ML16264A482
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Letter Sequence Response to RAI | |
|---|---|
CAC:MF7368, (Open) | |
Initiation Administration | |
MONTHYEARGO2-16-027, Fourth Ten-Year Interval Inservice Inspection (ISI) Program Relief Request 4ISI-062016-02-17017 February 2016
[Table View]Fourth Ten-Year Interval Inservice Inspection (ISI) Program Relief Request 4ISI-06 Project stage: Request ML16081A0052016-03-18018 March 2016 NRR E-mail Capture - Columbia Generating Station, Acceptance of Requested Licensing Action:, CAC No. MF7368,, Relief Request 4ISI-06, Code Case N-666-1 Project stage: Acceptance Review ML16236A0792016-08-23023 August 2016 NRR E-mail Capture - Request for Additional Information, Columbia N-666-1, Relief Request 4ISI-06, Use of Code Case N-666-1 on Socket Welded Connections CAC MF7368 Project stage: RAI GO2-16-128, Response to Request for Additional Information Related to Relief Request 4ISI-06 Regarding Code Case N-666-12016-09-20020 September 2016 Response to Request for Additional Information Related to Relief Request 4ISI-06 Regarding Code Case N-666-1 Project stage: Response to RAI ML16292A8722016-11-0303 November 2016 Relief Request 4ISI-06, Use of Code Case N-666-1 on Socket Welded Connections Requiring Repair Due to Vibration Fatigue, Fourth 10-Year Inservice Inspection Interval Project stage: Other 2016-03-18 |
| ML16264A482 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 09/20/2016 |
| From: | Javorik A L Energy Northwest |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 4ISI-06, CAC MF7368, GO2-16-128, N-666-1 | |
| Download: ML16264A482 (2) | |
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Adopt Technical Specification Task Force (TSTF)-425, Revision 3 ML18191A2031978-06-30030 June 1978 Response to NRC Request for Additional Information (Round 3 Questions) ML18191A2381977-12-16016 December 1977 Advising of Intention to Complete Evaluation Regarding BWR Relief Valve Control System & Associated Containment Loads for Wppss Nuclear Project No. 2 Is Scheduled During 2nd Quarter of 1978 ML18191A8101976-04-28028 April 1976 Wppss Nuclear Project No. 2 Post-Construction Permit Item Drywell/Wetwell Leakage Study ML18191A2741976-01-12012 January 1976 Wppss Nuclear Project No. 2. Clarification of Criteria, Pipe Rupture Protection Inside Containment ML18191A8131975-08-18018 August 1975 Wppss Nuclear Project No. 2 Response to Request for Information Main Steam Isolation Valve Leakage Control System 2022-07-11 |
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