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| Issue date | Site | Title | |
|---|---|---|---|
| ML18288A020 | 31 October 2018 | NUREG-IA-0482, International Agreement Report - Using Trace, Melcor, Cfd, and Fraptran to Establish the Analysis Methodology for Chinshan Nuclear Power Plant Spent Fuel Pool. | |
| ML18302A011 | 31 October 2018 | NUREG/IA-0483, International Agreement Report - Loss of Flow Analysis of Maanshan Nuclear Power Plant with RELAP5/SNAP. | |
| ML19035A005 | 28 February 2019 | NUREG/IA-0493 - International Agreement Report - the Ultimate Response Guideline Simulation and Study for Lungmen (ABWR) Nuclear Power Plant Using RELAP5/SNAP. | |
| ML19056A357 | 25 February 2019 | NUREG/IA-0496 - International Agreement Report - the Analysis and Study of ELAP Event and Mitigation Strategies Using Trace Code for Maanshan Pwr. | |
| ML19112A268 | 30 April 2019 | NUREG/IA-0509 - International Agreement Report - LBLOCA Uncertainty Analysis of Maanshan Nuclear Power Plant with RELAP5/SNAP and Dakota. | |
| ML20028D511 | 31 January 2020 | NUREG-IA-0517, Analysis of Maanshan Station Blackout Accident and Rescue Procedures Under Different Tube Plugging Situations with Trace | |
| ML20065C444 | 25 August 1982 | FitzPatrick | Trip Rept of 820526-27 Site Visit to Discuss Radiological Effluent Tech Specs & Offsite Dose Calculation Manual |
| ML20069H861 | 8 October 1982 | Cook | Radiological Effluent Tech Spec Implementation (A-2),DC Cook Nuclear Plant Units 1 & 2, Technical Evaluation Rept |
| ML20076D181 | 18 March 1983 | North Anna | RETS Implementation (A-2), Technical Evaluation Rept |
| ML20094L870 | 14 August 1984 | Shoreham | Testimony of Rl Mccarthy,Pr Johnson,Ef Montgomery & Sk Chen on Suffolk County Contention Re Replacement Crankshafts on Diesel Generators.Related Correspondence |
| ML20095G814 | 18 August 1984 | Catawba | Testimony of Gw Hallman,Rp Muschick,Sr Ward,Ja Gorman, CA Wells,La Swanger,Sk Chen,Jo Barbour,Jm Curtis & Rc Gamberg Re Problems Encountered in Diesel Generator Qualification Program.Related Correspondence |
| ML20100N665 | 1 November 1984 | Shoreham | Intervenor Exhibit I-66,consisting of Pages 1 & 129 of Transcript of Sk Chen 840515 Deposition in Washington,Dc |
| ML20100P264 | 17 September 1984 | Shoreham | Intervenor Exihibit I-18,consisting of Power & Energy Intl, Inc 840719 Rept, Crankshaft Torsional Stress Calculations for 8 L 17x21 Engine-Generator Set |
| ML20132C977 | 23 April 1985 | Big Rock Point | Radiological Effluent Tech Spec Implementation (A-2) Big Rock Point Plant, Technical Evaluation Rept |
| ML20136G029 | 29 May 1985 | Maine Yankee | Radiological Effluent Tech Spec Implementation (A-2),Maine Yankee Atomic Power Station, Technical Evaluation Rept |
| ML20210N395 | 15 January 1987 | Comanche Peak | Rev 2 to SAG.CP11, Sys Analysis of Cable Tray & Hanger Assembly for Comanche Peak Steam Electric Station,Units 1 & 2 |
| ML20236J540 | 16 June 1987 | Comanche Peak | Rev 1 to Procedure SAG.CP28, Procedure for Screening of Cable Tray Hangers to Assess Applicability of 1.25 MRM in Equivalent Static Method Analysis in Hanger Design Verification for Comanche Peak Steam Electric Station.. |
| ML20236N948 | 10 February 1998 | Saxton | Rev 0 to Calculation 77581-012-C-002, SG Qualification for Shipment |
| ML20236N963 | 10 February 1998 | Saxton | Rev 0 to Calculation 77581-012-C-003, Pzr Qualification for Shipment |
| ML21231A205 | 31 August 2021 | NUREG/IA-0527, Analysis of Main Steam Line Break Accident for 3-Loop PWR with RELAP5/MOD3.3 Code | |
| ML22053A190 | 28 February 2022 | NUREG/IA-0528, Uncertainty Analysis of Main Steam Line Break Accident for Maanshan PWR with RELAP5/DAKOTA |