Browse wiki

Letter  and Response to Request for Additional Information (RAI)

10 CFR 50.67 +, 10 CFR 50 Appendix K +, 10 CFR 50 +, 10 CFR 50.2 +, 10 CFR 50.90 +  and 10 CFR 50.55a#c +

Initiating Events +  and Mitigating Systems +

05000244  +  and 00244  +

ML13093A064 +, ML15166A075 +, ML010542030 +  and ML010540356 +

Exelon +  and David Gudger +

GDC 16 +, GDC 14 +  and GDC 53 +

NRC Generic Letter 84-04, Safety Evaluation of Westinghouse Topical Reports Dealing with Elimination of Postulated Pipe Breaks in PWR Primary Main Loops (Generic Letter 84-04) +, NRC Generic Letter 88-11, NRC Position on Radiation Embrittlement of Reactor Vessel Materials and Its Impact on Plant Operations +  and NRC Generic Letter 90-06, Resolution of Generic Issues 70, "PORV and Block Valve Reliability," and 94, "Additional Ltop Protection for PWRs" +

ML16034A139 +, ML16034A139 +, ML16034A139 +, ML16034A139 +, ML16034A139 +, ML16034A139 +, ML16034A139 +, ML16034A139 +, ML16034A139 +, ML16034A139 +, ML16034A139 +, ML16034A139 +, ML16034A139 +, ML16034A139 +, ML16034A139 +, ML16034A139 +, ML16034A139 +, ML16034A139 +, ML16034A139 +, ML16034A139 +, ML16034A139 +, ML16034A139 +, ML16034A139 +, ML16034A139 +, ML16034A139 +, ML16034A139 +, ML16034A139 +, ML16034A139 +, ML16034A139 +...

4.62963e-5 d (0.00111 hours, 6.613757e-6 weeks, 1.522e-6 months)  +, 8.333333e-4 d (0.02 hours, 1.190476e-4 weeks, 2.7396e-5 months)  +, 1.388889e-4 d (0.00333 hours, 1.984127e-5 weeks, 4.566e-6 months)  +  and 0.00132 d (0.0317 hours, 1.884921e-4 weeks, 4.3377e-5 months)  +

CAC:MF6713 +  and CAC:MF6358 +

NEI 04-10, E-mail from J. Whited to D. Filchner: Susquehanna Steam Electric Station Acceptance of License Amendment Request Implementation of TSTF-425 (TAC Nos. MF5151 and MF5152) +  and NEI 97-06, Steam Generator Conditioning Monitoring Report +

NUREG/CR-5750 +, NUREG/CR-4550 +, NUREG/CR-6928 +, NUREG/CR-7150 +, NUREG/CR-6268 +, NUREG-0677 +, NUREG/CR-2728 +, NUREG-2178, Response to October 28, 2015, Letter Regarding the Availability of NUREG-2178, Refining and Characterizing Heat Release Rates from Electrical Enclosures During Fire (RACHELLE-FIRE), Volume 1: Peak Heat Release Rates and Effect of Obstruct +, NUREG-2169, NUREG 2169 Suppression Data Set +  and NUREG/CR-6850, To Propose an Alternative Methodology to Distribute Transient Ignition Frequencies (Bins 3, 5, 6, 7, 11, 24, 25, 31, 36, 37) That Contains a More Structured Approach to Accounting for Influence Factor Variations within a Pau +

James Barstow +  and Enrique Villar +

Regulatory Guide 1.177 +, Regulatory Guide 1.200 +, Regulatory Guide 1.174 +  and Regulatory Guide 1.17 +

SR-3.0.2 +, SR-3.1.6.1 +, SR-3.5.2.8 +, SR-3.4.2.1 +, SR-3.1.6.2 +, SR-3.1.6.3 +, SR-3.1.8.2 +, SR-3.1.6.4 +  and SR-3.4.2.2 +

Steam Generator +, Reactor Coolant System +, Feedwater +, Service water +, Auxiliary Feedwater +, HVAC +, Residual Heat Removal +, Emergency Core Cooling System +, Decay Heat Removal +, Control Rod +  and Auxiliary Feed Water +

TS-3.4.15 +  and TS-3.4.17 +

TSTF-425 +  and TSTF-523 +

Office of Nuclear Reactor Regulation +  and Document Control Desk +

Internal Flooding +, Probabilistic Risk Assessment +, Aging Management +, Surveillance Frequency Control Program +, Large early release frequency +, Loss of Offsite Power +, Pressure Boundary Leakage +, Unidentified leakage +, Operational leakage +, Water hammer +  and Gas accumulation +

F-F3-01 +  and F-E5-01 +