ML19312B774
| ML19312B774 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 01/19/1978 |
| From: | Parker W DUKE POWER CO. |
| To: | Case E, Schwencer A Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7911190565 | |
| Download: ML19312B774 (2) | |
Text
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REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
DISTRIBUTION FOR INCOMING MATERIAL so-260 270/287 REC: CASE E G ORG: PARKER W O DOCDATE: 01/19/78 NRC DUKE PWR DATE RCVD: 01/26/78 DOCTYPE: LETTER NOTARIZED: NO COPIES RECEIVED
SUBJECT:
LTR 1 ENCL O ADVISING THAT INFO CONCERNING REASSESSMENT OF FRACTURE TOUGHNESS & POTENTIAL FOR LAMELLAR TEARING OF STEAM GENERATOR & REACTOR COOLANT PUMP SUPPORT MATERIALS IN RESPONSE TO NRC LTR DTD 10/4/77 WILL BE SUBMITTED BY FEB.
1978.
PLANT NAME: OCONEE - UNIT 1 REVIEWER INITI AL:
XEI OCONEE - UNIT 2 DISTRIBUTER INITI AL:
OCONEE - UNIT 3
- DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS ******************
NOTES:
1.
M.
CUNNINGHAM - ALL AMENDMENTS TO FSAR AND CHANGES TO TECH SPECS FRACTURE TOUGHNESS & POTENTIAL FOR LAMELLAR TEARING.
(DISTRIBUTION CODE A018)
FOR ACTION:
BPr _
m.
CER**LTR ONL INTERNAL:
REG FILE **LTn ONf .,
NRC PDR**LTR ONLY(1)
T '. "'
uNLY(2)
OELD**LTR ONLY(1)
-o HANAUER**LTR ONLY(1)
EISENHUT**LTR ONLY(1)
SHAO**LTR ONLY(1)
BAER**LTR ONLY(1)
BUTLER **LTR ONLY(1)
GRIMES **LTR ONLY(1)
J.
COLLINS **LTR ONLY(1)
R.
SNAIDER**LTR ONLY(1)
H.
LEVIN **LTR ONLY(1)
EXTERNAL:
LPDR'S WALHALLA. SC**LTR ONLY(1)
TIC **LTR ONLY(1)
NSIC**LTR ONLY(1)
ACRS CAT B**LTR ONLY(16)
DISTRIBUTION:
LTR 40 ENCL 0 CONTROL NBR:
780270014 SIZE: 1P o**o*o***********+*****************
THE END
- C A
7911190 Fgf h
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J' DUKE POWER COYP
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r Powza Bun 402 Sourn Caracu SrazzT, Gnuat.orTz, N. C. 2e242 wi u ia
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January 19, 1978 SCE Pett DENT
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N Mr. Edson G. Case', Acting Director Office of Nuclear Reactor Regulation
..( 7 U. S. Nuclear Regulatory Commission di4 Washington, D. C.
20555 T.
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4Y Attention:
Mr. A. Schwencer, Chief
,'*4g Operating Reactors Branch #1
Reference:
Oconee Nuclear Station Docket Nos. 50-269, -270, -287
'gV
Dear Sir:
Your letter of October 4, 1977 requested information necessary for a reassessment of the fracture toughness and potential for lacellar tearing of the steam generator and reactor coolant pump support materials. Preparation of this information is in progress and the submittal will be during February, 1978 along with an evaluation of the potential for lamellar tearing.
Very truly yours, w__ (-
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William O. Parker, Jr.
RLG:ge 780270014 ho \\b i/0