ML20126M444

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Revised Procedures,Including Rev 20 to VP-580, Plant Safety Verification Procedure & Rev 4 to AR-958, Wdh Annunciator Response
ML20126M444
Person / Time
Site: Crystal River 
Issue date: 12/16/1992
From: Marshall W
FLORIDA POWER CORP.
To:
References
PROC-921216, NUDOCS 9301080302
Download: ML20126M444 (25)
v • d • e


Text

.

l 1

I DOCUMENT TRANSMITTAL FORM 83273 80 3#A FOR DOCUMENTS TRANSMITTED TO DC DESK (NRC H DATE: 16 DEC 1992 D ATC H:

100 DOCUMENT NUMBER SHEET NUMDER REVISION NUMBER COPY NUMBER AR 958 04 24 VP 500 20 20 INSTRUCTIONS TO THE ADDRESSEE

--.------~~-

COMPLETE EACH OF THE INSTRUCTIONS DELOW WHICH ARE MARKED WITH AN "X

_X _ (1) VERIFY THE DOCUMENTS RECEIVED AGREE WITH THE ABOVE DESCRIPTION

_X _. (2) INCORPORATE THE TRANSMITTED DOCUMENTS INTO YOUR FILES

_X_

(3) DESTROY DOCUMENTS OR PORTIONS OF DOCUMENTS SUPERSEDED BY THE AGOVE

_ x _, (4; SIGN AND DATE IN THE SPACES BELOW INDICATING THAT YOU COMPLETED THESE INST 6UCTIONS.

(5: SIGN BELOW INDICATING THAT YOU HAVE READ AND UNDERSTOOD THE CHANGES AS IDENTIFIED X

( 6 _5 RETURN O DOCUMENT CONTROL, CRYSTAL RIVER UNIT 3, MAC#

NA1C NR2A _

SAIG FLORIDA POWER CORP.

P. O.

BOX 219 CRYSTAL RIVER FLA-34423-0219 (7' OUALITY PROGRAMS PERSONNEL HAVE READ AND UNDERSTCOD THE CHANCES TO THE AFFECTED G AP 'S SI-GUATURE OF ADDPESSEE DATE I N Dif'F;. DEN T Vt R IF IC ATION DATE (CPS) 080028 (DN4 9301080302 921216 0\\

1 PDR ADOCK 05000302 F

PDR i

Q PSVP REV. 20 DATE 11/25/92 VP-580 M

l PLANT SAFETY VERIFICATION PROCEDURE

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O This Procedure Addresses Safety Related Components ApprovedbyNSSh3

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VP-580 REV 20--

PAGE 1 of 19 PSVP

1.0 REACTIVITY CONTROL

\\

ACTIONS DETAllS 1.1 E Rx tripped, o CR0 Groups l thru 7 are fully THEN verify'Immediate Actions inserted.

Of AP-580, Rx Trip, are completed, o Intermediate range flux -

decreasing or source range detectors energized and decreasing.

o TVs or GVs closed, o " MAIN FW BLOCK"s closed.

o "LO LOAD FW-BLOCK"s closed.

o.PZR level 2 50 inches.

o Steam Hdr PRESS = 1010 psig, o Output Bkrs open.

o Verify ICS and NNI power is available.

Note NI-14-nil and NI-15-nil, neutron flux monitors may not bc.

reliable under accident conditions, due to cable assemblies possibly leaking.

1.2 E Neutron flux is o' Refer to EP-140, Emergency NOT decreasing, Reactivity. Control.

THEN verify Emergency Boration e.

l VP-580 REV 20 PAGE 2 of 19 PSVP

4 J.10 REACTIVITY CONTROL (CONT'D)

' ACTIONS DETAILS

~

1.3 If >1 control rod NOT fully o -If > 1 control rod-is stuck

inserted, THEN continue-boration until THEN verify Emergency Boration either of the following:

o Actual boron concentration-2.1925 ppmb OR.-

o Actual boron concentration 2 value determined by the Reactor Engineer 1.4 Jf Rx is NOT tripped, o Limiting Safety System Setting T!iEN observe plant parameters exceeded.

AND determine if Rx should be tripped.

o 2 or more MSIVs are closed.

o All MFW is' lost 2 15% FP.

o PZR level 2 290 inches.

o PZR level cannot be maintained

-> 100 inches during SGTR with.

HPI.

o SWT-1 < 1 ft. and level.cannot be restored, o SW flow is lost and cannot be restored.

O.

2 or more CROM stator TEMPS 2 180* F 1.'5. Verify 480V Bkrs are closed:

o 8kr 3305 o 8kr_3312:

a O

VP-580 REV_20 PAGE 3 of 19-PSVP

2.0 THERMAL CONTROL ACTIONS DETAILS ~

2.1 Verify RCS heat production is o SPDS indicates' stable te.ap, &

balanced.to OTSG heat removal press. and parameters are-within the post trip box.

o IF NOT, THEN determine cause of~

mismatch and make appropriate.

recommendations.

~

o if unexplained and significant' RC pressure decrease exists, THEN ensure proper operation:

o RCV-10, PORV o

RCV-14, PZR Spray Valve o

PZR Heaters o IF SPDS is NOT operable, THEN record RCS PRESS and TEMP on Enclosure 1 until plant is stable for ='30 min.

Note Due to possible high radiation conditions, Th and Tc indications may become unreliable-24 hrs after a LOCA.

2.2 If RCP's are NOT operating, Indications of Nat Circ:

THEN verify Nat Circ. exists or is developing.

o Verify Tc = Tsat 'of-OTSG.-

IE Nat Circ is NOT verified o Verify core AT develops and-AND adequate subcooling stabilizes, margin exists, IHEN refer to AP-530,.

o Verify incore TEMPS follows -

Natural Circulation.

Th within 10' F.

o WHEN OTSG PRESS is lowered, THEN verify Tc, incore TEMPS, and Th'iower.

a O

VP-S80-REV 20 PAGE 4 of 19 PSVP

9 2.0 THERMAL CONTROL-(CONT'0.1 ACTIONS DETAllS Note contains EFW inventory-requirements during a loss of offsite power cooldown to DHR.

2.3 lE Nat Circ exists, Nat Circ Cooldown Rates THEN verify proper Nat Circ coo'down rate.

RCS Tc -

  • F/hr

> 280*F s 10*F 280 to 150*F s 5'F

< 150*

s 2.5'F s 50*F

  • Only to be used if RCS PRESS is maintained above Nat Circ cooldown curve.

2.4 if Adequate subcooling margin Tsat Monitor-does NOT exist, Adequate Subcooling Margin IBfB verify:

o Full HPI or LPI flow, Reactor Coolant MARGIN o No RCPs operating,

.> 1500 psig 30*F.

o OTSGs at 95%

5 1500 to > 250-psig

50
  • F-s 250 to > 150 psig 70*F s 150 psig.

SPDS.

f s 200*F N/A o-Refer to AP-380, ES Actuation.

o -Refer to AP-360, Loss of DHR.

EO i

VP-580-REV-20 PAGE 5 of 19

.PSVP L

2.0 THERMAL CONTROL (CONT'D)

ACTIONS DETAILS 1 -

2.5 IE HPI actuated, THEN verify HPI flows balanced-and MUV-27 closed.

2.6 IE RCS PRESS is > 2400 psig, Refer to SPDS AND abnormal or ItifN verify PORV emergency operating procedures QB high point vents are in use to determine RCS PRESS used to reduce RCS PRESS.

limits.

2.7 E RCS pressure is s 200 psig 0P-404, Decay Heat Removal AND adequate subcooling margin System, Section 4.13,-Long-

-does not exist Term Post-Accident Cooling.

THEN verify boron precipitation actions are complete within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of the event.

2.8 IE any of the following STS cooldown rate limits:

conditions exist:

o RCPs t!0T operating,-

RCS. TEMP

  • F_

RATE LIMIT'

. At[D HPI flow exists

_through any nozzle while

> 280 s 50* 4 hr-RCS TEMP is < 500*F.

280 to 151 s 25* ) hr o STS cooldown rate limits exceeded while RCS TEMP

$ 150 s 10*F/hr-is < 380*F.

ItiEll verify EP-220, PTS, is being performed.

a i -

V P-580_-

REV 20 PAGE 6 'of 19 PSVP-

=

C.

2.0 THFJMAL CONTROL (CONT'.D).

Q "s

ACTIONS DETAILS m

2.9 1E Subcooling Margin is > 100*F, THEN verify-operation in accordance with abnormal and emergency operating procedure in use:

o HPI,LPI o MFW, EFW, EFIC o OTSG PRESS and level.

2.10 Verify required 0TSG level.

Required 0TSG levels Condition Level-

-Inadequate 80%-90%

subcooling margin.

NO RCPs 60%-70%-

and adequate subcooling margi, RCPs low and adequate.

Level subcooling margin Limits 1E OTSG Tube leak exists, AND adeq; ate subcooling margin does NOT exist, AND 2 2 HPI pumps are available, THEN verify affected 0TSG is' NOT being fed.

2.11 if EFW and MFW are NOT available, JH Q verify HPl\\PORV cooling.

2'.'12 1E OTSG' Tube Rupture has Refer to EP-390, OTSG. Tube

occurred, Leak.

IUfB verify proper cooldown 4

(f VP-580 REV-20 PAGE 7 of 19 PSVP

-2,0-THERMALCONTROL(CONT'DI ACTIONS DETAILS 2.13 lE incores indicate superheated Instrumentation for monitoring -

conditions, RCS inventory:

THEN verify EP-290, Inadequate Core Cooling,-

o Reactor Coolant Inventory is being performed Tracking System - will be AND monitor RCS inventory.

affected by HPI, LPI, or Natural Circulation flow.

o Reactor Coolant 1 Pump Void Trend Monitoring-System is-effective only when RCPs are operating.

1 O

a 0

-VP 580 REV 20 PAGE 8 of 19 PSVP

P

'3.0 'RADI0 ACTIVE INVENTORY CONTROL I

ACTIOyl DETAILS 3.1 Observe _ radiation monitors IE any monitor is_ indicating, for unexplained' trends.

an unexplained upward trend-THEN' advise SS00 of trend OR 1E any monitor is in alarm, THEN refer to AP-250, Radiation Monitor actuation.

3.2 Observe MS radiation monitors IE.any MS radiation monitor and RMA-12 for unexplained or RNA-12 indicates 0TSG leakage, trends.

THEN refer to EP-390, Steam Generatnr Tube Leak.

3.3 Observe for increased RCS o Observe:

leakage.

o RCP seals and dumpsters,.

(f a PZR level, 7

o RCDT. level, o MUT level, o hd sump level,

.o -Relief valve tailpipe TEMPS.

o-Refer to STS 3.4.6.2,.

Operational Leakage.

3.4 Verify fuel integrity.

Observe RML-1 Alarms _and-trends, a

O VP-580 REV 20 PAGE 9 of 19 PSVP-

9 4.0 E0VIPMENT AVAILABILITY ACTIONS

.DETA I L S -

4.1 Verify availability of borated o MUT level water sources for HPI/LPI pumps.

o-BWST level IF NOT, THEN REFER T0:

o If in Modes 1, 2 or 3, AP-380, ES Actuation, o If in Modes 4, 5 or 6, AP-360, loss of DHR.

4.2 Verify availability of HPI, o Cooling water - SW,RW,DC LPI and BS pumps, o Max flow for HPI pump 540 gpm o Min flow for, HPI pump with recirc valve closed 100 gpm.

o With suction from RB sump Os limit LPI_. flow to = 2000 gpm

& BS' flow to =-1200 gpm per train.

4.3 Verify water scarces for OTSG o EF Tank level 215 ft.

cooling.

o = CST level 2 5 ft.

o Hotwell level at.7-to 9 ft.

84 to 109 inches, o See~ Enclosure 2 for EFW requirements.

o See Enclosure 3 for other sources of water.

4.4 jf RCS PRESS < 600 psig i

AND adequate subcooling margin

- does fiQI ex i s t,

l THEN verify CFTs not isolated.

4 O

VP-580 REV 20 PAGE 10 of 19 PSVP

i 4.0 EQUIPMENT AVAILABILITY (CONT'D)-

7-t ACTIONS DETAILS

~

4.5 Verify SW and RW available o SW PRESS 2 110 psig.

.and SW cooling to the RCP's.

o Stable SW & RW Motor' Current.

IE.N0T, THEN ENSURE AP-330,.

LOSS of SW, is being performed.

4.6 Verify DC Cooling, if required.

o Stable DCP motor current' and discharge PRESS.

1E NOT, THEN ensure AP-360, Loss of a DC Heat Exchanger Outlet DH, is being performed.

TEMP < 105 F.

4,7 Verify ES busses energized &

o ES 4160V "A"

& "B".

Instrumentation power avai?)ble, o ES 480V "A"

& "B".

o ICS,- NNI-X and NNI-Y.

O 4.8 lE offsite power is NOT 1E within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> offsite available, power has-NOT been restored,-

AND offsite power will NOT be AND 2 EDGs are running restored within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, THEN notify the SS00 to:

THEN' verify EDG operation is within fuel oil consumption-o Order additional fuel oil limits and fuel oil reserves for emergency delivery are adequate.

within next 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />.

o Reduce'and maintain combined'EDG loads to s 2330 KW within next 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br />.

J 4.9 Verify Instrument Air pressure IA & SA low pressure alarms'at-available.

s 85 psig.

o SA-4-PI o IA-4-PI Db t'

VP-580 REV 20 PAGE 11 of 19 PSVP

L 1

4.0 EQUIPMENT AVAILABILITY (CONT'0)

\\'

ACTIONS DETAILS 4.10 Verify EFW available, o EFW is required when:

- o MFW not available or o No RCPs operating or o Adequate SCM does not' exist 4.11 Evaluate RB temp. & press.

o Strip charts located on AND inform SS00 of any-back of main control' board.

abnormalities.

4.12 MHEN VP 580 is stopped, THEN notify $500.

Note 1

Enclosures 4 through 7.are flow diagrams which provide an overview of symptom oriented transients:

o Enclosure 4 - LOSS OF SUBC00 LING MARGIN o -Enclosure 5 - INADEQUATE-CORE COOLING o Enclosure 6 - EXCESSIVE HEAT TRANSFER o Enclosure 7 - STEAM GENERATOR TUBE RUPTURE Note When the plant has been placed in a stable safe condition then review Emergency Plan Classifications and NRC reporting requirements. Perform AI-704 as time permits.

a o

VP-580 REV 20 PAGE 12 of 19 PSVP V

e

' ENCLOSURE 1-Cooldown Curve for Natural-Circulation and forced Flow

. (

2600; NORMAL POST TRIP WINDOW 2400

s..

\\

2200 NDT CURVE!

2000 ASCM CURVE 1800

\\-

$ 1600 I9 c.

NATURAL

  • 1400 CIRCULATION CURVE

.! 1200

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(9 OA 2

Q, 1000 O

800 E

s 600 SATURATION :

CURVE 400

'l 200i l

+

0I 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 i' sft of the Natural Circulation curve-if

~

RCPs are off,-

.~oldown rate 210 F/hr

'VP-580-

.REV 20-PAGE 13 of-19 PSVP

ENCLOSURE 2 Cooldown Requirements Vs. Hat Circ Cooldown Rates 1)

FW requirements and the time to cocidown 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.

4)

The minimum cooldown rate consistent with the above minimum time and FW requirements is-about 8.5'F/hr.

5)

Cooldown rates in excess of 8.5'F/hr do not decrease the FW or time requirements for cooldown.

6)

Cooldown rates less than 8.5'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*F/hr is then utilized.

For smaller time delays smaller cooldown rates may be utilized.

O 4

a LO VP 580 REV 20 PAGE 14 of 19 PSVP

-i ENCLOSURE 3-Sources of-Emergency Feedwater (EFW)-at the Crystal River ~Sitef

+

Condensate - Grade Sources

-Source Volume (cal)

Dedicated EFW Tank (EFT-2) 150,000 Condensate Storage Tank 139,000 Condenser Hotwells 150,000 DW Storage Tank, Unit 3.

450,000.

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' CD Sterage. Tank, Unit 5 500,000 AB DW Storage Tank, Unit 3 5,000 O

t 3

4

~

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.VP-580 REV 20 PAGE -15 of 19

-PSVP:

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ENCLOSURE 5 Inadequate Core Cooling i

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VP-580

.REV 20 PAGE 17 of.19

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N VP-580

.REV 20 PAGE 18 of 19 PSVP

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L ENCLOSURE 7 Steam Generator Tube Rupture 1_

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VP-580.

REV 20 PAGE 19 of 19

.PSVP

Rev. 4-12/09/92 Effective Date

/o8 /d 92

"' i =

--.adf "hNb,j{

Document Section t

l NF O R M ATION ONL_

2 g

l C. R. Nucicer l==: _

_ - 7_g ANNUNCIATOR RESPONSE AR-958 FLORIDA POWER CORPORATION CRYSTAL. RIVER UNIT 3 l

WOH ANNUNCIATOR RESPONSE THIS PROCEDURE ADDRESSES SAFETY RELATED COMPONENTS APPROVED BY:

Interpretation Contact h

h AA<L rt DATE:

/d

/7--

Interpretation

Contact:

Manager, Nuclear Dlant Operations l

-.s

. TABLE OF CONTENTS

.Q.

D' SECTION PAGE-1.0 PURPOSE............

1

2.0 REFERENCES

1 2.1 IMPLEMENTING REFERENCES....

I 2.2 DEVELOPMENTAL REFERENCES 1

3.0 PERSONNEL INDOCTRINATION 1-4.0 INSTRUCTIONS 1

5.0 FOLLOW-UP ACTIONS.

1 ENCLOSURE 1

Annunciator Response 2

O v

1 AR-958 Rev. 4 Page i

1.0 PURPOSE

-t 1.1 Establish a reference document for each Annunciator Window on the WO-WV Panel Lampbox.

1.2 Establish operator actions for valid Annunciator alarms on the WD-WV Panel Lampbox.

1.3 Establish a reference to other procedures which address operator actions for valid Annunciator alarms on the WD-WV Panel Lampbox.

2.0 REFERENCES

2.1 IMPLEMENTING REFERENCES None 2.2 DEVELOPMENTAL REFERENCES 2.2.1 INPO 90-021, Good Practice OP-217, Alarm Response Procedures.

()

2.2.2 Annunciator Window Engraving Drawing E-224-050.

3.0 PERSONNEL INDOCTRINATION None 4.0 INSTRUCTIONS 4.1 Respond to alarms on the WD-WV Panel Lampbox as indicated on

' Enclosure 1, Annunciator Response.

5.0 FOLLOW-UP ACTIONS None 4-O AR-958 Rev. 4 Page 1

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ENCtOSURE 1" l

(Page 1 of 2)l ANNUNCIA10R PANEL L OC Ail 0N RADWASTE DISPOSAt'rUBlCLE ANNUNCIAf09 PANLL WD-WV (H)

HORIZONTAL RDW T

WILDOW TITLE 1.

INDICATED CONDITION 1.

AUTO ACil0N SETPotNT.ENSING REFEREkCE'

.su!LDIhG 2.

OPERATOR ACil0N

  • VAllD ALARM ELEMENT 2.

' CONTROL RDOM OR Aux!LI ARY INDICAi!ON WHICH VERiff OR PINPOINT TROUBLE NUMBER &

LOCATION I

~

L EVAP CDSTE

1. a) Evap CDSTE demin "A" temp > 120*f.
1. a)

None.

I CEMIN "A"

2. a) Evap CDSit demin "A" temp indicator on WC
2. a) Stop flow to demineratizer.

WD-91-is

.WD-141 HIGH TEMP panet.

b) Determine cause of high temperature and correct.

'l uv-let EVAP CDSTE

~ 1. a) Evap COSTE demin'as" temp > 120's.

1. a) None.

DEMIN "a"

2. a) Evap CDSTE demin "B" temp indicator on WD
2. a) Stop flow to demineralizer.

WD-92.TS WD-141 MiGN TEMP panet.

~

b)' Determine cause of high temperature and correct.

4

'EVAP COSTE

1. al ' Evap CDSTE demin "A" dif f press '> 40 psid.
1. a)

None.

DEMIN "A".NICH

2. a) Evap COSTE demin "A" diff press indicator
2. 3) Stuice resin out and replace.

WD-211-PS.

WD-141-l DIFF PSESS on WD panet.

.WV 1-3 EVAP CDSTE

1. a) Evap CDSTE demin *B" dif f press > 40 psid.
1. a)

None.

DEMIN *E".M1GM

2. a) Evap CDSTE demin "B" diff press indicator-
2. a) Sluice resin out and replace.

WD-212-PS WD-141 Off5 PRESS on WD panet.

1 Wv-t-4 5

?

EVAP CDSTE 1, a) Evap CDSTE storase tank "A" t evel > 97.6%.

1. a ) - None.

).

'STGR T Akt "A"

2. a) Evap CDSTE storage tank "A* tevet
2. a) Open tank drain to maintain levet.

WD-97-LS)

WD 141

]

HICH LEVEL indicator on WD panet.

b) Determine cause of high level and correct.

uv-1-5 a

{

EVAP CDSTE

1. a)' Evap CDSTE storage tank "A" level 4 21.4%.
1. a)

None.

]

STOR TAhr "A"

2. a) Evap-CDSTE storage tank "A" levet'
2. a) Stop evap cond. pump 34.

WD-97-LS2 WD-141 Low LEVEL (ndicator on uD panet.

b). Determine cause of low level and correct, i

t

~

j WV-1 6 j

EVAP CDSTE

1. a) Evan CDSTE storage tank "85 level > 97.6%.
1. a) N one.'

i Sica TANC *B"

2. a) Evap CDSTE' storage tank *B" levet
2. a) Open tant drain to maintain tevet.

WD-98 LS1

~.WD-141 HIGH t E VE t -

indicator.on WD panet.

b) Determine cause of high levet and correct.

-t ev-1 7

'EVAP CDSTE 12 a) ' Evap CDSTE storage tank "B" Level. < 21.4%.

1. a).Stop evap cond. pump 38..

WD-98-LS2 WD-141 None j

LOW LEVEL

'. Evap CDSTE storage tank "B"

tevel 2.'a) :

STOR TANK "S"

2. a) indicator on WD panet.

b) fDetermine cause of low levet and correct.

WV-1-8 1

AR-958 Rev; 4-Page 2

a e

ENCLUSURE 1 3

(Page 2 of 2)

ANNUNCIATOR PANEL LOCATION 8ADWASTE DISPOSAt CUBICLE ANNUNCIATOR PANEL WD-WV (H)

HGRIZONTAL ROW 2

WINDOW TITLE 1

INDICATED CONDITION 1.

AUiG ACTION SETP0thi SENSING REFERENCE 2.

CONTROL ROOM OR AUKILIARY SUILDING 2.

OPERATOR ACTION - VALID ALARM ELEMikT WUMSER &

INDICATION WHICH VERIFY OR PINPOINT TROUBLE L OCA T ION WASTE CAS-

1. a) Waste gas surge tank diff press > 2.0 PSIG.
1. a)

None.

-SURGE' TANK HIGH

2. a) Local indicator.
2. a) Check valve lineup, determine cause and WD-203-PS3 WD-141 correct.

DIFF PRESS WV-2-1 UASTE' GAS

1. a) Waste gas compressor 38 outlet gas
1. a)

None.

COMPRESSOR 3B temperature > 150~F.

2. a) Check Su cooling water to compressor.

WD-152-TS WD-141 HIGH 1EMP

2. a)

WDP-1B temperature indicator on WD panet.

b) T ransf er to 3A compressor.

WV-2-2

. WASTE GAS

1. a) Waste gas compressor 3A outlet gas
1. a)

None.

CONFRESsoR 3A temperature > 150*F.

2. a) Check SW cooling water to compressor.

WD-153-TS WD-141 HIGN TEMP

2. a)

WDP-1A temperature indicator on WD panet.

b) Transfer to 36 compressor.

WV-2-3 CAflON DEMIN

1. a) Cation demin "A"

& "B" outlet strainer

1. a)

None.

"A"

& "B" differential pressure > 5 psid.

2. a) Flush strainer to spent resin storage WD-228-PS WD-141 WD-229-PS STRAIN HIGH D/P
2. a) Local indicator.

tank.

WV-2-4 ORAIN POT

1. a) Waste Gas Surge Tank Drain pot levet pl8"
1. s)

None.

-HIGH LEVEL H20

2. a) Open drain valve for drain pot to maintain WD-3-tS WD-141
2. a) local levet indication at the drain pot.

proper tevet.

b) Determine cause cf hich levet and correct.

VV-2-5 DE60R DEMIN

1. a) Deber desin intet header temperature
1. a)

None.

2. a) Secure flow to deeineralizer.

WD-45-TS WD-141 HIGH IhlET

> 120'F.'

temperature indicator b) Determine cause of high temperature and TEMP

2. a) Demin 1A/1B 1-intet correct.

on WD panet, VV-2 6 DEBOR DEMIN

1. a) Debor demin 3A differential pressure > 40
1. a)

None.

"A" HIGH DIFF psid.

2. a) Stulce resin and replace.

WD-207-PS1 WD-141 PRESS

2. a) Debor demin 3A D/P indicator on WD panet indicates that demin is fitted solid uv-2-7 (3.25 psid).

DEBOR DEMIN

1. a) Debor demin 38 differentian pressure
1. a) None "B" HIGH DIFF

> 40 psid.

2. a) Sluice resin and replace.

WD-208-PS1 WD-141 PRESS

2. a).Debor demin 3B D/P indicator on WD panat indicates that demin is fitted solid uv-2-8 (3.25 psid).

Rev. 4 Page 3 (LAST PAGE)'

AR-958

.....,3

.

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