ML18025A288
| ML18025A288 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 11/25/1975 |
| From: | Curtis N Pennsylvania Power & Light Co |
| To: | Butler W Office of Nuclear Reactor Regulation |
| References | |
| Download: ML18025A288 (8) | |
Text
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CONTROL NO:
13450 FILE:
NRC Dl IBUTION FOR PART 50 DOCKET
~ "FROM:
PPSL Allentown;. PA.
N.W. Curtis 11-25-75 11-28-75 DATE OF DOC DATE REC'D LTR XXX TWX RPT OTHER
-TO'RIG CC OTHER 0
SENTNRC PDR SENT LOCALPDR XXX XXX CLASS UNCLASS PROP INFO INPUT XXX DESCR IPTION:
Letter re. their letter-of 4-17 and 23-75.:
Letter providing additional info. on bhe adequacy of the Mark II Containment for,,
Sasq'uehanna Steam Elec..St'ation.'..
W/Ai:tach status program..;
(1 Copy Received)
PLANT NAME:
Sqsquehanna 8
1 8I 2-NO CYS REC'D 1
ENCLOSURES:
DOCKET NO:
5 -38 388
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18101 PHONEME t215) 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 Light Water Reactor Branch 1-<,
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- IISIIRC, SUSQUEHANNA STEAM ELECTRIC STATION MARK II CONTAINMENT DYNAMIC FORCING FUNCTION INFORMATION REPORT ER 100450 FILE 172 PLA-89 7
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Dear Dr. Butler:
In your April 17 and 23, 1975 letters to PPM, 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'ttachment 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 was transmitted by GE letter from I.F. Stuart to R. Boyd dated'ctober,'.
24,. 1975, and contains phenomena descriptions which will be used'o.evaluate. the'ark II containment on SSES.
This report was submitted later. than expected'ue to.
additional technical efforts required to complete the'FFR and, the'nclusion of phenomenologica1 information on Item 3.'s a consequence','tem',,the'lant 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'lant unique report.
On June 30, 1975 the Mark II Containment Owners presented,to.the'RCan 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:
P E N N 5 Y 1 VA N I A P OWE R 8
L I G H T COMP ANY
Dr. Walter R. Butler Page 2
PLA-89 1.
LOCA 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.
2.
Safet /Relief Valve Related Activities Item B.2 (Relief Valve Pipe Clearing for Ramshead) is covered by:
/
a.
for modeling, NEDO-20942 and NEDE-20942 P; b.
for test comparisons, NEDO-21062 snd 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 DFFR.
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 y.ours, 4uJ N.
W. Curtis Vice President-Engineering 0 Construction WEB:AAW
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LOAD CO'NBINATION FOR PaXRK II CONTAIN~1ENTS CONSIDERING HYDRODYNi&IIC LOADS EON
" LOAD
'COND.
Normal w/o Temp F
Po 1.4 1.7 1.0 1.0 To Ro Eo Ess PB PA TA RA Rr SRV l.'5 2
Normal w/Temp 1.0 1.3 1.0 1.0 1.0 1 ~ 0 Normal Ser.
Env.
1.0 1.0 1.0 1.0 '.0 1.0 1.25 1.25 Abnormal 1.0 1.0 1.0 4a Abnormal 1.0 1.0 1-.0 1 ~ 25 1'.0.
1.0 1.25 1.25 1.0 1.0 Abnormal Sev.
Env.
1.0 1.0 1.0 lol
- '.0 1.0 l.l
'Sa Abnormal
-Sev.
Env.
1.0 1.0 1.
l,l 1.0 1 ~ 0 7
Normal Ext. Env.
Abnormal Ext,. Env.
1.0 1.0 1.0 1.0 1.0 II 1.0 1.0 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'
1 ~ 0 1 0 1 ~ 0 1 0 LOAD DESCRIPTION D,
~ Dead Loads L ~ Live Loads P.
~ Prestressing Loads
.To ~ Operating Temperature Loads Ro ~ Operating Pipe Reactions Po ~ Operating Pressure Loads SRV ~ Safety/Relief Valve Loads
~ Operating-Basis Earthquake Ess
. PA
~ Pipe Break Temperature Load RA
~ pipe Break Temperature Reaction Loads
~ Reaction and jet forces associated with the pipe break
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