ML18191A284

WPPSS Nuclear Project No. 2. Mark II Containment - Supporting Program

ML18191A284
Person / Time
Site:	Columbia
Issue date:	09/16/1975
From:	Strand N Washington Public Power Supply System
To:	Parr O Office of Nuclear Reactor Regulation
References
G02-75-261
Download: ML18191A284 (8)

Text

.4 NRC DISTRIBUTION FOR PART 50 DOCKET MATERIAL

'TEMPORARY FORM)

CONTROL NO'ILE'ROM.

Washington Public Power Supply System

Richland, Wash 0

Strand DATE OF DOC 9-16-75 9-25>>75 XX DATE R EC'D LTR TWX RPT OTHER

-- -TO'r, OLan D ~ Parr CLASS UNCLASS PROPINFO XXX ORIG signgd INPUT CC OTHER NO CYS REC'D SENTNRC PDR SENT LOCALPDR DOCKET NO:

50-397 DESCRIPTION:

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I ENCLOSURES:

ACTP,v~'!

Mark II Containpent-Snpporting Program

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1 cy of enc'1 rec'd)

PLANT NAME:

WPPSS 0'2.

FOR ACTION/INFC'Rl'RATION

-1"75 JGB BUTLER (L)

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Washington Public Power Supply System A JOINT OPERATING AGENCY P. O. BOX 968 3000 GEO, WASHINGTON WAY RICHLAND. WASHINOTON SS352 P HONE (509) 946-968(

Docket No.

50-397 September 16, 1975 GO 61 0) p0Cl P>6@I r

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("P Mr. Olan D. Parr Light Hater Reactor's Project Branch 1

8i Division of Reactor Licensing U ~

S. Nuclear Regulatory Commission

!lashington, C.

20555

Dear Mr. Parr:

D HPPSS NUCLEAR PROJECT NO.

2 MARK II CONTAINMENT - SUPPORT ROGRA I

Letter, J. J. Stein to W.

R. Butler, BWR Hark II Contai m

Additional Design Information, dated June 5,

1975.

Attached is a copy of a description of the BWR Mark II Containment "Supporting Program" presented in a meeting with members of the NRC staff on June 30, 1975.

The description has been expanded to ide t f th t t-in and a

g nalytscal portions of the program and indicates the purpose and niy e

es-schedule for completion of each portion.

Two items, Analysis of Alternate Load Mitigation Design and HSRL-18 Mitigating Fix Testing, have been deleted from the preliminary Supporting Program discussed at the June 30 1975 t'

items are deleted for the present since they would be undertaken strictly devices.

F on a contingency basis relative to the ramshead and quencher load m't' ull scale

) n-plant testing of the ramshead device has been added i iga sng to the program.

Generally, the Supporting Program is intended to confirm the Preliminary Forcing Function Report which is scheduled to be submitted to you in September 1975 as indicated in the reference letter to you.

The Supporting

Program, described in the attached outline, is a more detailed schedule for item 5 of the schedule attached to the above referenced letter.

As sndicated s n the meeting on June 30, 1975, the Preliminary Forcing Function Report will be submitted for your review in September 1975.

It is intended I

,Hr. Olan D. Parr Page 2

September 16, 1975 G02-75-261 that this report will be reviewed and approved by the NRC as an acceptable method for handling S/R valve and LOCA hydrodynamic loads for containment design.

Very truly yours, NOS:CLF:mcr Attachment 0.

STRAND Assistant Director, Generation and Technology cc:

J. J.

Byrnes, Burns and Roe Incorporated, Hempstead, New York Dorsey Roe, Bonneville Power Administration, Portland, Oregon H.

R. Canter, Burns and Roe Incorporated, Hempstead, Nevi York Fred A. MacLean, General Electric Company, San Jose, California

HARK I I PROGRAM ACTIVITY A.

LOCA RELATED l.

"4T" Pool Swell Test 2.

Pool Sv(ell Velocity Breakthrough Model HARK II SUPPORTING PROGRAM ACTIVITY TYPE Test Analysis TARGET SCHEDULE 1st.

Quarter 1976 2nd. Quarter 1976 3.

Impact Tests on Pool Internal Structures 4.

Qualify Impact Model

'B.

SAFETY/RELIEF VALVE RELATED 1.

Relief Valve Pipe Clearing Model for Quencher 2.

Relief Valve Pipe Clearing Model for Ramshead 3.

In-Plant Test of S/R Valve Discharge Loads During Con-secutive Actuations Ramshead 4.

Relief Valve Consecutive Actuation Transient Analysis Test Analysis Analysis Analysis 8 Test Test Test Analysis 3rd. Quarter 1975 4th. Quarter 1975 4th Quarter 1976 3rd. Quarter 1975 3rd. Quarter 1976 4th Quarter 1976

HARK II SUPPORTING PROGRAM A. 1 "4T" POOL SWELL TEST

~0b'ective Evaluate the pool swell phenomena for a typical Hark II containment geometry to determine pool swell velocities, water slug thickness, breakthrough ele-vations and wet-well pressures in a near full scale vertical vent suppression.

system using one vent at the General Electric Pressure Suppression Test Facility (PSTF).

The information will be used to predict the loading on wetwell structural members and the diaphragm floor between the wetwell and drywell.

Ae2 POOL SWELL VELOCITY BREAKTHROUGH MODEL

~0b'ective Develop an analytical model for predicting water slug velocity, pool swell breakthrough and froth characteristics.

Impact loads on structures above the pool are dependent on these parameters.

An analytical model is desired to bridge the gap between test results and actual containment geometry.

This activity complements the "4T" test program as its analytical counter-part.

A.3 IMPACT TESTS ON POOL INTERNAL STRUCTURES

~0b'ective

'onduct pool swell testing on various structural shapes of pool estimate impact loadings on internal structures.

This activity scale shapes in the Pressure Suppression Test Facility (PSTF).

circular pipes and I-beams of various sizes plus steel grating.

be used to preduct impact loads.

internal s to involves one third The shapes include Test results wi,ll A.4 UALIFY IMPACT MODEL

~0b 'ective Confirm applicability of PSTF data to Mark II geometry and structures.

Evaluate impact test data for design application and analytical model verification. If necessary modify current analytical models.

Confirm design adequacy of analytical methods with pool swell data.

Document analytical methods, assumptions, experi-mental verification of analytical

methods, and experimental basis for specified loads.

This activity provides analytical modeling of the impact. tests on pool internal structures and components.

MARK II SUPPORTING PROGRAM B.l RELIEF VALVE PIPE CLEARING MODEL FOR UENCHER

~0b'ective 4

Develop an analytical model of this phenomenon.to provide an improved technical basis for design and greater flexibilityon design details.

Compare this analytical model to current test data.

This model will not include prediction of internal pipe pressure effects since they are being developed in activity B.2.

8.2 RELIEF VALVE PIPE CLEARING MODEL FOR RAMSHEAD

~0b'ective Document the Safety/Relief Valve Pipe Clearing Analytical Model in a supplement to the guad Cities Topical Report (NEDO-'10859).

This activity includes docu-mentation of the Safety/Relief Valve Pipe Clearing Analytical Model for a

ramshead including assumptions, justif'ication of analytical

methods, and des-cription of the experimental basis for the analytical models.

This will also include the development of analytical models to predict internal pipe pressures applicable to both the ramshead and the quencher.

B.3 IN-PLANT TEST OF SAFETY RELIEF VALVE DISCHARGE LOADS DURING CONSECUTIVE ACTUATIONS

~0b ective Measure the effect of consecutive Saf'ety/Relief Valve discharges on suppression pool pressures and internal pipe pressure.

Test data will be used to verify pipe internal pressure and water level for consecutive Safety/Relief Valve actuations.

Measurements will be made of strains imposed on a pressure suppression containment torus during consecutive valve actuations with varying delay times ('i.e., time between valve closure and re-opening) in order to determine maximum strain and variation of strain with delay time.

Additional data will be obtained to aid in defining the phenomena causing load changes.

Internal pipe pressure data and pipe reaction forces will be obtained for verification of analytical model.

Pressure measurements at various locations in the pressure suppression pool will be taken.

This testing is being conducted by the Mark I Group, however, the Mark II group is participating in order to obtain additional test 'data on pipe internal pressures, pipe reaction forces and pressure attenuation in the suppression pool.

B.4 RELIEF VALVE CONSECUTIVE ACTUATION TRANSIENT ANALYSIS Objective Develop analytical methods for predicting Safety/Relief valve discharge pipe pressures for both ramshead and quencher devices and containment loads associated with consecutive Safety/Relief valve actuations.

This analytical model includes the effects of a vacuum breaker and reflooding due to rapid steam condensation.

Both internal pipe pressures and pressures in the suppressi'on pool will be predicted.

Current test data will be evaluated and analytical models will be verified.

If necessary analytical models will be modified.

Verified analytical HARK II SUPPORTING PROGRAH models for first and subsequent Safety/Relief valve actuations will be documented.

This activity provides the analytical modeling of the testing done in Item 8-3 in order to correlate its applicability to the Hark II Containment geometry.