ML20106A187: Difference between revisions

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: 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
 
I Re: F01A-84-351    l
    ,                        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
 
i Re:  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                                                                                                  ._
 
Re:  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)"
i
 
Re:  F01A-84-351
          ~
      .                          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)
                          .}}

Latest revision as of 18:39, 18 May 2020

Affidavit of RA Pender Re Ohio Citizens for Responsible Energy Contention That Applicant Has Not Addressed Effect of Steam Erosion on Components Subj to Steam Flow
ML20106A187
Person / Time
Site: Perry  FirstEnergy icon.png
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

I Re: F01A-84-351 l

, 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

i Re: 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 ._

Re: 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)"

i

Re: F01A-84-351

~

. 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)

.