ML20067A292
| ML20067A292 | |
| Person / Time | |
|---|---|
| Site: | Shoreham File:Long Island Lighting Company icon.png |
| Issue date: | 11/25/1975 |
| From: | Wofford A LONG ISLAND LIGHTING CO. |
| To: | Stolz J Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20067A201 | List: |
| References | |
| FOIA-82-455 SNRC-70, NUDOCS 8212010401 | |
| Download: ML20067A292 (3) | |
Text
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3 November 25,197y 8
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Mr.
J.
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Stolz, Chief.
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Light Water Reactors Branch 2-1
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f.g Division of Reactor Licensing 4,
O U.
S. Nuclear Regulatory Commission Washington, D.C.
20555' sbiud y
BWR Mark II Containment Shorehan Nuclear Power Station - Unit 1 Docket #50-322
Dear Mr. Stolz:
In your April 18 and 21,1975 -letters to us, you requested that we provide further information on the adequacy
- of the Mark II containment for the Shoreham Nuclear Power Station with respect to recently identified hydrodynamic loads.
In Attachment "A" of our June,3, 1975 letter, we provided to you our schedule consisting of five itens for conducting an assessment of our containment structures.
Item 1, Suppression Pool and Relief Valve Piping Drawings, was submitted to you by letter dated July 30, 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 DFFR was trans-mitted by General Electric letter from I.
F.
Stuart to R. Boyd dated October 24, 1975.
It was submitted later than expected due to additional technical efforts required for a more complete report and the inclusion of phenomenalogical infor-mation on pool temperature monitoring.
Item 4, our plant unique containment assessment report, is now expected to be submitted in January 1976 as a result of the above delay.
We also expect to complete and include the description of the suppression pool temperatu'e r
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monitoring system in that report.
I 0212010401 821109 PDR FOIA HAFNER82-455 PDR
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L'ONG IOL. ND LIGHTING COM' NY
,e November 25, 1975 Mr.
J.
F.
Stolz Page 2 Item 5, an outline and schedule for the Mark II -
Supporting Program, was presented to NRC on June 30, 1975, by the Mark II Owners and confirmed by our August 25, 1975 letter to you.
The status of this Program is as follows.
For the LOCA Related Activities, Item A.-3 (Impact Tests on Pool Internal Structures) and Item A.4 (Qualification of Impact Model), General Electric has submitted reports NEDE-13426-P and NEDC-20989-2P (Vol. II) respectively.
'For the Safoty Relief Valve Related Activity, Item B.2 (Relief Valve Pipe Clearing Model for Ramshead) General Electric has submitted reports NEDO-20942 and NEDE-20942P 'concerning modeling and NEDO-21062 and NEDE-21062P concerning test comparisons.
The attached table of load factors will be used to
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evaluate the Shoreham Nuclear Power Station Containment as discussed with you at our August 21, 1975 meeting.
This c
table identifies the numerical values and is complimentary to Table 5.2-1 in the DFFR.
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In conclusion, this letter will serve to 'eference r
the above described documents on the Shoreham docket.
More-over, as a member of the Mark II Owners Group, we will be closely following the activities of the Supporting Program and keep you advised of progress.'" Any reports, data or analyses which become available during the Program, will be forwarded to the NRC through appropriate channels.
Very truly yours d
A. W. Wofford Vice President Attachment l
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,.!<q ATTACHMENT SNRC*70 e,
J LOAD CO*tBINATION FOR MARK II CONTAIN!!ENTS CONSIDERINO ll?DRCDYNA'1IC LOADS
- LO7D EON.
COND.
D L'
.F.
Po To R
E E
P o
o ss B
PA TA
_A R
1 Normal
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w/o Temp 1.4 1.7 1.0 1.0 2
Normal w/ Temp 1.0 1.3 1.0 1.0 1.0 1.0 4
3 Normal Ser. Env.
1.0 1.0 1.0 1.0 1.0 1.0 1.25 4
Abnormal.
1.0 1.0 1.0 1.25 1.D.
1.0 4a Abnormal 1.0 1.0 1.0
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1.25 1.0 1.0 5
Abnorma1 Sev. Env.
1.0 1.0 1.0 1.0 l'. 0 1.1 1.1 Sa Abnormal Sev. Env.
1.0 1.0 1.0-
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1.1 1.1 1.'O 1.0
+
6 Normal Ext. Env.
1.0 1.0 1.0 1.0 1.Q 1.0 1.0 7
Abnormal Ext. Env.
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
)
LOAD DESCRIPTION D = Dead Loads E
= Operating-Basis Earthcuake o
L = Live Loads Ess = Safe Shutdown Earthquake F = Prestressing Loads P
= SBA or IEA Pressure Load D
To = Operating Temperature Loads PA = LDA (LOOJ.) Fressure Load Ro = Operatin:; Pipe Beactions TA = Pipo Ercak Temperature Load,
Po = Operating Pressure Loads R
= Pipe Brcok Temperature React 6 A
SRV = Saf ety/Rolief Valve Loads R
= Reaction and jet forces assoe r
with the pipe b.cak P
l 6
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