ML20069N358
| ML20069N358 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 06/02/1994 |
| From: | FLORIDA POWER CORP. |
| To: | |
| References | |
| VP-540, NUDOCS 9406220356 | |
| Download: ML20069N358 (11) | |
Text
9
- D4ifUMENT TRANSMITTAL 15893 FOR DOCUMENT NOTIFICATION AND/OR TRANSMITTAL l
TO: NRC (BANKS CT)
MAC: N/A DESTINATION:
DESCRIPTION:
DATE:
Thu Jun 02 10:04:41 1994 CPY COPY TOTALS DOCUMENT REV COMMENTS INFO CNTL MSTR VP0540 06 10 1
0 0
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RVP Rev 6 VP-540
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v RUNBACK VERIFICATION PROCEDURE 1.0 ENTRY CONDITIONS J1 am 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 IMdfDIATE ACTIONS Note There are no immediate actions for this procedure.
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This Procedure Addresses Safety Related Components
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i VP-540 PAGE 1 of 10 RVP L
i
'3. 0 FOLLOW-UP ACTIONS yfRIFICATION DETAILS 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.
s 3.1 Verify Rx power is < limit for Selected limiting parameters:
plant conditions.
o if an asymmetric rod exists, THEN verify 1 60% FP for the RCP combination o if 1 MFWP or 1 MFWBP has tripped, THEN verify 1 55% FP o IE only 3 RCPs are operating, THEN verify 1 75% FP o if 1 MSIV has closed,
<- ~s
( )
THEN verify 160% FP o if I CWP has tripped, THEN verify FP has been reduced to limit condenser AT to 21" F o IE 1 CDP has tripped, THEN verify FP has been reduced to prevent trip of MFWBPs from low DFT level at 12 f t 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.
m us VP-540 REV 6 PAGE 2 of 10 RVP l
l
3.0 FOLLOW-UP ACTIONS (CONT'D1 yfRIFICAT10N DETAILS o
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 aporopriate recommendations.
3.5 Verify DNB parameters are DNB Limits within limits.
O 4 RCPs 3 RCPs Th 1 604"F Th s 604*F j
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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i VP-540 REV 6 PAGE 3 of 10 RVP
3.0 FOLLOW-UP ACTIONS (CONT'D) 1 VERIFICATION DETAILS The following steps need to be performed after the runback is complete and the unit stabilized.
Because of the transient nature 1
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 i 6.5% of group position o Verify all Safet? Rods are 100%
withdrawn o Verify that APSRs are within l
insertion limits of the COLR.
l l
3.7 Verify runback endpoint core Selected limiting parameters:
l thermal power.
l 0 E an asymmetric rod exists, THEN verify 1 60% FP for the RCP combination Os o H 1 MFWP or 1 MFWBP has tripped, THEN verify s 55% FP o E only 3 RCPs are operating, THEN verify 1 75% FP o E 1 MSIV has closed, THEN verify 160% FP o H 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 to prevent trip of MFWBPs from low DFT level at i 2 ft 10".
Ex-core NIs are consistent with core thermal power.
Total Feedwater Flow vs Reactor i
I Power, Enclosure 1, is consistent with core thermal power.
O
- v VP-540 REV 6 PAGE 4 of 10 RVP
3.0 FOLLOW-UP ACTIONS (CONT'D)
VERIFICATION DETAILS A
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 s
o Perform quadrant p 43r tilt calculation using i core Nis if computer unavailabi See, Quadrai.* 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.
VP-540 REV 6 PAGE 5 of 10 RVP
3,0 FOLLOW-UP ACTIONS (CONT'D)
VERIFICATION DETAILS 3.11 Observe MS radiation monitors o IE any radiation monitor trend and RMA-12 for indications of a indicates OTSG tube leakage, OlSG tube leak.
THEN refer to E0P-06, Steam Generator Tube Rupture.
j I
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 if RCS leakage is suspected, THEN use Enclosure 3 for RCS leakage calculation.
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 Whita lights used for flow indicators on ES panels for HPVs.
3.14 Deter:rine status of MSSVs.
o Observe video monitor l
s I
o Observe tailpipe rope indicator.
VP-540 REV 6 PAGE 6 of 10 RVP
320 F0ll0W-UP ACTIONS (CONT'0) l VERIFICATION DETAILS O
3.15 Determine availability of all o Volt meters and breaker and 4160V and 6900V buses, indications on MCB o Annunciator alarms.
3.161E 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.
ON]
3.19 Determine reporting o Refer to CP-lll, Initiation And requirements.
Processing of Precursor Cards And Problem Reports o Refer to AI-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 S50D.
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VP-540 REV 6 PAGE 7 of 10 RVP
ENCLOSURE 1 TOTAL FEEDWATER FLOW VS. REACTOR POWER TOTAL FEEDWATER FLOW VS POWER 13 MAXIMUM 3
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VP-540 REV 6 PAGE 8 of 10 RVP
ENCLOSURE 2 OUADRANT POWER TILT CALCULATION
-()
IF COMPUTER GROUP 59 IS NOT AVAILABLE THEN PERFdRM HAND CALCULATION
~
1 NI NI NI NI-8=
NI-5 + NI-6 + NI-7 + NI - AVERAGE POWER 4
+
+
+
=
4 QUADRANT POWER TILT LARGEST POSITIVE OUADRANT 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 SS00. At no time shall Heat Balance exceed NI power by more than 2.0% on any operable NI power range channel.
(a) Heat Balance (from group 59)
(b) NI NI NI NI -
Heat Balance NI-5 Heat Balance NI-6 Heat Balance NI-7 Heat Balance NI-8 i
9 l
VP-540 REV 6 PAGE 9 of 10 PV9
ENCLOSURE 3 RCS Leakaae Calculation i
i HPI FLOW - MU-23-F18-1/FI4 + MU-23-FI6-1/F12 + MU-23-FI5-1/FI'. +
MU-23-FI7-1/FI3 4
j l
MAKEUP FLOW + RCP SEAL FLOW + HPI FLOW -
LETDOWN FLOW = RCS LEAK RATE 4
+
+
=
MU-24-FI MU-27-FI HPI FLOW MU-4-FI RCS LEAK RATE N
4 d
I e
i 1
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VP-540 REV 6 PAGE 10 of 10 (LAST PAGE)
RVP i
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