ML20079M146
| ML20079M146 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 12/28/1983 |
| From: | Colitz J, Toole R GENERAL PUBLIC UTILITIES CORP. |
| To: | |
| Shared Package | |
| ML20079M137 | List: |
| References | |
| 1210-5, NUDOCS 8401270192 | |
| Download: ML20079M146 (12) | |
Text
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FOR USE L' UNIT I ONLY y',?;5 c,,
12/2E/83 IMPORTANT TO SAFETY NON-ENVIRONMENTAL IMPACT RELATED
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THREE MILE ISLAND NUCLEAR STAT. ION UNIT NO.1 ABNORMAL TRANSIENT PROCEDURE 1210-5 OTSG TUBE LEAK / RUPTURE Table of Effective Pages Page Revision Page Revision Page Revision Page Revision 1.0 1
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g;5 FOR USE IN UNIT l ONLY THREE MILE ISLAND NUCLEAR STATION UNIT NO. 1 ABNORMAL TRANSIENT PROCEDURE 1210-5 OTSG TUBE LEAK / RUPTURE NOTE:
1.
OTSG Tube leak: greater than 1 and less than 50 g;m.
2.
OTSG rupture: greater than or equal to 50 gpm.
l.0 IMMEDIATE ACTIONS W
l.
IF the reactor was not tripped; THEN close MO V'*-tna begin to reduce
- + a rate specifi t by
- e Shif t Super" s inimize the risk b
~ Safety Valve 1
ng.
2.
IF the reactor ile shut-T plete the immediate ting down;
. ions of ATP 1210-1 and SE-eed with plant cooldown r this procedure.
?.0 FOLLOW _UPAdl0N v
3 NOTE:
Refer to Ta~
Emergency Acti level Declara-tion guidan n OTSG isolatio n iderations forEmegg[
ector.
1.
Continue to re e
to less than ce t at the selected load reduct Consult OP 162ql lant shutdown for guidance.
NOTE:
When removing the first main feed pump (40% pwr),
remove the feed pump that is being steam fed from the affected OTSG if known.
Remove the feed pump per OP 1102-10.
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12'0 5 F6R USE IN UNIT I ONLY
- ""'=3 2.
By samoling OT5G's. sursey ng steam lines, coservation of OTSG i
1evels and feed rates. etc. determine affected CT5G.
NOTE:
Most affectec OTSG should indicate higher level, 8
lower feea rate. ana!or nigher Seta-Gamma, H.
Na". I_133 anc CS- " samole resuits.
________________________________________________________h.____________
CAUTION: When tne turbine is trioped it may ce etesh y to f
take manual control of turbine byoase l y to main _ -
tain seconcary pressure below the 5a' team safety valve setpoints.
3.
At less than 15 percent PWR take the turu'ne 6
anual and unloa:
/
to '0" MWE.
i at the turbine bypas alves automatically centrol he "
o sure belcw safety s setco Mts.
At "D" M E while closely n oring OTSG pressure. Observe trio t u
tur top valves closed.
I CAUTION:
The followi wer reduction an rip will cause a:
signifi shrinkage, ins re su
'cient make-up to ma ormal pressuri2e ve' Adhere to Pre evel Guide.
f 4.
Place the to n manual and c u
ducing Rx Pwr to less than 5%.
ess than 5% reac' (oct er, take cianual control of the t
'ne bypass valves and then trip the Reactor.
k l
Immediately adjuct TBV closed to control the initial cool down 5,
following Reactor trip and control OTSG pressure to prevent safety valve operation.
k 5.
If the OTSG level rule of 90-951 is in effect. raise the h
unaffected OTSG to 90-95% before raising the affected 0TSG to p
[
90-95%.
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- OR USE IN UNIT l ONLY Of;5 on i 6.
Steam both OTSG's to reduce RCS to less than.540 F.
7.
While reducing RCS temperature to less than 540 F turn off PZR Heaters and start pressurizer spray to depressurize RCS which minimizes the subcooled margin.
The Pressurizer Vent may be used to reduce RCS pressure.
If the pressure vent is not sufficient,
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the PORV may also be used.
NOTE:
Minimizing subcooling margins abov 25 will cause RCS temp / press to violate the fp mpression curve (OP 1102-11). This is e
only during rupture emergencies, and re e
ineering Evalua tio r to next heat up other than tube r
el pin compression es should not be vi 8.
When 5 minimized, con r turbine bypass valves and c
plant cooldown at le n 100*F/HR (1.6*F/ min).
(Refer to OP 11 2-11 for addi dance on BOP eq ment.)
9.
Reduce RCP's to one 1
, when the additiona ray is no longer required 1 SCM.
RCP's t e duced to less than 4 RCP's befor temp is decreased 1
0*F.
________________s.
RC_P_lAonfor(I p'a y.
WOTE:
y
_________ _ __ ___________________ m _____________________________
h 10.
Monitor tu e to shell delta T and maintain it less than 70*F using g
l MFN.
If this limit is approached while steaming, then reduce or b
secure the cooldown rate as necessary.
g 11.
Confirm affected OTSG by sampling.
12.
With RCS hotleg and incore thermocouples temperatures less than 540*F, isolate the affected OTSG if BHST level is less than 21 ft.
L
(
or off-site dose projections approach 50 mr/hr whole body or 250 b
mr/hr thyroid.
2 3.0
)
FOR USE IN UNIT i ONLY l
1210 avii = i i
FOR USE D! UNIT l ONLY 13.
If required to isolate the affected 0TSG(s). close the folleningi
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NOTE:
Assure MFP is being fed from unaffected OTSG or Auxiliary Steam. Assure gland steam is from the Aux.
Boiler.
MS-V-1A and B or C and D FW-V-17 A or 5 x
FW-V-5 A or B FW-V-16 A or B FW-V-92 A or B FW-V-85 A or B EF-V-30 A or B 9
MS-V-92 MS-V a
B or C and D MS-V-1 or B (close ma wheel)
MS-V-10 A or B MS-V-3 D/E/F or A/ C 14.
If both OTSG' r r tred to be is c can no longer be used as a a
proceed to A
-)
NOTE.
I OTSG pressure cannot_.be maintained less than 1000 psig, protect against any challenge to the MS t
J Safety Valves by opening the Turbine Byoass and/or
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Atmospheric Dump Valves.
- - - - - - - - - - - - - = - - - _ - - - - - - - _ - - - _ - - - - - _ - - - - - - - - - - _ - - - - - _ _ _ - - - - - - - - - _ - _
j 15.
Affected OTSG must be steamed without exceeding the tooldown rate limits to maintain less than 95 7. on operate range and less-than 4.0 7
Cr i t., t I t i, i I! s v i s.
1210_:
ws6 0 TOR USE W UNIT I ONLY 70*F tube to snell celta I, unless ei ner :ne 5WST is less
- nan 21 t
Ft. or off-site dose projections approacn 50 mr/hr whcle bCdy er 250 mr/hr thyroid.
NOTE:
Uncer emergency situa*iens, eloc ing/cinning of MS nangers when floccing tne at:::licaole MS lines is nc:
necessary.
If the MS lines are filled wi,thout blocking /pinningoftheMShangers,aneng)neering s
evaluation of the structural integrityGf'the' MS lines.
must ce performed prior to resuming operations..
16.
anan n or qua o 00 hr
.) coo down a by steaming both TSG's.
If the cocidow, rate greater than 100*f/hr. (1
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due to three HP cooling, secure the non-ES se pump and observe '
rottling criteria for the two ES e MU pumps.
17.
If essure is being c t
and an adequate subcooling margin exists, bypass rmal bypass pre re setpoints.
18.
If subcooled margi s,
hen isolate C -V-1A/
hen RCS pressure is les t equal to 700 p i 19.
Notify Radiol Controls of the s
. due to OTSG tube leak O
and to con'tnue *o survey the Int'ermedia:e and Turbine Buildings to determi Aeed for controlled as.
Initiate Emergency Plan if requred, as a result of the surveys.
20.
Notify Unit 2 Control Room to isolate auxiliary steam cross connect 1
=
by closing AS-V-23 and its bypass AS-V-209.
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Oh USE !b! UNIT l-ONLY RG= 0 For otner : nan tuce ructure. refer to NPSH curve in F'gure i ar: I f.
of 1102 11.
Refer to Figure 1 anc 1A of ATP 1210 10 for ru; tere
[_
emergency NPSH limits for cne RCP in each loco CDeration.
NOTE:
The eme gency NPSH anc SCM limits are olettec cn a Ocm:csite gra:n cut are verifie: using Cifferen:
instruments. Use those instruments as no:ec en l
figure 1 and 1A.
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22.
Decay iest Removai may be initiated at 300*F *, r: s sriccing a'l RCP s if the consecuences of icsing RCS loc br<e.2 fica are acceptable (i.e.
. t leg steam bubble).
23.
When on DH Re. v pressurize RCSM ven hea:er pressure :er CP 1104-4.
24 When e
ts, initiate p f e of cenaenser cartitien facto rveillance Test 1
9.6.
25.
If OTSG tube leakage e e limits of T
. Spec. 3.1.6.3, then an unschedule e vice inspection the af ettea OTSG must be conducte'd pr r artup pursuant et SDec. 4.19.3.C.l.
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TABLE 1 EMERGENCY ACTION LEVEL DECLARATION CRITERIA Condition Unusual Event Alert Site Gene al Tube :.eaK Alone igem - 50 gem 1 50 gem Any Tuce Leas N/A anc Satura:icr.
< 25*,5 occo'ec t
5p-Steam Generator Tube Leas N/A 1 gpm -
2 g
N/A Plus - Loss of Off-site Pow?r 50 gem Steam Generator Tube Leak N/A 1 gpm -
_ 53.cm N/A Plus - Steam Line Break 50 gpm 50'om -
~ 50.com Ni:
1c
~
Steam Generater Tube Leak N/A gsn Plus - Loss of Condenser Steam Generator Tube Leak N/A N(h
> 50 g;m N/A With 1% Failed Fuel RMA-5 Low Range riigh Alarm N/A N/A Offsite Dose Projection / Report Whole Body A
2 10mr/hr mr/hr
> 1R/hr Thyroid N/
> 50mr h 250 mr/hr
> SR/hr eu t.
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FOR USE IN UNIT i ONLY 5;Ln :.
STEAM GENERATOR ISOLATION CONS:DERATIONS FGR THE E/D W:TM CONCURRENCE SY THE ESD GENERAL 1.
Isolation of one or Doth OTSG's reduces the RCS cooldown rate which increases the time to reach cold shutdown and to terminate the crimary to secondary leak.
2.
Isolation of one OTSG when botn are leam'n; may increase th'e integ' ate:
dose since the release will continue from :ne uniso!ateo T G for a longer period.
3.
Isolation of both OTSG's reauires feed and bleed to + % w. i n coulc o
result in releases of steam or steam anc water cir
. l y t.
the atmosphere.
4.
An isolate OTSG may flood, after which it m. iot a cossicle to unisolate and return SG to service.
5.
Isolation of direct am re: eases to thq a.
onere is expecrea to reduce the offs
+ n.
id dose by a factb P ^ at least S.
6.
Isolation f duction should se on measured dose rate to Drecluce t W isolation.
I.
ISOLATION E OTSG SHOULD SOtVO IF
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l.
RCP's are not available al circulatio down may not be possible with one 0 in flow in one loop ca
,agnate and bubble could form hot leg as prima re ure is reduced.
2.
BothOTSG'sle@bu difference i ra e is less than a factor of eigl(
therwise, the dela i
Idown may negate the dose reduc '
Y, isolating one 0 11 1.
OTSG ISOLATI0 E DESIRABLE IF d
1.
RCP's a ating. the condenser is unavailable, only one OTSG is leaking anY iodine cose rates are nigh.
In this s.ituation nigh iodine release rates could be terminated by isolation of the
- leaking OTSG.
Although cooldown time is increased, radioactivity releases will be terminated and RCP operation enables control of the RCS which in turn allows cocidown of the leaking OTSG.
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1210-5 i
FOR USE W UNIT i DNL';
III OTSG ISOLATION CRITERIA SHOULD BE REEVALUATED IN THE FOLLOWING SITUATIONS
[
1.
RCP's Operating, condenser unavai!able, both OTSG's leaking, icdine dose rates are high - isolation of one OTSG may be desirable if the
^
leak rate in one OTSG is significantly (about 8) greater than in the other. The reduced dose rate from isolation of one OTSG must be weighed against the shorter coolcown time with steaming both OTSG's.
2.
Condenseravailable-IsolationofoneorbothOTSG's[gteatly increasescooldowntimesandincreasesriskofinapertehtor uncontrolled releases. A decision to isolate earire(%traft required by procedural guidelines should be based on me e' bote rates if possible.
In the absence of fuel failures, a t al leases under such conditions are expected to be quite lo 3.
Only one OTSG is leaking and BWST level 821 e t.- If the good OTSG is not exp d to leak because sNei Pube delta T is being controlled, t.
tion is not re ired.
ecall than the BWST level was base o h steam lines looded.
If only one OTSG may b
, then BWST depl uld not occur until 15 ft.
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1210-S o
FOR USE IN UNIT l ONLY
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SUMMARY
Both OTSG,
Both OTSG One OTSG Leaking more Leaking RCP Condenser leakino Than 907. to One Ecually ON Available Avoid isolation Avoid isolation Avoid isolaticn (III.2)
(III.2)
(III.2. I.2)
U ON Not Available Consider isolation Consider isolat o void isolation (II.1)
(II.1) of one (I.2) 0FF Available A
isolation Avot solation
. _ Avoid isolation TSG (I.1) ne OTSG (I.1) of one OTSG (I.1, I.2. III.2) 0FF Not Aval e
Avoid isol n
Avoid isolation Avoid isolation of one 0 of one OTS
.1) of one (I.1, I.2) y b
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1210-E
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.. s-TEMPORARY-SHORT TERM MEASURES TO REDUCE OR TERu!NATE RELEASES 1.
Releases can be temocrarily terminated by-a.
Terminating steaming to the concenser ard not steaming to atmosphere.
b.
Not more than 1 RCP snould be run.
c.
If natural circulation is lost steam again.
If steam generator pressure reatnec 1000 psi., steam again, d.
Heatuprate,followingterminationofsteaming,is(Esthtectobe 100-170*F.
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These steps may provide enough time to return an RCP to peeration, x
restore a concenser to service, or initiate protective'ntions, wnile delaying the initiation of feed and bleed coojAgg:
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