ML18025A578

Pennsylvania Power & Light'S 11/25/1975 Letter, Listing References to Previous Letters, to Summarize All Documents Submitted Adequacy of Mark II Containment for Hydrodynamic Loads

ML18025A578
Person / Time
Site:	Susquehanna
Issue date:	11/25/1975
From:	Curtis N Pennsylvania Power & Light Co
To:	Butler W Plant Licensing Branch 1
References
13450, 172, ER 100450, PLA-89
Download: ML18025A578 (6)

Text

NRC Dr RIBUTION FOR PART 50 DOCKE ATERIAL (TEMPORARY FORM)

. CONTROL NO: '13450 D FILE

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FROM PPSL DATE OF DOC DATE R EC'D LTR TWX RPT OTHER Allentown;. PA.

N.lf. Curtis 11-25-75 11-28-75 XXX

-- -TO ORIG CC OTHER SENTNRC PDR XXX XXX .

SENT LOCAL PDR CLASS UNCLASS PROPINFO INPUT NO CYS REC'D DOCKET NO:

XXX 1 50-387 8 DESCRIPTION: ENCLOSURES:

Letter re. their letter of 4-17 and 23-75.;

Letter providing additional info. on hhe adequacy of'he Nark II Containment for

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~ I ~~ a~P TWO NORTH NINTH STREET, ALLENTOWN, PA. 18101 PHONEs {215) 821-5151 November 25, 1975 Director of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, DC 20555

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ATTENTION: Dr Walter R Butler, Chief, ~~'--- I Light Water Reactor Branch 1-'2.

1 SUSQUEHANNA STEAM ELECTRIC STATION QO I/ 50-387 and MARK II CONTAINMENT '- DXNAMIC FORCING ~ IVg"i s CKET NOS.

50-388 FUNCTION INFORMATION REPORT ER 100450 FILE 172 PLA-89

Dear Dr. Butler:

In your April 17 and 23, 1975 letters to PPEcL, you requested that we, provide further information on the adequacy of the Mark II containment for Susquehanna SES (SSES) with respect to recently identified hydrodynamic loads. In the attachment to our June 5, 1975 letter, we provided. you with our program and schedule for conducting an assessment of the containment structures.

Item 1 of the attachment was submitted to you on August 7, 1975. Item 2 and a portion of Item 3 are covered by the Mark II Containment Dynamic Forcing Function Information Report (DFFR) NEDO-21061 and. NEDE-21061P. The'FFR vas transmitted. by GE letter from I.F. Stuart to R. Boyd dated October 24, 1975, and contains phenomena descriptions which vill be used'o.evaluate. the Mark II containment on SSES. This report was submitted later than expected due to additional technical efforts required to complete the DFFR and the inclusion of phenomenological information on Item 3. As a consequence, Item 4, the plant unique report, is now expected to be submitted by the end of January, 1976.

We expect to include the complete response to Item 3 in the plant unique report.

On June 30, 1975 the Mark II Containment Owners presented to the'RC an outline and schedule for the Mark Ii Supporting Program. This supporting program (Item" 5 of our June 5 letter) was submitted. to you on August 25, 1975. " tus of this program is as follows: I PENNSYLVANIA POWER 8 LIGHT COMPANY

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Dr. Walter R. Butler

. page 2 PI,A-89 AVOCA Related Activities Item A.3 (Impact Tests on Pool Internal Structures) and Item A.4 (Qualification of Impact Model) are covered by recently sub-mitted documents NEDE-13426-P Class III and NEDC-20989-2P (Vol. 2) respectively.

Safct /Relief Valve Related Activities Item B.2 (Relief Valve Pipe Clearing for Ramshead) is covered by:

for modeling, NEDO-20942 and NEDE-20942 P;

b. for test comparisons, NEDO-21062 and NEDE-21062 P.

The attached. table of load factors will be used to evaluate the SSES Containment as discussed with you at our August 21, 1975 meeting. This table identifies the numerical values and is complimentary to Table 5.2-1 in the DFPR.

The purpose of this letter is to reference these documents on the Susquehanna docket. Moreover, as a member of the Mark 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.

4uJCurtis W.

Vice President-Engineering 8 Construction WEB:AAW

~ W LOAD CO~'IBINATION FOR HARK II CONTAIN~tENTS CONSIDERING 'O'CDROD'CNANIC LOADS

" LOAD EQN. 'COND. ' Po To Ro Eo Ess PB TA SRV Normal w/o Temp 1.4 1 7 1.0 3..0 1.'5 2 Normal w/Temp 1.0 3..3 3..0 1 0 1.0 1 0

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NOIi<<al Ser. Env. 1.0 1.0 1.0 1.0 1.0 '.0 1.25 1.25 Abnormal 1.0 1.0 1.0 1 ~ 25 1' 0. l. 0 3..25 4a Abnormal 1.0 1.0 1.0 125 3.0 10

'5 Abnormal Sev.. Env. 3..0 1.0 1.0 1 0 1.0

'a Abnormal Sev. Env. 1.0 3..0 l,l 1.0 1.0 6 Normal Ext. Env. 1.0 1.0 1.0 1.0 1 Q 1.0 ,1.0 1.0 I

7 Abnormal Ext. Env. l. 0 1.0 l.0 leO 1;0 1.0 1.0 1.0 1.0 7a Abnormal Ext. Env. 1 0 1.0 1.0 liO 3. ~ 0 1.0 1 0 1.0 LOAD DESCRIPTION D Dead Loads Eo ~ Operating-Basis Earthquake I,ive Loads Ess Safe Shutdown Earthquake P. ~ prestressing Loads PB ~ SBA or IBA Pressure Load

.To ~ Operating Temperature Loads . PA ~ DBA (LOCA) Pressure Load

~ Operating Pipe Reactions TA ~ pipe Break Temperature Load .

Po ~ Operating Pressure Loads RA ~ pipe Break Temperature Reaction Loads SRV ~ Safety/Relief Valve Loads ~ Reaction and jet forces associated with tho pipe bz'eak r ~ w ~ <<%>> ~ r ~ 0 r ~