ML20100L489

Amend to Application for Ol,Incorporating Encl marked-up FSAR Pages to Reendorse Previous Commitment to Reg Guide 1.82 Re Containment Sump Screens.Fsar Will Be Revised in First Annual FSAR Update.Oath of Affirmation Encl

ML20100L489
Person / Time
Site:	Wolf Creek
Issue date:	04/12/1985
From:	Koester G KANSAS GAS & ELECTRIC CO.
To:	Harold Denton Office of Nuclear Reactor Regulation
References
RTR-REGGD-01.082, RTR-REGGD-1.082 KMLNRC-85-086, KMLNRC-85-86, NUDOCS 8504170014
Download: ML20100L489 (5)

Text

. . .

KANSAS GAS AND ELECTRIC COMPANY T>E ELECTRC COMPANY

@LENN L MOESTER vect entsiotNT huctgan April 12, 1985 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555 KMLNRC 85-086 Re: Docket No. STN 50-482 Ref: SLNRC 84-0018 dated 2/2/84 from NAPetrick, SNUPPS, to HRDenton, NRC Subj: Containment Sump Screens

Dear Mr. Denton:

Flow criteria associated with the containment sump screens were revised in SNUPPS FSAR Revision 13 which was provided by the Reference. Up to that time KG&E commitments to Regulatory Guide 1.82 criteria had existed unchanged in the PSAR and FSAR since the SNUPPS Utilities responded to PSAR question Q040.15 in 1974.

The change came about when the Wolf Creek Architect / Engineer made final containment flood level calculations and was submitted to the NRC at KG&E's initiative. Recently we have found that the change should not have been made and KG&E now desires to reendorse our former commitments to Regulatory Guide 1.82.

Attached are marked up FSAR pages which reflect those previous commitments.

These pages are hereby incorporated into the Wolf Creek Operating License Application. The FSAR will be formally revised in the first annual Wolf Creek FSAR update.

Yours very truly, GLK:bb

% Glenn L. Koester Vice President - Nuclear Attach xc:PO'Connor (2)

JCummins hh gDR504170014 850412

\

p ADOCK 05000482 PDR 201 N. Market -Wictuta, Kansas - Mail Address: RO. Box 208 i WIctuta Kansas 67201 - Telephone: Area Code (316) 261-6451

. . ,,. ~ _ . .

5 OATH OF AFFIRMATION STATE OF.. KANSAS )

) SS:

COUNTY 0F SEDGWICK )-

I,-Kent R. Brown, of lawful age, being duly' sworn upon oath, do depose, -

state and affirm that I am Group Vice President - Technical Services of

- Kansas Gas..and Electric Company, Wichita, Kansas, that I have signed the

~

foregoing letter of. transmittal for Glenn L. Koester, Vice President.-

. Nuclear of Kansas Gas and Electric Company, know the contents thereof, .

and that all statements contained therein are true.

~

KANSAS GAS AND ELECTRIC COMPANY

' ATTEST: I .

j

, By i e - Kent R. Brown Group Vice President-Technical Services E..D.~Prothro, Assistant Secretary STATE OFLKANSAS ')

) - SS:

-' COUNTY'0F SEDGWICK ) r BE IT REMEMBERED that on this 12th _ day of- April, 1985- , before . ,

me, Evelyn L'. Fry, a Notary, personally appeared Kent R. Brown, Group Vice President - Technical ~ Services of Kansas Gas and Electric Company,' Wichita, Kansas,'who is personally known to me'and who executed =the foregoing instru- I ment, and he duly acknowledged the execution of the'same for and on behalf

'of and as the act and' deed of said Corporation.

/h.........hWTTNESSWHEREOF,Ihavehereuntoset.myhandand'affixedmyseal'the I

g - 9,,,k'dhhhndyearabovewritten.-

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,, j Fflyn .L/ Fry! NotTry

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'My Commission expires on August 15, 1985.

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AttacMient to .

KMLNRC 85-086 1 of 3 SNUPPS Since the containment spray pumps are designed to operate with ('

entrained particles up to 1/4 inch in diameter and the minimum (,j constriction size in the spray nozzles is 7/16 inch, this screening is adequate to assure proper system operability.

Each screening barrier has supports which are designed to h withstand the differential pressure which would exist if the -

screens were 100 percent clogged. Both the screens and the -

W grating are designed'to withstand the differential pressure of 100-percent clogging, and sufficient screen area exists to

'O allow over 50-percent clogging both screens without degrading .

It spray pump NPSH. The sump baffle arrangement is shown in -

~g Figure 6.2.2-3.

The sump baffle arrangement does not allow flow into the sump

[ below 6 inches above the concrete floor level surrounding the 2 sump. This arrangement leaves ample depth for buildup of

?[ high-density. debris without affecting sump performance.

Additionally, the velocity of recirculated fluids approaching theatrach rack vill be betreen 0.01 and 0.09 fps - faral-l y med : cf cperation fvilvwing LOCA cr-MSLB 3 _and thus a low g velocity settling region for high-density particles is pro-sq vided. Tatic S . 2. 2-9 provides ficw velevitics at ccver-at 2,_

(6 tinc; and lec tions for a 1&rge LOCA and an MSLB. 3___

E Any debris which eludes the baffling, screens, and settling region passes into the sump through the 1/8-inch screen and

-$ will be drawn into the suction piping for the containment y spray and residual heat removal systems. Such debris is small

( enough to pass through any restriction in either: system or the reactor vessel channels, and will eventually be pumped back f'# oqf- into the containment.

~

o hf b A comparison of the containment recirculation sump design f

y features with each of the positions of Regulatory Guide 1.82,

" Sump for Emergency Core Cooling and Containment Spray Sys-s3 W 2 tems," is provided in Table 6.2.2-1.

% 6.2.2.1.4 Tests and Inspections Q~ gy

{  ::

• ~ Testing and inspection of components of the CSS, except those s in the spray additive subsystem, are discussed in this section.

Testing and inspection of components in the spray additive subsystem are discussed in Section 6.5.2.4.

_j Each containment spray pump has a shop test to generate com- -

plete' performance curves. The test includes verifying total differential head (TDH) and NPSH for various flow rates. A shop thermal transient analysis, from ambient temperature to 350-F in 10 seconds, has been performed on the CSS pump.

Results of that analysis assure that the design is suitable for the switchover from the injection to the recirculation phase.

Re 13 6.2.2-12 2 4

t SNUPPS .

TABLE 6.2.2-1 (Sheet 2) .

' Regulatory Guide 1.82 Position Recirculation Sump Design i '

4. The floor level in the vicinity The floor is level in the vicinity of the coolant sump location of the sump. However, a 6-inch con-should slope gradually down crete curb is provided on which the away from the sump. screen is supported to prevent high density particles from entering the sump.

5. All drains from the upper regions All drains in the upper regions of i of the reactor building should the reactor building are terminated terminate in such a manner that in such a manner that direct streams 4 direct streams of water, which of water which may contain entrained

, may contain entrained debris, debris will not impinge on the filter

! will not impinge on the filter assemblies.

1 assemblies.

6. A vertically mounted outer trash A vertically mounted outer trash rack

rack should be provided to prevent is provided to prevent large debris

large debris from reaching the fine from reaching the fine inner, screen.

inner screen. The strength of the This trash rack is designed to with-trash rack should be considered in stand the differential pressure which #

protecting the inner screen from would exist if it were 100 percent missiles and large debris. clogged.

7. A vertically mounted fine inner A vertically mounted fine inner screen

-screen should be provided. The is provided. Tabic 0.2.2 ^ ytuviceilb design coolant velocity at the the ccclant velocitiec fer a large LOCA:

1 inner screen should be approxi-mately 6 cm/sec (0.2 ft/sec).

&nd eu M5LL et ccvercl lecctions eud ag___

_at ecvaral operational tiacc. The ,

"g#

RzE 4

The available surface area intent of item 7 1. me t . 2_, w8g used in determining the design coolant velocity should be based 4 ,fa gg g,; g y/g ;w 3.c,.,,g'8 ,

mo T5 on one-half of the free surface Assumig Af one half OHA* frf' N"* **d 8

• g area of the fine inner screen to 4,g g 4,, +. .fy, 7,,,/;o f bloc.#ef e, // rat-conservatively account for partial

blockage. Only the vertical -f/c. suonf lfVelr's minimal, ed tdd Ne S&pwmps screens should be considered in determining available surface area. gI y g ;,] ,f. ,,,,,;,,, , m g g/m l ,s T O'" s'w~b /X

] G5 %s. ,

• R .

e, C., ' MS d SNUPPS TABLE,6.2.2-9 SUMP SCREEN AND APPROACH VELOCITIES FOR LOCA AND MSLB CONDITIONS #-

I' FLOW '

FLOOD DEPTHSII RATE, OPERATIONAL Pt E/ MODE Min Max FLOW VELOCITIES - AVERACEI FPS gpm Approach to Trash Racks (3)

Through rash Rack (4) At Inner screen (5)

Clogged LARCE LOCA o At ECCS Switchover 2002-1 2003-0 4800 0.07 0.27 0.26 o At Ctat. Spray Switchover 2003-5 2004-6 8750 0.08 0.29 o 0.28 During Long-Term Cooling (6) 003-6 2004-4 4800 ^

~0 0.16 MLSB 0.15 o At ECCS Switchover 2001-8 2-8 1200 0.02 0.08 -' O.08 o At Ctat. Spray Switchover 2003-0 2004-1 51 0.05 0.09 o 0.19 During Long-Term CoolingII 2003-1 2004-1 2 0.01 0.04 0.04 NOTES: ~

(1) .

Flood depths (minimum and maximum) fo each operational mode or (2)

Average flow velocities are based ase are taken from Tables 6.2.2-6 and 6.2.2-6a.

depth more accurately describes the average of the minimum and e expected flood depths. Minimum de ximum flood depths since the average flood and maximum depths are for wo t-case flooding analysis. hs are used for NPS!! available calculations, I3I The velocity This trash rack approach more acc v ocity is based on a point 6 inches in front of th tely describes the maximum velocity associated with detrash rack. No blockage is assumed.

is settlement.

(4)

This flow velocity 's based upon the free area between the trash rack bars.

assumed. Fifty rcant clogging of this area is ISI This flow ve city is based upon the free area of the sump screens exposed to flow.

area is ase med. Fi f t NN particle It should be noted that the 6-inch curb has been provided to prevent scre ercent clogging of this depth; The sump curb effectively reduces the free screen area by an additional 20 percen blockage ere fore, the effective blockage is approximately 70 percent.

by heavy for a 3-foot flood $EE (6) The W g {o elocities for long-term cooling following a LOCA assume that the containment spray system opera on is ter- $$

I7I m' ated, since the cooling function is completed at switchover and iodine removal has been accomplishe 6" The velocities for long-term cooling following an MSLB assume that containment spray system operation is t inated $0 and the RCS pressure is at 400 psig, which is above the shutoff head of the RHR pumps. As noted on Table 6. -6a, isolation ment. Lonof auxiliary feedwater to the broken loop occurs at 10 minutes which terminates blowdown to the conta' -

hot legs. g-term recovery from an MSLB will be through cooldown using the normal RHR suction from the primary loo Once flow is established from the primary loop, suction from the sump will not be required.

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