ML20106A187
| ML20106A187 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 02/01/1985 |
| From: | Pender R CLEVELAND ELECTRIC ILLUMINATING CO. |
| To: | |
| Shared Package | |
| ML20106A167 | List: |
| References | |
| OL, NUDOCS 8502110067 | |
| Download: ML20106A187 (24) | |
Text
i. e.
FOIA-84-351 APPENDIX 8 (CONTINUED)
Category 10 Region III Date POR Accession No.
Plant or Utility
- 11. 9/16/83 8309200268 Midland 12.
10/20/83 8310250522 Big Rock Point 13.
10/20/83 8310250538 Monticello 14.
10/20/83 8310250191 Palisades 15.
10/20/83 8310250275 Prairie Island 16, 10/28/83 8311040003 David-Besse 17.
11/4/83 8311070284 Kewaunee 18.
11/18/83 8311280042 Lacrosse
- 19. 2/6/84 8402080204 Fermi 20, 3/22/84 8403270246 Braidwood 21.
3/22/84 8403270246 Byron
- 22. 4/6/84 8404120271 Callaway Region IV Date PDR Accession No.
Plant or Utility 1.
11/28/83 8401040111 ANO 2.
12/5/83 8312300180 Cooper Nuclear Station 3.
2/10/84 8402210348 Fort Calhoun
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F01A-84-351 APPENDIX B (CONTINUED)
Category 10 Region V Date PDR Accession No.
Plant or Utility 1.
6/6/83' 8310200232 Memo re: SONGS 2.
10/14/83 8310200220 San Onofre 3.
12/5/83 8312120194 WNPSS-2 4.
3/9/84 8403130343 Rancho Seco 5.
4/10/84 8404240088 Trojan d
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F01A-84-351 APPENDIX B (CONTINUED)
Categories 12 and 13 1.
1/1983 NUREG/CR-2703
" Investigation of Special Puronse Processors for Real-Time Synthetic Aperture Focusing Techniques for Nondestructive Evaluation of Nuclear Reactor Vessels and Piping Components" 2.
4/1983 NUREG/CR-2789 (ORNL/NSIC-210) " Pressure Vessel Thermal Shock at U.S. Pressurized-Water Reactors:
Events and Precursors, 1963-1981" 3.
6/20/83 ACRSR-1033 - Accession No. 8307050361 - Fraley Memo to Dircks.
EDO, ACRS Coments on the Prioritization of Generic Issues 4,
7/15/83 ACRSR-1041 - Accession No. 8307260036 - Libarkin memo to Dircks, EDO, Additional ACRS Comments on the Prioritization of Generic Issues 5.
10/18/83 ACRSR-1058 - Accession No. 8310310465 - Ray, ACRS, letter to Palladino, NRC, ACRS Coments on the NRC Integrated Program for the Resolution of Unresolved Safety Issues A-3, A-4, and A-5 Relating to PWR Steam Generators 6.
11/1983 NUREG/CR-3391 (Volume 1) " LWR Pressure Vessel Surveillance Dosimetry Improvement Program" - Quarterly Progress Report -
January 1983 - March 1983 7.
11/22/83 ACRSR-1060 - Accession No. 8312090275 - Ray, ACRS, letter to Dircks, EDO, Generic Issue B-10, Hydrodynamic Loads on Mark III Containment Structures 8*
12/1983 NUREG/CR-3592'"Postirradiation Annealing Recovery of High Copper Reactor Pressure Vessel Weld Metal Toughness Properties" 1
9.
1/1984 NUREG/CR-3561 " Eddy Current Round Robin Test on Laboratory Produced Intergranular Stress Corrosion Cracked Inconel Steam Generator Tubes"
- 10. 1/1984 NUREG/CR-3562 " Steam Generator Tube Integrity Program Leak Rate Tests" - Progress Report
- 11. 1/1984 NUREG/CR-3579 " Steam Generator Group Project" - Progress 3
Report on Data Acquisition / Statistical Analysis
- 12. 2/1984 NUREG/CR-3581 " Steam Generator Group Project" - Annual Report 1982 1
- 13. 3/1984 NUREG/CR-3625 " Review and Discussion of the Development of Synthetic Aper +ure Focusing Technique for Ultrasonic Testing (SAFT-UT)
- 14. 3/1984 NUREG/CR-0975 (Vol. 2) " Compilation of Contract Research for the Materials Engineering Branch, Division of Engineering Technology" - Annual Report for FY 1983 L
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F01A-64-351 APPENDIX B (CONTINUED)
Categories 12 and 13 15.
3/1984 NUREG/CR-3200 (Vol. 3) " Eddy-Current Inspection for Steam Generator Tubing Program Quarterly Report for Period Ending September 30, 1983" 16.
3/1984 NUREG/CR-3334 (Vol. 3) " Heavy-Section Steel Technology Program Quarterly Progress Report for July-September 1983" 17.
4/1984 NUREG/CR-3391 (Vol. 2) " LWR Pressure Vessel Surveillance Dosimetry Improvement Program" - Quarterly Progress Report April 1983 - June 1983 18.
4/1984 NUREG/CR-3307 (Vol. 3) " Reactor Safety Research Programs" -
Quarterly Report July - September 1983 19.
4/1984 NUREG/CR-3546 "The Temperature Dependence of Fatigue Crack Growth Rates of A 351 CF8A Cast Stainless Steel in LWR Environment" 20.
4/1984 NUREG/CR-3295 (Vol.1) " Light Water Reactor Pressure Vessel Surveillance Dosimetry Improvement Program" - Notch Ductility and Fracture Toughness Degradation of A 302-B and A 533-B Reference Plates from PSF Simulated Surveillance and Through-Wall Irradiation Capsules 21.
4/1984 NUREG/CR-3295 (Vol. 2) " Light Water Reactor Pressure Vessel Surveillance Dosimetry Improvement Program" - Postirradiation Notch Ductility and Tensile. Strength Determinations for PSF Simulated Surveillance and Through-Wall Specimen Capsules 22.
4/1984 NUREG/CR-3506 "J-R Curve Characterization of Irradiated Low Upper Shelf Welds" 23.
4/1984 NUREG/CR-3672 "An Examination of the Size Effects and Data scatter Observed in Small-Specimen Cleavage Fracture Toughness Testing" 24.
4/1984 NUREG/CR-3740 "J-Integral Tearing Instability Analyses for 8-inch Diameter ASTM 106 Steel Pipe" 25.
4/1984 NUREG/CR-3770 " Pressurized Thermal Shock Evaluation of the Oconee l Nuclear Power Plant" - Accession No. 8405160359/
ADOCK/50-269T 26.
5/1984 NUREG/CR-3770 " Decay of Buoyancy Driven Stratified Layers With Applications to Pressurized Thermal Shock (PTS)"
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APPENDIX C RECORDS WITHHELD Category 10 1.
. Undated Draft SALP report on Catawba (26 pages) 2..
Undated Draft SALP report on TVA's Browns Ferry, Sequoyah, Watts Bar, and Bellefonte (81 pages)
Category 12 1.
Undated Draf t NUREG-0844, " Integrated Program for the Resolution of Unresolved Safety Issues A-3, A-4, and A-5 Regarding Steam Generator Tube Integrity" (348 pages)
.