ML18191A278

Wppss Nuclear Project No. 2. Mark II Containment Program. Load Combination for Mark II Containments Concrete Structures Hydrodynamic Loads

ML18191A278
Person / Time
Site:	Columbia
Issue date:	11/10/1975
From:	Strand N Washington Public Power Supply System
To:	Parr O Office of Nuclear Reactor Regulation
References
G02-75-310
Download: ML18191A278 (9)

Text

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NRC DISTRIBUTION FOR PART 50 DOCKET MATERIAL (TEMPO RA R Y FO R M)

CONTROL NO: 13223

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FROM. Washington Public Power.'- DATE OF DOC DATE REC'D LTR TWX RPT OTHER TO:

N.O. Strand'1-10-75 Supply System 'Richland, Wash ORIG CC 11-20-75 OTHER SENTNRC PDR XXXX

, Hr.;hlan D. Parr.. 1-signed ~ SENT LOCAL PDR CLASS UNC LASS PROP INFO INPUT NO CYS REC'D DOCKET NO'0-397 DESCRIPTION: ENCLOSURES'oad

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,r cQ P. 0. BOX 966 0 C o 0 N WAY RICHLAND, WASHINGTON II9352 PHONE (509) 946 9681 Docket No. 50-397 00CXBED November 10, 1975 QSNR G02-75-310 NOV Pot 1 "7 a LY U. S. l4IICT\AR IITCVIATO COMMISSlOH Moil Sooiloo

'0 ly(g gg Director of Nuclear Reacth~e~.a ion Light Water Reactors Project Branch 1-3 NOV80197g e U.S. Nuclear Regulatory Commission y4jI'C BKRSy IOII Washington, D.C. 20555 aaII 'S:<<i:>

Attention: Mr. Olan D. Parr Gp

Subject:

WPPSS NUCLEAR PROJECT NO. 2 MARK II CONTAINMENT. PROGRAM

References:

1) Letter, W.R. Butler to J.J. Stein, Supression Pool Hydrodynamic Loads During LOCA, April 17, 1975.

2) Letter, W.R. Butler to J.J. Stein, Pool Dynamic Loads Due to Relief Valve Operation, April 23, 1975.

3) Letter, J.J. Stein to W.R. Butler, BWR Mark II Containment-Additional Design Information, June 5, 1975.

(G02-75-163)

4) Letter N.O. Strand to O.D. Parr, Mark II Containment Information-Current Design Drawings, July 25, 1975.

(G02-75-210)

5) Letter, N.O. Strand to O.D. Parr, Mark II Containment-Suppor ting Progyam, September 16, 1975. (G02-75-261)

Dear Mr. Parr:

I In your April 17 and 2', 1975 letters (Refeyences 1 and 2) to us, you re-quested that we provide further information on the adequacy of the Mark II Containment on our WPPSS Nuclear Project No. 2 with respect to recently identified hydrodynamic loads. The purpose of this letter is to:

o Provide information relative to the status of the Mark II Supporting Program.

m Mr. Olan D. Parr Page 2 November 10, 1975 G02-75-310 o Reference recent generic documents containing information felt applic-able in determining Mark II containment dynamic loads on the WPPSS Nuclear Project No. 2 docket..

o Provide table of load factors for concrete structures.

lt In Attachment "A" of our June 5, 1975 letter (Reference 3), we provided to you our schedule for conducting an assessment of our containment struc-tures. Item 1 of Attachment "A" was submitted to you on July 25, 1975.

Item 2 and a portion of Item 3 of Attachment "A" are covered by the Mark II Containment Dynamic Forcing Function Information Report (DFFR) NEDO-21061 and NEDE-21061P. The DFFR was transmitted via GE letter from I.F. Stuart to R. Boyd dated October 24, 1975, and contains phenomena descriptions which will be used to evaluate the Mark II containment for the WPPSS Nuclear Project, No. 2. Item 2 was submitted later than expected due to additional technical efforts required to complete the DFFR and the inclu-sion of phenomenological information on Item 3. As a consequence, Item 4, our plant unique report, is now expected to be submitted in the December 1975 to January 1976 time period. We also expect to complete and include the remaining answers to Item 3 in that plant unique report.

On June 30, 1975 the Mark II Containment Owners presented to the NRC an out-line and schedule for the Mark II Supporting Program. This Supporting Pro-gram, Item 5, was submitted to you on September 16, 1975 (Reference 5).

The status of this Program is. as follows. Under LOCA Related Activities, Item A.3 (Impact Tests on Pool Internal Structures) and Item A.4 (gualifi-cation of Impact Model) are covered by recently submitted documents NEDE-13426-P Class III, and NEDC-20989-2P (Vol. 2) respectively. The following documents have been submitted to address Item 8.2 (Relief Valve Pipe Clear-ing for Ramshead) under the Safety/Relief Valve Related Activities:

1) For modeling - NEDO-20942 and NEDE-20942P.

2) For test comparisons - NEDO-21062 and NEDE-21062P.

The attached table of load factors will be used to evaluate the WPPSS Nuclear Project No. '2 concrete structures inside containment. This table identifies the numerical values and is complementary to Table 5.2.1 in the DFFR. As you know, our WPPSS Nuclear Project No. '2 containment is a free-standing steel structure'overned by Division 1 (NE-3000) of Section III of the ASME Code.

ez Mr. Olan D. Parr Page 3 November 10, 1975 G02-75-310's a member of the Mar k II Owners Group, we will be closely following the progress of the Supporting Program and keep you advised of its progress.

Any reports, data or analyses which become available during'the Supporting Program, will be forwarded to the NRC through appropriate channels.

Very truly yours, N.~ 0. STRA

~ D Assistant Dir ector, Generation and Technology NOS:GLG:kw Attachment cc: JJ Byrnes - Burns 8 Roe, Inc.

FA MacLean - General Electric D Roe - Bonneville Power Administration JJ Verderber - Burns 8 Roe, Inc.

LOAD CONBIHATION FOR tOR I I COHTAIHMENTS CONCRETE STRUCTURES HYDRODYNAMIC LOADS LOAD

~EN. COND ~ D L F P T R E 'B TA R SRV Ess PA RA Normal w/o Temp 1.4 1.7 1.0 1.0 1.5 Normal w/Temp 1.0 1.3 1.0 1.0 1.0 1.0 - - - - - - - '.3 Normal Ser. Env. 1.0 1.0 1.0 1.0 1.0 1.0 '1.25 1.25 Abnormal 1.0 1.0 1.0 1.25 - 1.0 1.0 - 1.25 4a Abnormal 1.0 1.0 1.0 1.25 1.0 1.0 Abnormal Sev. Env. 1.0 1.0 1.0 1.1 - 1.1 - 1.0 1.0 - 1.1 5a Abnormal Sev. Env. 1.0 1.0 1.0 1.1 1.0 1.0 Normal Ext. Env. 1.0 1.0 1.0 1.0 1.0 1.0 1.0 1.0

.Abnormal Ext. Env. 1.0 1.0 1.0 1.0 1.0 - 1.0 1.0 1.0 1.0 7a Abnormal Ext; Env. 1.0 1.0 1.0 1.0 - 1.0 1.0 1.0 1.0 LOAD DESCRIPTIOH 0 ~ Dead Loads E Operating-Basis Earthquake

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L Live Loads Safe Shutdown Earthquake ss, F Prestressing Loads B

SBA or IBA Pressure Load T Operating Temperature Loads 'A DBA (LOCA) Pressure Load R Operating Pipe Reactions TA Pipe Break Temperature Load P a Operating Pressure Loads RA Pipe Break Temperature Reaction Loads SRV Safety/Relief Valve Loads Rr Reaction and jet forces associated with the pipe break

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