ML20092F783
| ML20092F783 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 09/01/1989 |
| From: | Fitzwater L GEORGIA POWER CO. |
| To: | |
| Shared Package | |
| ML20092F288 | List:
|
| References | |
| CON-IIT05-002-131C-90, CON-IIT05-191-000C-90, CON-IIT5-191-C-90, CON-IIT5-2-131C-90, RTR-NUREG-1410 LO-IU-60315-001, LO-IU-60315-1, NUDOCS 9202190499 | |
| Download: ML20092F783 (13) | |
Text
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CEORGIA POWER FCWER GENERATION DEPARTMENT G.. h V0GTLE ELECTRIC GENERAT1h3 PLANT
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INSTRUCTIONAL UNIT TITLE:
RESPOND TO LOSS OF RESIDUAL HEAT NUMBER: LO-IU-60315-001-02 REMOVAL PROGRAM:
LICENSED OPERATOR TRAINING REVISION: 2 AUTUCR FITZWATER DATE:
8/9/89 APPROVED:
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REFERENCES:
VEGP PROCEDURE 18019-C REV 6. LOSS OF RFSIDUAL HEAT REMOVAL
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LO-IU-60315-001-02; R2cpond to Loss of Rasidual Heat Rimovel j*
PERFORMANCE OBJECTIVE Given indications of a loss or reduction of RHR capability, respond to loss of RER.
The 14 must restore the faultedlfalled RHR train (s) to operable 'ststus. If a required RHR train cannot be restored, the LO must shut down the train, refer to Technical Specification for additional requirements, and initiate appropriate actions to restore the train.-The LO.must comply with all applicable Technical Specifications.
All communication and activities must l
be performed in accordance with current. approved procedures, i
r INFORMATION During a normal plant cooldown, the RER system transfers heat from the RCS to the CCW systen to reduce the temperature of the reactor coolant to cold shutdown temperature. A loss of RHR capability could result in an uncontrolled RCS temperature rise and, over the long term, any of the following conditionst
- 1. RCS pressure increase F
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- 2. Thermal stresses
- 3. Reactor coolant boiling.
i A rapid increase in RCS. temperature is not expected if the reduction or loss of RER capability o,ccurs early rin the fuel cycle. However, if the reduction or loss occurs late-in the fuel cycle, an immediate, uncontrolled RCS temperature increase is probable because of the' presence of a high rate of-decay heat.- The rate of decay heat is not only' dependent on time and fuel cycle, but also on recent power history.
The highest rate of decay; heat will be present durina a shutdown at the end of the fuel cycle after extended operation at high power.
-Loss of RHR also means that a najor component of the-ECCS will not be l
available to provide emergency core cooling.in the event of a loss of l
coolina accident.
l The most likely causes of a reduction or loss of residual heat removal aret:
- 1. RHR penp trip
- 2. Failure of pressure transmitters in a.RHR train
- 3. KHR system breaks 4 pump / flow problems due to
- a. Loss of/ inadequate level
- b. Vortexing 1-1 --
LO-1U-60315-001-02; Rzepond to Loss of Keoidual Hect Removal t
- c. Pump cavitation An RHR pump trip is most likely to occur during operatien in mode-5 with the RCS loops partially drained for maintenance, due to air / gas binding of the RHR pump (s).
If this. occurs, remotely-operated RHR pump suction vents I
(HV-10465. HV-l'0466) can be opened to releane the air / gas.
l Failure of pressure transmitt.ers in a RHR train may cause cuction isolation valves to close, thus, causing a loss of suction.
This is. a Iw probability cause of reduction or loss of RER.
RHR System breaks are also unlikely; the following components are most susceptible to a break leading to a reduction or loss of RUR capabilit/:
- 1. pump seals
- 2. valve packing glands
- 3. heat exchangers (tube leaks)
- 4. piping (failure) t The symptoms of reduction or loss of residual heat removal are:
Unexplained decrose in RRR flow or (11scharge pressure Detected RRR system leakage An unexpectet' rise in RCS temperature whi.'.e RER is in operation Any observed loss of RHR capability while RHR is in operation i
The following annunciators may be present on loss 6f RER:
-- RHR PMp OVf.RLOAD annunciator alarm CCW TRAIN A(B) RHR PMP SEAL LO FLOW annunciator alarm NSCW TRAIN A (B) RER PMP MTR CLR 10 FLOW annunciator alarm 5
RER FMP OVERLOAD will occur on.ly with an RHR pump trip.
Symptoas 3 and 4 may also accompany a pump trip.
Plant Vogtle Procedure 18019-C. " Loss.of-Residual Heat Removal.' in entered l
when the symptcass of reduction or loss of RHR capability are present.
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goal of this procedure is-to The restore the faulted /fsiled RHR train (s) to operable status as quickly as possible.
l The RRR system is one of the few plant systems that has Technical Specification requirementa placed on it for all modes of operation. The -
response to loss or reduction of RRR capability in Procedure 18019-C is highly dependent upon the mode of operation and the limiting conditions of-the applicable Technical Specifications:
MODE T.S.
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LO-IV-60315-001-02: Rospond' to Loco of Racidual Host R:moval 1
4 3.4.1.3 l
5 1.4.1.1.1 (reactor coolant loops filled) 5 3.4.1.4.2 (reactor coolant loops not filled) l i
6 3.9.8.1 (water level above the top of the reactor pressure vessel j
riange grerter than ct equal to 23 feet) i
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- 3. 3.8.2 (water level above the top of the reactor pressure vessel flange less than 23 feet) i Tecanical specifications should be consulted for complete operating tequir<ments, i
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?cchnical specification requirements will vary depending on the mode of operation. Generally, a minimum of one RKR-train must be operable.
modes or plant condities.s toquire Certain two RMR trains to be operable. Every uffort should be made in Plant Vogtle ' Procedure 18019-C faultsel/ failed RNR trains to operhbin statun as quickly as possible.
to restore i
There has been many boss of RHK events. in the industry over the past 1
neveral years.
These events are significant because core volding and c7erhaatang can occur rather quickly.
Refer to Figure 2 " Time to Bull". Figure 3. " Time for Corn Unce $
- Figute 6 "Heatup Aate" curves located in AOP 18019 for b i h. a 9
and understanding of the urgency for recovery from loss of RRR eiett RESPnND TO LOSS G7 AHR t
This In*tructionsi Unit is divided into two sections:
l Rkt in Modes 4 or 5. and Section B. Loss of RRR in Mode 6.Section A.
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CECTION A - LOS3 OP RER IN NODES 4 Ok 5 CAUTION During midloop operation with NL dann installed and ina6 equate RCS venting a loss of RRR cooling will result in saturated RCS conditions within winu'ts, subsequently resulting in core uncovery sud requiring containment 10.
clost.re tuttistion, t
bonitor/Maintkin core cooling e
1his must be done continuously until you exit r
the procedure.
To do thin you w111 monitor the~ Cora Exit TC less restored; than 200'F and RNR: cooling.is t
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If Cero Exit TC isLgreater than 200 F or RER coottog is not restored, then initiate Procedure 91001-C.
" Emergency classification.'and Implementing
'Instructions"..You must niso evacuate non-essential personnel and initiate 1-3
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s LO-IV-60315-001-02: A30 pond to Lo s of R:sidual H:st Removal containment isolation.
Additionally verify the RCS is in tact and initiate charging flow to provide core cooling.
If core exist temperature is less thnn 200)F. then continue to monitor the TCs.
Should you lose the TC indication while in midloop operation, then raise RCS level to the top of the het leg (100 feet 3 inchen) and monitor temperature using RC"i wide range indicstion T ho t' if no RHR Train is operating. then nunpend any RCS boron reduction and if the steam generators are available maintain RCS tenperature below 3500 F by use of steam dump or atmospheric relief valves (one SG 1evel should be filled and maintained in the narrow range).
Concurrently with these actions. you wust monitor operating RHR pumps for cavitation.
Cavitation would be indicated by the discharge flow being lower than normal for the RCS pressure or by an unstable discharge These indications are locuted on the QNCB.
pressure.
PI-0614 Train A - Pressure PI-0615 Train B - Pressure FI<0618A Train A - Flow F1-0619 Train B - Flow If et any time during performance of this procedure, cavitation tbn stop the running RRR pump, realign misaligned valves. vent the
- occurs, affected pump using HV-10465 Trn A or HV-1LO466 Trn 3 valves usinC the QMCll located hand switches.
and cennot be observed toen11y.The valves are physically located in scaled enoms If HV-10465 is not closed when venting is cocplete.
the contaminated water from the vent will overflow from the vtat room dawn into the vestibule H-131 level C.
Failure to close HV-10466 will result in contaminated water on the floor of the room containing the and the actuation of the room snap level switch light on the QPCP.
vent i
i If Core Exit TCs are stable or lowing, then return to the apptcyriate UOP.
i t
If the TCn are rising, verify the affected RRR and CCW flow normal.
This may occur due to inadequate time from when the problem first occurred the time that you are at this step.
and If the TCs do not stabilize or begin to lower with normal flows, then an inadequate RCS inventory es/ exist.
Monitor / Reestablish Adequate RCS_Inventog To have adequate inventory you should have greater than 72% indication j
the RVLTS FR or local or remote level indication greater than 187 ft elev on If this does not exist, then you will take actions to restore the level.
Yn doin2 so, you will dispatch operatore as necessary to locate and isolate l
any leaks adjust c!.arging flow to return lesel or, if no charging la available, gravity fill the RCS from the RWSt.
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LO-10-60315-001-02 R : pond to Loco of Residusi Host R:moval If these act. ions do not result in level recovery, a leak may exist.
To locate the lesk you will isolate the RRR pump suction valves one at a time s
to isolate the jeek.
Additionally. you will be directed to AOP 18004-0 "RCS teakeged to restore the level.
After level is restored, then restore RER.
Restore RRR To restore RHH you will initiate procedure 4011 *RHR System". Also see LO-1U-12101-002. "Startup RHR".
Once RRH is restored. check RCS intact and determine is alternate RCS cooling is required.
Deterstne/ Establish Alternate RCS, Cooling The RCS temperature is the primary indicator of whether alternate cooling is required.
If RCS cemperature is greater than 20d P. then alternate RCS cooling may be tequired.
If the SGs are available, then use the steam dusps or ARVs for coiling, and maic.ain at least two SG 1evels greater than 17%. Also start all CRDH fans which will also rernove a significant amount of heat.
Start the containment cooling fans and maintain RCS pressure at 365 palb with PIR heaters and spray (if bubble in PZR) or charging and letdown (if Bolid).
Start an RCP 16 possible to provide forced flow for better heat transfer from the core to the steam generators.
Initiate Repairs This may take considerable time depending on th? cause of the event.
Additionally Technical Specifications mist now be consulted.
You will also return the system to normal operation.
This will require consultation with the TSC for recovery actions.
SECTION B - LOSS OF RHR IN MCDE 6 Check RCS level above RV flange with cavity ftJ1ed.
If not, so to E'StIO" A Suepend all opers,t, ions involving a reduction of RCS boron concentration.
Verify the loop nuetion valves are open.
- 1. 5 l
t o-IU-t>0315 -001-02 : Recpond to toss of Residual II ct Removal Verify the following valves are opent HV-8701A Train A IIV-87018 Train A HV-8702A Train B li 87028 Train B If any of these valves are closed, stop the affected itHV pump (s) and open the affected train suction valves.
Verify reactor cavity level in greater than 23 feet; Use local Tyson tubing or remote indication to verify reactor level, if less than 23 feet., restore cavit.y level or fill the vessel to 99 percent RVLIS FR.
Suspend all fuel _ movement.
Determine,j,f_any leaks exi g Check the Auxiliary Building and Contatrument Leak Detection System to determine if any leaks exist.
Dispatch an PEG to locate and isolate any leaks.
If a break occurs on the RHR System. stop the RHR pumps.
A,t, tempt to place either train of RRR in operation.
Initiate 13011. "RRR Syrtes," to place one train of RRR in opornh on.
Initiate repairs,_and applicable Technical Specification re3uirements.
When the RHR System is in operation. return to the appropriate UOP.
Start all containment cooling fans.
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Place both trains of the Sp,en1 Fuel Pool Cooling and Purification System in service.
Initiate 13719. " Spent Puel Pool Coolin$ and purification System.* to place both RHR trains in service.
, Place FMB HVAC 1n Service.
l Initiate 13320, "FHB HVAC Systes." to place FHB HVAC in service.
Ensure _RCS temperajure is greater than 185 degreea F.
l If RCS tempersture is lese, than 185 dagreen F. return to the placina either train of RHP in service step (proecdure step BG).
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9,tablish an RCS feed path from the Rust.
At least one CCP must in running.
Verify valve aligrunents for the operat.ing pumps.
Manually start a CCP and ulign the valves as necessary.
If feed from the RWST cannot be established. return to the placing either train of RifR in uervice step (Procedure step B6).
1-6 l
1,3-10-60315-001-02l Roepond to 1.o23 of R0sidual Hast R:novsl Establish an RCS_ bleed path.
Establish an RCS bleed path from at least one open loop.
Dispatch a PE0 to open the RCCT pump to RWST isolation valves 1901-U4-041 and 1204-U4-002 and the RCS dratti loop to RCDT ptisip laolation valve 1901-U4-242. Operate t.he RCDT pumps as necessary to maintain the reactor cavity level at greater than 23 feet ap.d the temperatere at less than 185 degrees F.
Check RitR Sgtera status.
If the RRR System cannot be placed in operation. return to the placing either train of IdtR in service s.tep (Procedure step B6).
Teminate bleed and feed.
Return to the UDP in effect.
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1.0-7U-60313-001 02: H:cpond to Loss of R:sidual Haet R: novo)
PERFORMANCE GUIDE The following steps are required to respond to loss of RHR:
SECTION A - LOSS OF RRR IN HODES 4 OR 5 1.
Monitor / maintain core cooling 2.
Monitor /reestabitah adequate RCS inventory 3.
Restote RRR 4.
Determine /estabitsh alternate RCS cooling 5.
Initiate repairs SECTION 11 - 1455 0F RHR IN H0DE 6 1.
Check RCS level above RV flange with cavity filled.
If not, so to Section A.
2.
Suspend all operations involving a reduction of RCS boron coacentration.
3.
Verify the loop suction valves are open.
4.
Verify reactor cavity level is greater than 23 feet.
i S.
Suspend all fuel movement.
6.
Determine if any leaks arist.
7.
Attempt to place either train of RHR in operation.
8.
Initiate repairs and applicable Technical Specification requirements.
9, Start all containment cooling fans.
10.
Place both trains of th< Spent Fuel Pool Cooling and purification System in service.
11.
Place FHH HVAC in service.
- 12. Enaure RCS temperature is greater than 185 degreas P.
13.
Establish an RCS feed path from the R'1ST.
14.
Estah)lah an RCS bleed path.
15.
Check RHR System status.
- 16. Terminate blted and feed.
17.
Return to the UOP in effect.
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LO-1U-6031$-001-02: R3: pond to Loss of Rosidual H:nt Removs1 SELF-TEST Before proceeding to the Task Practice. answer the following que641ons as completely as possible.
1.
List the symptoms of loss of RHR.
2.
List three annunciators which may be present on loss of kRR.
3.
Xf a feed path is to be estabilshed during Mode 4. the< ECGS punpa will provide feed. State the feed teth during Mode 6.
4.
Briefly s. tate the implications of loan of RRR early in core life versus late in core life.
5.
State the most likely causes of a reduction or loss of residust heat
- removal, s
4 4
1-9
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= - _.
l 14-10-6031 $-001-02 : Rscpond t.o Loco of Residual H3st Acmoval AN%TR$
1.
Unexplained dnmoge in RHR flow or discharge pressure Detected RRR syst em len'u6e An unexpected rise in RCS temperature while R}{R is in operation Any observed loss of RER capability while RHR is in oper.ation l
l 2.
RRR PMP OVERLOAD annunciator alaru CCW TRA'N A(B) R11R PKP DEAL LO FT OW annunciator alarm NSCW TRAIN A (5) RHR FMP PfrR CLR 14 FLOW annunciator alarm 3.
The RCDT pumps provide feed flow, as required, through the RWST via the CCFs back to the reactor vessel.
4.
A rapid increase in RCS temperature is not expected if the reduction or loss of RHR capability occurs early in ful cycle. However, if the reduction or losa occurs late in fuel cycle, an lamediate.
I uncontrolled RCS tempenture incresse is probable because of the presence of a high rate of dv. cay heat.
The rate of decsy heat is not only dependent en time and fuel cycle, but also on recent power history.
The highast rate of decay heat will be present during a shutdown at the end of fuel cycle af ter extended operation at high i
power.
5.
RHR purp trip Failure of pressure transmitters in a RHA train REN system breaks Puap/ flow problems due to loss of/ inadequate level, vortexing or pump cavitation 1
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LO-IU-6031$ 001-02: Respond to loss of Residual litet Rtwoval f
TASK PRACTICE i
1.
Peview Procedure 10019-C. " Loma of AIDt."
Be sure ttutt you understand all precautions. Ilaltatf ora, and steps.tsvociated with responding to loss of RIIR.
2.
Take this instructional unic And Procedure 18019-C. at.oss of RIIR" to the control room or simulator.
Be sure that you con locate all instctmentation associated with temponding to loes of R101.
3.
In the cot. trol room or simulator, simulate tenponding to loan of RIIR.
If ponsthle have a fellow k
trainee evaluate your performance using Procedure 18019-C. "I,ons of Ri?Ra and this instructional unit.
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LO-f U-60315-001-02; R2: pond to loss of Residual 11:st RImove.1 FFJDRACK ON TASK PRACTICE 1.
If you have any que:Jtions shout the precautions. limitations. or steps in Procedure 18019-C. " Loss of RHR". ask your instructor.
2.
You should have been able to locato all instrumentation associated with responding to. loss of RRR.
If you had any difficulty, ask your instructor for help.
3.
You should have simulated the steps necessary to respond to loss of RHR.
If you had any difficulty, re-read the pertinent sections of this instructional unit and the procedure. Resolve any questions with your instructor.
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