ML20058M585
| ML20058M585 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 09/14/1993 |
| From: | Marshall W FLORIDA POWER CORP. |
| To: | |
| References | |
| VP-580, NUDOCS 9310060238 | |
| Download: ML20058M585 (30) | |
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DOCUMENT TRANSMITTAL 1559 FOR DOCUMENT NOTIFICATION AND/OR TRANSMITTAL g ]oQ TO: NRC(DC DESK)
MAC:
DATE:
Tue Sep 14 11:33:53 1993 CPY COPY TOTALS DOCUMENT REV COMMENTS INFO CNTL MSTR i
VP0580 21 20 1
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i CSTRUCil0NS TO THE ADDRESEEE If TOU ARE A NOLCER OF A HARD CDPV.PLEASE YERITY THE DOCUMNfi8)MCEIVED AGREES WITH THE AB0VE DESCRIPT10K BE $URE TO DESTROV DOCUMENTIS) DR PORTIONS OF DOCUMENT (S) SUPER $[DED BY THE ABOVE.
THE $1CkATURE INDICATES THAT YOU HAVE RE AD AND DWDER$TAND THESE INSTRUCil0NS AND THE CHANGES TO THE DOCUMEhTS.
EETURN SIGNEO Ak0 D ATED TRANSMITT AL TO M AIL CODE
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NR2B
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[ Herida Pener Corpersties P.O. Ben 219 Crystal River. FL 34423 8215
$1GhATURE 0f ADDRESSEE DATE EDEPENDENT VERIFICAT10N IDemtiese 0mid DATE 0500 %
931006023S 930914 57 PDR ADOCK 05000302 [:
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'l REV 21 DATE 09/03/93 VP-580 PSVP 0O PLANT SAFETY VERIFICATION PROCEDURE i
1.0 ENTRY CONDITIONS Jf entry into the Emergency Operating Procedures is required, OB If use of VP-580 is directed by other procedures, THEN use this p.rocedure.
2.0 IMMEDIATE ACTIONS None
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b N F O R M ATI O N O N L \\g I"
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9 This Procedure Addresses Safety Related Components Approved by MNP0 4A4I.
Date 7 ll/ -$
VP-580 PAGE 1 of 29 PSVP w.
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e 30 FOLLOW-UP ACTIONS VERIFICATIONS DETAILS 3.1 During the performance of this procedure, ensure that Shift Supervision is made aware of any significant abnormal condition.
'{
NOTE When performing the verification steps, use more than one indication if available, to verify observed conditions.
3.2 Is the reactor subcritical with o Control rod groups 1 thru 7 are neutron flux decreasing?
fully inserted o Negative startup rate o Neutron flux decreasing i
3.3 Is the main turbine tripped and o Annunciator alarms output breakers 1661 and 1662 o Unit trip light O
open?
o GV's or TV's closed-o Output Bkr indicating lights 3.4 Does adequate subcooling margin o Refer to SPDS/Tsat monitors i
exist?
Adequate Subcooling Margin:
RCS Margin
> 1500 psig 30*F 1 1500 to 50*F
> 250 psig 5 250 to.
70*F
> 150 psig
$ 150 psig SPDS
-5 200*F N/A l
O VP-580 REV 21 PAGE 2 of 29 PSVP i
=
I 3.0. FOLLOW-UP ACTIONS (CONT)
VERIFICATIONS DETAILS 3.5 Are any RCP's running?
o Motor indicating lights i
o Motor amps o Flow chart recorder.
3.6 Are the ES 4160V and 480V buses o Voltmeters energized?
o Circuit breaker lights o Annunciator alarms 1
i 3.7 Is instrument air available?
o Air pressure indication 3.8 Does either OTSG pressure o SPDS indicate coupling with its' o Tc coupled with and tracking Tsat respective Tc?
for OTSG pressure t
O-3.9 Are both 0TSG levels trending Required 0TSG 1evel:
towards or at correct level for the plant conditions?
Inadequate Adequate SCM SCM No RCPs RCPs 80 - 90%
60 - 70%
LLL 3.10 Is feedwater flow to OTSGs o RCS temp changes excessive or inadequate ?
o OTSG level 3.11 Does either OTSG have steaming o OTSG level and pressure capabilities for decay heat o TBV's and/or ADV's.
removal?
3.12 Is RCS inventory being o Adequate SCM maintained 2 50" in the o Pressurizer level pressurizer?
O VP-580 REV 21 PAGE 3 of 29 PSVP
3.0 FOLLOW-UP ACTIONS (CONT)
VERIFICATIONS DETAILS 3.13 Is HP1 core cooling required?
o Loss of Adequate SCM o Loss of MFW and EFW i
3.14 If required, are the ECCS o Adequate SCM systems providing adequate core o In-core T/C decreasing cooling?
3.15 Is Tave correct for decay heat o 550 - 555'F forced RCS flow load and RCS flow conditions?
o 575 - 585'F natural circulation 3.16 Are there any unexpected o Red backlighted annunciators Priority One Annunciators?
l P
3.17 Is there a radioactive release o OTSG tube leak O-in progress?
o Containment integrity l
o RB sump pumps o RMA-2 trends and alarms 3.18 Are there indications of:
- a. Inadequate SCM o Tsat monitors o SPDS
- b. Inadequate Heat Transfer o SFCS o Undesired temp increase o RCS press increasing
- d. Steam Generator Tube Leak o RMA-12 o M5 line rad monitors I
J VP-580 REV 21 PAGE 4 of 29 PSVP
3.0 FOLLOW-UP ACTIONS (CONT)
VERIFICATIONS DETAILS 3.19 Is the correct E0P being Refer to the following table:
performed?
If the following condition exists, 181H the Operators should be using:
A Reactor Trip has or should have E0P-02, Vital System Status occurred Verification t
Adequate Subcooling Margin does NOT E0P-03, Inadequate Subcooling exist Margin Primary to Secondary heat transfer E0P-04, Inadequate Heat Transfer is INADEQUATE Primary to Secondary heat transfer E0P-05, Excessive Heat Transfer is EXCESSIVE Steam Generator Tube Leak >l GPM E0P-06, Steam Generator Tube exists Rupture Incore temperatures indicate > 20*F E0P-07, Inadequate Core Cooling superheat l
Entry into E0P-08 has been directed E0P-08, LOCA Cooldown O
from other procedures RC Natural circulation cooling is E0P-09, Natural Circulation required Cooldown Entry into E0P-10 has been directed E0P-10, Post-Trip Stabilization from other procedures
)
Loss of DHR occurs from RCS leak QR E0P-ll, Loss of Decay Heat Removal Both DHR trains become unavailable Neither 4160V ES bus can be E0P-12, Station Blackout energized 3.20 If required, are the four rules Refer to Enclosure 1, Rules of the E0P's being complied with?
o Loss Subcooling Margin o HPI control o EFW control o Pressurized Thermal Shock O
i VP-580 REV 21 PAGE 5 of 29 PSVP
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3.0 FOLLOW-UP ACTIONS (CONTl VERIFICATIONS DETAILS 3.21 IE SPDS is NQI available, Refer to Enclosure 2, Cooldown curves It!Eli plot RC pressure and for natural circulation and forced temperature trends on fl ow..
3.22 Have the reporting requirements-Refer to:
been reviewed?
o Al-500, Conduct of Operations o CP-111, Documenting, Reporting and Reviewing Problem Reports o EM-202, Duties of the Emergency Coordinator 3.23 Cooldown requirements vs natural cire. C/D rates and water sources for EFW are contained in Enclosure 3.
3.24 E0P performance may be followed Refer to the appropriate
Enclosure:
using flowcharts.
E0P-02, VSSV, Enclosure 4 E0P-03, ISM, Enclosure 5 E0P-04, IHT, Enclosure 6 E0P-05, EHT, Enclosure 7 E0P-06, SGTR, Enclosure 8 i
E0P-07, ICC, Enclosure 9 E0P-08, LOCACD, Enclosure 10 E0P-09, NCCD, Enclosure 11 E0P-10, PS, Enclosure 12 E0P-11, LDHR, Enclosure 13 E0P-12, SB0, Enclosure 14 i
VP-580 REV 21 PAGE 6 of 29 PSVP l
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j ENCLOSURE'1 (Page 1 of 4)
O'-
RULE #1 LOSS OF SUBC00 LING MARGIN R adequate subcooling margin is
- lost, IH S perform the following:
i 1.
Trip ALL RCPs immediately.
E RCPs were not tripped within 2 minutes after losing subcooling
- margin, JHM reduce running RCPs to 1/ loop.
2.
Ensure FULL HPI:
1.
Open MVP suction valves from BWST:
o MUV-73 o MUV-58 2.
Ensure 2 MVPs and their cooling water pumps are operating.
3.
Open all 4 HPI valves:
MUV-23 MUV-24 MVV-25 MUV-26 4.
Close MVP recirc valves:
o MVV-53 o MUV-257 3.
Ensure HPI flows are balanced.
Close MUV-27, Normal MU isolation E I narrow range HPI line flow indicates off scale high and is verified using the wide range indication, THEN isolate the high line, A_!LQ balance the other 3
- lines, lE.N_01, THEN balance all 4 HPI lines.
VP-580 REV 21 PAGE 7 of 29 PSVP s-
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ENCLOSURE 1 i
(Page 2 of 4)-
RULE #2 HPI CONTROL s
4 1.
Ensure FULL HPI.
1.
Open MVP suction valves from BWST:
i o MUV-73 o MUV-58 r
2.
Ensure 2 MVPs and their cooling water pumps are operating.
3.
Open all 4 HPI valves:
MUV-23 MUV-24 MUV-25 MUV-26 4.
Close MUP-recirc valves:
o MUV-53 o MUV-257 i
2.
HPI MUST be throttled to prevent IE MVP recirc valves are open,
)
exceeding:
THEN add 100 gpm for each running MVP to the indicated flow.
o Pump runout Maximum allowable flow to prevent j
o NDT limit runout is:
O o PTS guidelines o 1 MVP, 540 gpm l
o 2 MUPs, 1080 gpm o 3 MVPs, 1620 gpm 3.
HPI MAY be throttled anytime adequate subcooling exists based on incores.
4.
MVP recirc valves MUST be open MVP recirc valves:
prior to throttling HPI flow
< 200 gpm/ pump.
o MUV-53 o MUV-257 i
5.
HPI Termination Criteria:
LPI 2 1000 gpm/line for 2 20 minutes
.0_3 All of the following conditions exist:
o Adequate Subcooling Margin-o PZR level is 2 100" o OTSG Heat Removal o RCS leakage < MUV-31 capacity O
VP-580 REV 21 PAGE 8 of 29 PSVP.
1 l
ENCLOSURE 1 (Page 3 of 4)
RULE #3 O
EFW CONTROL
'l ACTIONS DETAILS-
]
1.
Ensure EFW flow limits are NOT i
exceeded.
- EFWPs Flow Running Limit 1
< 1000 l
'2
< 1300 2.
Required 0TSG level.
Inadequate Adequate Subcooling Subcooling Margin Margin No RCPs RCPs 80 - 90%
60 - 70%
LLL O
3.
1E adequate subcooling margin Required EFW flow for manual control:
does NOT exist, IHEH ensure OTSG levels are 2 OTSGs available,1200 gpm/0TSG continuously progressing towards 80 - 90%.
1 OTSG available, 2 400 gpm 4.
While progressing towards o If adequate subcooling margin does required level, EFW flow should NOT exist, be throttled to prevent OTSG THEy do NOT throttle total EFW flow PRESS from decreasing > 100 psi
< 400 gpm.
below desired setpoiet.
o If adequate subcooling margin-
O VP-580 REV 21 PAGE 9 of 29 PSVP
ENCLOSURE 1 (Page 4 of 4)
O' RULE #4 PRESSURIZED THERMAL SHOCK 1.
The PTS guidelines MUST be o Forced RCS Flow:
implemented when either of the Teoid c 380*F AND cooldown rate following conditions exist:
exceeds Techniccl Specifications -
limit.
o HQ Forced RCS Flow:
2.
PTS guidelines:
o Ensure minimum adequate subcooling margin is maintained.
o if cooldown is required, IHfH maintain cooldown rate within Tech Spec limits.
o PTS guidelines are applicable until an Engineering evaluation has been completed.
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O VF-580 REV 21 PAGE 10 of 29 PSVP i
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i ENCLOSVRE 2 i
C00LDOWN CURVE FOR NATURAL CIRCULATION AND FORCED FLOW i
O i
2600 NORMAL! POST TRIP WINDOW 2400 a-
.e s
M i
i NDT CURVE!
2000 e
ASCM CURVE 1800
\\
$ 1600 3
c.
NATURAL
- 1400 CIRCULATION 4
[
CURVE a 1200
. N O
E a, 1000 0
.i E
i o
a 600 N
..=
1 SATURATION ;
iCURVE 200 1
0 100 200 300 400 500 600 700 RCS TEMPERATURE
- F Acceptable region is:
o below and to the right of the NDT curve o
above and to the left'of the ASCM curve o
above and to the left of the Natural Circulation curve if RCPs are off and cooldown rate 2 5 F/\\hr
.O VP-580 REV 21 PAGE 11 of 29 PSVP F
ENCLOSURE 3 C00LDOWN RE0VIREMENTS VS. NAT CIRC COOLDOWN RATES
.O
- 1) FW requirements and the time to cooldown are controlled primarily by the characteristics of the ADVs and the cut-in conditions for the DHR system.
- 2) The time to cooldown from Rx trip is about 150 hrs.
- 3) The FW requirement to cooldown is about 735,000 gal.
i
- 4) The minimum cooldown rate consistent with the above minimum time and FW requirements is about 8.5 degrees F/hr.
- 5) Cooldown rates in excess of 8.5 degrees F/hr. do not decrease the FW or time requirements for cooldown.
- 6) Cooldown rates less than 8.5 degrees F/hr. increase both the FW and the time requirements for cooldown.
- 7) A time delay of 28 hours3.240741e-4 days <br />0.00778 hours <br />4.62963e-5 weeks <br />1.0654e-5 months <br /> from Rx trip will not significantly affect FW or time requirements if a cooldown rate of 50 degrees F/hr is then utilized.
For smaller time delays smaller cooldown rates may be utilized.
Sources of Emeroency Feedwater (EFW) at the Crystal River Site Source Volume (aal)
Dedicated EFW Tank (EFT-2) 150,000 Condensate Storage Tank 139,000 Condenser Hotwe'1s 150,000 DW Storage Tank, Unit 3 450,000 r
DW Storage Tank, Unit 1 147,000 DW Storage Tank, Unit 2 147,000 DW Storage Tank, Unit 4/5 500,000 CD Storage Tank, Unit 4 500,000 F
CD Storage Tank, Unit 5 500,000 AB DW Storage Tank, Unit 3 5,000 i
(
VP-580 REV 21 PAGE 12 of 29 PSVP
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E0P-04, REV-1 INADEQUATE HEAT TRANSFER, PAGE 2 of 2 N
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VP-580 REV 21 PAGE 29 of 29 PSVP
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