ML20137F596

Forwards Response to SER Open Item 3 Re Containment Sump Analysis,Per 850731 Meeting Presentation.Analysis Determines Effects of Sump Screen Blockage Due to Insulation Debris Generated by High Energy Line Break.Results Acceptable

ML20137F596
Person / Time
Site:	Vogtle
Issue date:	08/23/1985
From:	Bailey J GEORGIA POWER CO.
To:	Adensam E Office of Nuclear Reactor Regulation
References
GN-690, NUDOCS 8508270013
Download: ML20137F596 (13)

Text

Georgit Power Company Route 2, Box 299A W:ynisboro, Georgia 30830 Telephone 404 554-9961 404 724 8114 Southern Company Services, Inc Post Office Box 2625 m Sirmingham, Alabama 35202 Telephone 205 870-6011 Vogtle Proj.ect August 23, 1985 Director of Nuclear Reactor Regulation File: X7BC35 Attention: Ms. Elinor G. Adensam, Chief Log: GN-690 Licensing Branch #4 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555 NRC DOCKET NUMBERS 50-424 AND 50-425 CONSTRUCTION PERMIT NUMBERS CPPR-108 AND CPPR-109 V0GTLE ELECTRIC GENERATING PLANT - UNITS 1 AND 2 SER OPEN ITEM 3: CONTAINMENT SUMP ANALYSIS

Dear Mr. Denton:

Attached for your staff's review is an analysis to determine the effects of sump screen blockage due to insulation debris generated by high energy line break. This analysis formally documents information presented to your staff in a meeting on July 31, 1985. The results indicate that there is adequate NPSH for the containment spray and the residual heat removal pumps, which draw suction from the containment sumps, to perform their safety function.

If your staff requires any additional information, please do not hesitate to contact me.

Sincerely, J. A. Bailey Project Licensing Manager JAB /sm Attachment xc: D. O. Foster G. Bockhold, Jr R. A. Thomas T. Johnson (W/o Att.)

J. E. Joiner, Esquire D. C. Teper (W/o Att.)

B. W. Churchill, Esquire L. Fowler M. A.-Miller W. C. Ramsey B. Jones, Esquire (W/o Att.) Vogtle Project File L. T. Gucwa 0053V j & Rie I pd$

8508270013 850823 g,fFll,jft . }

/.g PLR ADOCK 05000424 l(If N' E PDR

o .

I. INTRODUCTION Open item 3 of the VEGP Safety Evaluation Report (NUREG-1137) identified a concern that a high energy line break within the primary containment might create sufficient insulation debris that subsequent build-up on the emergency core cooling system (ECCS) pump suction screens could impair operation of these pumps (Residual Heat Removal (RHR) and containment spray (CS)) by reducing the available NPSH below the required NPSH. In response to this concern, an evaluation was conducted to estimate conservatively the quantity of insulation debris that might be generated by a high energy line break and be deposited on the sump screens, the resulting head losses and the effect on the ECCS pump NPSH margins.

II. DESIGN BASIS BREAK At the request of the NRC staff to consider the limiting case, the debris generation and resultant impact on ECCS sump performance was reviewed for the double-ended rupture of the RCS hot leg at its connection to the steam generator.

The RCS loop 4 hot leg break at the steam generator nozzle was chosen for the following reasons:

o The RCS hot leg is the largest source of insulation in the RCS piping.

o The steam generator is the largest insulated component in the subcompartment.

o The surge line is unique to loop 4.

o The configuration of RCS branch lines and other insulated piping in the vicinity of the break is typical of the other three loops.

III. ASSUMPTIONS The containment emergency sump screen head loss evaluation for the double-ended rupture of the RCS hot leg at its connection to the steam generator (SG) inlet nozzle was based on the following assump-tions.

o The zone-of-influence was a jet cone expanding 45 degrees from the pipe outside walls and extending a distance of seven steam generator nozzle diameters (7D) from the break location. (Figures 1 and 2) i l

1

~

o The protective effects of the stainless steel jackets on the "Nukon" insulation was based upon test results in reference 1:

100% of the insulation within the zone-of-influence extending to a distance of 3 SG nozzle diameters from the break location was destroyed.

70% of the insulation within the zone-of-influence between 3 and 5 SG nozzle diameters from the break location was destroyed.

10% of the insulation within the zone-of-influence between 5 and 7 SG nozzle diameters from the break location was destroyed.

o The failure mechanism of destroyed insulation was assumed to be complete shredding and deposition of all shreds in the recirev]ating water.

o The water level in the containment was based upon RWST discharge during injection and switchover to recir-culation, plus the water volume of three accumulator tanks.

o Two different cases of debris distribution on the four containment emergency sump screens were considered.

Case I: Even Distribution Hydraulic model studies (reference 2) performed on a scale model of the VEGP containment emergency sump configuration showed that the approach velocities to the four sumps during two train operation was essentially the same. Therefore, it was assumed that transport of the debris, after exiting the steam generator compartmenL, was such that deposition on

-each of the sump screens was equally distributed. For this case, the volume of debris deposited on one sump was one quarter of the entire amount of debris generated by the postulated pipe break event.

Case II: Uneven Distribution In this case, it was assumed that debris distribution was governed by the pump flowrate rather than the approach velocity in the vicinity of the sumps. Because the recir-culation flowrate of the RHR pumps was different than the CS pumps while the flow area of the screens wag the same, debris deposition on the screens was also different. Based upon a ratio of individual pump flowrate to total recirculation flowrate, it was determined that each RHR sump screen received 31.7% of the total debris generated.and each CS sump screen received 18.3%.

2

o The shadow effect of the steam generator support ring and -the self-shadowing effect of the steam generator itself were considered. Insulation within the shadow zones was assumed to remain intact. (Figure 3) o The stainless steel jacketing on the insulation was assumed to sink immedinte13 and was not transported to the sump screens.

IV. METHODOLOGY ,

The emergency sump screen head loss is calculated using equation (2) in section 5.5 of NUREG-0897, Rev. 1 (reference 3).

The head losses due to fibrous debris blockage of the sump screens can be calculated by:

b c AH = a where, AH = Sump screen blockage losses Q = recirculation flow rate (ft /sec)23(ft H O) -

V =

volume of insglation debris deposited on screen (ft )

A =

effective (wetted) screen area

, i a = 68.3 b = from Reference 3 for "NUKON" 1.79'k insulation c = 1.07 s

"A" is further defined as follows:

A eff = effective open screen area per A

containment emergency sump (ft2) l T =

total screen cross section areg)per containment emergency sump (ft The equation then becomes b c f

! AH = a Q) fU h A T

, teff4 -

l l

i l

i 3

l

c IV. CONSERVATISMS Two conservatisms were inherent to the evaluation and their effects are qualitatively discussed in the following paragraphs.

o It was assumed that all insulation generated by the postulated pipe break event entered the recirculating fluid and eventually migrated to the containment sump screens, even though the break location was physically separated from the sump location by the secondary shield wal]. This assumption ignored settlement of the debris in low velocity water in the large region inside the secondary shield vall. It also ignored debris deposi-tion on obstructions in the flow path to the sumps, such as structural steel columns and equipment supports. This assuption maximized the transport of the shredded debris.

o The zone-of-influence jet was assumed to extend a dis-tance equal to seven times the steam generator nozzle inside diameter (ID) (31 inches) instead of RCS hot leg ID (29 inches). This assumption increased the volume of the shredded insulation.

V. RESULTS ,

For both cases evaluated, using a conservative estimate of the quantity of debris generated and transport, it was found that the available NPSH for the RHR and CS pumps exceeded the required NPSH for proper pump operation. The minimum available NPSH margin for the even distribution case was 2.5 ft. and for the uneven dis-tribution case was 2.2 ft.

Table 1 provides the input data for this evaluation. Table 2 summarizes debris distribution within the zone-of-influence. As shown in the table 3, the insulation debris generated by the break of the RCS het leg at the steam generator nozzle will not jeopardize Dun and CS pump operation at VEGP. This conclusion is based on the theoretically worst case where 100% of the insulation debris generated by the break is assumed to be completely shredded and migrate onto the containment emergency sump screens. The head loss due to the maximum theoretical debris blockage provides margin above the minimum NPSH requirements for the RHR and CS pumps.

4

r-Table 1 Input Data For Containment Emergency Sump Screen Head Loss Evaluation Volume of shredded insulgtion debris generated 182.8 by RCS hot leg break, ft (V)

Recirculation flow rate, ft 3 /sec (Q)

Per RHR pump (4500 gpm) 10.0 Per CS pump (2600 gpm) 5.8 Effective open screen area per sump, ft2 43eff) 22.9 Total screen cross section area per sump, ft2 (A ) 55.9 Pump NPSH required, ft RHR pump at 4500 gpm (pump runout) 19*

CS pump at 2600 gpm 15*

• Based on pump performance curve.

'l 5

Table 2 Zone-of-Influence Regions Debris Distribution VOLUME OF SHREDDED

% OF INSULATION INSULATION VOLUME OF INSULATION COMPLETELY gHREDDED WITHIN REGION REGION WITHIN REGION (ft ) (ft3)

(ft i

<3D 60 100 60 3D-5D 62.7 70 43.9 SD-7D 20.6 10 2.0 Steam Generator 76.9 100 76.0 TOTAL 219.6 -

182.8 6

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, -=. ,, --.------m- -y---.. 6 -.---. ,-- -

a .- .

i T

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s J VEGP .

TABLE 3 -

/

Emergency Sump Performance 1

NPSH Margin Debris NPSH Screen After ,

i Accumulated Margin Blockage Screen

~

on Each3 Screen Available Losses Blockage

. Pump ~ ft ft ft~ ft Case I: Even Distribution

CS 45.7 34.3 15.9 18.4 l q RHR 45.7 18.4 15.9 2.5 i

Case II: Uneven Distribution I

CS 33.5 34.3 3.4 30.9 4

RHR 57.9 18.4 16.2 2.2 e

i s

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i 4

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. . . -- .. _ - .. , _ _ . - ~ - _ , _ . . .. - . . - -. . _ .

- Figure 1 Steam generator, RCS hot leg and vicinity piping looking from east to west i

Figure 2 Steam generator, RCS hot leg and vicinity piping looking from west to east.

Figure 3 The shadow effect of the steam generator support ring and the self-shadowing effect of the S.G. (RCS hot leg not shown)

Color code of the zone-of-influence jet cone:

White - 100% distruction region (<3D)

Red -

70% distruction region (3D-5D)

Blue -

10% distruction region (SD-7D)

NOTE: Figures are for illustration purposes only.

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VI. REFERENCES

1. Hart, Gordon H., " Test Report: HDR Blowdown Tests with NUKON Insulation Blankets," dated February 18, 1985.

2. Final Report, Hydraulic Model Studies of Flow Conditions to Containment Emergency Sumps, September,1984 for A.W. Vogtle Plant.

3. Serkiz, A.W., " Containment Emergency Sump Performance,"

NUREG-0897, Revision 1, NRC, March 1984.

9