Letter Sequence Request |
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Results
Other: 05000302/LER-1978-037, Forwards LER 78-037/01T-1, 05000302/LER-1978-037-01, /01T-0:on 780804,B&W Reported That Atypical Weld Matl May Have Been Used in Constructing Plant Reactor Vessel.No Hazard to Health and Safety Determined, ML19308D758, ML19317G782, ML19317G791, ML19319D197, ML19340A474, ML19340A475, ML20062C376
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MONTHYEARML19319D9191978-08-0202 August 1978 Proposed Amend 59 to License DPR-54,revising Tech Specs Re Pressurization,Heatup & Cooldowm Limitations Per App 6 10CFR50.Class III Fee Encl Project stage: Request 05000302/LER-1978-037-01, /01T-0:on 780804,B&W Reported That Atypical Weld Matl May Have Been Used in Constructing Plant Reactor Vessel.No Hazard to Health and Safety Determined1978-08-11011 August 1978 /01T-0:on 780804,B&W Reported That Atypical Weld Matl May Have Been Used in Constructing Plant Reactor Vessel.No Hazard to Health and Safety Determined Project stage: Other ML19308D7581978-08-14014 August 1978 Confirms 780814 Telcon Re Possible Use of Atypical Weld Filler Wire.Requests Info Re Interim Measures,Operational Safety Assessment & Commitment to Maintain Interim Measures Pending Resolution of Issue Project stage: Other ML19317G7821978-08-16016 August 1978 Amend 22 to License DPR-54,revises Tech Specs Re RCS Pressure Temp.Tech Specs Encl Project stage: Other ML19317G7761978-08-16016 August 1978 Forwards Amend 22 to License DPR-54,safety Evaluation & Notice of Issuance Project stage: Approval ML19317G7871978-08-16016 August 1978 Safety Evaluation Supporting Amend 22 to License DPR-54 Project stage: Approval ML19317G7911978-08-16016 August 1978 Notice of Issuance & Availability of Amend 22 to License DPR-54 Project stage: Other ML19340A4721978-08-18018 August 1978 Responds to NRC 780814 Request for Info Re Possibility That Atypical Weld Wire Used in Mfg of Reactor Vessel.Until Determination Is Made,Util Will Operate on Assumption That Wire Was Used & Start Corrective Action Project stage: Request ML19308D9381978-08-18018 August 1978 Forwards Response to NRC 780517 Request for Addl Info Re Movement of Heavy Loads Near Spent Fuel Project stage: Request ML19340A4741978-08-22022 August 1978 Forwards Revised Operating Curves,Tech Specs Promised in Util Re Reactor Vessel Atypical Weld Matl & Bases for Tech Specs Project stage: Other ML19340A4751978-08-22022 August 1978 Revised Tech Specs 3/4.4.9 Re Operating Curves.Curve Diagrams & Bases for Tech Specs Encl Project stage: Other ML19319D1971978-08-31031 August 1978 Notifies of 781101 Possible Completion Date for B&W Chemical Analysis of Reactor Vessel Surveillance Matl to Determine Whether Atypical Weld Matl Used.Outlines Action to Be Taken on Results Project stage: Other 05000302/LER-1978-037, Forwards LER 78-037/01T-11978-09-0101 September 1978 Forwards LER 78-037/01T-1 Project stage: Other ML19308D8331978-09-0101 September 1978 Provides Review of Revised pressure-temp Operating Limits & Finds Them Acceptable.Amend Classification Form Encl Project stage: Approval ML20062C3761978-10-31031 October 1978 Forwards Tech Spec Change Requests 27 & 34,requesting Amend to App a of License DPR-72.Changes Concern Reactor Coolant Pump Power Monitors & Revisions to Heatup,Cooldown & Inservice Leak & Hydrostatic pressure-temp Curves Project stage: Other ML19257C7951980-01-28028 January 1980 Requests Withdrawal of 781031 Tech Spec Change Request 34 & Licensing Fee,Due to NRC Approval of BAW-1566, Evaluation of Atypical Weldment. Certificate of Svc & Affidavit Encl Project stage: Withdrawal 1978-08-18
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RCOULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
DISTRIBUTION FOR INCOMING MATERIAL 50-312
~tEC: REID R U ORG: MATTIMOE J J DOCDATE: 08/02/78 NRC SACRAMENTO MUN UTIL DIST DATE RCVD: 08/07/78 DOCTyPE: LETTER NOTARIZED: NO COPIES RECEIVED LTR 1 ENCL 40 SUBJEC T:
FORWARDING LIC NO DPR-54 APPL FOR PROPOSED AMEND NO 59: TECH SPEC PROPOSED CHANGE CONCERNING REVISION TO GECTION 3.1.2 " PRESSURIZATION. HEATUP, AND COOLDOWN LIMITATIONS" USING CRITERIA ESTABLISHED IN 10CFR50 APPENDIX G AND REG GUIDE 1.99, 3g ee
'MLOS6b REVIEWER INITIAL:
XJM PLANT NAME: RANCHO SECO (SMUD)
DISTRIBUTOR INITIAL:4
- DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS ******************
GENERAL DISTRIBUTION FOR AFTER ISSUANCE OF OPERATING LICENSE.
(DISTRICUTION CODE AOO1)
FOR ACTION:
DR,_CIIEF ORB #4 BC**W/7 ENCL INTERNAL:
E.
'*W/ ENCL NRC PDR**W/ ENCL I & E**W/2 ENCL OELD**LTR ONLY HANAUCR**W/ ENCL CORE PERFORMANCE BR**W/ ENCL AD FOR SYS & PROJ**W/ ENCL ENGINEERING BR**W/ ENCL REACTOR SAFETY DR**W/ ENCL PLANT SYSTEMS BR**W/ ENCL EEB**W/ ENCL EFFLUENT TREAT SYS**W/ ENCL J.
MCGOUGH**W/ ENCL EXTERNAL:
LPDR'S GACRAMENTO, CA**W/ ENCL REGION V**W/ ENCL TERA **W/ ENCL NSIC**W/ ENCL ACRS CAT B**W/16 ENCL DISTRIBUTION:
LTR 41 ENCL 40
. CONTROL NBR:
V SIZE: 1P+1P+3P gJ l
- oo********************************
THE END 8003 270 N3
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SACRAMENTO MUNICIF.U. UTILITY DISTRICT C 6201 S Street. Box 15830, Sacramento, Conforr ia-95813; (916) 452 2211 August 2, 1978
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Director of Nuclear Reactor Regulation g7 Attention: Mr. Robert W. Reid, Chief Operating Reactors, Branch No. 4 U. S. Nuclear Regulatory Commission Washington, D. C.
20555 Docket No. 50-312 Proposed License Amendment No. 59 Rancho Seco Nuclear Generating Station, Unit No.1
Dear Mr. Reid:
In compliance with Technical Specifications Section 3.1.2.6, Sacramento Municipal Utility District proposes Amendment No. 59 to Operating License DPR-54. The proposed amendment revises Section 3.1.2 "Precsurization, Heatup, and Cooldown Limitations" using criteria established in 10CFR50 Appendix G and Regulatory Guide 1.99.
The District considers this amendment to be classified under 10CFR170.22 Class III and is forwarding $4,000 with this application.
If you have any questions concerning this matter please contact Mr. R. W. Colombo at the Rancho Seco Nucle?.r Plant.
Sincerely, (h kw$
f
. J. Mattimoe Assistant General Manager and Chief Engineer Attachment 39 copies of above letter sent under separate cover
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