ML19317G999
| ML19317G999 | |
| Person / Time | |
|---|---|
| Site: | Rancho Seco |
| Issue date: | 08/18/1978 |
| From: | Mattimoe J SACRAMENTO MUNICIPAL UTILITY DISTRICT |
| To: | Reid R Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8004020657 | |
| Download: ML19317G999 (2) | |
Text
- - -.
- Y*
p f f,
Of REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
DISTRIBUTION FOR INCOMING MATERIAL 50-312 REC: REID R W ORG: MATTIMOE J J DOCDATE: 08/18/78 NRC SACRAMENTO MUN UTIL DIST DATE RCVD: 08/22/78 DOCTYPE: LETTER NOTARIZED: NO COPIES RECEIVED
SUBJECT:
LTR 3 ENCL 0 RESPONSE TO NRC LTR DTD OS/14/70... FURNISHING INFO CONCERNING MEASURES APPLICANT IS TAKING TO INSURE REACTOR VEGSEL INTEGRITY IN RESPONSE TO RECENT INFO FROM D&W CONCERNING POSSIBLITY OF ATYPICAL WELD MATERIAL IN UNIT 1 REACTOR VESSEL.
PLANT NAME: RANCHO SECO (SMUD)
REVIEWER INITIAL:
XJM DISTRIBUTOR INITI AL: Ok ocoono*********** DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS ******************
REACTOR VESSEL MATERIAL SURVEILLANCE (DISTRIDUTION CODE A021)
FOR ACTION:
DR ORS #4 BC**LTR ONLY(3)
ZWETZIG**LTR ONLY(1)
INTERNAL:
REG F
- LTR ONLY(1)
NRC PDR**LTR ONLY(1)
En*LTR ONLY(2)
OELD*nLTR ONLY(1)
MIPC**LTR ONLY(1)
HANAUER**LTR ONLY(1)
MATERIAL ENG BR**LTR ONLY(1)
AD FOR SYS & PROJ**LTR ONLY(1)
ENGINEERING BR**LTR ONLY(1)
REACTOR SAFETY BR**LTR ONLY(1)
PLANT SYSTEMS BR**LTR ONLY(1)
EEB**LTR ONLY(1)
HAZELTON**LTR ONLY(1)
HOGE**LTR ONLY(1)
R GAMBLE **LTR ONLY(1)
RANDALL**LTR ONLY(1)
EXTERNAL:
LPDR'S SACRAMENTO, CA**LTR ONLY(1)
REGION V**LTR ONLY(1)
TERA **LTR ONLY(1)
NSIC**LTR ONLY(1)
ACRS CAT D**LTR ONLY(16) i
! DISTRIBUTION:
LTR 41 ENCL 0 CONTROL NBR: '7020'^1mi -
t SIZE: 1P M
' ococco*****************************
THE END l
8004020 CT9 f
,m
~. v. a. :x1 m
n n.~...
2.
~. :..
$SMUD
~
SACRAMENTO MUNICIFAL UTILITY DISTRICT O 6201 S street. Box 15830, Sacramento, Ca'ifornia 95813; (916) 452-3211 August 18, 1978 Director of Nuclear Reactor Regulations Attention:
Mr. Robert W. Reid, Chief Operating Reactors, Branch 4 U. S. Nuclear Regulatory Commission Washington, D. C.
20555 Docket No. 50-312 Reactor Vessel Weld Material Rancho Seco Nuclear Generating Station, Unit No.1
Dear Mr. Reid:
Your letter of August 14, 1978 requested information about measures we are taking to insure reactor vessel integrity in response to recent information from Babcock & Wilcox concerning the possibility of atypical weld material in the Rancho Seco Unit i reactor vessel.
On August 11, 1978 the District proposed revisions to the Rancho Seco Unit No.1 Technical Specifications, including revised pressure / temper-l ature limits for heatup and cooldown of the reactor vessel.
1 These revised limits were based on a technical evaluation performed by Babcock & Wilcox assuming the atypical material was used in the construction of the Rancho Seco Unit 1 reactor vessel.
This fracture mechanics evaluation demonstrates that the structural integrity of the reactor vessel has not been compromised by the possible presence of this atypical material and that future operation of the plant can be conducted in accordance with the requirements of Appendix G to 10 CFR 50.
Our proposed revisions to the Rancho Seco Unit No.1 Technical Specifications were approved and issued as Amendment No. 22 to Facility Operating License No. DPR-54 on August 16, 1978.
Siiserely yours,
- d. NtaIM
,/d. J. Mattimoe Assistant General Manager and Chief Engineer i
--y.C r_:.__
_7 Y
AN ELECiRfC SYSTEM SERvlNG MORE THAN 600.000 IN IHE HFARI 0F CALfroaN1A