ML20126B720

Rev 2 to Off-Normal Instruction ONI-3-12, SG Tube Leak

ML20126B720
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	01/24/1992
From:	PORTLAND GENERAL ELECTRIC CO.
To:
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ML20126B698	List: ML20126B696 ML20126B706 ML20126B714 ML20126B718 ML20126B720 ML20126B723 ML20126B733 ML20126B741 ML20126B745 ML20126B749 ML20126B760
References
ONI-3-12, NUDOCS 9212220186
Download: ML20126B720 (19)

Text

b Lovel 1 Contrelled Distribution Maintained by Document Conhol Do not remove this document ler lidd work PORTIAND GENERAL ELECTRIC COMPANY TROJAN NUCLEAR FIANT November 8,1991 QUALITY-RELATED l

Revision 2

1. TCN OTT-NOP.% INSTRUCTION - CNI-3-12 INCORPORATED STEAM GENERATOR TUBE LEAK

'b Responsible Departments oneratieme Approved By:

M db L

Date I*N'"D l

QPHeedure Manager Effective Date I"*s M 1-59 A.

PMPost To terminat? a steam generator (S/C) tube leak not large enough to require safety injectionf (< l CcP Ar W.

FuW).

{

9, 3.

s m rTous Any of the following'may indicate primary to secondary leakage:

1.

Abnomal condenser air ejector radiation (PRM-6).

{

2.

Abnormal S/C blowdown or sample radiation (PRM-10 or PRM-17).

3.

Abnormal main steamline radiation (PRM-16).

4 Decreasing Reactor Coolant System (RCS) pressure.

5.

Decreasing pressurizer (PZR) level.

6.

Uncontrolled S/C level increase.

9 7.

Charging flow significantly greater than letdown flow.

Ef.

Q A D o A ro s a - (Pt " ' .).

}

MermAL m A ud s r& c.uac e

E E

2.NDM.909 ONI-3-12 Page 1 of 17 Revisica 2 9212220186 921217 PDR ADOCK 05000344 G

PDR

i

.e

,1 1

ETT.& CENEP.ATOR T19E LTJJ Step Action / Expected Response Response Not Obtained I

• • • • • • • • • • • u g

CAVIION N

e o-1

Prompt operator action is D

l

required to initiate plant

shutdown based on initial _ }f g 4 j

g j

indications of a small"but l

g steadily increasing 1/C tube ;

E F

• 1eak. This is due to toe g possibility of a minor leak ;

progressing to a major tube ;

rupture event in a short g period of time (CPT-012-91). ;

• • • • • • • • • • • e 1

• • • • • • • • • • h

• • ** ** ** ** eu CAUTION

• 3 IT S/C narrow rage (NR) level; i

2 to >951, an evaluation

should be made for S/G g

overfill considerations.

3

• Steam should not be released ;

i

from any S/C with level >95% ;

• prior to overfill evaluation.;

j

• • • • • • • • • • • v 4

}

NOTE

' Radiological Emergency Response Plan (RERP) actions should be performed in

_enrallel with this erecedure.

NOTE l

Personnel should be available f or sampling during this erecedure.

NOTE l

Charging pump suction will shift to RWST if volume control tank (VCT) level dreer to 1.L%.

1 Cheek ?ZR levels a.

Level - STABLE or INCREASING a.

Reduce letdown as required to maintain PIR level, l-Continued next tace ONI-3-12 Page 2 of 17

}

Revision 2 l

J

sTr>y cL'irPrr0R wir tr>J Step Action / Expected Response Response Not Obtained N

• • ** ** ** ** *u ** ** ** ** **

l CAUTION t

%w

• g Prompt operator action is D 1 3 required to initiate plant g pg

}

g

,f g shutdown based on initial g indications of a smal1%ut __ ;*s)

steadily increasing S/G tube ;

• 1eak. This is due te the g possibility of a minor leak g g progressing to a major tube ;

rupture event in a short

period of time (CPT-012-91). ;

• • • • • • • • • • • e

• • ** ** ** ** eu ** ** ** ** eg g

CAUTION g

• g IT S/G narrow rage (NR) level;

to >95%, an evaluation

• should be made for S/G

overfill considerations.

g g Steam should not be released ;

from any S/G with level >95% ;

g prior to overfill evaluation.;

• • ** ** ** ** *u ** ** ** ** **

l NOTE Radiological Emergency Response Plan (RERP) actions should be performed in l

_ parallel with thip erecedure.

NOTE Personnel should be available for sampling during this i

erecedure.

NOTE Charging pump suction will shif t to RWST if volume control tank (VCT) level drees te 1.LL 1

cheek P2R Level a.

Level - STABLE or INCREASING a.

Reduce letdown as required to meintain PIR level.

Centinued next eace ONI-3-12 Page 2 of 17

}

Revision 2

ETIAM CDiERATOR RfM LEAK St,p Action / Expected Response Response Not Obtained 1

ContLued IT PIR level is still oecreasing with one CCP at maximum flow through normal charging path, TEEN manually initiate safety injection and i

go to EI-0 REACTOR TRIP, SATETY INJECTION AND DIAGNOSIS, Step 1.

s I

2 Cheek Rc5 Pressure a.

Pressure - STABLE or INCREASING a.

Energize PIR heaters as required to maintain RCS pressure at 2235 psig, g

=

3 Initiate a Rarid shutdown:

)

a.

Reactor is in Mode 1 or 2 a.

Go to Step 4.

b.

6 Reactor / siO TD8 W I

wo rnia.s Yr moavres 1

f

1) Feduce power using COI-5 m

and GOI as guidance

2) Surveillance testing may be omitted at the Shift

(

Superviser's discretion NOTE A PRM-10 ALERT can be bypassed at C-41.

A DIGH alarm must be cleared by leem1 flushine.

4 Idetifv Rurtured S/C frer*

WHEN ruptured S'G is identified TEEN do Steps ; e i 6.

Continue

• Unexpected rise in any S/G NR with Steps 7 ttu ogh 9.

level inconsistent with ferd flow

- OR -

• PRM-10 high radiation

- OR -

• S/G sample high radiation

- OR -

• PP3-16 high radiatien

- OR -

• PPZ-17 hi*.. radiation g

-ec-

• PR m as Hics 24dia rew ONI-3-12 Page 3 of 17 i

Revision 2 Ci E

E N

~ :- -

J-l 1

i STEAM GDIERATOR TUBE 1.EAK Step Action / Expected Response Response Not Obtained g* ** ** ** ** TION g

CAU g_

IF the turbine auxiliary g feedwater (AFW) pump is g the only source of feed

flow. THEN steam supply to

the turbine AFW pump must be ;

maintained-from at least

one S/G.

3 1

i g* ** ** ** ** **N** ** ** ** *g j

CAUTIO g

4 d

j

Air shall be isolated AND g vented to a turbine auxiliary;

• feed pump (AFP) steam supply ;

j g valve that is operated by g-g handwheel to prevent valve

• damage.

j j

l 5

Isolate Flow From Affected S/G Adjust PORV to 1,125 psig.

)

j a.

Verify affected S/G a.

power-operated relief valve (PORV) controller setpoint at 1,125 psig b.

Check affected S/G PORV -

b.

When affected S/G pressure CLOSED is <1,125 psig, THEN verify S/G PORV closed.

IF 'iOT closed THEN place -

1 PORV controller in manual and i

close PORV.

IF PORV CANNOT be closed, THEN locally isolate FORV.

i i

I a

i Continued next once

)

ONI-3-12 Page 4 of 17 Revision 2 i-b

- - = _...._.-. -...

- -. ~... -,. - - -. - -

4 l

STEAM CENERATOR TUBE LEAK Step Action / Expected Response Response Not Obtained 5

Continued c.

Close af fected S/G turbine AFP c.

Close affected S/G turbine ATP steam supply valve AND steam supply root valves bypass walves:

Steare Sgp.ly Bvoasses S/fa Root Valve CV-1451 MS-'165. MS-166 A-MS-143 CV-1452 MS-167. MS-168 B

MS-026 CV-1453 MS-169, MS-170 0

MS-144 CV-1454 MS-1714 MS-172 D

MS-027 l

1) Have any available l

operator hold affected.

control switch in the closed position at C-05

2) Locally isolate steam supply valve:

a) Isolate AND vent air supply.

b) Loosen locknut with amergency wrench c) Turn handwheel clockwise until stem seats valve closed l

3) Locally close both bypass valves

{

4) Release control switch at C-05 d.

Verify blowdown and sampling d.

Manually close valves.

isolation valvrs from affected S/C - CLOSED e.

Complete reactor shutdown using GOI-5 and GOI-3 as guidance prior to continuing with this procedure l

Continued next care ONI-3-12 Page 5 of 17 l

Revision 2

.._,.._._,.a,

wm A-emi J

A

,e w

.-6.,'-

.x,a AI-

-,+MJ-s. sa n v

u d

ETEAM CENERATOR TUBE LEAK l

Step Action / Expected Response Response Not Obtained i

)y 1

5 Continued i

f.

Close affected S/G main steam f.

Perform the f ollowing:

isolation valve (MSIV) and MSIV bypass

1) Close all remaining S/G il MSIVc and MSIV bypasses.

I

2) Use intact S/G FORVs for heat removal.

-s i

3) Close the following steam valves at C-151.

I

• 2nd stage steam to moisture separator and

' reheaters (MSRs MO-3590A j

and MO-3590B.

j f

• ' Steam seals MO-3586-i and MO-3587.

t j

4) Continue on with this-procedure while dispatching A0s to j

perform the following

• Close air ejector e

I supplies MS-155 and

)

MS-117.

6

• Close steam to steam packing unloading-Valves MS-052.

4 I

• Isolate all steam line steam traps.

• Isolate all steam line samples.

g.

Verify steam line HP drains g.

Locally close steam line HP at C CLOSED drain root from ruptured S/G:

I SIG Drain Root A

MS-012 B

MS-009 C

MS-010 D

MS-011 E-1 i

ONI-3-12 Page'6 of 17

)

Revision 2 4

'r-

+.m.,

y

STEAM CENDLATOR '1 TIE LEAK i

Step Action / Expected Response Response Not Obtained i

6 Check a';f ected S/G Lgyllt Verify NR level - >5%

a.

Maintain feed flow to a.

affected S/G until level is >5%.

Continue with Step 7.

WHEN affected S/0 l

1evel >5%. THEN stop feed flow to affected S/G.

[

b.

Stop feed flow to affected S/G I

h CAUTION h

hIFanyPZRPORVopensdueto;

• high RCS pressure, THEN

Step 7.a should be repeated

after pressure drops below

the PORV setpoint.

g 7

Cht;) PZE PORVs and Block Valvtat I

a.

FORVs - CLOSED

- a.

IF PIR pressure < 2,335 psis, THEN manually close PORV.

IF any valve CANNOT be closed. THEN manually close l

its block valve.

i b.

Block valves - OPEN b.

Open block valves UNLESS closed due to faulty PORV.

8 Verifv Secondary Integrilyt.

IF NOT, THEN go to EI-0. REACTOR TRIP, SAFETY INJECTION, AND a.

All S/G pressures --NOT DIAGNOSIS, Step 1.

DECREASING IN AN UNCONTROLLED MANNER b.

All S/Gs - NOT COMPLETELY DEPRESSURIZED l

i' l-ONI-3-12 Pase 7 of 17 Revision-2 b

ew

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-we m+

w

.e a:ww,,.

se e.e

, w ar ge sa.

• +mww ar

.-re, w a me~*.e y4

.y, - -.

s ETI,4tjEELRAIQR TifBE LEAK 1

j Step Action / Expected Renpanen Response Not Obtained

}

4 ge **-** ** ** ** ** ** ** ** eg g

CAUTION g

g AFFs will trip at a CST g

g leyel of 35% unicas blocked. g i

• • ** ** ** ** ** an ** ** ** **

i 9

Cherk_lntaet S/0 Lurla*

4 a.

Verify NR level - >S%

a.

Maintain total feed flow I

i

>495 gym until NR level-

>$% in at least one S/G.

i 1

b.

Control feed flov to maintain b.

IF HR level in any intact i

NR level between 5% and 50%

S/0 continues-to increase dn an uncontrolled manner, THEN return to Step 4.

2 t

3 10 Block sla 3

a.

WHEN PZR pressure (1900 psig.

THEN block PER low pre.tsure SI steam 'IShe<533*F. THEN hlock b.

WHEN 7 SI s

(

g * * * * * ** *

• n o * * *

• n n - * * *

• CAUTION

\\

i

• Sudden changes of steam flew j i

j g with ateam dumps may cause i

• a main steam isolation.

11 Initlate RCS Cncidam s i

i a.

Determine required higheAt core exit TC temperature f rom tehle:

l AFFECTED REQUIRESCOREENIT PK-507 S/G PRESSURE.

IllERM000UPII TEMPERATURE SETTING i

l fpstg)

(ar) i

_11.200 536 7 aE3 l

1.100-1.199 525 6.95 l

-6.23 1.000-1.099 5_12-

__z 900-999 S Q1-5.60 SQO-899 487 4.82 1

1 700-799 472 4,,25 600-699 456-3.62 1

i.

Continued next pare 0.NI-3-12 Page 8 of 17

)

i Revision 2

!=

l i

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

- ~, - -.. -

STEAM CENERATOR TUBE LEAK Step Action / Expected Response Response Not Obtained 11 Continued b.

Dump steam from intact S/Gs to b.

Dump steam to atmosphere condenser. Maintain cooldown using intact S/G PORVs.

rate <100*F/hr Maintain cooldown rate 1

<100'F/hr.

1) Place steam dumps in l

STEAM PRESSURE MODE l

l

2) Place PK-507 in manual l

3) Slowly open pressure I

control valves (PCVs) and l

establish cooldown I

4) WHEN Tavg (553'F, place bypass interlock switch momentarily in BYPASS AND restart dumping steam c.-

Verify highest core exit TC -

c.

Return to Stzp 11.b.

< R3 QUIRED TEMPERATURE d.

Stop cooldown AND maintain d.

Control' PK-507 in manual AND required temperatures maintain required temperature.

1) Adjust PK-507 setpoint per above table

2) Place PK-507 in AUTO l

• • ** ** ** **-*n ** ** ** ** ** **

h f

CAUTION

• RCS cooldown in Step 11 should

• be completed before continuing l to Step 12.

• • ** ** ** ** *u ** ** ** ** ** **

12 Check Affected S/G Pressure -

IF affected S/G pressure continues STAPLE or INCREASING to decrease, to <250 psi above the pressure of the intact S/G(s) used for cooldown, THEN go to-EI-0, REACTOR TRIP, SAFETY INJECTION AND DIAGNOSIS.' Step 1.

13 Check RCS Subcooline based on core Go to EI-0, REACTOR TRIP, SAFETY' exit TCs - >45'F INJECTION, AND DIAGNOSIS, Step 1.

ONI-3-12 Page 9 of 17 Revision 2 1

.,,,,,. ~. -....... - -.

- +

_. - ~ - -. - - -

STEAM CENFD LTOR TUBE 1.EAK i

Step Action / Expected Response Response Not obtained

)

d 14 Depressurize RCS to Minimize Break Flow and Refill PZRt s.

Verify normal PIR spray a.

Go to Step 15. Observe

- AVAILABLE cautions before Step 15.

b.

Spray PZR with maximum available spray Verify PER pressure decreasing c.

IT PER pressure decrease is c.

RAPIDLY until ANY of the not adequate. THEN go to following conditions are Step 15.- Observe cautions 4

satisfied:

prior to Step 15.

2

• Both of the following:

l

1) RCS pressure - < AFFECTED l

S/G PRESSURE AND 1

2) PZR level - >51

[

- OR -

I

• PZR level - >75%

- OR -

• RCS subcooling based on g

F core exit TCs - <25'F d.

Close spray valves:

1) Normal spray valves

1) Stop reactor coolant 4

Pumps (RCPs) supplying

2) Auxiliary spray valve failed spray valve.

i e.

Go to Step 17.

4 5

i J

4 4

ONI-3-12 Page 10 of 17

)

Revision 2 4

~.

_ ~ _ -

STEAM CENERATOR TUBE LEAK i

Step Action / Expected Response Response Not Obtained I

f g* ** ** ** **

• n ** ** ** ** ** eg CAUTION g On rapid RCS cooldown and h

depressurization, void formationg g will occur in the reactor vesselg g head as evidenced by rapid g

g PZR level changes on

depressurization, spray, or g

g pressurization.

g a

• n ** ** ** ** ** **

• • ** ** ** ** *n ** ** ** ** ** **

h CAUTION h

IF a PZR PORV is used to

• depressurize the RCS, THEN g

g the pressurizer relief tank

(PRT) rupture disk may break.

• This may result in abnormal

• Containment conditions.

• n ** ** ** ** ** **

g* ** ** ** **

• u ** ** ** ** ** *g 4

CAUTION g

Cycling of the PZR PORVs may g result in PORV failure.

• • ** ** ** ** *u ** ** ** ** ** **

j 15 Deeressurire RCS Usine P2R PORV to Minimize Break Flow and Refill P2R:

a.

PZR PORV - AT LEAST ONE a.

Establish auxiliary spray AVAILABLE and. return to Step 14.b.

i b.

Open one PZR PORV until ANY of the following conditions are satisfied:

• BOTH of the following:

1T RCS pressure - < AFTECTED S/G PRESSURE AND

2) PIR level - >5%-

- OR -

• PZR level - >75%

- OR -

• RCS subcooling based on core exit TCs - <25'F Continued next care.

ONI-3-12 Page 11 of 17 Revision 2

SITAM GENERATOR TURE LEAK Step Action / Expected Response Response Not Obtained 15 Cantinued c.

Close FER PORV c.

Close PORV block valve.

d.

Verify spray valves - CLOSED

1) Normal spray valves

1) Stop RCPs supplying failed spray valve.

2) Auxiliary spray valve 16 Cher) LAC 1, fig,, c y - INCREASING Close PER PORV block valves.

IF pressure continues to decrease, THEN perform the following:

1) Manitor following conditions for indication of release from PZR FORVs

• Tailpipe temperature

• FRT level

• PRT pressure

• PRT temperature

2) Go to EI-0, REACTOR TRIP, SAFETY INJECTION, AND DIAGNOSIS, Step 1.

I 17 Check If Charrine Flow Should Be Reduced:

a.

RCS subcooling based on core a.

DO NOT reduce charging flow.

exit TCs - >25'T Go to EI-0. REACTOR TRIP, SAFETY INJECTION, AND DIAGNOSIS, Step 1.

b.

Secondary heat sink:

b.

IF neither condition sa s ed THEN DO NOT reduce

• Total feed flow to S/Gs -

charging flow. Go to EI-0,

>495 gpm AVAILABLE REACTOR TRIP, SAFETY

- OR -

INJECTION, AND DIAGNOSIS Step 1.

• NR level in at least one intact S/G - >5%

c.

RCS pressure - STABLE OR c.

DO NOT reduce charging flow.

INCREASING Go to EI-0, REACTOR TRIP, SAFETY INJECTION, AND DIAGNOSIS, Step 1.

d.

PZR level - >5%

d.

DO NOT reduce charging flow.

Return to Step 11.

ONI-3-12 Page 12 of 17

)

Revision 2

STEAM CENERATOR TUBE LEAK Step Action / Expected Response Response Not Obtained 18 Feduce Chareine Flow an_Necessarv

. with FCV-121 f

19 Control Chareine to Maintain PZR Level 20 Check Chemistry Parameters Notify Chemistry Technician to a.

take an RCS sample

1) Sample for boron and gross gamma activity 21 Alien CCP Suetion/Makeno Control, if Recuired a.

Open VCT outlet to centrifugal charging pumps (CCPs)

Valves MO-112B and MO-1120 b.

Close CCP suction from refueling water storage tank (RWST), Valves M0-112D and MO-112E c.

Set M/U controller in AUTO and START d.

Set boron flow control POT for greater than RCS concentration (4.32 = 1600 ppm on FK-110) e.

Adjust controller POT as necessary ONI-3-12 Page 13 of'17 Revision 2

.-. ~.-.. -.

~

i STEAM CDlERATOR. TUBE LEAK f

Step Action / Expected Response Response Not Obtained 22 Check If Letdown can Be Established:

a.

PZR level - >21%

a.

WHEN PZR level is >21%,

4 THEN do Step 22.b.

Go to Step 23.

b.

Establish letdown b.

Establish excess letdown:

-1) Verify component cooling

1) Verify that excess 4

water (CCW) supply and letdown divert return valves to seal water Valve CV-8143 is in and.let down heat exchangers the VCT position.

(KKs) MO-3295 and MO-3319

2) Open CCW to excess OPEN i

letdown KX MO-3299.

l

2) Open letdown isolation

3) Open excess letdown Valves LCV-459 and LCV-460 isolation Valves CV-8153 l

3) Open Containment isolation and CV-8154.

• ** Y~0I

4) Slowly open excess

4) Open PCV-131 letdown Valve HCV-123.

D NOT exceed 205'F at

5) Open desired letdown the EX outlet, TI-122 orifice isolation valve (s):

at C-12.

• CV-8149A

5) Increase CCW flow to seal a

water EX to maintain

• CV-8149B letdown temperature

)

4

• CV-8149C 1127'F.

1

6) Manually adjust PK-131 to 4

obtain 300 psig letdown HX outlet pressure. Place controller in auto i

4 i

i 4

ONI-3-12 Page 14 of 17 i

Revision 2 1

,,cm m -..-

.... - - =. -.. -..

.. - ~.. -.

4 STEAM CENERATOR TUEE LEAK Step Action / Expected Response Response Not Obtained g* ** ** ** ** ** **N**** ** ** *g CAUTIO g RCS and affected S/G pressure g

g must be maintained less than g

g the affected S/G PORV setpoint. !

• • ** ** ** ** ** ne ** ** ** ** **

23 Control RCS Pressure and M/U Flow to Minimite RCS to S/C Leakaret a.

Perform appropriate actions from table:

AFFECTED S/G(s) LEVEL PZR LEVEL INCREASING DECREARING OFFSCALE HICH

<21%

• Increase RCS Increase RCS

• Increase RCS makeup flow makeup flow makeup flow

• Depressurite

• Maintain RCS RCS using and affected Step 23.b S/G(s) pressures equal.

BETWEEN Depressurize Turn on Maintain RCS and 21% AND 50%

RCS using PZR affected S/G(s)

Step 23.b heaters pressures equal BETWEEN 50%

• Depressurize Turn on Maintain RCS and AND 75%

RCS using PZR affected.S/C(s)

Step 23.b heaters pressures equal

• Decrease RCS makeup flow

>75%

Decrease RCS Turn on Maintain RCS and makeup. flow PZR affected-S/G(s) heaters cressures ecual b.

Use normal PZR spray as b.

IF letdown in service, THEN required by Step 23.a use auxiliary spray.,IF NOT, THEN use one PZR FORV.

ONI-3-12 Page 15 of 17 Revision 2 1

.~

4 j

i i

j STEAM CENERATOR TUBE LEAK

))

i Step Action / Expected Response Response Not Obtained 24 Minimize secondary Contamination:

a.

Close condenser reject valves, CV-2954B and CV-2956B 4

b.

Open condensate demin bypass-valves, MO-7100A and MO-7100B 4

l c.

Isolate other unnecessary flow l

paths that could spread contamination j

25 Turn on PZR Hgaters as NecessaEy l

to Saturate PIR Water Temnerature f

at Ruotured S/C Pressurg 4

NOTE 1

If possible RCP "B" should l

run to provide normal i

l PZR serav.

{

26 Check RCP Status:

)

a.

RCPs - AT LEAST ONE RUNNING m.

Go to EI-0. REACTOR TRIP, 1

SAFETY INJECTION, AND l

j DIAGNOSIS, Step 1.

b.

Stop all but one RCP i

27-Check If SR Detectors Should Be j

Enerrized:

1 Intermediate range flux < 10-10 WHEN flux is <10-10 amps, a.

a.

I amps THEN do steps 27.b and c.

Go to Step 28.

b. ' Verify source range detectors -

b.

Manually energize source-ENERGIZED range.(SR)-detectore.

c.

Transfer NR-45 to indicate both SRs i

4 1

-0NI-3-12 Page 16 of 17

)

Revision 2 1

n r

.,r.

-,. a n:-

n

-w

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. _. ~. _.

4 STEAM GENERATOR TUBE LEAK Step Action / Expected Response Response Not Obtained 28 Shut Down Unnecessary Plant Eauipment by Performine the Aeprocriate Steps of COI-5, Section 3. and G01-3 29 Check Chemistry Parameters a.

Notify Chemistry Technician to take an RCS sample 2 to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> after the shutdown:

1) Sample for iodine 30 Go to Aeproerinte Post-SGTR Cooldown Method

• Go to ES-3.1, POST-SGTR COOLDOWN USING BACKFILL, Step 1

- OR -

• Go to ES-3.2, POST-SGTR COOLDOWN USING steam generator blowdown (SGBD), Step 1

- OR -

• Go to ES-3.3, POST-SGTR COOLDOWN USING STEAM DUMP, Step 1 END i

L

.0NI-3-12 Page 17 of 17 Revision 2 l

e%

,i 4 This TPP 12-4 Attactrnent 12 Revision 2 TCh 92 030.192 040.192107, 792160'fom is current.

Karl Oberloh 84hM April 17, 1992, i

"'QA RICDRO WHIh CO@t!TED"*

{

TEMPORARY CHANGE NOTICE TCh No.:

k I- " #27Y l

(Obtain from Control Room 1CN Master Log)

Affected Procedure NJnber: ONI 3-12 Current Revision No.2 Procedure

Title:

STEAM GENERATOR TUBE LEAK TCH oescriptive $mry: Adds PRM-26 to Symptons. Adds a value to Purpose for' Safety In.iection. Adds recuirement to shutdown the Reactor in 45 min. Adds PRM-26 as a method to identify leakina S/G.

List affected procedure page numbers:

1.2.3.

Reason for Procedure Change: (Select most appropriate reason below.)

W1N.M (a)

!* this TCN being submitted due to a change in regulatory or license requirementsf

_ Yes 4

j (b) is this TCH being submitted due to Plant configuration, equipment, of program changesi

_ Yes (c)

Is this TCN being submitted due to peccedure centent errors (not initiated by changes in Plant setpoints, equipment, of configuration)T

_ Yes

[d]

1s this TCN being submitted due to Procedure presentation or format errorsf

_ Ves 4

(e) 1s this TCN being submitted due to personnel performance / execution errors during use of the current revision.

Yes

[f]

18 this TCh being submitted due to personal preference on procedure form t or contentf 1Yes NW??*?N TCN evrteattea date: None 5

(If net specified, the TCN shall be incorporateJ into the Procedure.)

i Safety Evaluation Screening Checklist & Safety Evaluation attached, if required. Marked up copy of the procedure attached.

re.1 Ote+1ew k

711a aceti 17. 1992 Il YO-Suomitter's Printed ha1w / Signature / Pnone ho.

Date Tism i

2 N D*'., 9 4 Crpe ADelh 13 6-1 00R: Procedure Centrol Group 2 TFP 12 4-q Fa;e 1 of 2 Revision 2 Pa;e 55 of (2 L

a 4

e r.-.-

w w, e

ry, a

y<+wr~

a Procedure he. ONI 3 )

Rev.

L_

TC% ko, 97-2W TCk Acereveis:

Plant Managemnt approval (must be within reporting chain of Procedure Manager):

EhTTERA.1W b 7%'

Mn I M 7_-

Printed hame / $lgnature / Phone No.

Date 11ee Duty shif t Supervisor ($RD License holder) approval:

LA e d. hh d4 AFM

/7 2_

l%2 Printed hane /

rf / Phone ho.

Da t e ilme.

TCN 1mpirentation Date:

• I E

Time

/ 3 3[

(Date/ Time inserted in Control Room Master Copy)

Procedsre Womace* ee desiewe te comolete within 14 days:

[1]

Vill this change affect off-site PGt groups?

,,,,,,,, Y e s X ho If yes, notify those department (s).

Person (s) contacted:

Date:

.. Person (s) cents:ted:

Date:

NE3II.N.

trQTWts.TsiinTRitTaiwresrcrerWEEvo7tiaiit'6rirNEjirGiiRii47siTy~th9

)

I"9amr th'aveslhls2forationJs alsodymiltbitonithdrejan;nocuent nausmt

. _. System (TDH5 5%T Q ]t2,0C n "

'~')."

7 Checked by:

Ka*1 Obe'leh MWdM Date:

Arail 17. 1992 Print [ 51gnature Concurreace: (Procedure Manager's due within 14 days of Implementation)

-Concur:

Reject:

l Procedure Manager Date I

Attac*eent 12 TPP 12-4 Fage 2 cf 2 Revision 2 g

i Page 56 of 62 7