ML20212P337
| ML20212P337 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 06/05/1986 |
| From: | FLORIDA POWER CORP. |
| To: | |
| Shared Package | |
| ML20212N983 | List:
|
| References | |
| SP-435, NUDOCS 8703160072 | |
| Download: ML20212P337 (22) | |
Text
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C. R. NLcicar SURVEILLANCE PROCEDURE SP-435 FLORIDA POWER CORPORATION CRYSTAL RIVER UNIT 3 VALVE TESTING DURING COLD SHUTDOWN THIS PROCEDURE ADDRESSES SAFETY RELATED COMPONENTS APPROVED BY:
sPonsible tion Superintendent /
S erv' or
/-
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fe ~ $~ k Date INTERPRETATION CONTACT: Nuclear Reliability Supervisor 8703160072 870305 PDR ADOCK 05000302 P
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PART 2 SAF TY EVAL.UATION: Answer tne following cuestions and provide specific justification (use attacnment if necessary 1.is tne preenedity of an occurrence or tne consequence of an accident or maifunction of equipment important to safety as previously evaluated in the Final Safety Analysis Report. INCREASED?
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4 ve t.a s 2 is tne possiedity for a,n accident or malfunction of a different type otner tnan any previously evaluated in tFe Final Saf ety Anaiysis Report CREATED 7 a Yee,,GrNo Because: 44 ev e s.,
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t LICENSE REVISION REQUIRED: Final Safety Analysis Report C Yes,.4 No Technical Specification O Yes,IIs"No NRC Autnort2ation for Change Required C Yes,,J No (
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Semi Annual Reporting to NRC Required O Yes Alp' No.
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PROCEDU E APPROVALS PART 3 INTERIM CHANGE RESCINDED PART4
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Initial /Date 8.0 PernFOUISITES 8.1 Prior to commencement of surveillance, review Data Sheets I, II, and III, and Step 6.6 of this procedure.
/
l 8.2 Notify the Nuclear Shift Supervisor on duty prior to performance of this procedure.
8.3 The time-stroke measurements of the DH valves on Data Sheet II are to be done in coordination with the execution of OP-404, Decay Heat Removal System, Step 8.1.3.1.
/
NOTE:
If these valves have been completed within the last three months, N/A this step.
8.4 The time-stroke measurements of the RC valves on Data Sheet II are to be done in coordination with the
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I execution of OP-209, Plant Cooldown, Step 7.2.10.1.
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6 C R STEP 9.f 7
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If these valves have been completed within the
$p last three months, N/A this step.
9.0 TasTancTInan l
NOTE: On Data Sheets II and III, the " Observed Stroke Time" colema will designate the direction in l
which the stroke time is to be measured.
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Initial /0 ate 9.1 Complete Data Sheet II during power descent into cold shutdown.
9.2 Isolate MUV-253's actuator air supply and bleed the isolated air through the solenoid; record observation on Data Sheet III (Page 1 of 3).
9.3 Complete ' Power Loss Verification' and record stroke time for the appropriate valves of Data Sheet III, Part
'A*.
NOTE:
For all valves in Part
'A*, except MUV-253, verification of actuator power loss is fulfilled by stroking of valve.
9.4 Insure MUV-64 is open.
/
9.4.1 Open DHV-11.
/
9.4.2 Record makeup tank (MUT) fluid level indicated on MU-14-LR on Data Sheet III, Part "C" (Page 3 of 3).
9.4.3 observe the MUT level indicator for a minimum of 15 l
min.
9.4.4 Record MUT fluid level af ter the allotted time has expired on Data Sheet III, Part
'C' (Page 3 of 3).
9.4.5 If an increase in fluid has not occurred, initial the appropriate data space of Data Sheet III, verifying that check valve MUV-65 is closed.
9.4.6 ose DHV-11.
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SP-435 Rev. 1 7 Page 8 i
Initial /Date 9.5 This portion of the procedure requires approximately 200 ft. of hose for carrying desineralized water and approximately 1 hr. of hold time af ter hose is in place.
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9.5.1 Close DW-196.
/
9.5.2 close CGV-53.
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9.5.3 open DW-160.
/
9.5.4 Connect a desineralized water hose from any convenient source outside containment to any convenient deminer-alized water hose connection inside containment.
/
9.5.5 Open DW-159.
/
9.5.6 When water stops coming from DW-159, pressurize the downstream side of DW-162 by valving in the desiner-alized water hose connected in Step 9.5.4.
/
9.5.7 Collect the leakage from DW-159 for 1 hr.
Record the initial and final time, and the leakage on Data Sheet III, Part
'D'.
9.5.8 If the leakage is less than 1 gal, per hour, DW-162 is verified closed.
9.5.9 Isolate and remove the demineralized water hose connected in Step 9.5.4.
/
9.5.10 Open DW-196.
/
9.5.11 No additional restoration is necessary.
9.6 Stroke test and flow verification of EFV-1 and ETV-2.
SP-435 Rev. 1 7 Page 9
=
Initial /Cate 9.6.1 Initial Conditions a.
Main Condenser (CDHE-4B).
(1)
No vacuum exists in CDHE-4B.
(2)
CDHE 4B is available to receive approxi-mately 12,000 gallons of water.
b.
Condensate Storage Tank (CDT-1).
(1)
CDT-1 is not supplying water to another q
tank or system.
(2)
CDT-1 is not receiving water from another source.
/
(3)
CDT-1 level is stable (CD-67-L12).
/
c.
Valve lineup.
(1)
EW-3 is open.
(2)
EW-4 is open.
/
(3)
EW-1 is shut.
/
(4)
EW-2 is shut.
/
(5)
EW-36 is open.
/
d.
EFWP's are not running.
/
b.
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SP-435 Rev. 1 7,. j Page 10
/
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e Tr.1-a'_ ca e 9.6.4 Restore affected EF valves to pcsitions appropriate f
for plant conditions.
9.7 Ccaplete Data Sheet III and verify that each valve is restored to its NORMAL position by completing the
' Restoration Position' column with appropriate mark
(*0* for open,
'C' for closed).
9.8 (DELETED) 0.".'
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SP-435 Rev. ] 7 Page 12
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9.10.1 Ensure the following valves are:
ETV-55 in manual operation and closed.
/ JUNQ31 ETV-56 in manual operation and closed.
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ETV-57 in manual operation and closed.
'Juu o o tag ETV-58 in manual operation and closed.
4 )/ JUN 0 9 9.10.2 Open or verify open the following valves:
EFV-3 Open b, JUN 09 ETV-4 Open JN09' ETV-7 Open
/ "'N 0 9 !!
ETV-8 Open i JUN 09 ETV-11 Open i JUN 091
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ETV-14 Open
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ETV-32 Open
' JUN O 919
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EIV-33 Open
' JUW n R ]
9.10.3 Ensure the following valves are closed:
ASV-5/204 closed i JUN 0 9 !
FWV-34 Closed
/ JUN09 i FWV-35 Closed
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9.10.4 Manually start ETP-1 by using the
- pistol-grip' I,
i control handle on the main control board, having flow l
t j
initially recirculating back to the condensate Storage 10'7r644q T
l 9.10.5 Manually open EFV-57 and EFV-58 :: * ^^t : c r. w a f/ /
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I li SP-435 Rev. 1 7 Page15(ContinuedodPage15a) i./
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9.10.6 Record flow through the following flow indicators:
EF-23-FI 22.0 gym
> EFV-16 Open TlhT ' G $ d'
- > FWV-44 Open WTI < 0 -4%
EF-25-FI
~2 4 0 gym
> EFV-15 open 2 07 G -9 %
- > FWV-43 Open
> (z. CrSk 9.10.7 Close EFv-57 and ETV-58.
O.417>& 4-M; 9.10.8 Shut down and secure EFP-1.
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9.10.9 Flow verification in Step 9.10.6 verifies EFV-6 and ETV-7 opened.
(LN - {p b 9.10.10 Manually start ETP-2 by opening the auxiliary steas valves ASV-5/204, having flow initially recirculating back to the Condensate Storage Tank.
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' 4. m 4(4 9.10.11 Bring pump speed up to 4030 rpm.
Crc
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- 00'. s W/ e /L., co-c ~ 4 / $-4 9.10.12 Manually open ETV-55 and EFv-56 ::eafei*e l. e *= 4 k r ki n d p c..
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e.C ~so on-is e + y 9.os.13, 9.10.13 Record flow through the following indicators:
EF-24-FI RJo Mm gpm - > EFV-16 Open r A 'd m _n EF-26-FI R Vo gym - > EFV-17 Open c e Z
.-Pt 9.10.14 Close ETV-55 and EFV-56.
ce 'z-/c tt 9.10.15 Shut down and secure EFP-2.
'4 -/c -k 9.10.16 Flow verification in Step 9.10.13 verifies ETV-5 and ETV-8 opened.
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i SP-435 Rev. 1 7 Page 154 (Continued on Page 15b)
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Initial /Cate 9.10.17 Restore the following valves to their proper operational status:
ETV-55 automatic c
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EFV-56 automatic Aw_
/4-mW j EFV-57 automatic emv / 4-/o-N EFV-58 automatic ce 't-u#4 9.11 Inform the Shift Supervisor of the completion of this i
Surveillance Procedure and of the test results.
em /4 r#
10.0 sYsTot nrsronATrow 10.1 Restoration completed as noted in Section 9.0.
11.0 CONTIMcFMcIES 11.1 If a valve's stroke time is within the " Alert Range
- or exceeds the maximum allowable stroke time, refer immediately to CP-102, Inservice Inspection Pump and Valve Data Review and Corrective Action, for correc-tive action.
41
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!l SP-435 Rev. 1 7 Page 15b
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-DATA SHEET I-ENCLOSURE t VALVE TESTING DURING COLD SHUTDOWN
-Explanation of Enclosures-Before a non-asterisk denoted valve, shown on data sheets, is manipulated to measure stroke time, the valve's initial (NORMAL) position shall be compared to the associated remote indicator's designated position.
The FULL-STROKE position of the valve and the reacte indicator shall also be c0mpared.
The top of the valve sten shall correspond to a marking implanted upon the stem housing when in the NORMAL position and in the FULL-STROKE position (or other methods which verify that remote indicators are reflective of valve stem position).
The asterisk-denoted valves' positions shall be compared at least as frequently as scheduled refueling outages with at least one (1) comparison being made every 2 yrs.
If comparison is not to be performed, the data space shall be marked 'Not Applicable" (NA).
i Each valve shall be restored to its NORMAL POSITION by completing the l
' Restoration Position" column with the appropriate mark (0 or C).
If a valve's stroke time is within the " Alert Range" or exceeds the maximum allowable stroke time, refer to Section 11.0, Contingencies.
Performed By Date G-ll- %
Time ObdC Checked By Date [^ O-Time Ob/
SP-435 Rev. 17 Page 17 I
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C Acceotanc. Cni.ria Nor uET and O Ai.rt aans. Acceotance Cnt.na C unsatis+ c::ry; a-ec:,e Corrective Measures initiated NOT MET N as ses *ni:: ate:
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PART 1 C New (lTC M-Day Review Required On b Wk bb - b ~
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I TITLE PROCEDURE NO.
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PART 2 SAFETY EVALUATION: Answer the follow.cg questions and provide specific ju:tification p.se attachment if necessary) 1.ls the probability of an occurrence or the consequenc6' of an accident or malfunction of equipment important to safety as previously evaluated in the Final Spfety Analyps Report, INCREASED 7 A
i s, < o r clwp e incl < le.s ^ a ok.ha, / p'c l L LQ C Yes N No Because:
o l~6,,r
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SP-4 W rn.n 3.ls the margin i safety, as defined in the basis for any Technidt Specification, REDUCED? O Yes y No S1.5 Biss;s "si Am=<- 7.c ')
LICENSE REVISION REQUIRED: Final Safety Analys'is Reec:t O Yes d No l
Technical Specification C Yes d No NRC Authorization for CM.nge Required O Yes dr No (See bacir for Check'ist) l Semi Annual Reporting to NRC Required Yes ( No.
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1 PROCEDURE APPROVALS PART 3 INTERIM CHANGE RESCINDED PART4 i
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SGTR REV 04 Date 10/31/86 EP-390 i
s STEAM GENERATOR TUBE RUPTURE l
ENTRY SYMPTOMS 1.
OTSG steam line radiation monitor alarm (s)., '
2.
Radiation monitor alarm (s) on RM-A2, RM-A4, and RM-A12.
THIS PROCEDURE ADDRESSES SAFETY RELATED COMPONENTS i
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Date 10/31/86 Mtg.#
86-44 Approved By NPM d
Date
//
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SGTR REV 04 Date 10/31/86 EP-390 ACTIONS IMMEDIATE REMEDIAL 1.
Close:
Close:
o MUV-49 o
MUV-50 o
MUV-51 2.
Start load reduction at J. 5%/ MIN.
Refer to OP-204, Power Operation.
SGTR REV 04 Date 10/31/86 EP-390 FOLLOW-UP ACTIONS DETAILS 1.
Maintain PZR level II unable to maintain PZR level 100" - 220".
constant with normal makeup, THEN:
a.
Open BWST suction to MUPs b.
Start second MUP c.
Open one or more HPI valves o
MUV-23 o
MUV-25 o
MUV-24 o
MUV-26.
2.
II reactor tripped by RPS, Refer to AP-580, Reactor THEN go to Follow-up step 6.
Protection System Actuation.
3.
II unable to maintain PZR level 2 100",
THEN o
Trip reactor o
Go to Follow-up step 6 i
i o
Refer AP-580.
Refer to Reactor Protection System Actuation.
l l
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SGTR REV 04 Date 10/31/86 Ep-390 FOLLOW-Up (Cont'd)
ACTIONS DETAILS 4.
WHEN < 12% reactor power, WHEN < 12% reactor power, AHD MS pressure controlled THEN:
by TBVs, a.
Select Turbine Mode:
THEN trip turbine.
o
" MANUAL" QE o
"OpER-AUTO" b.
Lower turbine-generator load to ~ 50 MWE c.
Ensure header pressure is controlled by TBVs.
d.
Trip Turbine and ensure output BKRs open.
5.
WHEN reactor power is 1 5%,
NOTE:
When reactor is tripped turbine bypass valve THEN:
setpoint goes to 1010#.
o Trip reactor o
Refer to Ap-580.
Refer to Reactor protection System Actuation.
Ep-390 page 4 of 13 SGTR
A SGTR REV 04 Date 10/31/86 EP-390 FOLLOW-UP (Cont'd)
DETAILS ACTIONS 6.
II subcooling margin < 0, THEN go to EP-290.
Go to Inadequate Core Cooling.
NOTE:
If RCP's have not been stopped within 2 minutes upon detection of inadequate Subcooling Margin, they must be kept running.
7.
II adequate subcooling margin RC SUBCOOLING does HQI exist, PRESSURE MARGIN THEN:
- F o
Establish full HPI
> 1500 20 o
Stop all RCPs 1 1500 50 o
Refer to AP-380.
Refer to Engineered Safeguard System Actuation.
NOTE:
When adequate Subcooling Margin is restored, it is desirable to restart at least one RCP per loop to aid in RCS depressuriza-tion and cooldown.
8.
Maintain PZR level 1 100".
E SGTR REV 04 Date 10/31/86 EP-390 FOLLOW-UP fCent'd)
ACTIONS DETAILS 9.
Start:
o cooldown with both OTSGs.
o Depressurization of RC o
De-engergize PZR heaters.
o Cooldown of RC o
Establish:
PZR spray OR Open PORV if RCP's are lost.
o Maintain minimum subcooling margin.
10.
IE.:.
o Cooldown at i 100*F/HR o
Main condenser is o
Maintain OTSG tube-to-shell available AT I 100*F.
AND o
Maintain RC PRESS AHD TEMP above fuel pin compression o
Normal makeup (MUV-31) curve per Enclosure 1.
is maintaining PZR level AND o
RCPs operating, THEN:
a.
Establish normal cooldown limits.
b.
Go to Follow-Up step 12.
SGTR REV 04 Date 10/31/86 EP-390 FOLLOW-UP (Cont'd)
ACTIONS DETAILS 11.
IE main condenser is HQI o
WHEN RC TEMP > 500*F, available THEN cooldown at 1 240*F/HR.
QR HPI is required to maintain PZR level o
WHEN RC TEMP 1 SOO*F QR RCPs are HQI operating, THEN cooldown at i 100*F/HR THEN establish emergency o
Maintain OTSG tube-to-shell cooldown limits.
AT I 150*F.
o Fuel pins in compression limits may be violated as necessary, per Enclosure 1.
i 12.
Determine affected OTSG.
o Observe MS radiation monitors o
Compare OTSG levels and feed flows.
I o
Notify Health Physics to survey main steam lines.
I 13.
II affected OTSG can HQI be i
identified, CONDITION LEVEL THEN establish required o Any RCP operating Low Level OTSG level in both OTSG's.
Limit o No RCP's 655 (Refer to o Adequate Subcooling AP-530)
Margin o Less than Adequate 955 Subcooling Margin (Refer to AP-380) o < 2 HPI pumps 955 available EP-390 Page 7 of 13 SGTR
~ _. _ _ _ _ _ _ _ _ _. _ _ _.,...
SGTR REV 04 Date 10/31/86 EP-390 FOLLOW-UP (Cont'd)
ACTIONS DETAILS 14.
WHEN affected OTSG has been Isolate from affected OTSG:
identified, o
FW Pump Turbine Steam Supply THEN isolate Aux loads from affected OTSG.
o Aux Steam Supply o
Gland Steam' Supply o
EFP-2 Steam Supply o
Deaerator Steam Supply 15.
WHEN RC T 1 540*F, CONDITION LEVEL H
THEN-o Any RCP operating Low Level a.
Stop steaming affected Limit OTSG o
HQ RCPs 6 5 *.
b.
Establish required (Refer level in unaffected 6
Adequate to OTSG subcooling margin AP-530) c.
Go to Follow-up step o
Less than adequate 95S.
,17.
subcooling margin (Refer to AP-380) o
< 2 HPI pumps available 95%
l SGTR REV 04 Date 10/31/86 EP-390 FOLLOW-UP (Cont'd)
ACTIONS DETAILS 16.
II BWST volume is determined o
Based on BWST usage rate vs.
to be insufficient for time to cooldown at existing completion of plant cooldown cooldown rate, the operator due to a large type of tube will use this information and leak / rupture, sound judgement to determine necessity to steam affected THEN it is permissible to OTSG to aid in RCS cooldown.
steam the affected OTSG, as necessary, as long as o
Cooldown with both OTSG's 100*F/HR cooldown rate is via:
not exceeded.
Turbine Bypass Valves RE Atmospheric Dump Valves if condenser is not available NOTE:
If 1 OTSG can maintain 100*F/HR cooldown rate, do HQI steam affected OTSG for cooldown rate purposes.
Ep-390 Page 9 of 13 SGTR
L SGTR REV 04 Date 10/31/86 EP-390 FOLLOW-UP (Cont'd)
ACTIONS DETAILS 17.
Maintain affected OTSG(s)
OTSC tube to shell 6T limits:
by:
Normal cooldown - 100*F o
Feeding for Emergency cooldown - 150*F Low level limit RC SUBCOOLING Tube-to-shell AT PRESSURE MARGIN o
Steaming for PSIG
- F Level < 9 5 *.
> 1500 20 OTSG PRESS < 1000 1 1500 50 PSIG Promotion of Natural Circula-tion Subcooling margin limits Cooldown of up to 100*F/HR, when BWST volume is insufficient for complete cooldown I
18.
WHEN RC PRESS < 1700 PSIG, o
RC-1 AHD HPI has n21 actuated, o
RC-2 AHD cooldown is controlled o
RC-3.
THEN bypass HPI o
"A" AHD o
"B".
s SGTR REV 04 Date 10/31/86 EP-390 FOLLOW-UP (Cont'd)
ACTIONS DETAILS 19.
WHEN RC T 500 - 510*F Maintain RCP-1B running if c
establish 1 RCP in each possible loop.
20.
WHEN RC Tc < 500*F, o
Cooldown at 1 100*F/HR THEN:
RC PRESSURE SUBCOOLING MARGIN o
Continue cooldown at maximum rate PSIG
- F o
Minimize subcooling
> 1500 2 20 margin 1 1500 2 50 NOTE:
21.
WHEM OTSG pressure is < 725 II unaffected generator PSIG and > 600 PSIG, approaches 600 PSIG THEN bypass OTSG AHQ the affected generator remains > 725 PSIG isolations.
THEN it may require:
I o
Stopping cooldown to allow pressures to equalize j
o Steam affected generator to lower its pressure to < 725
[
I PSIG Depress "< 725 PSI OTSG press EFIC ACT. BYPASS" pushbuttons for:
Channels A, B,
C, D.
i 1
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4 SGTR REV 04 Date 10/31/86 EP-390 FOLLOW-UP (Cont'd)
ACTIONS DETAILS 22.
WHEN RC PRESS < 900 PSIG, o
RC-4 o
RC-6 m cooldown is controlled, o
RC-5 THEN bypass LPI.
o "A"
M o
"B" 23.
Continue RC depressurization o
Refer to OP-209, Plant and cooldown to atmospheric Cooldown.
pressure.
NOTE:
When on Decay Heat System Cooling, Nitrogen may be placed on OTSG's to further reduce /stop the PRI/SEC leak out to the Secondary System.
l l
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SGTR REV 04 Date 10/31/86 EP-390 ENCLOSURE 1
^
FUEL PIN COMPRESSIOS 2600 i
i i
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2400 2200 2000 1800 52 m
a 1600 m
.@ 1400 E
f a
NO RCPs
\\
1200
~
1000 i
.2 2 RCPs I
1 800 l
l 600 I
I 400 200 O
00 200 300 400 500 600 RC TEMP,TC EP-390 Page 13 of 13 SGTR
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