ML19296D102

From kanterella
Jump to navigation Jump to search
Single Loop Operation LOCA Analysis for GE Fuel,In Conformance w/10CFR50 App K (Nonjet Pump Bwr)
ML19296D102
Person / Time
Site: Big Rock Point File:Consumers Energy icon.png
Issue date: 03/31/1977
From:
GENERAL ELECTRIC CO.
To:
Shared Package
ML19296D077 List:
References
PROC-770331, NUDOCS 8002290341
Download: ML19296D102 (12)
v • d • e


Text

,

BIG ROCK POINT ?LiJ;T SINGLE-LOOP OPERATION LOSS-OF-C00L22;T ACCIDI:;T A';ALYSIS FOR GE!IR/d ELECTRIC TJEL IN C05F0FSJ2iCI *JITH 10CFR50 APPETDLI R (NON-JET PU1L2 30! LING L'ATER RIACOR)

ILGCH 31,1977 CENERAL ELECTRIC C0!9.WI 8002 2.903

\\

l,., u.o m.__, c-. m..<

a In July 1975, a loss-cf-coolant accident analysis for Big Rock Pcint was perfor ed uhich assumed that both of the plant's external recirculatica lecps were operating (Reference 1).

Both loop cperate in the normal code of operation.

Ho-ever, the plant en-also operact with only one recircula:lon loop in serrice ( s ingle-lce p

~

operation).

Operation in this ecdc changes come of the inputs to the accidant analysis.

This report describes the results of the single-lcop analysis, expressed in terns of fuel P.APLF.CR limits.

This report contains informatica supple = ental to Ref erence 1.

The secticas of Ref erence i describing ground rules of the analysis, ECCS descriptica, fuel types analy:cd, approved cc:puter cec 2s. and the single-f ailure analysis apply to this analysis also and are not repeated here.

The retaining sections of :his report describe assu=pticas and results particular to the single-lcop analysis ac applied to General Electric fuel caly.

b.t.cr e 1r)

.2._- r -.r s e.,/ 3 3

.hs 1.crJe suws

  • .a..

s wo u m

When cperating vi:h only a single loop, une locp is active (pump running) and :he other is inactive (pu p no: running).

10 is assumed tha: the inactive lcop is

isolated, i.e.,

na pu=p suc:icn and discharge valves, as well as the bypass valve, are all closed.

This is the situation which occurs when a pump seal f ails, for cxs=ple (Reference 2).

This analysis does not consider cperation with the inactive loop permitting ei:her na: ural circulatica or back ficv.

With one isolated loop, the si;nifican: input pars =eters, including those which change frc: the July 1975 analysis, are listed in Tabla 1.

_L_O Cc..=

  • p..

e 3.-

. *;. r

~~

n a -* ;== m = r.a t-

.,3.= =.= r..e y.c.i r e.=.=.=.* -v..

~..

u.

Full-sired pipe breaks were postulated in three locaticas to determine the location of the ucrat break:

Location Descriotion A

24" recire. suctica of the active leep.

This is the loca:1cn of :he Design Basis Accident (D3A) of Reference 1.

3 20" recire. discharge of the isolated loep.

C 24" recire. suction of the isolated leop.

Since location 3 produced a peak cladding temperature (PCT) higher than the ?CT at locaticas A or C, locacica S was identified as the lccation of :he worst full-sfaed pipe break.

A variety of breaks c: aller than full-si cd were then analy:cd at locatica 3.

These breahs, along with full-sized breaks of other primary pipes, are listed lu Table 2.

AP PI:0'l D CO."'"~.-~ R

,'0 D E S

'Ihree GE computer codes, approved by the US"?,C Co Appendix ; analyses, vere used in this analys ts.

.se:erence i e:: pia ans how

n.... u.u.c., an: m.-r
7. are usec to predict the Big Rock Point loss-of-coolan: transien:.

fAJE and CRA5!I are described,

in Reference 3, and CECA?-1:I is descri':ed in Rafarence 4 Pw b m.5 e-

- -. u.. r 3 "s e. Lv. e r. a e

Ut a

Table 3 lists the impor tan t results for ::.e breaks lis:ed in Table 2, when analy:ic; the heatup of " edified-F f uel at 5000 MWD /T.

1: is seen tha: :he 0.500 ft.2 b r eak in the recirculation discharge of the ina e:ive loep (10.ca:i:n 3) is :he vorst L:cah, f rom the behavior of the peak cladding temperature.

The local c:cidatica never gets near the upper li=1: of 0.17.

Table 4 shows the behavior of.MATLHOR vi:h axposure fer M dified-? fuel.

The second column gives the MA?iHCR lini: f or dcuble-leep Operati:n, as calcula:cd for the DE\\

La Reference 1.

The :nird colu n gives :he MA?;E;K lini: f:: s ingle-locp opera ti:n, as calculated for the 0.500 ft.

vors: break in this analysis.

The f:ur:h colar shows the "APLHCR cffset. :: decrease,':e veen the se::n: nd :hird colu :s.

T.:e naxinus MAPLHCR off se: is 0.5 be/ f t.

a t. 15,000 P.O/T exposure.

CCNCLUSION For Modifiad-F fuel, it is conscreative to appl, the :::<.i :: MA?iEOR cifset of 0.5 kv/ft. 20::ss :he exposure range of tne dou':le-10:p MA?LE 7 lini:s :: 05:afn the s ' - - 1 C.S o p." 's". 2.G.'. 1.4...'.....

Because of the similarity of F fuel to Modifiad-? fuel as der:ns::sted

  • 'a v's?LEGR limits of Ref erence 1, applica:ica of the n --"- 0.5 kv/ f:. MA?LHOR eif se t de.1/ed for Modified-? :.el should he valid for F fuel.

Table 5 gi.es :he MA?; HOR 11 i:s gc so,y. rue,. - e..

z.

au o..

.,., g n..,..,.......

c,.a.

..-.,:,,..,2....-..

- z1oa.,-

t.

a sfe t c s o - o ~.. ' c. '

s.'-~,i.

-o_

o a.. a..*...*. ' ' =. n..=._..-,

. -. '... '. =. ' '. -

.e r

.-~-.. ~-...'-,- 0.4 '. n'.:.

free the double-1 cop numbers.

$c~$ $lMM nrrtRrsCzs 1.

" Big Rock Poin-Plan::

Loss-of-Coolan: A::id an: Analysis f:r General Electric Fuel in Conf or:ance with ICCFRSO Appendix ; (5:n-je: ?urp 3:ilin; Ja:c: Reactor),'

July 11, 1975. This repor: Was Appendix A cf the.'uly 25,.??5 sub:1::21 by Consumers Power C :paay to the USNRC, Cccke: 50-155, License DFF.-6.

2.

" Big Reck Point Single Loop ECCS Analysis," letter fro: H. W. Keiser (CPC) to R. M.

Fairfield (CE), 5cvenber 4,1976.

3.

UEEE-20566?, "Ceneral Elcetric Conpars Analv:ical Model for L:ss-of-Coolan Analysis in Accordance with ICCFR50 Append:cc

," Severber 1975.

4 MEDO-20lS1, "GECA?-III:

A Mocel for the Predic: ion of Pellet-Cladding Thernal Condu c t uce in IJR Fuel Rods," Neve:5cr 1973.

TABLE 1 SIC'i!FIC.UC IN?LT PARA."ETERS PAPM ETER VAI';E Core Ther=al Power 244.8 If4t (corresponds to 102 of (no change) licensed =axt=u: power of 240 }f4t)

~

Steam Drue Steam Flev 275.7 lb=/sec.

(corresponds to 244.8.'Gt)

(no change)

Reactor vessel Pressure 1350 psig (corrcscending saturati~a (no eb' ge) cc=perc*.ure,is 3M I'7 Prl=ary Syste: Volu=e 3585 ft.

(vas 3639 ft.~)

Active I,oep Recirculation Flov 7.1 x 10 lb /hr.

6 (for 2 loops, was 11.2 x 10 lbm/hr.)

TA3LE 2 BIG ROCK POI'.7 3REAX SPECTRUM FOR SINGLE-LOOP OPERATION BREAK AREA, ft.

Recire. disenarge-isolated loop full-sized break 1.600 (location 3) 80% full-st:cd 1.280 (location 3) 60% full-si:cd 1.000 (locatica 3)

Smaller breaks 0.750 (location S) 0.500 (location 3) 0.375 (locatica 3) 0.250 (locatica 3) 0.100 (location 3) 0.050 (location 3) 0.025 (lecatica E) 0.008 (location S)

Full-sized breaks in other pipes Do neceu-2.5482 Riser 1.7252 Steam Line 0.6303 Feedvat e:

0.4481 Recire. Discharge - active loop

. 3636 No::lc Core Spray 0.07439 Ring Core Spray 0.009392 Rectre. Succica - active loop (DSA) 3.926 (location A)

Recire. Suction - isolated loop 2.326 (locatica C)

TABLE 3 BREAK SPECT?.UM OUANTIT!ES R SINCLE-LOOP OPEEATICN PEAK LOCAL PCI OXIDE BREAK F

FRACTION +

FAILURE l.600 ft.

2183

.068 No::lc Spray (location B) 1.280 2177-

.067 No::le Spray 1.000 2182

.068 No::le Spray 0.750 2183

.069 Nozzle Spray 0.5002 2192

.072 No: lc Spray 0.375 2162

.066 No::lc Spray 0.250 2168

.063 No :lc Spray 0.100 2076

. 04 9 No::le Spr:y 0.050 1977

.03L Nc::lc Spray 0.025 1788

.012 No::lc Spray 0.000 1422

.002 No :lc Spray Downec cr 1949

.03G "o::le Sp:ay Riser 2118

.052 No::le Spray Stes: Line 2021

.035 Nozzle Spray Feedveter 19G6

.023 Nozzle Spray Reed re; - Ei.s'..;rge Active Loup 2155

.061 Nozzle Spray No::lc Core Spray No uncovery 1 RDS Valve Ring Core Spray 1337

.001 1 RDS Valve Recire. Suction -

Active Loop 2144

.059 No::lc Spray Recire. Suctica -

Isolated Loop 2096

. 048 Nozzle Spray

  • Worst break
  • Core-wide metal-water reaction o:cidation 6 0.50~

Continued TA3LE 3 - ERE.G SPECTRLSI Qt1/C;TITIES FOR SINGLE-LCO? 0?IFATION CHAST04 SAFE 02 Cc=puter Run Lug Numbers:

770315-04760-3920N 770231-11264-2329N 770315-12137-3921N 761222-15421-2505S 770315-22999-39225 770290-26198-2S18S 770224-17317-2S2'N 770230-261S7-2S17S 770225-257S2-2S27N 770210-27657-2320S 770330-24315-3929N.

770209-25491-23195 77020S-27461-2316S 770214-26453-2322S

T/2LE 4 PJPLHCR OFFSET '/ALUES FOR v.0DIFIED-F FL'EL Exposure Double-Loop Operation Single-Loop Operation Offset mm/T P.AP LHC R, kv/ft.

P.AP LH C R, ht/ft.

MAPLRC?, h'/ft.

200 9.5 9.1 0.4 5000 9.9 9.5 0.4 10000 9.9 9.5 0.4 15000 9.8 9.3 0.5*

20000 8.7 8.4 0.3 25000 8.4 8.1 0.3

  • Maxfru: offset chosen f or aoplicatica to double-loop operation EGLHGR to obtain single-loop opcretion EG:.HGR Ifnit.

e Co=puter Run Log Nu=bers:

770321-26977-3923N C2AST04 770231-10317-391%

C" uT04 770330-07621-392SN CHAST04 770208-26157-2817S SAFE 02

TA3LE 5 RECC15::DED FUJLHCF LUC *S Double-Loop Operation Single-Leop Opera:ica Exposurc

.APLHCR, 6 /ft.'

192LHGE, h /ft.**

h*JD/T F Fuci

. Mod-F Fu el

? Fuel

.v.:d-F Fuel 200 9.4 9.5 8.9 9.0 5000 9.7 9.9 9.2 9.4 10000 9.7 9.9 9.2 9.4 15000 9.6 9.8 9.1 9.3 20000 S.6 8.7 8.1 8.2 25000 8.3 8.4 7.8 7.9

  • Reference 1
    • 0btained bf applying 0.5 h/f t. offcet to double-loop cu=bers.

ADDE!!EU'4 A

$C

[* O Y O Q 1 M f, D l'. I (

R

,y

l... O a a d [ C 6a t.

4su NUCLEAR ENERGY SYSTEMS DIVISION GENERAL ELECTRIO COMPANY,175 CURTNER AVE.. SAN JOSE, CALIFORNIA CS125 G-EJ-7-66 November 29, 1977 Mr. S.

S.

Chan Consumers Power Company 1945 West Parnall Road Jackson, Michigan 49201

SUBJECT:

BIG ROCK POINT SINGLE LOOP ECCS ANALYSIS

REFERENCES:

1) Letter, HM Keiser to RM Fairfield,

" Big Rock Point Single Loop ECCS Analysis", 11/4/76

2) Report, " Big Rock Point Plant, Single Loop Operation, Loss-of-Coolant Acci-dent linalysis for General Electric Fuel in Conformance with CFR50 Appendix K (Non-Jet Pump Boilir.g Water Reactor) ",

3/31/77

Dear Mr. Chan:

This is in response to your letter of July 11, 1977 con-corning the Big Rock Point Single Loop ECCS Analysis.

Your letter listed three questions.

The responses to these ques-tions are given below.

Question 1 Reactor vessel pressure should be 1350 psia, not 1350 psig (see Table 1 of the analysis in Reference 2).

Response 1 The correct value of reactor vessel initial pressure is indeed 1350 ps.ia.

Table 1 of Reference 2 contained a typo-graphical error which should be corrected to read "1350 psia".

An initial pressure e5 1350 psia has been used in all Big Rock analyses since 1975.

-continued-

Mr.

S.

S.

Chan November 29, 1977 G-EJ-7 66 Question 2 The minimum recirculation flow rate in the Big Rock Point Technical Specifications is 6 x 10' lbm/hr which is, lower than the active loop recirculation flow of 7.1 x 10* lbm/hr assumed in this analysis.

Please provide the reason for using 7.1 x 10' lbm/hr and give a qualitative estimate of the 6

ef fect on MAPLI!GR if a recir culation flow of 6.0 x 10 lbm/hr had been used in this analysis.

Response 2 The value 7.1 x 10' lbm/hr used in the single loop analysis for the initial active loop recirculation ficw was taken from item 4 of Reference 1.

Reference 1 provided specific inputs, including the initial active loop recirculation flow, to the single loop analysis in response to questions from General Electric prior to performing the analysis.

A qualitative estimate of the effect on MAPLHCR of using 6.0 x 10' lbm/hr is possible.

Three breaks (a big break, the worst break, and a small break) were analysed with SAFE.

The change in core uncovery times and rated spray times are given below.

Big Break Worst Break Small Break 2

2 2

Break 1.600 ft 0.500 ft 0.025 ft 7.1 x 10'~lbm/hr Uncovery time, sec.

4.02 10.75 205.04 Rated spray time, sec.

27.66 63.98 251.49 Time between uncovery 23.64 53.23 46.45 and spray, sec.

6.0 x 10' lbm/hr Uncovery time, sec.

3.93 10.22 203.53 Spray time, sec.

27.72 64.60 250.15 Time between uncovery 23.79 54.38 46.62 and spray, sec.

Change in time between un-

+0.15

+1.15 0.17 covery and spray, sec.

- continued -

Mr.

S.

S.

Chan November 29, 1977 G-EJ-7-66 For the 0.500 ft 2 break, the heatup rate for Mod-F iuol at 5000 MWD /T is 3.64*F/sec. at time of rated spray.

Delaying rated spray results in an estimated PCT increase of (1.15 sec.)

(3. 6 4 a F/sec. ) = 4.2 F, which is an insignificant increase.

Since the current PCT is 2192 F, an increase of 4'F would not result in a PCT in excess of 2200 F.

Hence, no change in MAPLHGR would be expected for the worst break and limiting fuel if 6.0 x 106 lbm/hr had been used in the single loop analysis.

Question 3 Past operation of the Big Rock Point Plant with one active loop has been limited to about 200 MWt due to MCHFR' limits.

Please provide a qualitative estimate of its effect on MAPLHGR.

Response 3 The MAPLIIGR limits for single loop and double loop operation are shown below, along with the ratio comparing the MAPLHGRs (Mod-F fuel):

Exposure Double Loop Single Loop Single MUD /T _

MAPLHGR, fw/ft M APLilGR, kw/ft Double 20e 9.5 9.0 0.95 5000 9.9 9.4 0.95 10000 9.9 9.4 0.'S 15000 9.8 9.3 0.95 20000 8.7 8.2 0.94 25000 8.4 7 '. 9 0.94 lissuming that the double loop MAPLHGRs permit full power opera-tion at 2 4 0 n.v t, then reducing powar to 200 MWt for MCHFR reasons results in a power ratio of 0.83.

Thus, single loop operation is limited in power by a 17 ?. MCliFR derate, and not by MAPLHGR, which requires at most a 6% derate.

If you have any further questions, please do not hesitate to call.

Very(trulvvours, l

0i

q.,l 'K {J,
  • 07 J'Eb L M.

A.

Costandi Product Service Engineer BUR Services M/C 881 - Ext. 51615 MAC:nmd

.

Retrieved from "https://kanterella.com/w/index.php?title=ML19296D102&oldid=4817109"