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M 8307130203 780728 PDR ADOCK 05000289 P NL ry,._- , _ _ . y_..-.-- . _ , . _ _ _ 3 | |||
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maemtana,u s.=sessa Team,e moe m u s | |||
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[ July 28, 1978 * | |||
/ | |||
b Mr. 8. E Masetts . | |||
Reacter Systems Branch . | |||
Divistem of Systems safety . .. | |||
Office of Nuclear Reactor Asgulaties- | |||
* E S. Nucigar Regulatory Ceanissica | |||
.'. Washington, D.C. 20535 . | |||
I Seferencess (1) Letter and Inclosure 5. F. F. Bass. Jr., NRC, to E. E. Suhrke. 34W, March 18. 1977, subject Technical issues for Vender Partietsattoa . | |||
j . (2) Letter, James L Taylor, 34W. to C. E.Hazetis, ' | |||
l- .. NBC, Angust 22, 1977, same subject | |||
==Dear Mr Nasetis:== | |||
Raclased are three (3) copies of our responses to 'the so selected technical issues published in NU21G.0128 and NORIG-0133, requested by your letter of March 18, 1977 (Beforence 1). These responses are in accordance with our 3] 1stter of August 22, 1877 (Reference 2). ' | |||
!; If you have ear further questions conceratag this matter.- | |||
lj , | |||
plasse contact Mr. William R. Speight (1st. 2SO2)'ei y taff.,.. | |||
,d | |||
, Very Ln truly yoursiyr . - - . | |||
[k | |||
.3 James N. Tay1 | |||
.. ,. Nasager, Licensing .. . | |||
s | |||
' .; 4117:dsf . | |||
Inclosures' . .' | |||
f{ ces R. 3. Bersum (3(w) *- ' --. ~ | |||
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, ae t** = ws ' s* L. R. Cartia | |||
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: 1. O. Yesburgh W. R. Speight | |||
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ha genent of stuastes Men ssfet, cende testement'in pvstostiene steas une ereas ucsoents , | |||
.j r4'.Babcock M tsad W11ces basically supports the NRC position as expressed | |||
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i (. | |||
q in asNURgf. | |||
back 0134 La regards to the use of sea. safety grade equipment s. | |||
g n' g * | |||
. to safe co onents during a staan-Line break. ' The g number e issues ra sed y secondary.systes transients is large L | |||
* t. and ceaplex enough, that a systematic approach to all secondary | |||
; treasient issues should be undertshes. Therefore, in lieu of | |||
;g** . | |||
reiterattar the analysis assumptions currenti in recent SAR sub- | |||
., mittals. SW proposed a series of meetin a vi the Ceanission , | |||
1eading towards final resolution of the asues involved with , . l 5f .s - | |||
secondary system induced trsasiests. | |||
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1s,s,3g,J,,a Delaved less of Offstte Power Pe11ewiar a LOCA* I l | |||
tU * . . , , A. Offsite power remains available following a LOCA: the ' | |||
8 | |||
* diesels start; at seas time after the LOCA effsite power It %* sg is interrupted; critical lead 2 are interrupted for a - | |||
'i' | |||
:q .* | |||
short time until sequessed en to the diesels. . | |||
: 3. Offsite power reaalas available followier a LOCA: the * | |||
* i, " | |||
* diesels starts at some time after the LOCA and the ECC5' | |||
: . signal is reset offsite 9 * ** aketdeum leads (met ECCS)are power sequencedis laterrupted, sa (the safe '. | |||
.~ | |||
I' diesels any mise have been stepped, is which case:ther will have to be restarted). * | |||
: f. I .g ~ | |||
. 33333331: . . . | |||
: j. - | |||
This 1sses raises the sencets that the less of offsite power at | |||
? . 4 * | |||
$ sees time follow a LOCA would result in auch more severe de* . | |||
esasequences than i effsite power were test sensurrent'with the t' ! **. ** . | |||
LOCA transient. A study was performed to assess the nazimum I' - *"*..*.s est of a less of offsite power (LOOP) at say time fellowing 9 | |||
LOCA. A minor increase as peak claddiar temperature was ebtained: however, due to the sufficiently Iow probability for | |||
. ., this assurrease. 34w fests that it is met necessary to consider g; . | |||
* 1007 subsequent to the LOCA. ,,,,- , | |||
pellowing the LOCA. the ISPAS signals will actuate the* diesels, and will attala rated voltage"and speed withia 10 sesseds. | |||
. If offs te power is them.last at seas time after the LOCA. ..' | |||
M automatic sequencing features are provided se that interrupted ECCS flew '.e the core is fally re-established withia 20 seesada. | |||
Per BEN's plaats, the ESPAS signal is act required to be reset. | |||
j* Thus, part 3 et this issue is met to be~ addressed. | |||
l l Am. t of a eaded LOOP t* afteranalysis a LOCA.has Thebeenworstperforand ease break, to assess an 8.5L theftp double | |||
..* . break 'et the piump discharge with a Co | |||
* 1.0. for SEN's 205 FA plaats was re. analyzed assuming a LO3P at the time the CFT's ' | |||
empty (36 seceeds). A delay of le seconds was them assumed before the BCCS flow to the core was fally re established. A | |||
] - | |||
100P at the time the CFT's empty will yield the naziana tapast en peak sladding temperature for the fellowias reasons | |||
. 1. Prior to the time t:se CFT's empty, the laterruptions of- | |||
. ECCE. flow because of a 100P would be less than 10 seconds g* des to the continued flew free the CPT's. Thus, the imps weeld be less severe than ti.at analysed. | |||
; 2. At any time after the CPT's empty, the amount of time | |||
* hat ECC3' flow would be interrupted dos to a LOGP | |||
* weald be the same as that studied. Newever, for a 1007 | |||
,? that occurs lates thaa the time the CPT's empty, the j . sore geench frams would be higher and the sore decay | |||
, heat lower than that analysed. Both of these conditions y | |||
, will result in less-severe ceaseguences than that en=imad. | |||
4 . | |||
i | |||
! 1 ,. .. . . . | |||
I j | |||
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t | |||
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h % | |||
- . . . . . . . . . ~ . . _ . - < < | |||
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il* : - | |||
f.i . | |||
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is lessense to issue 4 (Cent'd)., . | |||
The results of the ' analysis showed that the peak cladding j- g temperature Sacreased 70 7 to 2144,,7. ,, , | |||
* It is important to mete that this ame1 7sis was' performed'for ' | |||
:l ' ." . 34W's 305 FA staats which utilize Mark C (17 x 17) feel. Das to | |||
, a alty en Mark C refleeding heat transfer esaditions (0.3 | |||
* tiplier sa the F12 CIA predicted coefficients), the sensequences | |||
?, | |||
of the LOOP ars highly everestimated. Because of the penalty. . | |||
8 peak sladding temperatures occur,at opprezimately 100 seceeds Ie | |||
, , rather than at approvinately 40 seconds as obtained for plaats with Mark 3 (15 x 15) feel. The extended ties to reach the anaimmt cladding temperature after the time the CFT's empty toads | |||
'i-; | |||
to enp*1fy the impact of the LOOF. Realistically q- - that stad?.iag temperatures would increase less tha. n 30 it isF.espected l f-The results of the analysis discussed above obviously seemd the' | |||
* I effect of a LOOF subsequent to the LOCA for all Sgv plaats. Ia * | |||
} | |||
Nl 4 ' | |||
addities,is it hshould be meted that the scenarie of events # | |||
'j! analysed ble imprehable. If the less of offsite poser is t4 : a result of a gr perturbaties due to the LOCA, the less shea14 | |||
,. g escur within the first few secoats which is the.present analysis method. Thus, this sencess addresses an indey=d==t less ed Pouer. _ . . | |||
. The probability of am 1A. ' t less of effsite poser la a | |||
* ens neer period, according to WASE.1400, would be about one skaase | |||
-l.i8 la 50.300. The likeltheed of a large LOCA is about ene chasse | |||
' ;5 e4 la 10.000 per reacter year. Furthermore, the analysis that was | |||
- per. | |||
: e. formes.e .aa assumes in 20 a stagle is .ma se failure seen, of.on.e. th .diesel,whi.ch to.4 r. is about -ility of - - ~ | |||
;; this sequence of events is very les e | |||
* t* As illustrated for SEN's plaats, the tapact of a LOOP subsequest . | |||
-l to a LOCA results is only a miner impact sa peak sladding ture and does met endanger the public health. Also, the .,j ii* | |||
* ability of the event is estremely low. Thus, the LOOP , | |||
11 swing a LOCA meed met be seasidsrod for 30f's plaats. j | |||
~ | |||
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Ms Analysis of Postutsted Roseter Caetant Pm Reter | |||
* aes:ure incaments | |||
!i; | |||
* ih n . b.r=== . | |||
'y the situaties of a concurrent i.e. staultaneens locked retor e | |||
and less of offsite power is considered as incredible event. | |||
Therefore, the situaties analyzed la response to this issue is a l locked roter event with less of offsite power resulting from *the .~, | |||
subsequest rascter. turbine trip. , | |||
:* The sequence of events for a tacled*Reter'Transiest with a less-t,. of effsite power as analyzed is gives in Table 1. As can be seen. . | |||
[ | |||
I | |||
* a cesservative value of ISO millisecents is used for the time between turbine stop valve acties ase less of power to the RC | |||
. ! - Famps. The systes rosynsee is shown in Figures 1. I and 3 for if\ L the mestros power, .systen pressure ar.4 AC flow respectively. | |||
The resultant D(31 ase stad temperature response is skews is | |||
, . Figure 4. As is clearly shows. the less of offsite pewer has a. , | |||
=,{ segligible result en the peck clad tesysrature. This cesparative lg result holds true for all 34W reacter types, altheagh the -result ef the locked retor transient asy vary depending sa plaat type. | |||
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. TABLE ,1 . | |||
.t, - | |||
smicancs or avaurs . | |||
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s . ! | |||
, g i , | |||
q' {i Svent pse.Sec i- . | |||
locked later occurs 0.9 | |||
.[. . | |||
Esaster Trips es plus/ plow E | |||
.;i O' . 31 - - -.. - | |||
1 | |||
*IME' Occurs * . | |||
14 . | |||
8.79 4 ii | |||
* Seds l'egia Isserties | |||
~ R | |||
!. 5 _ | |||
' 1.5. ,. . . . . . . - - | |||
- e'f. | |||
f,,I Tartise Trip S'ignal ' . . . . . _ | |||
m j . ' | |||
lTmbine Step Yalve 751p 1.38 , 7 | |||
* 1.64 ~,.- | |||
.8 rid Cheervelt'ge a Oscars e g' }. | |||
i.j | |||
* i | |||
. 2.03 (1ese of - | |||
g offsite power) - | |||
\ . .i4 | |||
.Canetdows Response **.. | |||
* t | |||
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[ | |||
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;I | |||
.+ | |||
* A 5.13 sec trid underveltage with severalisA/E's. a cesservative estimate based a | |||
,.upes discussions 3-where less of offsite power occurs. This is the point ' | |||
, j g | |||
;} - | |||
**This is the period of time fattowing inittetles of pump | |||
. . coastdown for which essentially se flow degradaties is | |||
.. observed. - | |||
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: a. Theprotectionphikesophyemployedbyall11Wplaatsagatast' flew 71 f amena11cs has been the use of a flux-te. flew trip feature. | |||
J. parther protecties agatasc less of pusrs It isisS&W'rprovided by the that posities pump | |||
.; , power mesitor status trip functies.these two 373 trip functions adequate | |||
*pestvisted transiests and no addittoast protective devices are accessary. Justificaties of this posities is gives is the | |||
.I'' - | |||
fellowing persgraphs. | |||
' A simplistic view of as underfrequency transions is to assume a t | |||
. , , 1 to 1 ratie betwesa percent frequency decar and percent fle reducties. | |||
Ig . | |||
Therefore, the 1 to 1 ratie assumpties Also,is thecesservative an i4- primary assumed issue has to azist been decayfer the este, discussies whereas.toinfollow. reality, there exists two W. frequency limits to c Weder. Cae is the decay rats for.a sua. | |||
ai , tained underfrequency transients the other is a minimum frequency | |||
,. . above which sufficient flev exists as prevent CNE fres occurring. | |||
J. | |||
* per aes sustained decay rates that recover to assimal frequencies prior to totalThe frequency fluz.to. flew dec.ty trip below setpoint this ralue, the core is determined by one. remains 3 | |||
* protected. | |||
,: L. | |||
m | |||
* . two. er four pusy coastdeva depending en whethe j' *l ** * " , - | |||
pissp somiters, respectively.the plaat is protected against that Thefisw reductie | |||
:41 . nised,f the source, l.a.. less of pump (s) er underfrequency. | |||
l 'i e less fluz.to o . flew trip setpoint then deteraiaes the sustsiaed decay | |||
..- rate for which protecties is provided and typically ranges fres . | |||
. 1.6 Et/sec to 1.6 Nt/sec for 34W plaats. ~ | |||
If 1911 et rated power is divided by the flas.ts. flew rette.Ifa 4 | |||
conservative this flow is ceaverted flew is established by the 1 to asuch ratie that assumpties no CN1into occurs. a | |||
) * | |||
. say frequency decay rate that It is the recevers.before responsibility the is below typical values of 5d to 37 Ns. | |||
* *ef each applicaat to deseastrate grid stability within this range. | |||
l | |||
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+ | |||
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as- . | |||
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- As as intriating)which event, couldthereoccurare noTo be as taitiating event, a l- | |||
^I failures (FMVF's by esiattag 341f safety analyses. | |||
h re, , | |||
FMYF would have to be postulated la the seceadary r line plant w e as sa example, a less of feedwater accident erhculd | |||
.;{ feedwate . ' | |||
,? | |||
, '! ( | |||
break weald benad valve blockage. ie ins Ne other valv , | |||
t r. | |||
't esisting redundancy requirements failures for of safety re f-As a sia le failure folieving as event,hich there are are noc separa o a valve blockage and safety concerns ggi,ded, that valves w i ! already opes are assumed to retaan astegrity. - | |||
[ | |||
r, Regarding the afog of data gathering lacking; however, several programs, we feel ftha 9$ . | |||
3enerally the availafailure in forty years to is determine ndervsy. | |||
presenti prob- T I* | |||
j! ' | |||
- excellent industry programs to col set such data are u ; | |||
i' " and it must be coatluded that data sufficientskility | |||
- . ~ . - - . . . | |||
lsa est nl ' It is expected that the eversti probability # | |||
- of an event p u pMYF et a critically located valve is very law. - . | |||
j *! ' -- .. ; | |||
i ; t, - | |||
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g t - | |||
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s 11 ; .. | |||
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y 1 . | |||
i I . . ._. _. . . . . _ . | |||
._ ,,.r i 2, f F15 [9.36 9 0)- "- | |||
325[09331- | |||
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.}} |
Latest revision as of 02:22, 16 February 2020
ML20024C743 | |
Person / Time | |
---|---|
Site: | Three Mile Island |
Issue date: | 07/28/1978 |
From: | Taylor J BABCOCK & WILCOX CO. |
To: | Mazetis G Office of Nuclear Reactor Regulation |
References | |
TASK-07, TASK-7, TASK-GB GPU-0494, GPU-494, NUDOCS 8307130203 | |
Download: ML20024C743 (13) | |
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y c:; mis' Babecci(rM!cox %. m , , . . en - maemtana,u s.=sessa Team,e moe m u s h * ~. [ July 28, 1978 *
/
b Mr. 8. E Masetts . Reacter Systems Branch . Divistem of Systems safety . .. Office of Nuclear Reactor Asgulaties-
- E S. Nucigar Regulatory Ceanissica
.'. Washington, D.C. 20535 .
I Seferencess (1) Letter and Inclosure 5. F. F. Bass. Jr., NRC, to E. E. Suhrke. 34W, March 18. 1977, subject Technical issues for Vender Partietsattoa . j . (2) Letter, James L Taylor, 34W. to C. E.Hazetis, ' l- .. NBC, Angust 22, 1977, same subject
Dear Mr Nasetis:
Raclased are three (3) copies of our responses to 'the so selected technical issues published in NU21G.0128 and NORIG-0133, requested by your letter of March 18, 1977 (Beforence 1). These responses are in accordance with our 3] 1stter of August 22, 1877 (Reference 2). '
!; If you have ear further questions conceratag this matter.-
lj , plasse contact Mr. William R. Speight (1st. 2SO2)'ei y taff.,..
,d , Very Ln truly yoursiyr . - - .
[k
.3 James N. Tay1 .. ,. Nasager, Licensing .. .
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- 1. O. Yesburgh W. R. Speight
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ha genent of stuastes Men ssfet, cende testement'in pvstostiene steas une ereas ucsoents ,
.j r4'.Babcock M tsad W11ces basically supports the NRC position as expressed . { ; L.
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i (. q in asNURgf. back 0134 La regards to the use of sea. safety grade equipment s. g n' g *
. to safe co onents during a staan-Line break. ' The g number e issues ra sed y secondary.systes transients is large L
- t. and ceaplex enough, that a systematic approach to all secondary
; treasient issues should be undertshes. Therefore, in lieu of ;g** .
reiterattar the analysis assumptions currenti in recent SAR sub-
., mittals. SW proposed a series of meetin a vi the Ceanission ,
1eading towards final resolution of the asues involved with , . l 5f .s - secondary system induced trsasiests.
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1s,s,3g,J,,a Delaved less of Offstte Power Pe11ewiar a LOCA* I l tU * . . , , A. Offsite power remains available following a LOCA: the ' 8
- diesels start; at seas time after the LOCA effsite power It %* sg is interrupted; critical lead 2 are interrupted for a -
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short time until sequessed en to the diesels. .
- 3. Offsite power reaalas available followier a LOCA: the *
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- diesels starts at some time after the LOCA and the ECC5'
- . signal is reset offsite 9 * ** aketdeum leads (met ECCS)are power sequencedis laterrupted, sa (the safe '.
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I' diesels any mise have been stepped, is which case:ther will have to be restarted). *
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This 1sses raises the sencets that the less of offsite power at
? . 4 * $ sees time follow a LOCA would result in auch more severe de* .
esasequences than i effsite power were test sensurrent'with the t' ! **. ** . LOCA transient. A study was performed to assess the nazimum I' - *"*..*.s est of a less of offsite power (LOOP) at say time fellowing 9 LOCA. A minor increase as peak claddiar temperature was ebtained: however, due to the sufficiently Iow probability for
. ., this assurrease. 34w fests that it is met necessary to consider g; .
- 1007 subsequent to the LOCA. ,,,,- ,
pellowing the LOCA. the ISPAS signals will actuate the* diesels, and will attala rated voltage"and speed withia 10 sesseds.
. If offs te power is them.last at seas time after the LOCA. ..'
M automatic sequencing features are provided se that interrupted ECCS flew '.e the core is fally re-established withia 20 seesada. Per BEN's plaats, the ESPAS signal is act required to be reset. j* Thus, part 3 et this issue is met to be~ addressed. l l Am. t of a eaded LOOP t* afteranalysis a LOCA.has Thebeenworstperforand ease break, to assess an 8.5L theftp double
..* . break 'et the piump discharge with a Co
- 1.0. for SEN's 205 FA plaats was re. analyzed assuming a LO3P at the time the CFT's '
empty (36 seceeds). A delay of le seconds was them assumed before the BCCS flow to the core was fally re established. A
] -
100P at the time the CFT's empty will yield the naziana tapast en peak sladding temperature for the fellowias reasons
. 1. Prior to the time t:se CFT's empty, the laterruptions of- . ECCE. flow because of a 100P would be less than 10 seconds g* des to the continued flew free the CPT's. Thus, the imps weeld be less severe than ti.at analysed. ; 2. At any time after the CPT's empty, the amount of time
- hat ECC3' flow would be interrupted dos to a LOGP
- weald be the same as that studied. Newever, for a 1007
,? that occurs lates thaa the time the CPT's empty, the j . sore geench frams would be higher and the sore decay , heat lower than that analysed. Both of these conditions y , will result in less-severe ceaseguences than that en=imad.
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il* : - f.i . 3 * *. . [ is lessense to issue 4 (Cent'd)., . The results of the ' analysis showed that the peak cladding j- g temperature Sacreased 70 7 to 2144,,7. ,, ,
- It is important to mete that this ame1 7sis was' performed'for '
- l ' ." . 34W's 305 FA staats which utilize Mark C (17 x 17) feel. Das to
, a alty en Mark C refleeding heat transfer esaditions (0.3
- tiplier sa the F12 CIA predicted coefficients), the sensequences
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of the LOOP ars highly everestimated. Because of the penalty. . 8 peak sladding temperatures occur,at opprezimately 100 seceeds Ie
, , rather than at approvinately 40 seconds as obtained for plaats with Mark 3 (15 x 15) feel. The extended ties to reach the anaimmt cladding temperature after the time the CFT's empty toads 'i-;
to enp*1fy the impact of the LOOF. Realistically q- - that stad?.iag temperatures would increase less tha. n 30 it isF.espected l f-The results of the analysis discussed above obviously seemd the'
- I effect of a LOOF subsequent to the LOCA for all Sgv plaats. Ia *
}
Nl 4 ' addities,is it hshould be meted that the scenarie of events #
'j! analysed ble imprehable. If the less of offsite poser is t4 : a result of a gr perturbaties due to the LOCA, the less shea14 ,. g escur within the first few secoats which is the.present analysis method. Thus, this sencess addresses an indey=d==t less ed Pouer. _ . . . The probability of am 1A. ' t less of effsite poser la a
- ens neer period, according to WASE.1400, would be about one skaase
-l.i8 la 50.300. The likeltheed of a large LOCA is about ene chasse ' ;5 e4 la 10.000 per reacter year. Furthermore, the analysis that was - per.
- e. formes.e .aa assumes in 20 a stagle is .ma se failure seen, of.on.e. th .diesel,whi.ch to.4 r. is about -ility of - - ~
;; this sequence of events is very les e
- t* As illustrated for SEN's plaats, the tapact of a LOOP subsequest .
-l to a LOCA results is only a miner impact sa peak sladding ture and does met endanger the public health. Also, the .,j ii*
- ability of the event is estremely low. Thus, the LOOP ,
11 swing a LOCA meed met be seasidsrod for 30f's plaats. j
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'y the situaties of a concurrent i.e. staultaneens locked retor e
and less of offsite power is considered as incredible event. Therefore, the situaties analyzed la response to this issue is a l locked roter event with less of offsite power resulting from *the .~, subsequest rascter. turbine trip. ,
- The sequence of events for a tacled*Reter'Transiest with a less-t,. of effsite power as analyzed is gives in Table 1. As can be seen. .
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- a cesservative value of ISO millisecents is used for the time between turbine stop valve acties ase less of power to the RC
. ! - Famps. The systes rosynsee is shown in Figures 1. I and 3 for if\ L the mestros power, .systen pressure ar.4 AC flow respectively.
The resultant D(31 ase stad temperature response is skews is
, . Figure 4. As is clearly shows. the less of offsite pewer has a. , =,{ segligible result en the peck clad tesysrature. This cesparative lg result holds true for all 34W reacter types, altheagh the -result ef the locked retor transient asy vary depending sa plaat type. ..l. .
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- a. Theprotectionphikesophyemployedbyall11Wplaatsagatast' flew 71 f amena11cs has been the use of a flux-te. flew trip feature.
J. parther protecties agatasc less of pusrs It isisS&W'rprovided by the that posities pump
.; , power mesitor status trip functies.these two 373 trip functions adequate *pestvisted transiests and no addittoast protective devices are accessary. Justificaties of this posities is gives is the .I -
fellowing persgraphs.
' A simplistic view of as underfrequency transions is to assume a t . , , 1 to 1 ratie betwesa percent frequency decar and percent fle reducties.
Ig . Therefore, the 1 to 1 ratie assumpties Also,is thecesservative an i4- primary assumed issue has to azist been decayfer the este, discussies whereas.toinfollow. reality, there exists two W. frequency limits to c Weder. Cae is the decay rats for.a sua. ai , tained underfrequency transients the other is a minimum frequency
,. . above which sufficient flev exists as prevent CNE fres occurring.
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- per aes sustained decay rates that recover to assimal frequencies prior to totalThe frequency fluz.to. flew dec.ty trip below setpoint this ralue, the core is determined by one. remains 3
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l 'i e less fluz.to o . flew trip setpoint then deteraiaes the sustsiaed decay
..- rate for which protecties is provided and typically ranges fres . . 1.6 Et/sec to 1.6 Nt/sec for 34W plaats. ~
If 1911 et rated power is divided by the flas.ts. flew rette.Ifa 4 conservative this flow is ceaverted flew is established by the 1 to asuch ratie that assumpties no CN1into occurs. a
) * . say frequency decay rate that It is the recevers.before responsibility the is below typical values of 5d to 37 Ns. * *ef each applicaat to deseastrate grid stability within this range.
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h re, , FMYF would have to be postulated la the seceadary r line plant w e as sa example, a less of feedwater accident erhculd
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[ r, Regarding the afog of data gathering lacking; however, several programs, we feel ftha 9$ . 3enerally the availafailure in forty years to is determine ndervsy. presenti prob- T I* j! '
- excellent industry programs to col set such data are u ;
i' " and it must be coatluded that data sufficientskility
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