ML19254D943

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Forwards Preliminary Results of Steam Line Break Analysis Prepared by S&W.Mathematical Error Discovered in Calculational Model Resulting in Incorrect Assumption Re Feedwater Flow.Correction Due 791101
ML19254D943
Person / Time
Site: Beaver Valley
Issue date: 10/25/1979
From: Carey J
DUQUESNE LIGHT CO.
To: Wigginton D
Office of Nuclear Reactor Regulation
References
BVPS:JJC:621, TAC-12263, NUDOCS 7910300350
Download: ML19254D943 (10)


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DUQUESNE LIGHT COMPANY Beaver Valley Power Station Post Office Box 4 Shippingport, PA 15077 October 25, 1979 BVPS:JJ1:621 Feedwater Break Analysis Mr. Dave Wigginton Lincensing Project Manager Beaver Valley Unit No. 1 United States Nuclear Regulatory Commission Division of Operating Reactors Washington, DC 20555

Dear Dave,

Enclosed is a copy of the information that I have received from Stone & Webster.

Please be advised that in the course of the Stone & Webster Quality Assurance Review of these results, a mathematic error was discovered in calculational model. The effect of this error was to incorrectly assume that a portion of the FW flow to the intact SGs was spilled to the containment.

The correcting of this error will yield somewhat longer times to arrive at the peak containment pressure.

I hope to submit the Quality Assurance approved results for docketing in early November.

Sincerely,

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J. Carey Technical Assistan't - Nuclear JJC:krg

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3EAVER 7 ALLEY POWER STATION - UNIT NO 1

DUQUESUE LIGHT COMPANY MAIN STE AM IJNE BRE AK ANALYSTS - J.0.MO. 1 W 2.03 At tached please find the preliminary results of the BV-1 Main Steam Line Break Analysi s.

'd e understand, per your Mr. Jack Carey, i. hat you will transmit this information to the NRC as preliminary information not for docketing.

A final annlysis comparing different units has been requested by the NRC; and will also be transmitted to you to be forwarded to the URC.

If you have any questions please call.

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NOTES OF TELEPHOT4 CONVERSATION Date of Call:

October 1, 1979 J.O.!!o. 13352.03

Subject:

BV-1 MAIN STEAM BREAK ANALYSIS Farticipants:

Duquesne Idght Company -

Gil Moore Clifford Dunn Jack Carey Nuclear Regulatory Ccemission -

David WigEenton Janice Kerrigan Elinor Adensam David,Ehum Stone & Webster Engineering Corp. -

W. C. Drotleff E. A. Warman R. M. Stark C. E. Ader F. A. Elia, Jr.

E. A. Thomas B. F. Jones As requested by the NRC at their meeting, Septenber 21, 1979, DLC and SEW reported the status of the BV-1 main steam line break (in the containment) analysis.

Assumptions used in the analysis and the preliminary results of the EV-1 analysis are attached.

Calculated auxiliary feedvater pump run-out flow for the broken loop is approxi-mately 1600 gpm, for the two intact loops is approximately 200 gpm each, 900 gpm coming from the turbine driven pump and 550 gpm coming from each motor driven pump. A containment backprescure of 20 psig was included in the broken 1cep system resistance.

In response to the NRC's question regarding the chance in auxiliary feedvater pump-runout flow, SEW stated that 2800 cpm was based on pu..p characteristics, whereas the 2000 gpm was based on a more detailed analysis including calculated system resistance.

The NRC asked for a telecepy of tho attached assumptions and tables which are to be marked preliminary information, not for docketing.

In addition, the NRC asked for a response to the following questions:

1.

What main feedvater isolation valvo closing timo was used in the analysis?

2.

What is the maximum main steam line volume botveen the broken stoca Cenerator and the nearost main steam line stop valve?

3.

Khat is tho maximum main steam lino voluto botveen the camaged steam Cencrator stop valvo and tho other steam generator stop valves?

4 What is tho total of 2 and 3 abovo?

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5.

What is the maxi =um feedvater volume between the main feedvater isolation valve and the steam generator?

6.

Provide Westinghouse furnished mass / energy release for the 1.4 sq ft break for all power levels available.

A copy of S&W's responses to the above questions is attached.

The responses were sent to NRC, attention Elinor Adensam, 301-492-7617, telecopier number 7371, on October 3, 1979.

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Assumetions:

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Main steam non-return valve functions instantanecusly to isolate the fau.f,ed stsam generator break from reverse main steam flow.

2.

Blovdown :..te of the faulted steam generator is calculated by SW/W, feedvater flow control valve goes to full open, zero pressure drop through the steam generator for 30% and 103% cases.

3.

The two intact steam generators stay pressurized.

43 Steam generators are isolated by controls ce.. sing the break.

5 Auxiliary feedvater flow is available within ten seconds, with run-out flow going preferentially to the faulted steam generator per system hydraulics.

6.

Heat transfer coefficient is constant, heat transfer vs. tico per co=puter code.

(~ 1200 BTU /lb) 7.

Containment backpressure is 20 psig for all cases.

8.

Single active failure is one CIB resulting in minimum safeguards; i.e., failure of one-half of the containment sprays.

9 No operator action is assumed.

10. All auxiliary pumps operational.

Footnotes (1 ). Initial Conditions - 10.4 PSIA, Service Vater T = 86 F, Tc = 105 (SAT)

(2). Initial Conditions - 11.6 PSIA, Service Water T = 32 F, Tc = 105 (SAT) 1229 111

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Vestinghouse 1.4 33.0 305 38.0 30 (')

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  1. C.No. /3352. 03 Sto&E 4 k/EBS72=K Anwers to URC 0 estions on Prelininary Beavor hiley 1 Con ainmnt Pressure Analysis 1.

What nain feedwater isolation valve closing tino was used in the analysis?

' Answer:

7.5 sec.

2.

What is the naxinun min steam line volune between the broken steam generator and the nearest min stean line stop valve?

3 Answer:

985 ft (Loop A) 3.

What is the raxinun min stean line volume between the danced steam generator stop valve and the other steam generator stop valves?

3 Answer 8,000 ft (0 used in the analysis) 4.

What is the total of 2 and 3 above?

3 Answer:

8,985 ft (985 used in the analysis) 5.

What is the maxinun feedwater volume between the min feedvater isolation valve and the steam generator?

3 Answer:

283 ft 6.

Provide the Vestinghouse furnished mass and enercy release data for the 1.4 sq. f t. break for all power levels available.

Response

Vestinghouse data as inputted to our analysis are given in the attached sheets.

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