ML20100J325
| ML20100J325 | |
| Person / Time | |
|---|---|
| Site: | Shoreham File:Long Island Lighting Company icon.png |
| Issue date: | 08/16/1983 |
| From: | LONG ISLAND LIGHTING CO. |
| To: | |
| Shared Package | |
| ML20100J250 | List: |
| References | |
| 29.010.01, NUDOCS 8504100453 | |
| Download: ML20100J325 (25) | |
Text
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- $UBMITTED: (,)
[d ad-SP Nth! bed:
29.010.01 Y[ f APPdOVED:
Y AF REVISION:
4 (Plant Manager / f
//
I//4/ N EFFECTIVE DATE:
,' a EMEkGE!4CY SHUTDOWN kJ1EK6EhCY PRuCt. DURE M ( - l-f
2.0 SYMPTohS
1.1 Any of the following annunciators actuated, in addition to those designating specific cause of scram.
1.1.I kX AUTO SCxAM CHAN!iEL Al AND/Uh RX AUTu SCIUJ1 CHANNt.L A2 AND RX AUTU SCanM CnAhSEL b1 ASD/OK RX AuTu SCkd1 CnANI.EL b2 1.1.2 MAhUAL SCKAM SWITCH TRIP SYSTEM A AND t!AI.UAL SCRAM SWITGn TRAP SYSTr218 1.2 14utron/ power level rapidly decrersing.
2.0 ACYoMATIC ALTIONS:
rx b
2.1 All rods inserted.
2.2 Scram Discharge Volume vent and drain valves shut.
3.0 I!!!!Eu1 ATE ACTIONS:
II.ITIALS 3.1 Place the Mode bwitch in SnUTUULIN.
<4 3.2 Verify a rapid flux dect, ease.
3.3 Verify all control rods inserted.
If all rods did not insert, refer to SP 29.024.01, Transient With Failure to Scram.
3.4 Monitor reactor vessel level and if level can not be maintained initiate SP 29.023.61 level Control.
FEB 251985 1
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4.0 SUBSEQUr; tit ACTION:
4.1 Insert SnN & IkM detectors: switch april /KBM recorders to IKM's.
4.2 Trip the main turbine when it is nearly unloaded.
Af ter the initial water level transient (reactor water level has 4.3 reached a low and is >l2.5" and increasing):
4.3.1 If two feed pumps are running, trip one. Also trip.one condensate booster pump and condensate pump, in that order.
4.3.2 Take nanual control of RCIL and/or HPCI if they are,;
operating.
The scram signal should be reset and the CKD system returned to 4.4 normal, as soon as practicable:
4.4.1 Ascertain which channel caused the scram, bypass the
<t Discharge Volume high Level Scram and rrset the KP;S.
4.4.2 It scram cannot be reset, verify that the Scram Discharge Vulume vent and drain valves are closed.
the main turbine has been properly tripped 'by 4.5 Ensure that verifying the following:
- 4. 5.1 Turbine stop valves shut.
4.5.2 Turbine control valves shut.
()
- .5.3 Coubined intermediate stop valves shut.
4.5.4 Extraction line isolation valves shut.
4.5.5 Exciter field breaker open.
4.5.6 Buth generator output breakers open.
4.5.7 Turbine speed decreasing.
4.6 Verify that the Reactor hecire Pumps are running.
If not. restart the xeactor Kecirc Pumps.
4.7 It !!SIV's are open:
4.7.1 Maintain reactor pressure at less than 960 psig with the bypass valves.
SP 29.010.01, nev. 4 f-'S Page 2
\\j
Mestcra cnd maintain racetor v2ter leval betwasn 34" cnd l
4.7.2 4 2".
l' If decay heat is inadequate, shif t auxiliary steam loads l
4.7.3 to the Aux. Boiler.
j 4.8 11 MSIV's are closed and cannot be readily reopened:
Operate reactor relief valves as required to maintain 4.8.1 reactor pressure at less than 960 psig.
4.8.2 Operate RCIC and/or etPCI to restore and maintain reactor water level between 12.5" and 54.5".
4.8.3 lbnitor suppression pool temperatures and initiate suppression pool cooling as required.
conditions at this time. Prepare for startup Ecevaluate plant 4.9 from the apprupriate condition, or continue with normal plant shutoown, if warranted.
When the cause of the scrau has been determined and corrected, 4.10 obtain permission from the Operating Engineer or t.hief Operatirg Engineer to E!artup the plant.
,i-.
- ark all 1till* hit-603 recorders - time and date of scram.
4.11 5.0 FloAL CUSDITIUhS:
ready for restart or ready for continued shutdown under 5.1 Plant nornal shutdown procedures.
Log ti.e follo4ug information in the Control Room Log book:
5.2
[
5.2.1 Mode switch position prior to scram.
5.2.2 keactor power level prior to scram.
l 5.2.3 KPV pressure prior to scram.
5.2.4 Any control rods that did not fully insert.
k 5.2.5 Decay heat removal moce.
I' 5.2.6 Cause of scram.
l 5.2.7 Scram Ecport initiated.
=
I 5.3 Main turbine on turning gear.
x Reactor feed pumps tripped during this procedure on turning gear.
5.4 SP 29.010.01, key. 4 D
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6.0 DISCUbSION
6.1 An t.nergency Shutdown is an automatic reactor scram caused by RPS instruments fulfilling their design function or an operator manually scramming the reactor to mitigate an unsafe condition.
s
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6.2 A reactor scram may also be the result of an accidental RPS trip or a planned test.
6.3 This procedure provides information and instructions t'o' place the plant in a safe condition following any type of reactor scram.
6.4 The operator shall initiate a manual scram whenever an unsafe operating condition exists which cannot be immediately corrected. An unsafe operating condition shall be considered to exist when there is a situation such as:
6.4.1 Full Scram signal generated with no Auto Scram 6.4.2 loss of All hormal Power 6.4.3 Total loss of cooling water systems 6.5 Situations may arise which will allow control room personnel a f ew moments to prepare.for an impending scram. Any actions during this time period, which will reduce the impact of the scran on the plant and the system, bhould be carried out as time permits. The following list can be considered as a guideline.
j 6.5.1 kun the recirc pumps back to 45% in master-auto mode.
6.5.2 Switch the recire puup controllers to manual and reduce to minimum
<4 speed.
L 6~. S. 3 Trip one reactor feed pump, condensate booster pu:np and condensate
?
pump, in that order.
l-6.5.4 Start the main turbine motor suction pump.
6.5.5 liotify the System Operator.
6.6 If at all possible, maintain condenser vacuum as a heat sink for the Even if the reactor is isolated and KCIC/Rhk steam condensing is reactor.
in service, the condenser should remain available for use.
If RCIC, HPCI or ADS is used, the suppression pool may eventually need cooling as required by Technical Specifications.
I l
I A'J SP 29.010.01, Rev. 4
\\
Page 4
b
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)
- Submitted:
[h SP Number 29.023.03 sviewed:
m
/
Revision 9
pproved:
Effective Date
'- 2 7-#
(Plant M6n/ge'Y')
MC 1
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CONTAINMENT CONTROL EMERCENCY PROCEDURE l
r 1.0 PURPOSE The purpose of this procedure is to control primary contain=ent temperatures, pressure and level.
2.0 ENTRY CONDITIONS Enter the paragraphs of this procedure as required by the entry condition. The paragraphs can and should be perforred concurrently with each other as the entry q
conditions dictate and concurrently with the procedure from which it was entered.
- V 2.1 The entry conditions for this procedure are any of the following:
?
Paranraph i
2.1.1 Suppression Pool Temperature Above 90*F 3.1 2.1.2 Dryvell Temperature Above 145'F 3.2 2.1.3 Dryvell Pressure Above 1.69 psig 3.3 2.1.4 Suppression Pool Level Above +6" 3.4 2.1.5 Suppression Pool Level Belov -6" 3.4 2.2 Notify the Watch Ergineer to classify the event per EPIP 1-0 and initiate l
the Emergency Plan as required.
FEB 251985 h0 00 30b o
h 3.0 CPERATOR ACTIONS Supp Pool Tarp >90'F 3.1 MONITOR and CONTROL suppression pool t,emperature by performing the
- (']
following:
V 3.1.1 Attempt to close any open 3.1.1 Refer to SP 23.116.01 SRV which is not required (Main and Auxiliary to be open by cycling the Steam).
valve switch.
3.1.2 11[ the open SRV is stuck 3.1.2 Refer to SP 29.010.01 l
l
- open, (Emergency Shutdown)
THEN scram the reactor.
cal' TION If continuous LPC1 is required to assure adequate core cooling, do not divert RPR pumps from the LPCI rode.
CAUTION Do not start an RHR punp if the associated Eeergency Diesel Cenerator load is above 2250 Kk'.
l 3.1.3
))[ suppression pool 3.1.3 Refer to SP 23.121.01
) (' '
temperature exceeds 90*F, (Residual Feat Reroval (RHR) System)
THEN operate available l,
suppression pool cooling.
l l
3.1.4 IF, suppression pool
' 3.1.4 Refer to SP 29.010.01 temperature reaches 110*F, (Emergency Shutdern)
THEN scram the reactor.
CAUTION Cooldown rates above 100*F/hr may be required to accomplish Steps 3.1.5 and 3.1.6.
?
r I
SP 29.023.03, Rev. 9 Page 2 Ov
[
l CAUTION 3
Do not depressurize the RPV below 110 psig unless motor driven sJ/
pumps sufficient to maintain RPV vater level are running and the systems are available for injection.
CALTTION Refer to Figure 7, 8 or 9 for NPSH requirements for pumps taking a suction from the suppression pool.
3.1.5 IF suppression pool temperature cannot be j
maintained below the heat capacity temperature limit of Figure 1, THEN eaintain RPV pressure below the heat capacity temperature limit of Figure 1.
[:
y 3.1.6 IF suppression pool temperature AND RPV pressure cannot be restored SE maintained below the heat capacity temperature limit (Figure 1),
l THEN open all ADS valves AND Proceed to SP 29.023.05 (Rapid RPV Depressurization).
I SP 29.023.03, Rev. 9 Page 3 l0 l
3.2 MONITOR and CONTROL drvw311 tceptreture Dryvell Tsmp >l45'F by performing the following:
3.2.1 IT drywell terperature Eceeds 145'F, THEN operate all available dryvell cooling.
CAUTION If continuous LPCI operation is required to assure adequate core ;*
cooling, do not divert RHR pumps from the LPCI mode.
CAUTION Whenever the teeperature indicated on L-993 and L-994 exceeds th'e teeperature in the cabic, the actual RPV water IcVel may be any-where below the elevation of the lower instrument tap when the instrutent reads below the indic:ted level in the table.
Indicated Teeperature Level Instrument Any
+235 in.
Shutdown Ranr,c (0 to 400 in.)
Any
-308 in.
Fuel Zone A (-308 to -108 in.)
(~'l An,v
-308 in.
Fuel Zone B (-308 to -108 in.)
\\- '
110*F
+180 in.
Upset Range (0 to 180 in.)
371*F
-142 in.
Wide Range A (-150 to +60 in.)
395*F 8 in.
Narrow Range A (0 to 60 in.)
600*F
-150 in.
Wide Range B (-150 to +60 in.)
600*F
-0 in.
Narrow Range B (0 to 60 in.)
l 3.2.2 IF drywell temperature l
approaches 296*F, THEN shutdown the Reactor Recirculation Pumps MD
?-
Shutdown the Drywell Fans I
MD l
Initiate drywell sprays.
SP 29.023.03, Rev. 9 Page 4
/~
! d'
r CAUTION Do not depressurize the RPV below 110 psig unless motor driven
(("}h
./
pumps sufficient to maintain RPV vater level are running and the systems are available for injection.
CAUTION Cooldown rates above 100*F/hr may be required to accomplish Step 3.2.3.
CAUTION Refer to Figure 7, 8 or 9 for NPSH requirements for pumps taking a suction from the suppression pool.
3.2.3 JJ[ drywell temperature 3.2.3 NOTE 3,,
near the cold reference Dryvell cold refer-leg temperature instruments ence leg temperature reaches the RPV saturation instruments are limit and indicated RPV L-993 and L-994, water level is less than
-38",
O THEN open all ADS valves Ah3 Proceed to SP 29.023.05
~
(Rapid RPV Depressurization),
i 3.2.4 JJ[ drywell temperature cannot be maintained below 296*F, THEN proceed to SP 29.023.05 (Rapid RPV Depressurization).
SP 29.023.03, Rev. 9 Page 5 O
-s--*
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1 1
3.3 MONITOR rnd CONTROL privary containmtnt Conteinnant Press > 1.69 paig pressure by performing the following:
()
CAUTION Elevated suppression chamber pressure may trip the RCIC Turbine on high exhaust pressure, 25 psig.
CAUTION Do not start a Post LOCA Hydrogen Recombiner if the associated Emergency Diesel Generator load is above 3150 KW.
3.3.1 Operate the Post LOCA 3.3.1 Refer to SP 23.402.01 Hydrogen Recombination (Primary Containment
('f Systen.
Post LOCA Hydrogen Recombination)
CAUTION
$b Do not start an MSIY Leakage Cer. trol Subsysten if the associated Emergency Diese: Generator load is above 3250 KW.
(
0 3.3.2 Operate the MSIV Leakage 3.3.2 Refer to SP 23.406.01 Control Systen if (MSIV Leakage Control necessary.
System) 3.3.3 Sample and analyze primery containment atmosphere to L
ensure environmental release Ifmits are met.
3.3.4 IF drywell temperature is 3.3.4 Vent the prinary below 212*F, containment through IT48*MOV-031B and AND IT48*MOV-035B to the Post LOCA Hydrogen Release limits are met, Recombination Systen I
Primary Containment THEN vent the primary Atmospheric Purge containment.
Filter FLT 008.
NOTE This venting vill vent N2 inte'second-ary containment.
Evacuation of the Reactor Building may be necessary, p)
SP 29.023.03, Rev. 9 s,
Page 6
h*
a CAUTION If continuous LPCI operation is required to assure adequate core cooling, do not dirert RHR pumps from the LPCI mode.
3.3.5 INITIATE suppression pool sprays BEFORE The suppression chamber pressure reaches the suppression pool spray limit (Figure 3).
3.3.6 If, suppression chamber pressure reaches the pressure suppression limit (Figure 4),
THEN SHUTD0k'N the Reactor Recirculatien pumps AND N
Shutdown the drywell fans
!O
^""
Initiate drywell sprays as l
necessary to maintain suppression chamber pressure j
below the pressure suppression limit.
j s
SP 29.023.03, Rev. 9 Page 7 1O I
l
CAUTION 7]
Do not depressurize the RPV below 110 psig unless motor driven e
Q pumps sufficient to maintain RPV water level are running and the systems are available for injection.
CAUTION Refer to Figure 7, 8. or 9 for NPSH requirements for pumps taking a suction from the suppression pool.
CAUTION Cooldown rates greater than 100'F/hr may be required to accc plish. Step 3.3.7.
3.3.7 E suppression chamber pressure cannot be ma n-tained below the pressure suppressis.. limit (Figure 4).
THEN epen all ADS valves r~
V Proceed to SP 29.023.05 l
(Rapid RPV Depressurization).
i l
1 i
SP 29.023.03, Rev. 9 Page 8 l n 4
k 3.4 MONITOR and CONTROL suppression pool water level Supp Pool Level by performing the following:
> +6" or b -6" 3.4.1 Maintain suppression pool water level between +6 and -6".
3.4.2 IJ; suppression pool water 3.4.2 Refer to SP 23.202.01 level is BELOW -6",
(HPCI. System) or SP 23.119.01 (RCIC System)
THEN initiate suppression pool makeup.
CAUTION Do not depressurize the RPV below 110 psig unless motor driven purps sufficient to maintain RPV vater level are running and the systems are available for injection.
CAUTION Cooldown rates above 100*F/hr may be required to accomplish Steps 3.4.3, 3.4.8, and 3.4.9.
~
()
CAUTION Refer to Figure 7, 8, or 9 for NPSH requirerents for pumps taking a suction from the suppression pool.
3.4.3 IJ; suppression pool level 3.4.3 NOTE cannot be maintained (1)
Suppression Pool above.the heat capacity RTD's will not level limit (Figure 5),
indicate water tenperature below a THEN open all ADS valves water level of -24".
To determine suppres-AND sion pool water temperature below Proceed to SP 29.023.05
-24", place the RER (Rapid RPV Depressurization).
system in the sup-pression pool cooling mode and determine the pool temperature from PNL Hil-614 TE Ell N 004A (B).
SP 29.023.03, Rev. 9 Page 9 O
1 e
..,_..n...
....~.,,, _.
3.4.3 NOTE (2)
The HPCI and RCIC exhaust spargers are uncovered at -46" and f, 7)
(*
the ECCS pumps lose suction at -54".
3.4.4
))[ signals of hiFh suppression pool water level (+6)
QR Low condensate storage tank water level (3'4") occur.
A THEN confirm automatic transfer of/or manually transfer HPCI and RCIC suction from the condensate tank to the suppression pool.
3.4.5 JJ[the suppression pool water level cannot be maintained below +6" Ah3 Adequate core cooling is
- assured, O
'\\ s THEN terninate injection into the reactor vessel from sources external to the primary containment.
3.4.6 Notify Radiochemistry to sample and analyze sup-pression pool water to ensure suppression pool discharge limits are met.
3.4.7
))[ suppression pool water 3.4.7 Refer to SP 23.708.01 level is above +6" (Fuel Pool Cleanup)
AND 5
Discharge limits are met.
THEN lower suppression pool level.
SP 29.023.03, Rev. 9 Page 10 0
3.4.8 IJ[ cuppressicn posi v3ter 1evel cannot be maintained below the suppression pool load limit.
e THEN saintain RPV pressure below the load limit of Figure 6.
)
f 3.4.9 JI[ suppression pool water i
level and RPV pressure I
cannot be restored or maintained below the sup-pression pool load limit, i
THEN open all ADS valves l
AND Proceed to SP 29.023.05 l
(Rapid RPV Depressurization).
3.4.10 JJ[ primary centainment water 3.4.10 Refer to Figure 10.
level reaches +24 ft.,
,s..
NOTE The zero point on THEN terminate injection Figure 10 is the into the RPV from sources pressure difference external to the primary between 1Z93 PR 501A containnent irrespective of (B) and IZ93 PR 105A
/N whether adequate core (B) prior to g
j v
cooling is assured.
exceeding +60" in the suppression pool.
4.0 REFERENCES
4.1 SP 23.116.01, Main Auxiliary Steam 4.2 SP 23.121.01, Residual Heat Removal (RHR) System 4.3 SP 29.010.01 Emergency Shutdown 4.4 SP 29.023.05, Rapid RPV Depressurization 4.5 SP 23.402.01, Primary Containment Post LOCA Hydrogen Recombination l
SP 29.023.03, Rev. 9 Page 11 O
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