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Category:- No Document Type Applies
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Pages in category "- No Document Type Applies"
The following 200 pages are in this category, out of 5,828 total.
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- 3F0311-07, Attachment B, Response to Request for Additional Information Required for the Development of the Confirmatory LOCA and Non-LOCA Models
- 3F0608-05, Response to Request for Additional Information Regarding Relief Requests 07-001-SS, Revision 0, Alternate Criteria for the Reactor Vessel Support Skirt to Perform Limited VT-3 Visual Examination on 3 Areas 120 Degrees Apart .
- 3F0610-08, Pef Letter to FDEP NPDES Permit Renewal App CR 4 & 5 January 25, 2010
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- DCL-08-057, Response to Request for Additional Information on License Amendment Request 07-04, Proposed Technical Specifications Change to Relocate Surveillance Test Intervals to a Licensee-Controlled Program (Risk Informed Technical ...
- DCL-10-028, Diablo Canyon, Units 1 and 2, Attachment 4 to DCL-10-028, History DCPP PRA Model Development and Update
- DCL-10-028, Diablo Canyon, Units 1 and 2, Attachment 5 to DCL-10-028, Summary Statement of Diablo Canyon Power Plant PRA Model Capability for Use in TS 3.8.1 Completion Time Extension Submittal
- DCL-11-104, Attachment 1: List of Regulatory Commitments
- DCL-12-119, Response to Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.3 Seismic Unit 2, Part 2 of 3
- DCL-13-021, Performance Demonstration Initiative (POI) Program Alternatives and Their Bases with Respect to ASME Code Section Xi, Appendix Viii Supplement 11 Requirements
- DCL-15-034, Final Response to Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 Flooding. Part 2 of 2
- DCL-15-035, Diablo Canyon Units 1 & 2 - Response to NRC Request for Info. Pursuant to 10 CFR 50.54(f) Seismic Aspects of Recommendation 2.1 of Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident: Seismic Hazard Screening Report.
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- L-05-080, Exhibit D (Part 4): Excerpt from the Beaver Valley and Perry 2005 License Transfer Application
- L-08-229, Responses to a Request for Additional Information in Support of License Amendment Request No. 07-005
- L-08-241, Attachment 1, Applicable Portions of the U.S. Nuclear Regulatory Commission (NRC) and Davis-Besse Nuclear Power Station (DBNPS) Improved. Technical Specification (ITS) Conversion Website, Section 3.5 RAIs
- L-09-028, Response to Request for Additional Information the 2008 Steam Generator Tube Inspection Report
- L-11-165, Enclosure C - Binder 1 of 2, Davis-Besse Nuclear Power Station, Unit No. 1 (DBNPS) References. (Tab a 8 Through T 30)
- L-14-147, ODCM: Index, Matrix and History of ODCM Changes
- L-16-092, Information Pertaining to Foreign Ownership, Control, or Influence. Part 4 of 6
- L-20-191, Energy Harbor - Enclosed May 2020 NPDES Discharge Monitoring Report, Beaver Valley Power Station & Supplemental Monitoring Data for Outfall 001 (Dissolved Oxygen)
- L-2001-115, Explanation of Reported Areal Densities in Florida Power Light Letter L-2001-115
- L-2005-012, Enclosure 2, St. Lucie Unit 2, Responses to NRC Requests for Additional Information on WCAP-16208-P, Revision 0, NDE Inspection Length for CE Steam Generator Tubesheet Region Explosive Expansions.
- L-2005-057, State 401 Certification Update
- L-2010-123, Substantial NPDES Permit Revision St. Lucie Plant Response to FDEP RFI 1
- L-2010-259, St. Lucie, Unit 1 - License Amendment Request for Extended Power Uprate, Attachment 5; Appendix B, Additional Codes and Methods
- L-2012-248, Attachment 1 to L-2012-248, Evaluation of Proposed Change (Redacted)
- L-79-002, Allegation Document Regarding RI-2002-A-0137, Preliminary Opinion
- L-99-007, NPDES Permits No. SC0030856 Renewal Application (LP 252)
- L-MT-12-090, Westinghouse, LTR-A&SA-12-8, Rev. 1, Attachment B, Recommendations for Inspections of the Monticello Replacement Steam Dryer.
- L-MT-13-020, Enclosure 1 - Responses to the Gap Analysis
- L-PI-14-020, Enclosure 3 - Prairie Island Nuclear Generating Plant, Unit 2 - NTTF Recommendation 2.3 - Seismic Updated Seismic Walkdown Report (Redacted)
- L-PI-22-004, L-PI-22-004 Prairie Island Nuclear Generating Plant, Unit 2, 10 CFR 50.55a Request No. RR-08, Request for Alternative to ISTC 3630(f)
- LIC-05-0057, Revised Relaxation Request for First Revised Order (EA-03-009) Establishing Interim Inspection Requirements for Reactor Pressure Vessel Heads at Pressurized Water Reactors
- LIC-13-0140, Attachment 3 - Strategy to Protect Fort Calhoun Station from Beyond Design Basis Flood - Redacted
- LR-N12-0124, Salem Generating Station, Units 1 and 2 - Attachment 1 to LR-N12-0124, Generic Letter 2004-02, Updated Supplemental Response for Salem Regarding Generic Letter 2004-02
- LR-N22-0016, Radiological Survey of Site Property to Be Used for Offshore Wind Port Facility
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