ML20141K852: Difference between revisions

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| number = ML20141K852
| number = ML20141K852
| issue date = 09/22/1970
| issue date = 09/22/1970
| title = Forwards 700910 Ltr from Util Transmitting Change Request 3 to Plant TS
| title = Forwards from Util Transmitting Change Request 3 to Plant TS
| author name = Morris P
| author name = Morris P
| author affiliation = US ATOMIC ENERGY COMMISSION (AEC)
| author affiliation = US ATOMIC ENERGY COMMISSION (AEC)
Line 12: Line 12:
| case reference number = FOIA-91-282
| case reference number = FOIA-91-282
| document report number = NUDOCS 9203250303
| document report number = NUDOCS 9203250303
| title reference date = 09-10-1970
| package number = ML20091A092
| package number = ML20091A092
| document type = INTERNAL OR EXTERNAL MEMORANDUM, MEMORANDUMS-CORRESPONDENCE
| document type = INTERNAL OR EXTERNAL MEMORANDUM, MEMORANDUMS-CORRESPONDENCE

Latest revision as of 10:10, 12 December 2021

Forwards from Util Transmitting Change Request 3 to Plant TS
ML20141K852
Person / Time
Site: Oyster Creek
Issue date: 09/22/1970
From: Morris P
US ATOMIC ENERGY COMMISSION (AEC)
To: Hendrie J
Advisory Committee on Reactor Safeguards
Shared Package
ML20091A092 List: ... further results
References
FOIA-91-282 NUDOCS 9203250303
Download: ML20141K852 (1)


Text

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UNITED STATES

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ATOMIC ENERGY COMMISSION

.[ p WASHINGTON, D C, 20545 1

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Sept embe r 22, 1970 ,

Docket No. 50-219 ,, ., , ; f]B

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' j;,01015 Af EGUARDS Dr. Joseph M. Hendrie Chairman, Advisory Commit +ee on. Reactor Safeguards U. S. Atomic Energy Commission Washington, D. C. 20545 F

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Dear Dr..Hendrie:

Three (3) , copies of the following are transmitted for the information of the Committee:

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Letters from Jersey Central Power & Light Company -

i

. 1. dated September 10, 1970, transmitting Change Request No. 3 to the Oyster Creek Technical Specifications;

2. dated September 11, 1970, in response to the AEC letter of August 6,1970, concerning furnace sensitized stain-

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. less steel; and

3. dated September 14, 1970, transmitting a Su= nary Technical

' Report regarding Secondary Containment Leak Rate Testing at the Cyster Creek Station.

J.

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I Sincerely, poter A. Morris, Director Division of Reactor Licensing

Enclosures:

As stated ((3 })

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9203250303 910807 PDR FOIA DEKOK91-282 PDR

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