ML17297B166

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Forwards Response to Open Item 8 in Section 1.9 of NUREG-0857, Ser
ML17297B166
Person / Time
Site: Palo Verde  Arizona Public Service icon.png
Issue date: 01/05/1982
From: Van Brunt E
ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
To: Tedesco R
Office of Nuclear Reactor Regulation
References
RTR-NUREG-0857, RTR-NUREG-857 ANPP-19829-JMA, NUDOCS 8201130362
Download: ML17297B166 (28)
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Text

REGUL>>)RY. I>>VFORYIATION DISTRIBUT>> SYSTEM (RIDS)

ACCESSION iVBR: 8291130362.

DOCi,DATE: 82/01/05 VQ>>TIARIZEOi: YES DOCKEIT FACILi:STN 50-528'iallel V'erde 4uc lear Stat i opr 'Uni t i,'Ariiona Pupil i 8'TN 50 5'29 Piallol V'er de 4ucl ear Station)

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Uni t 3( Arizona Pu'ol i 08000530 AUTH ~ iVAlYIEI AUTHOR>> AFF>>ILII'AiT>>IO>>V VAN 'BRUNT'rE>>,EI.riiopai Publ>>ic'ervice C'ol.

REC'IPT, VAlYIE RECIIP>>IEiVfl AFF ILIIATIO>>4 TEDESCORR

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Assi stahti Director for Liicensing SUBJECIT-:

Ftirwa'rds r esoopse tol Ooen Item 8 in Sect i op 1 ~ 9 i>>IURKG'85>>7'E'" "SKR '"l 0ISTRIBUTEDR CEDEli 000>>0 CORKER RECEIYED:LITE $

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TITLE PSAR/FGAR.

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MlllRa lltQ RU!wtcpllClle CKOEQINDHW P.o. BOX 21666 PHOENIX, ARIZONA85036 January 5,

1982 ANPP-19829 JMA/KWG Mr. R. L. Tedesco Assistant Director for Licensing Division of Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C.

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Subject:

Palo Verde Nuclear Generating Station (PVNGS) Units 1, 2 and 3

Docket Nos.

STN-50-528/529/530

~

File:

81-056-026 G.1.10

Reference:

NUREG-0857, "Safety Evaluation Report" related to the Operation of Palo Verde Nuclear Generating Station Units 1, 2 and 3, dated

November, 1981

Dear Mr. Tedesco:

Please find attached our response to Open Item No.

8 identified in Section 1.9 of the referenced document.

It is presented in draft FSAR format and will be, incorporated in a future amendment.

If you have any questions, please contact me.

Very truly yours, I

EEVBJr/KWG/av Attachment cc:

J. Kerrigan P. Hourihan R. Greenfield A. C.

Gehr (w/a)

E.

E. Van Bru

, Jr.

APS Vice Pres dent, Nuclear Projects ANPP Project Director

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STATE OF ARIZONA

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I, John M. Allen, represent that I am Nuclear Engineering Manager of Arizona Public Service Company, that the foregoing document has been signed by me for Edwin E. Van Brunt, Jr., Vice President Nuclear Projects, on behalf of Arizona Public Service Company with full authority so to do, that I have read such document and know its contents, and that to the best of my knowledge and belief, the statements made therein are true.

Sworn to before me this (oM day of n M. Allen

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1982 otary Public My Commission expires:

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6.2.1.5 Rinimum Containment pressure Analysis for Performance Ca abilit

. Stud es on er enc re o in S stem 6.2,1.5.1 Introduction and Summar Appendix K to 10CFR50 provides the required aod acceptap'{q features of emergency core cooling system (ECCS) evaluation models.'

Included in this list is the requirement that the containment pressure assumed in the evaluation of ECCS performance not exceed a pressure calculated conservatively for that purpose.

The result presented herein was obtained using the method and models approved by the Nuclear Regulatory Comission (HRC).

This result demonstrates that the transient containment pressure

response, based on Palo Verde design parameters, is not more limiting than the generic response used in the ECCS performance analysis for the System 80 Standard Plant, which is presented in Section 6.3.3 of the CESSAR-,

FSAR (Reference 2}.

6.2.1.5.2 Pathod of Calculation See CESSAR-F Section 6.2.1.5.1 6.2J.B.3 ~IL P The ECCS performance analysis for the System 80 Standard Plant is intended to be applicable to and referenced in this Palo Verde Safety Analypis Report.

Therefore, the input used for the minimum containment pressure analysis was chosen such that the results, which were used in the ECCS per formance analysis of CESSAR-F Section 6.3.3, conservatively enveloped the Palo Verde design.

The input used for the analysis presented herein employed parameters specific to the Palo Verde containment design, including representation of the effect of operating the eight inch power access purge system.

6.2.1,5.3.1 Mass and Ener Release Data The mass and eneroy released to the containment for the limiting large break LOCA, 1.0 x DEG/PD, is listed as a function of time in Table 1.

The quantity of safety injection fluid that is assumed to spill from the break is discussed in Section 6.2.1.5.3.5.

6.2,1,5.3.2 Initial Containment Internal Conditions The ini,tial containment Temperature Pressure Relative Humidity conditions which have been used for this analysis are:

5O F

({ninimum}

13.4 psia (minimum) 100$

(maximum}

For each parameter, the conservative direction with respect to minimizing the containment pressure appears in parentheses.

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6.2.'.5.3.3 Containment Volume Th~ maximum net free containment volume assumed for this analysis is 2,600,000 ft.

-6,2.1.5.3.4.

Active Heat Sinks In order to conservatively maximize the heat removal capacity of the containment active heat sinks, the containment sprays are assumed to be actuated imediately following the break, and to operate at their maximum capacity assuming the minimum spray water temperature.

The assumed operating parameters for the containment sprays are as follows:

Flow Rate Temperature 77IIO gal/min (total, all pumps) 60 F

6.2.1.5;3.5 Steam Mater'ixin h

v)))a)

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.The effect of'ondensing 'containment steam with spilled KCS water upon the

, containment pressure is calculated in the manner described in Section III.D.2

"-k)of Reference 3.

The effective ECCS spillage rate is shown as a function of

-',~>time iq Figure l.

f

.'$6.2.1.5.3.6 Passive Peat Sinks

'",,<,'The surface areas and thickness of all exposed containment passive heat sinks

,'~ are listed in Table 6.2.1-8A.

To conservatively maximize the heat transfer to hese passive heat sinks, the surface areas are assumed to be at the maximum of

.;~'heir uncertainty ranges, and their thermal properties

{conductivity and heat

l.capacity} are a'iso maximized.

6.2.1.5.3.7 Heat Transfer to Passive Heat Sinks

)

See CESSAR-F Section 6.2.1.5.3;7.,

l 6,2.1.5.3,8 Containment Pur e

S stem The analysis presented in this section has been performed including the effects of the eight inch power access purge system.

The power access purge system is assumed to be operating at the time of the postulated LOCA.

The purge system isolation valves are fully closed 5.0 seconds after a containment isolation actuation signal generated by high containment pressure

{5.0 psig).

It is assumed that only drY air is removed from the containment atmosphere through the purge system.

Tkis conservatively minimized the calculated containment pressure.

I f

vs>l 6.2.1.5.4 Results" For the limiting large break LOCA, 1.0 x DEG/PD, the minimum containment pressure response for Palo Verde is not more limiting than the minimum containment pressure response used in analyzing the 'performance of the ECCS.

A comparison of the Palo Verde and generic System 80 containment pressure response is shown in Figure 2.

The responses of the containment atmosphere and containmlent sump temperatures for Palo Verde are shoran in Figures 3 and 4

respectively.

These results clearly shoe that the CESSAR containment pressure envelop has not been violated by using Palo Verde specific design parameters.

As such, System 80 ECCS performance results presented in CESSAR-F Section 6.3.3 are applicable

'o Palo Verde.

s

~ TABLE 1

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(theat I ef 8)

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BLO'~eCO'~IN AND REFLOQD MASS AND ENERGY RELEASE 1.0 X DOUBLE ENDED GUIL'OTINE BREAK IH PUt~P DISCHARGE LEG

~

~

~

~

Titrate

~sec 0

.05

.10

. l5

',20

.25

.35

. 45~

.60

.80 1.0 1.4

).8 2.2 2.6 30 3.4

'.8 4 4 5.2

,", 6.0

6.8 7.6 8.4 9.2

)0.0

)1.0

)2.0

13. 0
14. 0 Mass Flow

)bm/sec) 0.0 7.097 x 10

8. 2847 8,2234
8. 0164
8. 0621
7. 8749 9.7544

-7. 6083 7 5353

7. 4282
7. 1519
6. 8132 6.1414 5.3776 5.0588
4. 8416
4. 6063
4. 2674
3. 5744 3.)232
2. 8498
2. 6988 2.'6244 2.5071 2e3875
2. 2127

). 9730 1, 4056 1.0867 x 1

0.0 3.9747 x 1

4, 6555 4, 6171

4. 5023
4. 5320
4. 4326
4. 3682
4. 2885
4. 2496 4.) 9)2
4. 0418
3. 8600
3. 486S
3. 0602
2. 8906
2. 78) 6
2. 7169
2. 5319
2. 2329
2. 0305
l. 8713 1.7547
1. 6879
1. 6090
l. 5354 1. 4380
1. 3389 07 1.1824

).0224 x 10 Energy Re)ease 8Tu/SEC Integral of Hass F)ov

)be 0.0 3.6574 x )03 7.3531 x 104

).)464 x 10

l. 5532
l. 9547 2.7470 3.5251 4-6751
6. 1934 7.6878 x )05 1.0608 x 10
l. 3394
1. 6014 1.8299
2. 0381
2. 2356
2. 4267
2. 6958
3. 0080 3.2743
3. 5123
3. 7331
3. 9465
4. 1518 4.3476 4.5779 4.7884
4. 9597 5,0800

-" 10 Integral of Energy Release (BTU) 0.0 2.0497 x 10 4.1238 6.4326 8,7170 x 107 1.0973 x 10

l. 5430
1. 9811
2. 6291.

3,4852 4.3282

5. 9769
7. 5534 9.0393 x )0g 1.0338 x 10

).1525 1.2657

1. 3759
l. 5335 1, 7234
1. 8933
2. 0492
2. ) 937
2. 3315 2.4633
2. 5891
2. 7378
2. 8767
3. 0029 3.)132 x 1

0 il lJ S

il II' t

t (2'd;)

(Sheet 2 ofl'3)

BLOe'/DOrlH AND REFLOOD FeASS AND EilERGY RfLEASE 1:0 X DOUBLE END"D GUILLOTINE/E BREAK IR PUf1P DTSCHARGE LEG Tfme

~eee Mass Flow ibm/sec Energy Release BTU/SEC Integral of Mass Flow ibm)

Integral of Energy Release

~BT~(U

15. 0
16. 0 li.0 lse 0
19. 0
20. 0
21. 0
22. 0
23. 0
24. 0
25. 0 9.7275 x 10
7. 4384
5. 8326
5. 2488
6. 7388
6. 8805 6.3304 5.2770 4.3468
4. 1383 2.4047 82.1 92.1 102.'1 112.1 122.1 132".1 142.1 152.1 162.1 172.1 182.1 192.1 202. 1, 222.1 1.8045 2; 1736 2.1524 2.1427

)2. 1296 2.1261 2.1339 2.1101 2,1463 2.1490 2.1493 2.1661 2.1682 2.1912 x 10 25.-2

. 2.4476 x 10 Time of Annulus Downflow Start of Refload t,'values 32.1 "

0

42. 1 0
52. 1 0

62.1 0

72.1 1.9920 x 10 9.,1101 x 10

7. 8313
5. 7784

~ 5. 0939

5. 4679--
4. 8114
3. 9007 3.0069
2. 3716
2. 1111 1, 3428 1.3378 x 10 5.1854 x 10
5. 2711

. 5.3367

5. 3897
5. 4501
5. 5198
5. 5860 5.6442
5. 6922
5. 7324

- 5.7674

. 5.7738 x 10 below are 0

0 0

0 2.6000 x 2.3552 2.8370 2.8094 2.7966 2,7795 2.7749 2.7852 2.7541

.2.8014 2.8049 2.8052 2.8272 2.8300 2.8600 x 5. 7738

5. 782 5 5, 8013 5. 82 13 10'.8429 5.8643 5.8857 5.9070 5.9283 5.9496 5.9710 5.9925 6.0140 6.0356
6. 0572 6.1007 x 105 for steam only}

5.7738 x 10 5.7738 5.7738 3.2098 x 10 3.2949 3.3622

3. 4148
3. 4685 3.5209 3.5644
3. 5988 3.6255 3.6470 3,6651 3.6683 x 10 3.6683 x 10 3.6683 3.6683 3.6683 3.6796 3.7042 3.7302 3.7584 3.7865 3.8143 3.8421 3.8699 3.8977 3.9257 3.9537 3.9818 4.0100 4e0382 4.0950 x 10

I'

l.

~

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,. T!!Sty 1

!.Cont'g) (Sheet 3 of 3}

BLQQDG'Ai AND REFLQQD f4A55 AND ENERGY RELEASE

.l.0 X DOUB{ E E'>DED. GUiLL07INE BREAK IN PU'1P DISCHARGE LEG c'

~

T~me

~eec)

Mass 'Flow ibm/sec integral of Energy Release Mass Flow BTU/SEC lbm3 Integral of Ener~ Release (8TU

>>e

~

M le'42, 1

262.1 282,1 302.1 322.1 342,1 362.1 382.1 402.1 422.1 442.1 462.1

'82.1 502.1 522.1 542.1 562. 1 582. 1 602.3 632.1 02 2.1968 x 1

2,2132 2.2326 2.2412 2.2544 2.2618 2.2619 2.2700 2.2775 2.2773 2.2866 2;2860-2.2803 2.2802 2.2824 2.2751 2.2684 2.2752 2.2743 2,2744 x 1

0'.8673 x l 2.8886 2.9140 2.9252 2.9425 2.9521, 2.Q523 2.Q629 2.9726

. 2.9724

'.9844 2.9837

, 2.9763 2.9762 2..9790 2.9695 2.9607 2.9696 2.9684 2,9685 x 1

0'.1446 x 10 6.1888 6.2332 6.2779 6.3228 6.3679 6.4131 6.4584 6.5039 6.5495 6.5951 6.6407 6.6864 6.7320 6.7776 6.8231 6.8686 6.9141 6.9595 7.0276 x 10 08 4.1523 x

1 4.2099 4.2679 4.3262 4,3848 4.4437 4.5027 4.5618 4.6212 4.6803 4.7403 4.8003 4.8593'.9193 4.9784 5.0379 5.0972 5.1566 5.2158 5.3047 x 108

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08000 I

FIGURE 1 COf':.BIf')ED SplLLAGE AND SPRAY.

INTO CONTAIHNENT iH il 92000 ONE TANK SPILLIN6 DIRECTLY TO CONTAINNENT 50000 24000 EFFECTIVE ANf/ULOS SPILLA6E A

"i EFFECTIVE Pur<P SPILLAGE CONTAINYiENT SPRAYS 0

90 80 120 160 TINE AFTER BREAKS SECONDS 20

'4 l

60 ARIZONA CONTarNVEZT PRESSURE ANALYSIS KITH PURGIHG CESSAR FSAR 20 560

K tl I

FIGURE 5 t-ONTAINYENT TE[<PEMTuBE, 2OO 160 Q

20O 400 TIYiE, SECONDS

0 1/

I 0

0'00 160 I

00 0

0 100" 2oo 500 600 500

~I TIYiE SECONBS

0 fi gr t

h'I'

STATE OF ARIZONA

)

) ss.

COUNTY OF MARICOPA)

I; Edwin E. Van Brunt, Jr., represent'hat I am Vice President Nuclear Projects of Arizona Public Service Company, that the foregoing document has been signed by me on behalf of Arizona Public Service Company with full authority so to do, that I have read such document and know its contents, and that to the best of my knowledge and belief, the statements made therein are true.

Edwin E.,Van Brunt, Jr.

Sworn to before me this

day of 1981.

Notary Public My Commission expires:

~ ~

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