ML17318A556

Forwards ECCS Analysis Using Approved Westinghouse Feb 1978 Evaluation Model.Eccs Will Meet Acceptance Criteria Presented in Code for Breaks Up to & Including double-ended Severance of Reactor Cooling Pipe

ML17318A556
Person / Time
Site:	Cook
Issue date:	01/11/1980
From:	Hunter R INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	Harold Denton Office of Nuclear Reactor Regulation
References
AEP:NRC:00322C, AEP:NRC:322C, NUDOCS 8001150426
Download: ML17318A556 (90)

Text

REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION NBR:8001150426 DOC ~ DATt: 80/01/11 NOTARIZED: NO DOCKET FACiL:50".516 Oonaid (:, Cook Nuclear Power Plantr Onit 2i .Indiana 8 05000316 AOYH ~ NAME AU f HOB AFFILIATION IDENT HUNTERrR ~ ST Indiana 8 Hichigan Electric Co,

• RECAP ~ NAME HEC lP AFF ILLATION DENN~rH ~ RE Office oi'uclear Reactor Regulation

SUBJECT:

Forwards ECCS analysis using approved Westinghouse Feb 1978 evaluation model,ECCS wil) meet acceptance criteria presented in code for bieaks up to 8 including double ended severance of reactor cooling pipe, DISTRIBUTION CODE: A039S COPIES RECEIVED:LTR g ENCL ( SIZEe TiTf;E Resp to Lesson Learn Ta'sk Force" 'Westingliouse NOTES; OTES KKNn A B ~

~u yLL A /NBTZ VZ TB Z k K.

RECIP IE,NT COPIFS RECIPIENT COPIES If) LT'rA ENCL AC'l ION:

ID t'.OOE/NAME 10'BC Cga M/ / 7" f;TTH ENCL CODE/NAME INTERNAL: EG F IL 17 I 8 E 2 2 1

1 -g-v 1 i

1 i 2 NAC POR 1 i 20 CORk, PERF BR i i 21 ENG BR i i 22 kEAC SPif &R i 1 23 PI ANT SYS BR i i 2C EBB' 1 1 25 EFLT TAT SYS i LPDR i 1 NSIC i 1 5 J OLSHINSKI "' i 1 6 J KERRIGAN i 7 J HURDION i i 8 C WILLIS 1 G iMBRO 1 ST Te MELFORD 2 M FIELDS i i A ANDERSON i OELD i 0 Or REILLY i EXTERNAL: ?6 ACRS 16 16

~g pe TOTAL NUMBFR OF COPIES REQUIRED: LTTR ~ ENCL

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8, INDIANA IIi MICHIGAN ELECTRIC COMPANY',.

O. BOX 18 BOWLIN G GR KEN STATION NEW YORK, N. Y. 10004 January 11, 1980 AEP:NRC:00322C Donald C. Cook Nuclear Plant Unit No. 2 Docket No. 50-316 License No. DPR-74

Subject:

Peaking Factor Limits at Unit 2 In Light of Revised Analysis Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555

Dear Mr. Denton:

The purpose of this letter is to formally transmit to'ou information which was presented at a meeting held on January 10, 1980 and which was attended by members of your staff, by AEP and by Westinghouse Electric Corporation.

Attachment A contains an ECCS analysis for Unit 2 of the Cook Plant using the approved Westinghouse February 1978 evaluation model. This analysis resulted in a total F of 2.02 while our previously submitted and approved analysis using the October 1975 model with the .Correct metal-water reaction de-scription yielded an Fq of 2.11. The data explaining this reduction in Fq when using the newer model is contained in Attachment B. The February 1978 -analysis and the change in peaking factors associated with its. use-was discussed in detail at the referenced meeting wherein all attendees agreed that the February 1978 analysis is valid.

In light of the data presented in draft NUREG-0630, the total Fq for Unit 2 was further reduced by 0.03 as explained in our letters of January 8, 1980 (AEP:NRC:00322A) and January 9, 1980 (AEP:NRC:00322B). We have accepted this further reduction in Fq to 1.99'voluntarily.

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Nr. Harold R. Denton, Director AEP:NRC:00322C Finally, we have reviewed the revised Technical Specification Figure 3.2-2 submitted in AEP:NRC:00322B. This review confirms that the submitted figure is properly based on the February 1978, Unit 2 specific large LOCA analysis and the Unit 2 small break analysis previously submitted and approved (FSAR Section 14.3.'2),

and is therefore correct.

ery tr ly your RSH:em R. S. Hunter Vice President cc: R. C. Callen G. Charnoff J. E. Dolan R. W. Jurgensen D. V. Shaller-Bridgman

ATTACHMENT A TO AEP:NRC'00322C

The Loss of Coolant Accident (LOCA) has been reanalyzedfor sj ~ -2 . The foll.owing information amends the Safety Analysis Report section on Major Reactor Coolant System Pipe

'Ruptures. The, results are consistent with acceptance criteria provided in reference 1.

The description of the various aspects of the LOCA analysis is given

[2]. The individual .computer codes which comprise the in'CAP-8339 Mestinghoush Emergency Core Cooling System (ECCS) evaluation model are described in detail in separate reports [3-ag.a'long with code modifi-cations specified in references 7, 9 and 10. The analysis presented here was performed with the February 1978 version of the evaluation model which includes modifications delineated in references 11, 12, 13 and 14.

A ~

4 C

The analysis of the loss of coolant. accident is performed=at 102 percent of the licensed core power'ating. The peak linear I

power and total core power used in the analysis are given in Table 2.- Since there is margin between the value of peak linear power density used in this analysis and the value of the peak linear power-density expected during plant opera-tion, the peak clad temperature calculated in= this analysis is greater than the maximum clad temperature expected to exist.

Table 1 presents the occurence time for various events throughout the accident transient.

Table 2 p'resents selected input values and results from the hot fu'el rod thermal transient calculation. For these results, the hot spot is defined as the location of maximum peak clad temperatures.- That loca- .

tion is specified in- Table 2 for each break analyzed. The location is indicated in feet which presents elevation above the bottom of the active fuel stack.

Table 3 presents a summary of the various containment systems parameters Lo< IC.

and structural parameters which were used as input to the CR computer code -

used in this analysis.

l Tables 4 and 5 present ref lood mass and energy releases to the contain-

'ment, and the broken loop accumulator mass and energy release to the containment, respectively.

The results of several sitivity studies are reported . These results are for conditions which are not limiting in nature and hence are reported on a generic basis.

Figures 1 through 17 present the transients. for the principle parameters for the break sizes analyzed. The following items are .noted:

Figures 1A - 3C: guality, mass'elocity and clad heat transfer coeffi-cient for the hotspot and burst locations Figures 4A - 6C: Core pressure, break flow, and core pressure drop.

The break flow is the sum of -the flowrates from both ends of the guillotine break. The core pressure drop is taken as the pressure just before the core inlet to the pressure just beyond the core outlet Figures 7A - 9C: Clad temperature, fluid temperature and core flow.

The clad and fluid temperatures are for the hot spot and burst locations Figures 10A - 11C: Oowncomer and core water level during reflood, and flooding rate Figures 12A - 13C: Emergency core cooling system flowrates, for both accumulator and pumped safety injection

Figures 14A -

0 15C: Containment pressure and core power transients Figures 16, 17: Break energy release during blowdown and the contain-ment wall condensing heat transfer coefficient for the worst break

Conclusions - Thermal Anal sis For breaks up to and including the double ended severance of a reactor coolant pipe, the Emergency Core Cooling System will meet the Acceptance Criteria as presented in 10CFRg).46 .~ j That is:

1. The calculated peak clad temperature does not exceed 2200 F based on'a total core peaking factor of ~ O 2.- The amount of fu'el element cladding that reacts chemically with water or steam does not exceed 1 percent of the total amount of Zircalloy in the reactor.

3. The clad temperature transient is terminated at a time when the core geometry is still amenable to cooling. The cladding oxidation limits. of 17K are not exceeded during or. after quenching.

\

4. The core temperature is reduced and decay heat is removed for an extended period of time, as required by the long-lived radioactivity remaining in the core.

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References for Section ~ .4.1 e

1.. "Acceptance Criteria for Emergency Core Cooling Systems for Light Mater Cooled Nuclear Power Reactors", 10CFR50.46 and Appendix K of 10CFR50.46. Federal Register, Volume 39, Number 3, January 4, 1974.

2. Bordelon, F. M., Massie, H. W., And Zordan, T. A., "Westinghouse

. ECCS Evaluation Model-Summary," WCAP-8339, July 1974.

3. Bordelon, F. M., et al., "SATAN-VI Program: Comprehensive Space-Time Dependent Analysis of Loss-of-Coolant," WCAP-8302 (Pro-pr ietary Version), WCAP-8306 (Non-Proprietary Version), June 1974.

, 4. Bordelon, F. M., Et al., "LOCTA-IV Program: Loss-of-Coolant Tran-

'sient Analysis," WCAP-8301 (Proprietary Version), WCAP-8305 (Non-Proprietary Version), June 1974.

5. Kelly, R. D., et al., "Calculational Model for Core Ref looding after a Loss-of-Coolant Accident (WREFLOOD Code)." WCAP-8170 (Proprietary Version), MCAP-8171 (Non-Proprietary Version), June 1974.

I T. 8 Raymond M. ," Long Term Ice Condenser

'sieh, Containment-LOTIC Code 5m) SuPPlement 1," WCAP 8355 Supplement 1, Way IP75. WCAP-8354 (Proprietary), July 1974.

Letter from K. Kniel to J. Tillinghast, December 27, 1974-

"Order for Modification of License for the Donald C. Cook Nuclear Plant Unit l."

~

7. Bordelon F. M., et al., "The Westinghouse ECCS Evaluation Model:

Supplementary Information," WCAP-8471 (Proprietary Version), WCAP-8472 (Non-Proprietary Version), January 1975.

8. Salvatori, R., "Westinghouse ECCS

- 0

- Plant Sensitivity Studies,"

WCAP-8340 (Proprietary Version), WCAP-8356 (Non-Proprietary Ver-sion), July 1974..

I

9. "Westinghouse ECCS Evaluation Model, October, 1975 Versions," WCAP-8622 (Proprietary Version), WCAP-8623 (Non-Proprietary Version),

November, 1975.

10. Letter from C. Eicheldinger of Westinghouse Electric Corporation to D. S. Vassalo of the Nuclear Regulatory Commission, letter number NS-CE-924, January 23, 1976.

11. Kelly, R. D., Thompson, C. M., et, al., "Westinghouse Emergency Core Cooling System Evaluation Model for Analyzing Large LOCA's During Operation With One Loop Out of Service for Plants Without Loop Iso-lation Valves," WCAP-9166, February, 1978.

12. Eicheldinger C., "Westinghouse ECCS Evaluation Model, February 1978 Version," WCAP-9220-P-A (Proprietary Version), WCAP-9221-A (Non-Pro-prietary Version), February, 1978.

13. Letter .from T. M. Anderson of Westinghouse Electric Corporation to John Stolz of the Nuclear Regulatory Commission, letter number NS-TMA-.1981, Nov. 1, 1978.

14. Letter from T. M. Anderson of Westinghouse Electric Corporation to John Stolz of the Nuclear Regulatory Commission, letter number NS-TMA-2014, Dec. 11, 1978.

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TABLE 1 LARGE BREAK TIME SEQUENCE OF EVENTS DECL C.*/a DECL C~c DECL <o O. g 0Sec)

(Sec) (Sec)

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1.0 OECLG 1 PC TUSE PLUCClNC CORRECT Sl FLOVS NEV LOTIC V/PAlNT CORE PR.OROP

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FIGURE 10 a REFLOOD TRANSIENT DECLG(CD = / o )

DOWNCOMER,AND CORE WATER LEVELS

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FIGURE ll z. REFLOOD TRANSIENT - DECLG(CD = /.o )

CORE INLET VELOCITY

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C ~ V 0.0 5.0 ln E.

tt. 0 tn

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Coklp AhTHKHT PhESSUhf FIGURE 14 ~'ONTAINMENT PRESSURE - DECLG(CD ~ /.o )

1.0000 AHERlCAN ELECTRlc POVER COHPANY AHP UNIT 2 FEB 1ST'OOEL i+0 OECLG 1 PC TUBE PLUGGlNG CORRECT Sl FLOVS NEV LOTlC V/PAlNT POVER

~ Oo8000 O.

0.6000 0.1000 Oe F000 0.0 Cl C)

TlHE lSEC)

FIGURE 15 ~ CORE POWER TRANSIENT - DECLG(CD ~ /.n )

1.1000 AHERlCAH ELECTRlC POWER CONPAHY AMP UH1T 2 FEB 1978 HOOEL O.B OECLG 1 PC TUBE PLUGClHG CORRECT Sl FLOWS HEll LOTlC W/PAIHT OUAL1TY OF FLUIO SURSTI 6 ~ 00 FTt ) PEA)le 7.50 FTt+)

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I I

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~ . ~, c 'a I ~

100.00 AMERICAH ELECTRIC POWER COMPANY AMP, UNIT 2 FEB t9?8 MOOEL 0.8 OECLC 1 PC TUSE PLUCGINC CORRECT Sl FLOWS HEW LOTIC WJPAIHT MASS VELOCITY, SURSTI 6.00 FT( I PEAKI  ?.50 FTI ~ 1 u ?5.000 I

Al I

50.000 25.000 u

CI 0.0 g %5.000 Z

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TIME (SEC)

FIGURE -2 $ ASS VELOCITY DECLG(CD = o. g )

I AHERICAN ELECTRIC P04ER COHPANY AHP UNIT 2 FEB 1978 HODEL 0.8 OECLC I PC TUBE PLUCGINC CORRECT Sl FL04$ NE4 LOTIC 4/PAINT Boa.oa NEAT TRANS. COEFFICIENT BURSTS S.OO FTI,) PEA)le 7.50 FTI+)

500.00 Ioa.oa 300.00 200.00 40.000 cn 30.000 20.000 All)ll s.oooa 5.0000 a.ooao 3.0000 2.ooao I.oooo 8

C) o 8 TIHE (SEC)

FIGURE 3) HEAT TRANSFER COEFFICIENT - DECLG(CD 0 P )

.2500.0 AMERICAH ELECTRlC POMER CONPAHY A P UHlT 2 'EB 1978 HOOEL

-0.8 OECLG l PC TUBE PLUGGlHG CORRECT Sl FLOMS HEM LOTlC M/PAlHT

'PRESSURE -

CORE BOTTOM t )'OP, li) c 20M.O 1500.0

,1

~ ~ a 1000.0 500.00

.0.0 CI Cl T1HE [SEC)

~~

CORE PRESSURE

- DECLG(CD =. 0, q j FIGURE 4 g P

~ ~

I.OOE+5 .

AMERICAN ELECTRIC POWER COMPANY AMP UNIT 2 FEB 1978 MOOEL 0.8 OECLG 1 PC TUBE PLUGGING CORRECT Sl FLOWS NEV LOTIC V/PAINT BREAK FLOW 7.50E+Oi

~h 5.00E+Ol 2.50E+i 0 0

\

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~

TIME {SEC)

BREAK FLOH RATE

- DECLG(CD = oip )

FKGURE 5 $

~ '0 * .

"~ 4 p

70.000 AMERICAH ELECTRIC POMER COMPAHY AMP UHIT 2 FEB I978 MOOEL 0.8 OECLG . I PC TUBE PLUGGIHG CORRECT Sl FLOMS HEY LOTIC V/PAIHT CORE PR.DROP 50.000 cL 2$ .000 0.0

-2$ .000

-50.000

-70.000 CI o

CI CI CI oCI CD CI o o CV CD TIME (SEC)

FIGURE 6 b CORE PRFSSURE DROP - DECLG(CD = > g)

2500.0 AHERICAH ELECTRIC POMER COHPAHY- AMP UHIT 2 FEB )978 HOOEL O.B DECLG I PC TUBE PLUCGIHG CORRECT SI FLOMS HEM LOTIC M/PAIHT CLAD AVG ~ TEMP ~ HOT ROD BURST ~ 6 ~ 00 FT( ) PEAK ~ 7 ~ 50 FTI ~ )

cL 2000 0

'D4

!500.0 C

CD oC IOM.O 500.00 0.0 CD CD CD o CD CD TIHE {SEC)

FIGURE 7 J) PEAK CLAD TEMPERATURE - DECLG(CD ~ 0. g )

C h

C

2000.0 AHERILAII ELECTRIC POMER CONPANY AHP UNIT 2 FEB 197B HOOEL 0.8 OECLG 1 PC TUBE PLUGGING CORRECT Sl FLOMS REV LOTIC ll/PAINT FLUIO TEHPERATURE BURSTI 6+00 FTI ) PEAKo 7.50 FT(N)

I 1750.0 cI 1500.0 1250.0 I

1000.0 I

750.00 4

500.00 250.00 0.0 CI 8 CI CI CI CI 'l~ CI CI

~ I TlHE (SEC)

FIGURE .8 g FLUID TEMPERATURE - DECLG(CD = 0 8)

7000.0 AHERlCAN ELECTRIC POVER COHPAHY AMP UH1T 2 FEB 1918 HOOEL 0 ~ 8 OECLG 1 PC TUBE PLUGG1RG CORRECT Sl FLOMS NEV LOTlC M/PA)NT Z-FLOVRATE CORE 'OTTOH ( ) TOP (o) 5000.0 2500.0 I

O I

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~ h l

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CI O 4 O O O O O O Ill lfI T1 HE 1 SE C) f FIGURE 9 L CORE FLO>l (TOP AND,BOTTOM)

- DECLG(CD o o"F )

20.000 AHERICAN ELECTRIC POWER COHPANY AHP UNIT 2 FEB 197B HOOEL O.B OECLCI I PC .TUBE PLUGGING CORRECT Sl FLOMS NEM LOT[C M/PAINT MATER LEVEL(FT) 17.500 15.000 12.500 10.000 I

~w 7 5000 5.0000 2.5000 OeQ CI 8 C7 CI C) 8 TIHE (SECI E)GORE ]P $ REFLOOD TRANSIENT - DECLG(CD = 0 g ).

DOWNCOMER AND CORE WATER IEYELS

2.0000 AHERICAH ELECTRIC POUER CONPAHY AhlP UHIT 2 FEB 1978 HODEL 0.8 OECLG 1 PC TUBE PLUGGIHG CORRECT Sl FLOMS HEM LOTIC M/PAIHT FLOOO RATE{IH/SEC) 1.7500 1.5000

~ ~

g 1.2500 Q 1.0000 0.7500 0.5000 0.2500 0.0 CY Cl Cl

~

g TIHE (SEC)

FIGURE ll $ REFLOOD TRANSIENT - DECLG(CD = o' )

CORE INLET VELOCITY

I.OOE+Oi AMERICAN ELECTRIC POVER COMPANY AMP UNIT 2 FEB 1978 MOOEL 0 ~ 8 OECLG I PC TUBE PLUGGING CORRECT Sl FLO'ilS NEU LOTIC M/PAINT ACCUM. FLOM cn 8000.0 8000.0 F000.0 2000.0 0.0 CI CI CI CI CI C3 Cl CI CI CI CI CI IM n

TIME (SEC)

FIGURE 12 5 ACCUMULATOR FLOW (BLOWDOWN) - DECLG(CD =0 g )

a.:( I E

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COllP4ATHKtlT PAKSSUAK FIGURE l4 II CONTAINMENT PRESSURE - DECLG(CD = 0. g)

1.0000 AMERICAH'ELECTRIC POWER COMPAHY AMP UNIT B FEB 1978 MODEL 0.8 OECLG I PC TUBE PLUGGIHG CORRECT Sl FLOMS HEM LOTIC V/PAIHT POMER cl 0.8000 0.6000

~ O.OOOO I

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FIGURE 15 5 CORE POWER TRANSIENT - DECLG(CD = o, g )

~

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5.00E+07 AMERICAN ELECTRIC POVER COMPANY AMP UNIT i? FEB 197B MOOEL O.B OECLG 1 PC TUBE PLUGGING CORRECT SI FLO'VS NEV LOTIC V/PAINT BREAK ENERGY

~ 3.00E%7 I.COEN)7 CO

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FIGURE 16 BREAK ENERGY RELEASED TO CONTAINMENT

!,()

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4 rl 1.1000 AMERICAN ELECTRIC PO'MER COMPANY AMP UNIT 2 FEB 1978 MOOEL 0.6 OECLC I PC TUBE PLUGGING CORRECT Sl FIOMS NEW LOTIC M/PAINT OUALITY OF FLUIO BURSTr 6 ~ 00 FT( ) PEAKr 7.50 FT(+)

1.2500 I

LJ 1.0000 0.7500 I

0.5000 0.2500 0.0 oooo aD aD Q a a OOOOO a Q O O OOOO~

oa oa ooaooa D OOOOD O

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L FIGURE 1 c FLUID QUALITY - DECLG(CD = o.g )

~ )(" C 01 10,0.00 AMERICAN ELECTRIC POVER COMPANY AMP UNIT 2 FEB 1978 MOOEL 0 ~ 6 OECLG I PC TUBE PLUGGING CORRECT Sl FLO'MS NEW LOTIC V/PAINT MASS VELOCITY BURST ~ 6 ~ 00 FTI ) PEAK ~ 7 ~ 50 FT{+)

u 75.000 I

CCC I

50.000 25.000 0.0 0

)

4 -25.000 X

-50.000

-75.000

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a 8 8 888a8 ~

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FIGURE 2 c MASS VELOCITY

- DECLG(co .=

AMERICAN ELECTRIC POMER COMPANY AMP UNIT 2 FEB (978 MODEL 0.6 DECLG I PC TUBE PLUGGING CORf)ECT Sl FLOWS NEM LOTIC M/PAINT 600.00 HEAT TRANS. COEFFICIENT BURSTc 6 ~ 00 FT( ) PEAKED 7.50 FT(+)

500.00 100.00 x 300.00 200.00

~ 40.000 cn 30rooo

à 20.000 6.0000 5.0000 i.oooo 3.0000 2.0000 I.oooo

(~C Ig

'C CI C)

CD CD CO Cl a Cl CI CS I/\

TIME (SEC)

\

FIGURE 3 c HEAT TRANSFER COEFFICIENT - DECLG(CD ~ v.('

2500.0

'MERICAN 0 ~ 6 OECLG PRE SSURE I

CCRC

) c CTRIC PO'MER COMPANY TUB Bw ~ T'3M l ) TOP ~ I+)

AMP UNIT 2 PLUGGING CORRECT Sl FLOMS FEB I978 MOOEL KEM LOTIC M/PAINT 2000.0 l500.0

~

Ot 500.uU ci 0 CD CD CD CD CD CD CD CD CD CD CD CD CD cu TIME (SEC)

CORE PRESSURE 'ECLG(CD = o.~ )

FIGURE 4 c

I.OOMI5 AHERICAN ELECTRIC POWER COHPARY AHP UNIT 2 FEB I978 HOOEL 0.6 OECLG l PC TUBE PLUGGING CORRECT Sl FLOWS NEW LOTIC u/PAIHT BREAK FLO'W 1.50M)i 5.00bOi 2.50E+Oi 0.0

-2.50E+Oi

-5.00E+Oi

-7.50E+Oi

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'FKGURE 5 ~ BREAK FLOM RATE - DECLG(CD' o.4 )

70.000 AHERICAH ELECTRIC POVER CONPAHY AMP UHIT 2 FEB 1978 NOBEL 0.6 OECLG I PC TUBE PLUGGIHG CORRECT Sl FLOVS HEV LOTIC V/PAIHT CORE PR.OROP 50.000 R 25.000 0.0

-25.000

-50.000

-70.000 Cl Ch CI Cl CD C)

C) C3 ID Cl CI C) C) a Al n C5 TIHE {SEC) ..

.FIGURE 6 j, CORE PRESSURE DROP - DECLG(CD ~-o,G )

4,'

~ ~

2500.0 AHERICAN ELECTRIC POWER COMPA}IY AHP UNIT 2 FEB 1978 MOOEL 0 ~ 6 OECLG 1 PC TUBE PLUGGING CORRECT SI FLOWS NEW LOTIC WIPAINT CLAO AVG ~ TEMP ~ HOT ROO BURST ~ 6 ~ 00 FT( ) PEAK ~ 7 ~ 50 FTI+)

H 2000.0 o

o CL 1500.0 X

W I

C o 1000.0 500.00 0.0 o

a o CI D

Ill TIHE (SEC) 4~

FIGURE 7 g - PEAK CLAD TEMPERATURE - -

DECLG(CD = o 4 )

2000.0 AMERICAN ELECTRIC POWER COMPANY AHP UNIT 2 FEB 1978 HOOEL 0,6 OECLG I PC TUBE PLUGGING CORRECT Sl FLOWS NEV LOTIC U/PAIHT FLUIO TEMPERATURE 'BURST ~ 6 ~ 00 FTI ) PEAK ~ 7 ~ 50 FT(+)

1750.0 1500.0 1250.0 I

1000.0 CI 750.00 La 500.00 250.00 0.0 C) C) CI Cl CD C) Cl ID TIHE {SEC)

FIGURE 8 C- FLUID TEMPERATURE - DECLG(CD = 0 4 )

OOOO.O AMERICAN ELECTRIC POMER COMPANY AMP UNIT 2 FEB I978 MODEL, 0.6 DECLG' PC TuBE PLUGGING cORREGT Sl FLONS NEM LOTIC uiPAINT 2-FLOVRATE CORE BOTTOM ) TOP e* (+)

5000.0 lLI CI1 CO 2500.0 I

CC la.

I IV 0.0

-2500.0

-5000.0

-1000.0 Cl aC) CI C3 C) CI C) CI Al TIME (SEC)

FIGURE 9~ CORE FLOH (TOP AND BOTTOM) DECLG(CD = oi6 )

4 .

k

~

~

20.000

" AHERICAN ELECTRIC POMER COHPANY AHP UNIT 2'EB 1978 HOOEL 0.6 OECLG I PC lUBE PLUGGING CORRECT SI FLOMS NEU LOTIC "II/PAINT VATER LEVELIFT) 17.500

'15.000

. 12.500 10.000

~ 7.SOOO

~ s.oooo 2.5000 0.0 Cl C)

C)

C)

C) AJ TIHE (SEC)

FIGURE 10 g REFLOOD TRANSIENT - DECLG(CD = g,g)

DOMNCOMER AND'CORE MATER LEVELS 1

2.0000 AMERICAN ELECTRIC POVER COMPANY AMP UNIT 2 FEB 1978 MOOEL 0.6 DECLG I PC TUBE PLUGGING CORRECT SI FLO'VS NEV LOTIC V/PAINT FLOOO RATE(IN/SEC) 1.7500 1.5000 1.2500 1.0000 Lal

~ 0.7500 C) 0,5000 0.2500 0.0 aC) Cl Cl CI CD Cl C)

Cl TIME {SEC)

FIGURE ll c REFLOOD TRANSIENT " DECLG(CD g' )

CORE INLET VELOCITY

~ tg ~

Q l g I.OOE+Oi AMERICAN ELECTRIC POVER COMPANY AMP UNIT 2 FEB 1978 MODEL 0.6 DECLG I PC TUBE PLUGGING CORRECT Sl FLO'VS NEV LOTIC V/PAINT

/ ACCUM. FLOV

's

~ ~

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~ T CI x 6000.0 C

~,

2000 0., c" 0.0 E3 CI ED Cl C7 C)

C)

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FIGURE 12 g ACCUMULATOR FL'01< (BLOHDOWN) - DECLG{CD = y,g )

4

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I.0000 AHERICAN ELECTRIC POllER COHPANY AHP 'UNIT 2 FEB 1978 HOOEL 0.6 OECLG 1 PC UBE PLUGGING CORRECT SI FLOVS NEV LOTIC V/PAINT POVER

~ 0.8000 0.6000 0.1000 0.2000 0.0 C3 CS Cl Cl o C3 TIHE (SEC)

FIGURE 15 c. CORE POWER TRANSIENT - DECLG(CD = y, g )

ATTACHMfNT B TO AEP:NRC:00322C

TABLE 1 TIME SEQUENCE OF EVENTS OCT'75 W/ZIRC FIX FEB'78 ANALYSIS REACTOR TRIP SIGNAL 0.72 0.71 SI SIGNAL 4.64 4.83, ACCUt4JLATOR INJECT 14.5 14.6 SI INJECTS 29.64 29.83 END OF BYPASS 27.72 33.18 END OF BLOWDONN 32;04 39.07 BOTTOM OF CORE RECOVERY 44.48 48.97 ACCUMULATOR EMPTY 56.83 56.42

MASS DEFICIT IMPACT OCT'75 W/ZIRC FIX FEB'78 ANALYSIS LIQUID REMAINING 8 EOB 25163.4 lbs. 35299.9 lbs.

BYPASS DEFICIT 28324.3 lbs. 30487.5 lbs.

LIQUID REMAINING FOR REFILL 0.0 4812.4 lbs.

EOB ACCUMULATOR DELIVERY RATE 4600.0 lbs./sec.

AVAILABLE REFILL TIME DIFFERENCE 1.05 sec.

EOB DIFFERENCE 5.46 sec.

sec.

'.49 BOC DIFFERENCE

TABLE 2 RESULTS OCT'75 W/ZIRC FIX FEB'78 ANALYSIS FQT 2.10 2.02 PCT 2188 F 2,171 F ZPCT 8.0 FT 7.5 FT ZR/H20 RXM 7.71% 6.36K Z ZRH20 RXH 8.0 FT 7.5 FT HOT ROD BURST 36.8 SEC 40.6 SEC Z HRBURST 6.0 FT 6.0 FT

0 TABLE 3 OCT'75 W/ZIRC FEB '78 ACCUMULATOR EMPTY TIME 56.83 SEC 56.42 SEC ZD 9 ACCUMULATOR EMPTY TIME 15.99 FT 10.'35 FT ZC 9 ACCUMULATOR EMPTY TINE 2.01 FT 1.55 FT a

STEAN COOLING. STARTS 86.63 SEC 59.57 SEC Zp O'TEAM COOLING 16.0 FT 10.7 FT ZC 9 STEAM COOLING 2.72 FT 1.715 FT FULL DOWNCOMER TINE 63.6 SEC 128 SEC ACCUMULATOR WATER YOLUME 377.67 FT '223.37 FT PER TANK 9 BOC

4

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, MAJOR MODEL CHANGE IMPACTS A) 15 X 15 FLECHT - NO IMPACT B) WATER PACKING - AS NOTED EARLIER C) DYNAMIC STEAM COOLING - 60'F [WCAP 9220 -P-A]

D) 8= 1.25 DURING REFLOOD - REFILL 5 REFLOOD BENEFIT E) CODE MAINTENANCE 5 ANALYTICAL IMPROVEMENT - LESS THAN -12'F

INPUT CHANGES IMPACT A) SATAN 1') CORE POWER IN SATAN*

2) STEAM GENERATOR INITIALIZATION/T-INLET"

3) INCREASED SAFETY INJECTION

4) MICELLANEOUS*

B) REFLOOD

1) BROKEN LOOP ACCUMULATOR SPILL TO SPRAY**

2) INCREASED SAFETY INJECTION

3) LOWER PLENUM VOLUME REVISION C) LOTIC

1) PAINT ON CONTAINMENT SURFACES**

O), LOCTA

1) AXIAL NODING SCHEME - NO IMPACT

2) INITIAL ROD GAP GAS'BACKFILL PRESSURE

• LESS THAN 25'F IMPACT

• • LESS THAN 3'F IMPACT