PNP 2015-022, Relief Request Number RR 5-1, Proposed Alternative, Extend the Current ASME Code of Record Into the Fifth 10-year ISI Interval for ISI Related Activities
LIC-14-0109, Evaluation of a Through-Wall Leak in a Raw Water Elbow in Support of Relief Request
NL-13-2521, ISI Program Alternative HNP-ISI-ALT-18, Version 1
RA-13-027, Response to Request for Additional Information - Relief Requests for the Fifth Ten-Year Inservice Inspection (Lsi) Interval
L-13-076, 10 CFR 50.55a Notification of Impracticality and Requests for Alternatives Supporting the Third and Fourth to-Year Inservice Inspection Intervals
NL-12-1446, Proposed Inservice Inspection Alternatives VEGP-ISI-AL T-05 and VEGP-ISI-AL T -06 for Implementation of Extended Reactor Vessel Inservice Inspection Intervals
ULNRC-05891, Enclosure 1: Callaway Plant Unit 1 License Renewal Application - Request for Additional Information Set 4 Responses
LR-N11-0213, Inservice Inspection (Lsi) Program Plan, Fourth Ten-Year Interval
NL-11-0242, Proposed Alternative in Accordance with 10 CFR 50.55a(a)(3)(i), HNP-ISI-ALT-11
PNP 2011-006, ASME Section XI 90-Day Inservice Inspection Summary Report
ULNRC-06349, Callaway, Unit 1 - Enclosure 3 to ULNRC-06349 - Document A22-1690-001, Rev. 0, Decommissioning Cost Analysis for the Callaway Energy Center, Section 5, Page 3 of 6 - Appendix C, Page 3 of 10
NL-10-1663, VEGP-ISI-ALT-03, Version 3, Proposed Alternative for the Third ISI Interval
NG-09-0825, Response to Request for Additional Information Regarding the License Renewal Application - Aging Management Review Line Items
0CAN090801, GL 2004-02 Final Supplemental Response
RS-03-077, Proposed Alternative Method of Repair for Control Rod Drive Mechanism Canopy Seal Weld
CPSES-200300632, Revised Relief Requests B-7, B-8, B-9 Rev. 1 & C-6, Rev. 1
IA-87-530, Final Response to FOIA Request for Documents Re Facility. Document Identified in App a Withheld in Entirety (Ref FOIA Exemption 7)
NSD-NRC-97-5285, Forwards W Revised Response to NRC RAI Re AP600 Shutdown PRA & Surge Line Flooding
2CAN038604, Requests NRC Approval to Utilize ASME Code Case N-411, Alternative Damping Values for Seismic Analysis of Piping, for Response Spectrum Analysis of Selected Piping.Planned Use of Code Case Listed.Fee Paid
BSEP-96-0083, Notifies NRC of Util Intent to Extend Second 10-Yr Insp Interval for Units 1 & 2
05000483/LER-1985-018, :on 850329,diesel Generator B Inadvertently Started During Surveillance Testing of Load Shedder & Emergency Load Sequencer.Caused by Technician Error. Technician Counseled & Cabinets Labeled
05000255/LER-1983-015-03, /03L-0:on 830221,during post-maint Test on Diesel Generator 1-1,generator Frequency Increased to Approx 65 Hz. Caused by Speed Setting Potentiometer & Mechanical Governor Being Out of Adjustment.Corrective Adjustments Made
CP-202300322, Response to Requests for Additional Information Regarding Review of the License Renewal Application – Sets 2 and 3
05000260/LER-1992-003-02, :on 920423,unexpected Group 4 Primary Isolation Signal Received,Resulting in Closure of HPCI Steam Supply Isolation Valves.Caused by Inadvertent Installation of Test Plug.Test Plug Marked
BW130007, Inservice Inspection Summary Report
RS-14-111, Supplemental Response to NRC Request for Information Pursuant to 10CFR 50.54(f) Regarding the Flooding Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident
BW080003, Thirteenth Refueling Outage Steam Generator Inservice Inspection Summary Report
BVY 04-106, Technical Specification Proposed Change No. 263 - Supplement No. 18 Extended Power Uprate - ECCS Pump Net Positive Suction Head Margin
BSEP-98-0090, Provides Comments on Draft SE Re Conversion to Improved Tech Specs.Encl 2 Provides Draft SE pages,marked-up to Reflect Comments as Well as Addl Editorial Comments