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MONTHYEARML19319E2711976-04-22022 April 1976
Discusses 760227 Revision to 10CFR50.55a Re Inservice Insp Testing Requirements for ASME Code Class 1,2 & 3 Components. Dates Re Next 40 Month Insp Period & Submission of Tech Specs Amend Reflecting Revised Regulation Requested
Project stage: Other
ML19309B0431978-01-10010 January 1978
Forwards Guidance for Preparing Pump & Valve Testing Program Descriptions & Associated Relief Requests.Guidance Should Be Followed When Submitting Proposed Inservice Insp & Testing Programs
Project stage: Approval
ML19269D4841979-05-14014 May 1979
Ack Receipt of Claiming Exemption from Class III Fee for Proposed Tech Specs Amend 63.Submittal Is Not Exempt from Fee Since NRC Review Effort Is Required
Project stage: Approval
ML19210E0061979-10-17017 October 1979
Ack Receipt of Proposed Inservice Insp & Testing Program in Lieu of ASME Code Requirements for Nuclear Power Plant Components.Relief Is Granted,Pending Completion of Detailed Review
Project stage: Other
ML19254F5371979-10-24024 October 1979
Requests Addl Info Re Inservice Testing Program.Forwards Questions Re Valves That Can Be partial-stroke Tested Periodically
Project stage: Other
ML19210E0121979-10-30030 October 1979
Notice of Granting of Relief from ASME Section XI Inservice Insp & Testing Requirements.Relief Granted,Pending Completion of Detailed Review of Inservice Insp Code Requirements
Project stage: Approval
ML19210C4811979-11-0606 November 1979
Confirms Commitment to Submit Revised Inservice Insp & Testing Program & Answers to Encl 1 of by 791212
Project stage: Other
ML19256G4801979-12-12012 December 1979
To Proposed Amend 63 to Tech Spec Sections 3 & 4 Re Limiting Conditions for Operation & Surveillance Stds, Respectively
Project stage: Other
ML19256G4751979-12-12012 December 1979
Forwards Revision 1 to Proposed Amend 63 to Tech Specs Sections 3 & 4 Re Limiting Conditions for Operation & Surveillance Stds,Respectively
Project stage: Other
ML19256G5531979-12-24024 December 1979
Corrected Pages 4-4,4-11 Through 4-13,4-16,4-45,4-47 & 4-56 to Inservice Testing Program.Includes Results from Makeup/ HPI Sys,Decay Heat/Core Flood Areas,Raw Water & Cooling Water & Turbine Sampling Tests
Project stage: Other
ML19256G5481979-12-24024 December 1979
Forwards Corrected Pages to Implementation Review of Inservice Insp Testing Program
Project stage: Other
ML19260D2801980-01-22022 January 1980
Requests Info Re Effects of Valve Lineup Procedural Changes within 45 Days
Project stage: Other
ML19310A3601980-05-30030 May 1980
Forwards Revision 1 to ASME Code Class Valve Testing Requirements Pp 4-5 & 4-6 Re Program Changes Resulting from 790718 Operational Review for Implementation of Inservice Testing Program.Requests Addl Relief Due to Changes
Project stage: Other
ML20058G3611982-07-28028 July 1982
Application for Amend 82,Revision 1 to License DPR-54, Correcting Typographical Errors in Tech Spec Table 4.14-1 & Addressing Temporary Use of Mechanical Snubbers on Steam Generator External Auxiliary Feedwater Header
Project stage: Request
ML20135H8101985-09-19019 September 1985
Rescinds Proposed Amend 82,Rev 1,dtd 820728,to Tech Specs as No Longer Timely.Proposed Amend 75,Rev 2,dtd 850409,replaces Mechanical Snubbers W/Hydraulic Snubbers & Incorporates Corrected Typos
Project stage: Other
ML20137Y8851985-09-30030 September 1985
Forwards Amend 76 to License DPR-54 & Safety Evaluation. Amend Revises Tech Specs to Provide Conformance W/ Regulations Governing Inservice Insp & Insp of Steam Generator Tubes Set Forth in 10CFR50.55a(g)
Project stage: Approval
1979-12-12
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Text
I i S:JUD SACRAMENTO MUNICIPAL UTILITY DISTRICT O 6201 S Street, Scx 15830. Sacramento, California 95813; (916) 452-3211 December 12, 1979 Director of Nuclear Reactor Regulation Attention:
?!r. Robert W. Reid, Chief Operating Reactors, Branch No. 4 U. S. Nuclear Regulatory Commission Washington, D. C.
20555 Docket No. 50-312 Proposed Amendment No. 63 Revision 1 Rancho Seco Nuclear Generating Station Unit No. 1
Dear ?!r. Reid:
As a result of meetings held October 3 and 4, 1979, with members of SRC staff to review our ISI/IST program, we are submitting Revision 1 to Proposed Amendment No. 63 to the Rancho Seco Technical Specifications.
Staff suggestions with regard to not testing safety-related equipment when the redun-d.in t equipment is inoperable or out of service for any other reason have been incorporated.
Any questions on this matter may be hat.dled through !!r. R. Colombo of my staff.
Respectfully submitted, E.4 kM
/ '
J. J. ?fatticoe Assistant General Manager and Chief Engineer JP!:WBG:j im Subscribg and sworn to before me this /7 day of Decenber, 1979.
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