ML20066F714
| ML20066F714 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 11/15/1982 |
| From: | Hukill H GENERAL PUBLIC UTILITIES CORP. |
| To: | Eisenhut D Office of Nuclear Reactor Regulation |
| References | |
| 5211-82-270, NUDOCS 8211190141 | |
| Download: ML20066F714 (18) | |
Text
.
GPU Nuclear Corporation
- a,,,.I Nuclear m'arS x8o e
Middletown, Pennsylvania 17057 717 944-7621 TELEX 84-2386 Writer"s Direct Dial Number:
November 15, 1982 5211-82-270 Office of Nuclear Reactor Regulation Attn: Darrell G. Eisenhut Division of Licensing U. S. Nuclear Regulatory Commission Washington, D.C.
20555
Dear Sir:
Three Mile Island Nuclear Station, Unit 1 (n!I-1)
Operating License No. DPR-50 Docket No. 50-289 Fire Protection - Alternate Shutdown Capability Attached please find a listing of equipment and operator actions for achieving cold shutdown within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in theevent of a postulated fire in the control and/or relay rooms at TMI-1.
We are providing this as a result of our verbal commitment to the NRC staff on November 5, 1982.
Sincerely, 1f
.D.Il\\ kill Director, DII-l liDil:CJS:vj f Attachment cc:
R. C. Haynes,w/o att.
R. Conte, w/o att.
J. Van Vliet, w/att.
00o 8211190141 821115 PDR ADOCK 05000289 F
PDR GPU Nuclear Corporation is a subsidiary of the General Public Utilities Corporation
a
..p
, INTRODUCTION The attached table provides the actions required to successfully complete the remote shutdown of TMI-l in the event of a fire in the cable spreading room or control room.
The following assumptions were made in the develop-ment of this procedural guideline:
1.
No credit is taken for any actions from the control room except reactor trip.
2.
Evolution must be carried out with or without offsite power available.
Loss of offsite power may occur at anytime.
3.
Any or all automatic signals may fail to actuate.
4.
A single spurious actuation may occur at anytime during the evolution.
5.
There are five available operations personnel:
a.
Shift supervisor b.
Two control room operators c.
Two auxiliary operators 6.
Spurious actuation which might result in a rapid ractor transient will be dealt with directly from the remote shutdown station.
7.
This is written for "A" side components, but may be changed to "B" side at later date.
Assuming only the minimum condensate storage tank volume of 150,000 gallons per tank will allow at least 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> of sustained hot shutdown conditions prior to beginning a cooldown, cooldown will be accomplished in less than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> from the start of the fire.
Additional water sources are available in the condenser hot well and deminerclized water storage tank which were conservatively ignored in this avaluation.
The term " cut and jumper" refers to a procedure which shall be developed for each component identified as requiring this operating mode. The procedure will identify those control wires which must be disconnected or cut in order to remove any possible maintained command signals.
It will also identify terminals which must be jumpered in order to energize the appropriate motor contractor or relay.
It is intended that the " cut and jumper" activity for each component will be performed at the component's power source.
CUI_DELINES FOR SilUTDOWN SEQ.
KEY NO.
ACTION RSDS LOCK OTilER INDICATION CONTROL DISCUSSION 1
Isolate X
A.
Required quickly Communications system from relay B.
This capability does room (Announce not presently exist.
fire and dispatch personnel to stations) 2 Transfer control of X
OTSC level and EFW and ADV A.
Local switches in EF-V-30 A/B and OTSG prewure on valve control vicinity of remote shutdown MS-V-4A/B to RSDS RSDP. Also on RSDP panel for transfer on one channel and take manual RCS temp, PZR and on CB elev. 338 for the control level and RCS other channel.
(Notes 7, 8 and 9) pressure on RSDP B.
Spurious opening of valves will be overridden) 2a De-energize X
PZR level on Local Breaker A.
lleaters should be de-pressurizer heaters RSDP energized to prevent damage if auto trip on level fails.
B.
Open breakers at IE 6 1F Reactor Bldg. litg. Swgr. on TB elev. 322'.
3 Close valves MS-V-8A X
OTSG pressure, A. TBP valves open results in and MS-V-8B to deal RCS temp and rapid overcooling.
Isolation with stuck open TBP RCS pressure on required to prevent potential valves RSDP thermal shock.
GUIDELINES FOR SilUTDOWN SEQ.
KEY NO.
ACTION RSDS LOCK OTilER INDICATION CONTROL DISCUSSION 4
TRIP REACTOR X
SRM on RSDP A.
Reactor may be tripped f rom (Turbine trip will Trip from 1G and IL SWGR (CB elev. 322) occur automatically on Control reactor trip. This will Room B.
Letdown may or may not iso-be a protected circuit late automatically on reactor to assure function) trip.
(Turbine normally trips on reactor trip or LOOP) 5 TRIP MFW pumps X
OTSG level A.
Spurious failure of EW FW-P-1A/B on RSDP Reg valve would result in rapid overfill of OTSG (See Notes 1, 2,
3, 4 and 5)
B.
Auto trip on LOOP 6
Verify power Bus energized available to "D" Bus lights at RSDS for Buses: 1D, 1P, IR, lA ES MCC, lA ES V MCC, lA ES Screen Ilouse MCC, 1C ES V MCC
CUIDELINES FOR SilUTDOWii SEQ.
KEY NO.
ACTION RSDS LOCK GTilER INDICATION CONTROL DISCUSSION 6a Start motor driven X
OTSG level and A.
Close breaker on 4150V AC pumps EF-P-2A pressure on RSDP.
ES-SWCR-1D (CB clev. 338)
Also, RCS temp, (Normally start on LOFW)
PZR level and RCS B.
Potential spurious, failure (If offsite power is pressure on RSDP could prevent EF-P-2B from lost, diesels would be starting started prior to this step) 7 a) Electrically close X
BWST level on A.
Spurious failure of these Dil-V-6A and RSPD.
valves would result in rapid
"'""E"
""U b) Dil-V-6B X
X*
Valve position at Building sump Valve location B.
Key locks at 1A-ESV-MCC and IB-ESV-MCC on AB elev. 305
- Dil-V-6A is powered of f the protected diescl rencrator "lA ' and will be provided with positis e control at 1C ESV MCC Independent of the fire area iircuits.
D11-V-6B is powereI downstream of dienel generator "13" which is not protected for alternate shutdown use.
If offsita power is availabli, Dil-V-6B may be operated at the IB-ESV-NCC independent of the fire area circuits. With Loss of
)ffsite Power, Dil-V-5B will be manual 11 c'losed and itt circuit breaker manually opened at the IB-ESV-MCC to 1: olate th a line containing D'l-V-6B.
8 Verify that MU-V-3 X
Pressurizer level A.
Manual letdown isolation has closed (Letdown manually and MU tank level valves are in auxiliary building Isolation) Close MU-V-close on RSDP elevation 281 ft.
97B, HU-V-99 and MU-V-valve 109B if required.
e GUIDELINES FOR SilUTDOWN SEQ.
KEY NO.
ACTION RSDS LOCK OTilER INDICATION CONTROL DISCUSSION 9
Electrically X
X Valve position at A.
Key locks at lA and 1B ESV-open MU-V-36 and (manual) valve location MCC (AB clev. 305 ft.)
MU-V-37, or verify valve and open MU-V-37 stroke B.
Manually close at AB elev.
manually if needed.
MU-V-37 if 281 ft.
loss of off-site power 10 Electrically close X
X Local at valve A.
Valve on AB elev. 281 ft.
MU-V-217 and manually (LOOP) close if LOOP B.
Not powered from ES bus 11 Isolate MU-V-17 X
At valve A.
MU-V-17 is an air operated by closing manual valve which is unprotected.
MU-V-91A or B valve stroke B.
Valves on AB elev. 281 ft.
12 Control MU flow with X
PZR level and MU A.
MU-V-16B is an ES powered MU-V-16B (Jog Control) in normal range valve and is the preferable con-trol for MU (MU-V-16B also Close MU-V-16A if it X
PZR level on RSDP minimizes nozzle thermal shock) opens spuriously B.
Closure of MU-V-16A is required to prevent PZR filling 12a Start NS-P-1A X
Periodically A.
RC pump motor cooling via check NSCC temp nuclear services closed cooling 12b TRIP RC pumps if req'd X
in AB 6900 V
' water after checking Nuclear Switchgear l'
Services closed cooling wate r temp.
o
GUIDELINES FOR SliUTDOWN SEQ.
KEY NO.
ACTION RSDS LOCK OTilER INDICATION CONTROL DISCUSSION 12c NR-PIA (Start)
X Panel in Plant NR-VIA (Open)
X Panel in Plant 13 Start D/G: Offsite D/G Status Lamps 1st sign of LOOSP Bus ID status power is unavailable and for " Cranking" lamp is not lit.
D/G " cranking" diesel fails to start
" Running" at RSDS or " running" lamps are lit.
automatically a)
Isolate circuits and X
secure D/G feeder Ckt.
ID 4160" breaker 1, open position SWGR Cubiclo ID2 b)
Isolate circuits and X
secure bus ID incoming I D SWGR breaker ISB-D2 in Cubicle open position ID2 c)
Isolate circuit and X
Secure bus IE incoming LD SWGR breaker ISA-D2 in open Jubicle position IDIS d)
Isolate External CRTS X
ID 4160V switch-Start /Stop and command D/G to it D/G gear room at ID 4160V start ianel Switchgear
[D/G room room) i l
GUIDELINES FOR SilDTDOWN SEQo KEY NO.
ACTION RSDS LOCK OTilER INDICATION CONTROL DISCUSSION 13 Continued e)
Isolate Breaker control X
circuits for following at bus ID load and open Cubiclc breakers:
X(lD3)
MU-P-1B X(lD8)
RR-P-1A X(lD10)
Dil-P-1A X(ID6) f)
Close D/G Breaker X
" ready to load'.'
Operator observes " ready to load' Cubic 1(
indication light indicator at SWGR ID prior to 1D2 at ID SWGR Bus ID closing D/G breaker volts and amps at ID SWGR g)
Reclose EFW motor X
breaker
'160V SWGR Cubicic ID3 Re-close breakers (if opened) feeding:
Transformer IP Jubicle ID5 Transformer 1R Jubicle IDll NOTE:
D/G may start due to spurious signal at any time - See Note 10
GUIDELINES FOR SiluTDOWN SEQ.
KEY NO.
ACTION RSDS LOCK OTilER INDICATION CONTROI.
DISCUSSION 14 If seal injection X
Indication of A. 6900V SWGR on Turbine Building
,is lost, manually seal injection elev. 322 ft.
trip reactor coolant flow on RSDP pumps 15 Reestablish MU flow Local panel will ye A.
MU-P-1A or MU-P-1B if LOOP or spurious provided with the following:
will be lost on LOOP failure of MO-P-1A:
Control for B.
MU-V-20 closed to prevent 1.
Close MU-V-20 X
Status for the the following RC pump seal damage following valves: on local panel 2.
Start MU-P-3A X
N "E MU-V-36 MU-P-1A Provided for MU-V-32 throttling 3.
Start DR-P-1A X
MU-V-37 MU-P-3A
""' ~
--^
4*
Start DC-P-1A X
MU-V-14A DC-P-1A 5.
Start MU-P-1A X
MU-V-20 DR-V-1A M--
MU- -
t
< >se 6.
Open MU-V-20 X
DR-V-1A 7.
Throttle MU-V-32 X
Manually con-trol MU-V-20 8.
Open and close X
and 32 on AB MU-V-12 and 14A elev. 281 ft.
as required Status for the following pumps:
MU-P-1A MU-P-3A MU-P-1A DR-P-1A Status for MU-V-12 Cqntrol of and MU-V-14A on MU-V-12 and RSDP MU-V-14A on RSDP
CUIDELINES FOR SilUTDOWN SEQ.
KEY NO.
ACTION RSDS LOCK OTilER INDICATION CONTROL DISCUSSION 16.
Transfer Group 8 IIcaters X
Local indiation NA A.
!!anual at 480V-ES-SWGR to engineered safeguards Existing at bus (Control Building elevation bus IP if offsite power Plant 322 ft.)
is not available.
Procedure 17.
Spurious llPI X
PZR level and RCS A.
Trip MU-P-lC at 4160V SWGR Initiation pressure on RSDP IE (AB clevation 338 ft.)
18.
If !!U tank level drops X
MU tank level and A.
This provides MU alignment to less than 55 inches, BWST level on RSDP from BWST open MU-V-14A and close
!!U-V-12 until MU tank level is greater than 66 inches.
CUIDELINES FOR SilUTDOWN SEQ.
KEY NO.
ACTION RSDS LOCK OTilER INDICATION CONTROL DISCUSSION y
19.
If RCS pressure decreases PZR level and RCS A.
PORV (RC-RV2) may to less than 2000 psi and pressure on RDSP spuriously open. Action PZR level is increasing to de-energize it will result or stable, then:
in closure of valve.
- a. De-energize PORV X
B.
Rapid action would be If this is not effective,
~
required to prevent RCS saturation and llPI initiation.
then
- b. Close spray valve X
C.
Ilanual control of spray valve at the 480V-EC-CC-1A (CB elev. 322 ft.)
D.
Spray valve open depressurization rate of about 1.1 psi /sec.
20.
Reduce number of RC X
Pump power indic-A.
Key lock switch on pumps to one per loop.
ation adjacent to 6900V SWGR on Turbine (Trip B & D pumps)
RSDS Building elevation 322 ft.
CUIDELINES FOR SilUTDOWN SEQ.
KEY NO.
ACTION RSDS LOCK OTilER INDICATION CONTROL DISCUSSION 21.
Proceed with normal X
RCS pressure, RCS EFW & ADV A.
Manual control of cooldown using EFW, ADV temp, OTSG control on spray valve at the and sprays.
pressure, OTSG RSDS 480V-ES-CC-1A (CB elev. 322')
level and PZR level on RSDS 22.
De-energize PZR heaters X
Local at bus Use Plant A.
At 480V-ES SWGR-IP on to reduce pressure.
Procedures CB elev. 322' Open circuit breaker 23.
Re-establish letdown IC-PIA X
On RSDS On RSDS IC-VIA X
On RSDS On RSDS IC-V2 X
On RSDS On RSDS IC-V3 X
On RSDS On RSDS X
On RSDS On RSDS IC-V4 MU-VIA X
On RSDS On RSDS Need to repower from lA iesel W -M.1, V2A)
MU-V2A X
On RSDS On RSDS MU-V3 X
On RSDS On RSDS MU-V8 X
On RSDS Manual at valve Open breaker first (IA RW MCC)
MU-V70A X
At valve location Manual at valve MU-V110 X
At valve location otanual at valve MU-V109A, B X
At valve location Manual at valve MU-V98 X
At val.ve location Manual at valve
CUIDELINES FOR SilUTDOWN SEQ.
KEY NO.
ACTION RSDS LOCK OTilER INDICATION CONTROL DISCUSSION 24.
Establish RB cooling -
Supply Nuclear River Water, Nuclear Service &
Reactor River Water &
Start RB Fan:
24a.
Open NS-V-52A & NS-V-53A X
Bleed air A.
Valves NS-V-52A & 53 supply off Open on loss of inst. air.
24b.
Open breakers for X
llandwheels B.
Breakers on 480V ES RR-V-3A/4A then manually CC-1A (CB Elev. 322')
open valves.
Valves at IB clev. 295' RR-V5 X
llandwheel C.
Open if RR-V6 fail shut.
24c.
Start RR-P-1A X
D.
Manually start from CB clev. 322' 24d.
Start RB cooling fan E.
Manual at 480V-ES-CC
( All-E-l A) 1A (CB Elev. 322')
25.
Control Building X
recirculation fan cut &
(All-E-18A and All-E-19A)
Jumper at MCC
CUIDELINES FOR SIIUTDOWN SEQ.
KEY NO.
ACTION RSDS LOCK OTilER INDICATION CONTROL DISCUSSION 26.
Open Co-V-10A & B X
llandwheels A.
Open breakers at (Isolation valves for 480-V-TP-CC-1A and 1A condensate storage tanks)
Radwaste CC on TB elev. 322' then locally open valves is closed. This assures that adequate condensate storage tank inventory will be ava.ilable.
27.
Stop RCP-lC (normal X
A.
6900V SWGR on turbine shutdown procedure if building elev. 322 ft.
offsite power available) 28.
Bypass IlpI injection X
A.
Manually close relays on when primary <1750 psi cut and ES channel relay cabinets IA, and >l650 psi jumper at B, C and 2A, B, C (CB clev. 338')
E.S.
Actuation Cabinets 29.
Bypass LPI injection X
A.
Same as above when primary <,900 psi cut and and >500 psi jumper at E.S.
Actuation Cabinets
CUIDELINES FOR SiluTDOWN SEQ.
KEY NO.
Acr10N RSDS LOCK OTilER INDICATION CONTROL DISCUSSION 30.
Isolate Core Flood tanks X
A.
Breakers at the 480V (close valves CF-V-1A,B) cut and ESV-CC-1A (Fil elev. 281')
jumper at 480V ESV-CC-lC 31.
Align Dil Removal System:
A.
Breakers at 480V a.
Open breakers for the ESV-CC-1A (AB-305) following valves:
Dil-V-4 A, 5 A, 7A &
BS-V-2A X
llandwheels b.
Open breaker for B.
Breaker at 480V Dil-V-3 X
llandwheels ESV-CC-lC (Fil-281')
c.
Manually close or C.
Aux. Building check closed elevations.
Dil-V-5A/Dll-V-7A/
BS-V-2A X
llandwheels d.
Manually open or D.
Aux. Building check open elevations.
Dil-V-3 X
llandwheels Dil-V-4A X
llandwheels Dil-V-12 X
llandwheels
CUIDFLINES FOR SilllTDOWN SEQ.
KEY NO.
ACTION RSDS LOCK OTilER 1NDICATION CONTROL DISCUSSION F
e.
Open valves X
E.
Breakers at 480V Dil-V-1 & 2 cut &
ESV CC-lC (Fil 281')
remotely jumper at ESV-CC-lC F.
Operate with breaker open for Dil-V1 or Dil-V2 to prevent spurious opening 32.
Open RC-V-4 remotely X
A.
Breaker at 480V ESC-CC-lC cut &
(Fil ele. 281')
jumper at ESV-CC-lC 33.
Close Dil-V-19A X
A.
Manual valve in AB (throttle valve for decay manually heat removal flow) stroke valve 34.
Start Jecay lleat removal X
Decay heat flow &
A.
Breaker at 4160V Pump temp. on local ES-SWGR-lD (CB elev. 338')
(Dil-P-1 A) panel 35.
Throttle open X
RCS Temp. on RSDS A.
Manual valve in AB Dil-V-19A (Control manually for cooldown rate cooldown rate) stroke valve
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NOTES ON SPURIOUS ACTUATIONS 1.
Spurious stopping at EF-P-1 may occur. This is not a concern since a motor driven EFW pump will be started.
2.
Closing of EF-V-1A or B may occur.
Suction is still available from 1 (one) condensate storage tank.
3.
If EF-V-2A or 2B closes, the vaaffected SG is still being fed.
4.
MS-V-13A or B are redundant c air operated) steam supply valve to the EFW turbine.
Failure of any one in a closea position is inconsequential. Also, }$-V-10A and B would be available.
5.
MS-V-10'A or B are the motor driven steam valves to EF-P-1.
Failure of any one is inconsequential and MS-V-13 A and B would be available.
6.
MU-V-20 and MU-V-32 may spuriously close. These valves are required to provide seal injection. These valves will be monitored from the RSDS and will be reopened locally if required.
7.
MS-V-2A or 2B may spuriously close. This will isolate OTSG A or B ADV & TBV.
Remaining OTSG can be used for decay heat removal.
MS-V-2A or 2B will also isolate OTSG A or B from turbine driven EFW. The remaining valve is sufficient to provide continued turbine driven EFW. Motor driven EFW will be available as well. Further time is available for operator action to open valve.
8.
Spurious closure of MS-V-4A or 4B (ADV) will result in adequata decay heat re-moval capability from the unaffected ADV. Control can be transferred to the remote shutdown panel and the closed valve can be remotely reopened.
9.
If reactor coolant pumps trip spuriously or an LOOP, the EFW System can be used to raise the OTSG level to 50% in a controlled manner and a normal transition to natural circulation will result.
10.
Diesel Generator may start due to spurious actuation signal. D/G breaker is interlocked with the incoming feeder breakers which will prevent its closure if incoming breakers are closed. The interlock circuits do not run through the relay or control rooms. D/G may reamin operating at idle until loss of of fsite powers (LU0SP) confirmed. On LOOSP, operator at ID switchgear will take positive control of the incoming and D/G feeder breakers and will manually load the diesel generator.
If failure of the auto load shedding circuit is concurrent with D/G Start and LOOSP, generator overload protection connected to a separate dedicated set of fuses will trip the D/G breaker. The operator will eventually take manual control of the D/G feeder breakers and of the component feeder breakers and will manually load the diesel generators.
11.
The breaker for DH-V1 or DH-V2 will be maintained in the open position during normal operation to preclude spurious opening of both valves.