 1/2 on sase S/G).
si 15.
Lc-lo S/C level (610 percent 2/3 on any one S/G).
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16.
Safety inje:: ion.
tJ Turbine trip, above F-7.
17.
- - - 18.- - - Manual trip, 1/2.
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A01 Units 15 2 Page 2 of 5 Rev. 3 II.
AUTOM.ATIC ACTION A.
Turbine trip - reac:or trip 3.
Auxiliary feeddwater pt:ps star: on lo-lo s:ea: generator level.
C.
Generator breakers trip, 6900V uni boards auto transfer.
D.
Automatic stea: du=p actuation.
E.
Stea: genera:or feedva:er regulator, regulator bypass, and =ain feed-water isolation valves close at 554*F III. D'MEDIATI OPERATCR ACTION A.
Verify turbine trip - reactor trip.
1,.
All rods in - Escrgency bora:e 1"9 pp: for each rod not. fully inserted.
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2.
Turbine stea: stop valves closed.
Deter ine reactor coolant syste: status.
1.
Auxiliary feedwater pc=ps running.
2.
Pressurizer pressure and-level within expected range. (1900-2235 psig). (24-60 percent level).
3.
Tavg controlling to 547'F.
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Contain ent pressure and :e:perature acr:al (-0.1 psid +0.3 psid)
(85-100*F. upper cc:part=en:, 100-120*F. lower cc: par::ent).
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5.
Generator breakers open, 6.9-kV unit sta: ion service transferred.
6.
Sten: generator reedwater regula ce, regulator bypass, and =ain iao-latica valves shut.
C.
Announce, " Reactor Trip".
?RICAUTION: Auto =atic controls are not to be placed in anual unless it is apparen: the aute=atic action has failed.
If a control L-is placed on anual, i: zust be checked frequently for proper
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A01 Units 1&2 Page 3 of 5 Rev. 3 k
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l A.
If the reac:or trip is a result of safety injection syste actuation, refer to EDI-1, " Loss of Reactor 2colan:~'; E31-2, " Loss of Secondary
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Coolant"; or E01-3, " Steam Generator Tube Failure".
If the trip is a result of a power blackout, refer to E01-5, " Station Blackou:".
1 B.
'*erif y proper auto atic actuation of the au.xiliary f eedwater syste:.
(1) the two :stor driven and one steas-driven feed pumps started, 1
j (2) level control valves open, (3) flow to each steas generator of 440 gps or being =odulated to aintain levels at 33 percent.
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1.
If only one (1) motor-driven auxiliary feedwater pu=p is operable to deliver water to :he stea: generators, the reactor coolan: pu=ps should be stopped and MSIV's closed on loops without feedwater tiow.
t CAUTION: The reactor coolant pu=ps should be stopped only after it I
is certain that other auxiliary feedwater pu=ps cannot be placed in servi:e apd 1 sinute after lo-lo level is reached j
in any steas generator.
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j 2.
Should any steam generator (s) have steam pressure indications ab-no r:a ll-low with respect to the other steam genera:or(s), auxiliary feedwater flow :o the steam generator (s) having the aonor: ally low I
pressures should be diver:ed to the steam generator (s) having a hign pressure.
i CAUTION Se aware of ICS psi 4? safety injection signal.
3.
Auxiliary feedwater should be controlled to bring :he steam generator levels back to the normal no-lcad value of 33 percent and :o keep Tav; slightly above the no-load ralue of 547*F., (The te:perature should ne:
be allcwed to go below 5 7'F).
If the need for auxiliary feecwa:er is asscciated wi:h an accident discussed in one of the detailed energency instructions, the procecure in those instructions should be icilcwed.
1 C.
If the :ain f eedwa:er system is available, =anually operate the =ain feed-vater system as re; aired to Saintain steas genera: r water at 33 percent level.
i 1.
Transfer control of the :ain feedwater pu=ps and the feedwater control valves to manual.
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2.
Zero the feedwater control si;nal.
3.
Manually rese: the feedwater isolation. Open sain feedwater isolation va.ve.
L1 4
Vary feefwater pu=p speed and the feedwater regulator bypass valve po-sition as required.
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A01 Units 152 Page 4 of 5 Rev. 3 IV.
SUBSECCENT CFERA!CR A Ti:N (Cont.)
C.
5.
If Tavg cannot be :aintained > 547'? and/or level at 33," in stea:
generators with =ain feedwater pumps, rransfer to auxiliary feed-water pu p centrcl.
CAL' TION: Particular care cust be taken to avoid feeding water to the stea: generators too rapidly at zero load in order to avoid cooling the reactor coolant below 547'F.
' 'h e a core decay beat is low, rapid feeding of the stea: gen-I erators can cause large reductions in reactor coolant syste te perature.
CAUTION: Rapid feeding of water into one s:ca: generator =ay result in pressure differences sufficient to initiate safety injection by stca: line high d ?.
D.
The stca dump control should be transferred to the =ain steam header pressure control : ode, and the set pressure adjusted to hold a stea pressure of 1005 psig.
NOTE: In order to conserve stea: generator water, the set pressure should not be adjusted below 1C05 psig even though the reactor coolant te perature ay rise considerably above :27'F. until it is deter ined that the stea: generator water sevels in operable stea: generators are no Tcnger falling and are above 20 percent level span on the wide range level recorders.
E.
Verify the containment ventilation syste is no r=a l. Three coolers operating in,each co= par::ent, upper and lower.
F.
Transfer NR45 to SR and IR.
Maintain C.
Verify normal pressurizer pressure of approxicately 2235 psi;.
pressuri:er level at 25 percent for zero load.
H.
As :ain turbine s;eed approaches 1300 r/ sin, verify auto s: art of bearing lube oil pu=ps.
As speed approacnes zero, start bearing oil.ift pu ;s and place turbine on turning gear when s:oppec.
i J.
Establish and maintain hot standby conditions. Ref er to G01-4, " Plant at w.
Hot Standby with Xenon Present."
'a' hen the cause of the reactor trip has been determined, cc plete the LJ K.
Reactor Trip Re port, Appendix A.
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If the cause of the trip cannot be corrected and it is deter inec to be unsafe to :sintain the plant in a hot standby condition, proceed to the cold shutdcun condition; refer to G01-3, " Plan: Shutdcwn fr:: Minicus Load to Cold Shutdown Condi: ion."
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ACI-! - L* nits 1 5 2 Page 5 of 5 Rev. 3 S..-. ql..,.,, - - u... R a....,,,
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If the cause of the reactor trip can be correc:ed, the plant may 1
be returned :o operation. Refer to CCI-2, " Plant Startup Fros Hot Standby to Mini =un Load.
V.
DISCUS 3 ION The reactor is : ripped by deenergizing tne control and shutdown rod drive mechanisss, thereby allowing the rods to drop, uni =peded, into the reactor core.
A reactor trip cay be initiated autc=a:ically by the reactor protectica systes or =anually by the operator f roc the control room.
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ACI-l - Units 152 Appendix A Page 1 of 2 Rev. 3 REACTOR TRIP REPORT Unit No.
Reactor Trip No.
Date i
SI actuated yes no Tise CAUSE Operator Error Equipsent Failure Safety Systes Other PLA.W CONDIT!CNS (Prior to Trip)
Rx Mode (1 thru 6)
Rx Pressure Rx Power PRZ level Steas Flow Tavg Feedwater Flow PLANT EVOLUTICS (Prior to Trip)
Starting Up Shuti!ng Down Steady Operation Systes Test Power Charge Cther CENERATOR Synchronized Yes No.
Output We NOTIFICATIONS
~ Chemistry Lab at Health Physits Lab at i
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Operating Supervisor at C
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I A01 Units 1 & 2 Appendix A Page 2 of 2 Re v. 3 3RIEF DESCRIPTION OF TRIP ATTACH TiiE FOLLC*'INO (Charts, etc. )
t Unit Operator
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