ML20106A187

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
Issue date:	02/01/1985
From:	Pender R CLEVELAND ELECTRIC ILLUMINATING CO.
To:
Shared Package
ML20106A167	List: ML20106A165 ML20106A174 ML20106A187 ML20106A218
References
OL, NUDOCS 8502110067
Download: ML20106A187 (24)

Text

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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

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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)

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