ML18025A292

Letter Attaching the Outline of the BWR Mark II Containment Supporting Program

ML18025A292
Person / Time
Site:	Susquehanna
Issue date:	08/25/1975
From:	Curtis N Pennsylvania Power & Light Co
To:	Butler W Office of Nuclear Reactor Regulation
References
Download: ML18025A292 (12)

Text

0 ...

NRC DISTRIBUTION FOR PART 50 DOCKET MATERIAL

~

s (TEMPORARY FORM)

CONTROL No: 9169 FILE'ROM:

Penn. Power & Light Co. DATE OF DOC DATE REC'D LTR TWX RPT OTHER Allentown, Pa. =18101 8-25-75 8-28-75 To: ORIG CC OTHER SENTNRC PDR XX Dr. Walter R. Butler 1 si ned SENT LOCAL PDR CLASS UNCLASS PROPINFO INPUT NO CYS REC'D DOCKET No:

1 38 DESCRIPTION: Ltr furnshing addi info re Mar ENCLOSURES: Mark II Supporting II contaiments & trans the following: for the Susquehanna Plant Units Program 1 & 2....

(1 cy enc1 rec'd)

Yio gojglriog g{B]KBIjE%

PLANT NAME.- Suseqhehanna Plant Units 1 & 2 FOR ACTION/INFORMATION UT ER (L) SCHWENCER (L) ZIEMANN (L) REGAN (E) nErO(L)

W opies W/ Copies W/ Copies W/ Copies W/ COPIES CLA K (L) STOI Z (L) DICKER (E) LEAR (L)

W/ Copies W/ Copies W/ Copies W/ Copies PARR (L) VASSALLO (L) KN I G H TON (E) SPIES W/ Copies W/ Copies W/ Copies W/ Copies KNIEL (L) PURPLE (L) YOUNGBLOOD (E) LPM W/ Copies W/ Copies W/ Copies W/ opuses INTERNAL DISTRIBUTION EG FILE 2 TECH REVIEW DENTON LIC ASST A/T IND .

SCHROEDER G R IMES R. DIGGS (L) BRAITMAN GC, ROOM P-506A MACCARY QAMMILL H. GEARIN (L) SA LTZMAN OSSI CK/STAF F KNIGHT KASTNER E. GOU LBOU R NE { L) MELTZ ASE PAWLICKI BALLARD P. KREUTZER (E)

IAMBUSSO HAO SPANGLER . LEE {L) PLANS BOYD TEI LO .RUSHBROOK{L) MCDONALD OGRE {L) ENVI Ro S. REED (E) CHAPMAN.

EYOUNG (L) NOVA MULLER M. SERVICE (L) ~~~(Ltr)g N~Ae$ ,

SKOVHOLT {L) cross DICKER S. SHEPPARD (L) aC. COU~E GOLLER (L) (Ltr) IPPOI ITO KNIGHTON M. SLATER (E)

PETERSON P. COLLINS ytEDESCO YOUNGBLOOD H. SMITH (L) HARTFIELD (2)

DENISE S,COLLINS EGAN S. TEETS (L) KLECKER EG OPR LAINAS OJECT LDR G. WILLIAMS(E) EISENHUT I LE 5 R EG I ON (2) BENAROYA V. WILSON (L) WIGGINTON MIPC VOLLMER HAR LESS R. INGRAM (L)

M. DUNCAN VAtebA EXTERNAL DISTRIBUTION LOCAL PDR Wilkes Barre, Pa.

ll TIC (ABERNATHY) {1){2){'IO)NATIONAL LABS 1 PD R-SAN/LA/NY tg- NSIC (BUCHANAN) 1 W. PENNINGTON, Rm E-201 GT 1 BROOKHAVEN NAT LAB G. ULRIKSON ORNL

'I AS LB 1 CONSULTANTS 1 Newton Anderson gI CRS tettes1Neettt/SENT NEWMARK/B LUME/AGBA8 I AN

a

~ ~ ~ ~

O,Regulatory Docket File TWO NORTH NINTH STREET, ALLENTOWN, PA. 18101 PHONEs (215) 821-5151 s j(I~1 I l- >

j'ILiI.i)LP '~

OO AUGERS>yg ~

p<rr 9 U" II's-~'> "'IElreT August 25, 1975 ,4~'bPfy Lull Sccllc2 Dr. Walter R. Butler, Chief OL g Dockets No's Light Water Reactors Branch 1-2 Division of Reactor Licensing U.S. Nuclear Regulatory Commission Washington, DC 20555 SUSQUEliANNA SES SUPPORTING PROGRAM FOR MARK II CONTAINMENTS ER 100450 FILE 840-2 PLA-So

Dear Dr. Butler:

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

The outline has been expanded. to identify the testing and. analytical portions of the program and indicates %he purpose and, scheclule for completion of each portion. Full scale in-plant testing of a ramshead. device has been added to the program. Analysis of Alternate Load Mitigating Design and. "SRL-1" Mitigating Fix Testing have been deleted. because no additional load mitigating devices have been identified as necessary. The attached outline is a more detailed schedule for item 5 of the Mark II Containment Program attached to our letter dated, June 5, 1975.

The Supporting Program is intended to Cnnfirm the Preliminary Forcing Function Report (PFFR) which is scheduled. to be submitted to you in September, 1975. It is intended. that the PFFR will be reviewed and. approved by the NRC as an acceptable method, for hand1ing S/R valve and LOCA hydrodynamic loads for containment design.

Very truly yours, P kf i~~

N. W. Curtis Vice President-Engineering 5 Construction WEB:DEB PENNSYLVANIA POWER e L IGHT COMPANY

~ rh ~ ~

lr r I 4 = 0 Ik 1

..h ~ ~

1 "'I I

rl I

I, I I kk 1

I I - ~

~ hr 1 I

~ 'I 1 I k k ~ h ) \I lkkll Ill hkkh hl" I

1

~- )

I hl tll I I'LD ,.

1 k hk .'.'. l) ~ ~

= ~ <r ~ \ -

'I I I '

k, h ~ 14 lr - 1 r I II

~, k 1 I 1 k

'gegiletory Docket Pile MARK II SUPPORTING PROGRAM 8

~)g(J lvjL",r P"tc8 ACTIVITY TARGET MARK II PROGRAM ACTIVITY TYPE SCHEDULE A. LOCA RELATED

l. 4T Pool Swell Test Test 1st. Quarter 1976

2. Pool Swell Verlocity Break-through Model Analysis 2nd. Quarter 1976

3. Impact Tests on Pool Inter-nal Structures Test 3rd.. Quarter 1975

4. Qualify Impact Model Analysis 4th. Quarter 1975 B. SAFETY/RELIEF VALVE RELATED Relief Valve Pipe Clearing Model for Quencher Analysis 4th-,, Quarter 1976 II

2. Relief Valve Pipe Clearing Analysis Mod.el for Ramshead and Test 3rd,. Quarter 1975

3. In-Plant Test of S/R Valve Dis-charge Loads During Consecutive Actuations for Ramshead Test 3rd.. Quarter 1976

4. Relief Valve Consecutuve Actuation Transient Analysis Analysis 4th. Quarter 1976

<<r I ~

~ ii $ J<<<<<< I N

~ >>r>>>>.I

~ I II r~ ~

v r>>

>>r

>>t r'- ~ ,I'<<I'I ~ . >> I I << ~, <> rg~ I I r<<qr ~ ~,

<<~,~<<I ~ 'll, -pA

~ . If

~

I r p ~

'<< I<<t I<

~

Ael "4T" POOL SWELL TEST

~Gb ective Eva1uate the pool swell phenomena for a typical Mark II containment geometry to determine pool swell velocities, water slug thickness, breakthrough elevations and. wetwell pressures in anear 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

,I

~01 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.

Ae3 IMPACT TESTS ON POOL INTERNAL STRUCTURES

~Ob ective Conduct pool swell testing on various structural shapes of pool internals to estimate impact" loadings on internal structures. This activity involves one third scale shapes in the Pressure Suppression Test Facility (PSTF).

The shapes include circular pipes and. I-beams of various sizes plus steel grating. Test results will be used to predict impact loads.

A.4 UALIFY IMPACT MODEL

~01 ective v

Confirm applicability of PSTF data to Mark II geometry and structures.

Evaluate impact test data for design application and. analyticalmodel verification. If necessary modify current analytical models. Confirm design adequacy of analytical methods with pool swell data. Document analytical methods, assumptions, experimental verification of analytical methods, and. experimenta1 basis for specified. loads. This activity provides analytical modeling of the impact tests on pool internal structures and components.

t~

<<I ~

~ 'U elf I te L) I

~ <<I ',

~ e l II <<1, '<< I, 0'

I II *, i Q) ~

I t<<~'I" I ~

A I

g<<J I I,<< I I I

~

e tt <<1,e,=<<tt I

i tl

• eg,<< ~, JI ll 1

~ I 1

I 1<< ~ I II r I

~ lll ~ <<4)

B.l RELIEF VALVE PIPE CLEARING MODEL FOR QUENCHER

~Ob ective Develop an analytical model of this phenomenon to provide an improved technical basis for design and greater flexibility on 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.

B.2 RELIEF VALVE PIPE CLEARING MODEL FOR RAMSHEAD 0~beet ive Document the Safety/Relief Valve Pipe Clearing analytical model in a supplement to the Quad Cities Topical Report (NEDO-10859). This activity includes documentation of the Safety/Relief Valve Pipe Clearing Analytical Model for a ramshead including assumptions, Justification of analytical methods, and description of the experimental basis for the analytical models.

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

Be3 IN-PLANT TEST OF SAFETY/RELIEF VALVE DISCHARGE LOADS DURING CONSECUTIVE ACTUATIONS

~Ob ective Measure the effect of consecutive SRV discharges on suppression pool pressures and. internal pipe pressure. Test data will be used to verify pipe internal pressure and water level for consecutive SRV 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 reopening) 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 re-action 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 poole B.4 RELIEF VALVE CONSECUTIVE ACTUATION TRANSIENT ANALYSIS

~Ob ective

ha I' ~,

a h,Pa

t. Ja a

a

~ rl a aa w Ii P T h

,I

'I aa a *t ir I 'l ~ ~

r, P Ph ~ ir f P

' I" 1

~ -

a

'll:

~ a ~

f" ~ I ~

II I 'I h ~

a.t ga

-a i ~

a a

a,l ag la a ra I a

~ ap a Pg I ~ 'I

~ ~

~P a I, I a ah

~, ~ )la Ia a. a)J

~ 'I I I rP P

~ ~

'() lit ha t 'I

Develop analytical methods for predicting S/R valve discharge pipe pressures for both ramshead and. quencher devices and containment loads associated. with consecutive S/R 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 suppression 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 models for first and sub-sequent SRV actuations will be documented. This activity provides the analytical modeling of the testing done in Item B.3 in order to correlate II its applicability to the Mark Containment geometry.

4(

H ~

~ ' l>>S~," >V~ I>> '>> >>>i C'>>>>4 ', " ~ IP>>" ",l'>>' I>> I fp $ )>>I>>

I ~

',I Hr.

I 1' 4

~ ~, . 0'gg>> >,>>a'-

0 ":

( ~-

'" ~

i>>,

e I

~ ~

I

>0 BQ .>. >>

C

~ 2", "

f .

">> .'I i " ",ge',

,~A

>> ~