ML20069N844
| ML20069N844 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 06/02/1994 |
| From: | FLORIDA POWER CORP. |
| To: | |
| References | |
| PROC-940602, NUDOCS 9406230231 | |
| Download: ML20069N844 (37) | |
Text
_ _
.DOCUf4ENT TRANSMITTAL.15897 FOR DOCUMENT NOTIFICATION AND/OR TRANSMITTAL TO: NRC (DC DESK)
MAC: N/A DESTINATION:
j DESCRIPTION:
DATE:
Thu Jun 02 10:04:41 1994 CPY COPY TOTALS i
DOCUMENT REV COMMENTS INFO CNTL MSTR
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AP0545 04 7
1 0
0 AP0660 07 7
1 0
0 VP0540 06 20 1
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t ESTRUCilDNS TO THE ADDRESSEE:
IF YDU ARE A HDLDER DF A HARD CDPY.PLEASE VERIFY THE DOCUMENT (SiRECEIVED AGREES W11H THE ABDVE DESCRIPilDN.
BE SURE 10 DESTROY DDCUMENilSI DR PDRilDNS DF DOCUMENT ($1 SUPERSEDED BY THE ABDVE.
s THE SIGNATURE INDICATES THAT VDU H AVE READ AND UNDERSTAND THESE INSTRUCTIDNS AND THE CHANGES TD THE DOCUMEN18.
l RETURN SIGNED AND DATED TRANSMITTAL 10 DDCUMENT CDNTROL WITHIN 2D DAY $ AT MAIL CDDE:
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NR2B
_ SA1G NA1C i
[ FloridaPowerCorporaties Deemment Centrol Cryotel River Energy Comptes 1570D W. Power Line St. -
Crystal 1tiver, FL 34425-87DB SIGNATURE DF ADDRESSEE DATE l
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f EDEPENDENT VEnfFICATIDN icentrol Room Desumente Dalyl DATE 9406230231 940602 PDR ADOCK 05000302
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v PR REV 04 AP-545 PLANT RUNBACK 1.0 ENTRY CONDITIONS J.E any of the following conditions exist:
o Asymmetric rod o loss of 1 RCP o Loss of 1 MFWP o Loss of 1 MFWBP, THEN use this procedure.
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AP-545 PAGE 1 of 13 PR
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BLANK PAGE i
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AP-545 REV 04 PAGE 2 of 13 PR
2.0 IMMEDIATE ACTIONS g
g ETIONS DETAILS 2.1 Ensure plant is running Runback Limits back to 5 maximum % FP.
Condition Maximum % FP Asymmetric rod 60% FP Loss of 1 MFWP 55% FP Loss of 1 MFWBP 55% FP Loss of 1 RCP 75% FP 2.2 IF runback is due to loss Ensure:
of 1 MFWP, THEN ensure proper FW o FWV-28 "FW DIS CROSS-TIE" is valve positions.
opening C
i o FWV-29 B MBV is closing o FWV-30 A MBV is closing.
2.3 Stabilize RCS PRESS Stabilize RCS PRESS using:
between 2130 and 2180 psig.
o PZR heaters o PZR spray o PORV.
O AP-545 REV 04 PAGE 3 of 13 PR
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AP-545 REV 04 PAGE 4 of 13 PR i
3.0 FOLLOW-UP ACTIONS ACTIONS DETAILS 3.1 Notify personnel of plant SOTA conditions as required.
Plant operators SS0D to evaluate plant conditions for entry into the Emergency Plan System Dispatcher.
3.2 E an asymmetric condition exists on two or more control rods, THEN trip the Rx AND GO TO E0P-2, Vital System Status Verification, beginning with step 2.1.
O4
%J 3.3 CONCURRENTLY PERFORM VP-540, Runback Verification Procedure.
3.4 E at any time while performing this procedure the Rx trips, THEN GO TO E0P-2, Vital System Status i
Verification, beginning with Step 2.1.
3.5 E Rx power is > 75% FP, AND one MFWBP trips, THEN trip one MFWP.
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AP-545 REV 04 PAGE 5 of 13 PR
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3.4 LF_ the Rx trips, g.
THEN GO TO E0P-2, Vital System Status Verification, beginning with step 2.1.
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O AP-545 REV 04 PAGE 6 of 13 PR
3.0 FOLLOW-UP ACTIONS (CONT'D)
ACTIONS DETAILS 3.6 JF RCP has tripped, THEN ensure an oil lift pump has Auto started.
3.7 Maintain imbalance within Observe SPDS imbalance limits.
Adjust APSRs to maintain imbalance l
Refer to the COLR for limits.
3.8 Ensure Rx power stabilizes Runback Limits at s maximum % FP.
Condition Maximum % FP Asymmetric rod 60% FP Loss of 1 MFWP 55% FP Loss of 1 MFWBP 55% FP Loss of 1 RCP 75% FP 3.9 Ensure Tave stabilizes between 577 and 581'F.
3.10 Ensure PZR level stabilizes bet.veen 200 and 240".
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AP-545 REV 04 PAGE 7 of 13 PR
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.0 3.4 If the Rx trips, THEN GO TO E0P-2, Vital System Status Verification, beginning with step 2.1.
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AP-545 REV 04 PAGE 8 of 13 PR 4
e 3.0 FOLLOW-UP ACTIONS (CONT'D)
ACTIONS DETAILS Note Changing Tc instruments may affect FW flows and Tave.
)
3.11 lE 3 RCPs are operating, Proper Tc for operating RCP:
THEN ensure narrow range 4
Tc is selected for the Operating RCP Narrow operating RCP in the affected loop.
in the affected range loop Tc RCP-1A TT1 RCP-1B TT3 RCP-lC TT1 RCP-1D TT3 nN]
3.12 IE 3 RCPs are operating, Proper RCS PRESS instrument:
THEN ensure narrow range RCS PRESS control is Loop with Narrow range selected to the loop with single pump operation.
single RCP Channel r.oaration Selection A
AP-545 REV 04 PAGE 9 of 13 PR
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/7 3.4 lE the Rx trips, V
THEN GO TO E0P-2, Vital System Status Verification, beginning with step 2.1.
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AP-545 REV 04 PAGE 10 of 13 PR
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3.0 FOLLOW-UP ACTIONS (CONT'D) p-sg
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ACTIONS DETAILS 3.13 Ensure A Tc stabilizes between -5 and +5'F.
3.14 Ensure MS Hdr PRESS stabilizes between 870 and 900 psig.
3.15 Verify quadrant power tilt Refer to Computer Group 59.
is within limits.
If NOT, THEN refer to ITS 3.2.4, Quadrant Power Tilt.
3.16 If runback was due to 1
Refer'to ITS 3.7.3, Os Loss of 1 MFWP or Condition C Loss of 1 MFWBP, AND FWV-28 is open, 2
Select "EFIC CHANNEL A MAIN THEN align EFIC MFWI FW ISOLATION MAIN FW PUMP l
for FWV-28 open operation.
TRIP" key switch to "BOTH" located in CRD Room, RR3A i
3 Select "EFIC CHANNEL B MAIN FW ISOLATION MAIN FW PUMP TRIP" key switch to "BOTH" located in B EFIC Room, RRSBl 3.17 IE a RCP is tripped, THEN refer to ITS 3.4.1, RCS pressure, Temperature, and Flow departure from nucleate boiling (DNB) limits.
AP-545 REV 04 PAGE 11 of 13 PR j
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.4 IE the Rx trips, I!!G GO TO E0P-2, Vital System Status Verification, 3
beginning with step 2.1.
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1 AP-545 REV 04 PAGE 12 of 13 PR
l 3.0 FOLLOW-UP ACTIONS t00NT'D)
ACTIONS DETAILS i
3.18 1E asymmetric rod exists, Refer to:
AND the Rx remains l
- critical, ITS 3.1.1, Shutdown Margin THEN ensure Rx power is 1 60% of allowable power ITS 3.1.4, Control Rod Group based on RCPs, Alignment Limits AND notify the Reactor Engineer.
ITS 3.2.5, Power Peaking Factors.
3.19 If an asymmetric rod o
Insert control rods manually exists AND the Reactor is OR determined to be subcritical, o Trip the Reactor and THEN, at a minimum, insert THEN GO TO E0P-2, Vital System rod groups 5, 6, and 7.to Status Verification, beginning establish Mode 3 with step 2.1.
reactivity conditions.
3.20 IE power reduction was 2 15% FP in I hr, THEN notify Chemistry.
3.21 GO TO OP-204, Power Operation.
i AP-545 REV 04 PAGE 13 of 13 (LAST PAGE)
PR
7 4
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TT REV 07 AP-660
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TURBINE TRIP 1,0 ENTRY CONDITIONS J F Rx powe r i s < 45. F P,
AND any of the following conditions exist:
o Turbine trip -
o 2 50'F AT between condensers o
2 55'C Generator Avg cold gas TEMP o
2 104*C Generator stator bar discharge TEMP o
Condenser vacuum is 2 10 in-Hg absolute, THEN use this procedure.
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This Procedure Addresses Safety Related Components i
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CT Approved by MNPO [48#
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AP-660 PAGE 1 of 13 TT
4 1
a BLANK PAGE O
AP-660 REV 07 PAGE 2 of 13 TT
2.0 IMMEDIATE ACTIONS ACTIONS DETAILS 2.1 Depress "TURB AUTO STOP TRIP" push button.
2.2 Ensure TVs QR GVs are closed.
- 1. Select all MSIVs closed:
If NOT, THEN close MSIVs.
Close MSV-411 Close MSV-412 Close MSV-413 Close MSV-414 2
Control 0TSG PRESS using ADVs:
o MSV-25 "STM GEN A ADV" o MSV-26 "STM GEN B ADV" 2.3 Stabilize RCS PRESS.
Stabilize RCS PRESS using:
PZR heaters PZR spray PORV I
AP-660 REV 07 PAGE 3 of 13 TT
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AP-660 REV 07 PAGE 4 of 13 TT
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3.0 FOLLOW-UP ACTIONS g
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ACTIONS DETAILS 3.1 Notify personnel of plant SOTA conditions as required.
Plant operators SS00 to evaluate plant conditions for potential entry into the Emergency Plan System Dispatcher 3.2 CONCURRENTLY PERFCRM VP-540, Runback Verification Procedure.
3.3 Ensure ICS runback to 5 15% FP.
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3.4 Ensure output Bkrs are o Ensure open Bkr 1661 open.
o Ensure open Bkr 1662 If NOT, 1
At rear of MCB TGF, select THEN select the Backup "BKR TRIP C0ll SELECTOR Trip Coils and attempt to SWITCH" to " BACKUP":
open the Output Bkrs.
o Bkr 1661 on " BACKUP" 1F Output Bkrs fail to o Bkr 1662 on " BACKUP" open using Backup Trip
- Coils, 2
Open Output Bkrs:
THEN notify Dispatcher to separate CR-3 from the o Bkr 1661 open 500KV grid.
o Bkr 1662 open.
3.5 Ensure RCS PRESS Stabilize RC PRESS using:
stabilizes from 2130 to 2180 psig.
PZR Heaters PZR Spray PORV.
AP-660 REV 07 PAGE 5 of 13 TT
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AP-660 REV 07 PAGE 6 of 13 TT l
4
3.0 FOLLOW-UP ACTIONS (CONT'D)
ACTIONS DETAILS 3.6 If at any time while performing this procedure, the Rx trips, THEN GO TO E0P-02, Vital System Status Verification, beginning with step 2.1.
3.7 Ensure the main generator
" FIELD BKR" is open.
3.8 Select the " VOLT REG" to "0FF".
3.9 Ensure the main turbine Ensure started:
oil pumps have Auto started.
o TBP-2 "TG BRG OIL PP AC" o TBP-8 "HP SEAL OIL B/U PUMP".
3.10 Isolate the MSR high 1
Depress " RESET" push button pressure bundles.
on RH control panel.
- 2. Isolate MS to the high pressure bundles by closing:
MSV-29 "RH TK 3A 150" MSV-30 "RH TK 3B IS0" MSV-31 "RH TK 3C IS0" MSV-32 "RH TK 3D 150".
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AP 660 REV 07 PAGE 7 of 13 TT
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1
,-s Applicable Carry-over steps:
3.6 lE the Rx trips, THEN GO TO E0P-02...
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AP-660 REV 07 PAGE 8 of 13 TT
3.0 FOLLOW-UP ACTIONS (CONT'D) 7~
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ACTIONS DETAILS 3.11 Ensure MS Hdr PRESS stabilizes 870 to 900
)
psig.
l 3.12 Maintain PZR level 200 to o Adjust "PZR LEVEL CONTROL" 240".
"SETPOINT" to adjust PZR level.
o Adjust MUV-51 " LETDOWN FLOW" controller to adjust letdown fl ow.
3.13 Ensure Tave stabilizes 577 to 581*F.
/N 3.14 Ensure OTSG levels are
(,
maintained at LLL.
3.15 Notify SP0 to isolate DFT SP0 to close HVV-103 DFT vent to vent to atmosphere.
atmosphere.
3.16 Notify SP0 to isolate SP0 to close:
FWHE-5A and FWHE-5B drains to DFT.
o HDV-47 FWHE-5A drain to DFT o HDV-48 FWHE-5B urain to DFT.
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AP-660 REV 07 PAGE 9 of 13 TT
Applicable Carry-over steps:
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3.6
.lf the Rx trips, THEN GO TO E0P-02...
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AP-660 REV 07 PAGE 10 of 13 TT l
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3.0 FOLLOW-UP ACTIONS (CONT'D)
ACTIONS DETAILS 3.17 Ensure Turbine Drain Ensure turbine drain valves are open Valves are open.
and not isolated:
Turb ne Drain Valves
..__TDV-1 TDV-6 TDV-2 TDV-7 TDV-3 TDV-8 TDV-4 '
TDV-9 TDV-5 TDV-10 TDV isolation valves TDV-104 TDV-106 O
3.18 J.F ' power reduction was 2 15%FP in I hr, THEN notify chemistry to perform ITS required RCS sampling.
3.19 Notify SP0 to isolate MSR SP0 to select "CLOSE" at "MSR high pressure and LP REHEATER DRAINS CONTROL PANEL" bundle vents to FWHEs.
located 119 ft TB.
High Pressure and LP Vents to FWHEs:
_ HDV-539 HDV-540 HDV-543 HDV-544
_ HDV-547 HDV-548 HDV-551 HDV-552 l
O AP-660 REV 07 PAGE 11 of 13 TT
4 1
J Applicable Carry-over steps:
3.6 1E the Rx trips, THEN GO TO E0P-02...
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O AP-660 REV 07 PAGE 12 of 13 TT l
3.0 FOLLOW-UP ACTIONS (CONT'D1 ACTIONS DETAILS 3.20 Notify SP0 to isolate MSR SP0 to close locally:
high pressure drain tank drains to FWHEs.
HDV-1 HDV-3 HCV-5 HDV-7.
3.21 WHEN "TURB AT ZERO SPEED" 1
Ensure turning gear control alarm is actuated, switch is in "AUT0".
THEN ensure turbine goes on turning gear.
2 Ensure TBP-6, "TG BRG OIL LIFT PUMP" is running.
lE turning gear does NOT Auto
- engage, THEN select "TG TURNING GEAR O
MOTOR" control switch to
" MAN",
AND notify SP0 to engage turning gear locally.
3.22 1E turbine was tripped due to exceeding condenser vacuum limits, THEN notify Sy;tems Engineering to evaluate per vendor instructions.
3.23 IF plant shutdown is
- required, IHEN GO TO OP-208, Plant Shutdown.
If NOT, THEN GO TO OP-203, Plant Startup.
AP-660 REV 07 PAGE 13 of 13 (LAST PAGE)
TT
RVP Rev 6 VP-540 t
RUNBACK VERIFICATION PROCEDURE 1.0 ENTRY CONDITIONS JF any of the following conditions exist:
o ICS automatic runback is in progress o
An operator controlled manual runback is in progress o
Use of VP-540 is directed by another procedure, THEN use this procedure.
2.0 IMMEDIATE ACTIONS Note There are no immediate actions for this procedure.
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This Procedure Addresses Safety Related Components k, (_ bbw Date L t 'W
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Approved by MNPO y
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VP-540 PAGE 1 of 10 RVP
'3. 0 F0ll0W-UP ACTIONS d
VERIFICATION DETAILS o
NOTE During the runback, some parameters are constantly changing and cannot be verified until the new power level is reached and the unit has stabilized.
This procedure is written assuming that performance of this procedure is begun while the runback is in progress.
If it is not, then later steps may be more important than those that are listed first, and may be performed out of order.
3.1 Verify Rx power is < limit for Selected limiting parameters:
plant conditions.
o if an asymmetric rod exists, THEN verify s 60% FP for the RCP combination o IE 1 MFWP or 1 MFWBP has tripped, THEN verify s 55% FP o '.lE only 3 RCPs ars operating, THEN verify 1 75% FP o
IF 1 MSIV has closed,
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T5EN verify 5 60% FP o lE 1 CWP has tripped, THEN verify FP has been reduced to limit condenser AT to 21* F o if 1 CDP has tripped, THEN verify FP has been reduced to prevent trip of MFWBPs from low DFT level at 1 2 ft 10".
3.2 Verify control rod index will Immediately notify the SSOD if the remain in the acceptable region control rod index will be in the of the insertion limit curve of restricted or unacceptable regions the COLR during the runback.
of the curve.
9 O(V VP-540 REV 6 PAGE 2 of 10 RVP
3.0 FOLLOW-UP ACTIONS (CONT'D)
VERIFICATION DETAILS
-s g
3.3 Verify that imbalance is within o Observe SPDS imbalance display limits.
o Refer to COLR for imbalance limit.
3.4 Verify RCS heat production is o SPDS indicates stable TEMP and balanced to OTSG heat removal.
PRESS parameters are within normal operating box o See Enclosure 1 for Total Feedwater Flow Rates vs. Reactor Power o
IF NOT balanced, THEN determine cause of mismatch and make appropriate recommendations.
3.5 Verify DNB parameters are DNB Limits within limits.
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4 RCPs 3 RCPs Th 1 604*F Th s 604"F l
RC PRESS RC PRESS 2 2062 psig 2 2062 psig RC Flow RC Flow 2 140 mlb/hr 2 105 mlb/hr IF NOT, THEN refer to ITS 3.4.1, DNB Parameters.
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VP-540 REV 6 PAGE 3 of 10 RVP
3.0 FOLLOW-UP ACTIONS RONT'D1 VERIFICATION DETAILS
,/~T LJ NOTE The following steps need to be performed after the runback is complete and the unit stabilized.
Because of the transient nature of a runback condition, the order of performance of these steps may need to be adjusted to the individual transient.
3.6 Verify control rod status.
o Verify all rods aligned within 6.5% of group position o Verify all Safety Rods are 100%
withdrawn o Verify that APSRs are within insertion limits of the COLR.
3.7 Verify runback endpoint core Selected limiting parameters:
thermal power.
o E an asymmetric rod exists, THEN verify 5 60% FP for the RCP combination o E 1 MFWP or 1 MFWBP has tripped, THEN verify 1 55% FP o E only 3 RCPs are operating, THEN verify 1 75% FP o E 1 MSIV has closed, THEN verify 1 60% FP o E 1 CWP has tripped, THEN verify FP has been reduced to limit condenser AT to 21' F o E 1 CDP has tripped, THEN verify FP has been reduced 1
to prevent trip of MFWBPs from low DFT level at 1 2 ft 10".
Ex-core NIs are consistent with core thermal power.
Total Feedwater Flow vs Reactor Power, Enclosure 1, is consistent with core thermal power.
VP-540 REV 6 PAGE 4 of 10 RVP
3.0 FOLLOW-UP ACTIONS (CONT'D)
VERIFICATION DETAILS o
3.8 Verify core AT is consistent Expected core ATs.
with core thermal power.
o With 4 RCPs running:
44 "F AT 100%
=
33 *F AT 75%
=
26.4 'F AT 60%
=
24.2 F AT.
55%
=
o With 3 RCP's running:
44 F AT 75%
=
32.7 *F AT 55%
=
26.4 *F AT.
45%
=
3.9 Verify quadrant power tilt o Refer to Computer group 59 which within steady state limits.
updates once every 6 min o Perform quadrant power tilt calculation using Ex-core NIs if computer unavailable.
See, Quadrant Power Tilt Calculation o
IF NOT, THEN refer to ITS 3.2.4, Quadrant Power Tilt.
3.10 Observe radiation monitors and o if any atmospheric radiation recorders for unexplained monitor is in alarm, trends.
THEN refer to AP-250, Radiation Monitor Actuation o Observe annunciator monitor display for alarm or warning conditions o Observe radiation monitors and recorders on back of MCB including RB high range monitors.
'J VP-540 REV 6 PAGE 5 of 10 RVP
'3.0 FOLLOW-UP ACTIONS (CONT'D)
VERIFICATION DETAILS G
q, 3.11 Observe MS radiation monitors o E any radiation monitor trend and RMA-12 for indications of a indicates OTSG tube leakage, OTSG tube leak.
THEN refer to E0P-06, Steam Generator Tube Rupture.
3.12 Observe for increased RCS Observe:
leakage.
o RCP seal PRESS and dumpster frequency o PZR and MUT level trends o RB sump and RCDT level trends o MU flow control valve position and MU flow o E RCS leakage is suspected, THEN use Enclosure 3 for RCS leakage calculation.
O 3.13 Determine status of:
o Acoustic monitors o
PORV o
PZR reliefs o Annunciator alarms o
PZR HPVs o
RCS HPVs o Computer points for tailpipe TEMPS:
RCV-8 R205 RCV-9 R206 RCV-10 R207 o White lights used for flow indicators on ES panels for HPVs.
3.14 Determine status of MSSVs.
o Observe video monitor o Observe tailpipe rope indicator.
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VP-540 REV 6 PAGE 6 of 10 RVP 4
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3.0 FOLLOW-UP ACTIONS (CONT'D)
VERIFICATION DETAILS 3.15 Determine availability of all o Volt meters and breaker and 4160V and 6900V buses.
indications on MCB o Annunciator alarms.
3.16 IF_ any equipment malfunctions during transient, THEN determine if required per ITS.
3.17 Review alarm summaries for o Review annunciator alarm summary unexplained alarms.
o Review computer alarm summary.
3.18 Determine if entry into the Emergency Plan is required per EM-202.
rh 3.19 Determine reporting o Refer to CP-111, Initiation And requirements.
Processing of Precursor Cards And Problem Reports o Refer to Al-500, Conduct of Operations o Determine if a Nuclear Network entry is required for the event o Refer to SP-296, Documentation of Allowable Operating Transient Cycles.
3.20 WHEN VP-540 is stopped, THEN notify SS00.
VP-540 REV 6 PAGE 7 of 10 RVP
ENCLOSURE 1
~
TOTAL FEEDWATER FLOW VS. REACTOR POWER TOTAL FEEDWATER FLOW VS POWER 13 MAXlMUM
---..'"'".s.' ~ ' -^" ~ '
12 EXPECTED
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to 20 30 40 50 60 70 80 90 100
VP-540 REV 6 PAGE 8 of 10 RVP
ENCLOSURE 2 OUADRANT POWER TILT CALCULATION
()
IF COMPUTER GROUP 59 IS NOT AVAILABLE THEN PERF0RM HAND CALCULATION NI-5=
NI-6=
NI-7=
NI-8=
NI-5 + NI-6 + NI-7 + NI = AVERAGE POWER 4
+
+
+
=
4 QUADRANT POWER TILT LARGEST POSITIVE OVADRANT POWER
-l X 100
=
AVERAGE POWER
-l X 100
=
Ex-core NI Calibration If [ Heat Balance - NI Power] is 2 0.8% RTP notify the SSOD. At no time shall Heat Balance exceed NI power by more than 2.0% on any operable NI power range i
channel.
(a) Heat Balance (from group 59)
O*
(b) NI-5=
NI-6=
NI-7=
NI-8=
=
Heat Balance NI-5
=
Heat Balance NI-6
=
Heat Balance NI-7 Heat Balance NI-8 i
O VP-540 REV 6 PAGE 9 of 10 RVP
~
ENCLOSURE 3 RCS Leakaae Calculation HPI FLOW = MU-23-FI8-1/F14 + MU-23-FI6-1/FI2 + MU-23-FIS-1/Fil +
MU-23-FI7-1/FI3 MAKEUP FLOW + RCP SEAL FLOW + HPI FLOW -
LETDOWN FLOW = RCS LEAK RATE 1
+
+
=
MU-24-FI MU-27-FI HPI FLOW MU-4-FI RCS LEAK RATE O
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i VP-540 REV 6 PAGE 10 of 10 (LAST PAGE)
RVP i