ML20155F315

From kanterella
Jump to navigation Jump to search
First Partial Response to FOIA Request for Documents.Records Subj to Request Encl & Identified in Apps a & B
ML20155F315
Person / Time
Issue date: 11/02/1998
From: Racquel Powell
NRC OFFICE OF ADMINISTRATION (ADM)
To: Williams O
JRA ASSOCIATES
Shared Package
ML20155F320 List:
References
FOIA-97-488 NUDOCS 9811050398
Download: ML20155F315 (6)
v • d • e


Text

_ _ _ _ _ _ _ ._

NRC FORM 464 Pirt I U.S. NUCLEAR REGULATORY COMMISSION P U3All'A D ht(/

RESPONSE NUMBER

( im  !

p*" % 97-488 1 RESPONSE TO FREEDOM OF INFORMATION ACT (FOlA) / PRIVACY RESPONSE -

k ***+' ACT (PA) REQUEST TYPE u E-REQuESrER DATE Ophelia Williams W 0 219!s PART l. -INFORMATION RELEASED

{j No additional agency records subject to the request have been located.

{] Requested records are available through another public distribution prograrr See Comments section.

r [ APPENDICES ~ ~ ~ Agency records subject to the request that are identified in the listed appendices are already available for J

A ,

public inspection and copying at the NRC Public Document Room.

F iAP'PENOlCES~~ '

Agency records subject to the request that are identified in the listed arpendices are being made available for l B public inspection and copying at the NRC Public Document Room.

E j Enclosidls information on how you may obtain access to and the charges for copying records located at the NRC Public Document Room,2120 L Street, NW, Washington, DC.

ra fAPP$NDICEs Ml B ' Agency records subject to the request are enclosed.

~~

r~ 'Recordisiibject to the request that contain information originated by or of interest to another Federal agency have been referred to that agency (see comments section) for a disclosure deterriination and direct response to you.

Q We are continuing to process your request.

g See Coninients.

PART 1.A - FEES AuoVNT * - ~ ~ ' ^' You will be billed by NRC for the amount listed. None. Minimum fee threshold not met.

I ~~ You will receive a refund for the amount listed. Fees waived. l e ig' --

PART l.B -INFORMATION NOT LOCATED OR WITHHELD FROM DISCLOSURE ,

] No agency records subject to the request have been located.

Certain information in the requested records is being withheld from disclosure pursuant to the exemptions described in and for

- the reasons stated in Part II.

~ This determination may be appealed within 30 days by writing to the FOIA/PA Officer, U.S. Nuclear Regulatory Commission,

- Washington, DC 20555-0001. Clearly state on the envelope and in the letter that it is a "FOIA/PA Appeal."

PART t.C COMMENTS (Use attached Comments continuation page if required)

Record B/2 is copyrighted. This recordy may be inspected ONLY at the PDR.

c

/

d'

~

9811050398 981102 '

PDR FOIA WILLIAM 97-488 PDR SIG%URL - F REEQOM OF INTURMA l'lON I AND PHIVAGY AGI OFFICtiH I

~

Rus. Q{ % -f)n sellLA. Powell ,

'/ \

1 NRC FORM 464 Part 1 (61998) PRINTED ON RECYCLED PAPER This form was designed using informs j

'qgIIoGO W6 j

0 Re: FOIA- 97 488 -

APPENDIX A t

RECORDS ALREADY AVAILAELE IN THE PDR ACCESSION NO. DATE NUMBER DESCRIPTION 1 9404010163 NUREG -1368, " Preapplication Safety Evaluation Report for the Power Reactor Innovative Small Module (Prism) Liquid-Metal Reactor" 2 1997 9707180165 NUREG-1350, Volume 9, " Nuclear Regulatory Commission Information Digest" 3 9103260127 NRC Inspection Report No. 99900067/91-01," Notice of Violation and Notice of Nonconformance" 4 9712180168 Generic Letter (GL) 97-06, " Degradation of Steam Generator (SG) Internals" 5 10/96 9610150128 WCAP-14707/8, "Model 51 SG Limited Tube Support Plate Displacement Analysis for Dented or Packed Tube to Tube Support Plate Crevices" 6 9703280305 Summary of 11/20/96 Meeting 7 9801210249 Supplement to Braidwood Unit 1, Cycle 7 Interim Plugging Criteria Report 8 9712290223 SECY Paper on GL 97-06 9 9801770234 Summary of 12/11/97 Meeting 10 9705190029 Summary of NEl Meeting on 5/1/97 11 9701230189 Minutes of CRGR Meeting No. 296 - Part 2 12 9709040243 Request for Review and Endorsement of Final GL 13 9611260323 Request for Review of GL

_ . . _. .. . . . . . . _ . _ . . _ _ _ _ _ _ _ _ . . . . _ . = . _ . _ _ . _ ... . . . _ _ . _ _ _ _

9 14 9612310078 Notice of Opportunity for Public Comment on GL 15 9602060170 Information Notice (IN) 96-09 16 9607030266 IN 96-09, Suppl 1 17 9803090208 WCAP-15031," Evaluation of EdF SG internals Degradation -Impact of Causal Factors on W 51 Series SG" 18 9712220415 Modes of Degradation Detected on EdF Units 19 9705050045 Summary of 4/10/97 Meeting w/PG&E to discuss attemate SG tube repair method involving locked tube support plates

20. 4/96 9607100298 NUREG/CR-6365, Steam Generator Tube Failures" i
21. 2/97 9703100272 NUREG/CP-0154," Proceedings of the l CNRA/CSNI Workshop on Steam Generator  !

Tube Intergrity in Nuclear Power Pl ants"

22. 3/92 9301150097 Report of Nuclear Safety Commission on,

" Steam Generator Tube Break at Mihama Electric Power co., Inc. Occurred on 2/9/91

23. 3/13/91 9104230317 Memo to the Commission, Subject; Ministry of International Trade & Industry Investigation into the Mihama Event
24. 2/14/91 9104230308 Memo to the Commission,

Subject:

Kansai Mihama Unit 2 Event (2/9/91)

25. 11/91 9301150119 Report, " Final Report on Steam Generator Tube Break at Mihama Unit Two of Kansai E!ectric Power Co., Inc. Occurred on 2/9/91 i

l l

l

a0 4

FOIA-97-488 APPENDIX B RECORDS BEING RELEASED IN THEIR ENTIRETY l (If copyrighted identify with *)

N_0_ DATE DESCRIPTIONHPAGE COUNT) l

1. Undated Court of Arbitration of the International Chamber of Commerce, Furnas Centrais Electricas, S.A., Claimant, v. Westinghouse Electric Corporation l ICC Case No. 6320/Cl (135 pages) 2
2. 8/25-29/91
  • Proceedings, Fifth International Symposium on Environmental l

, Degradation of Materials in Nuclear Power Systems - Water Reactors (86 i pages) i I I

3. Undated India: Regulating Agency (24 pages) f 4. Undated 3 Steam Generators - French (4 pages)
5. Undated German Experience in Steam Generator Maintenance and Repair (19
pages)
6. 2/2/78 Review of Russian Papers (84 pages)
7. Undated Appendix B, Extended Information from U.S. NRC Resporm includes Responses from Questions 1E and 2B (7 pages)
8. Undated Ringhals 3 and 4 Steam Generators hevised Plugging Criteria for Roll Transition Area, Theoretical Analysis (29 pages)
9. Undated Alloy 600 Primary Water SCC, A User's (Belgian Electricity Board) Point of View (22 pages)
10. Undated Application of Probabilistic Fracture Mechanics to Estimate the Risk of Rupture of PWR Steam Generator Tubes (12 pages)
11. Undated Safety Significance of Steam Generator Tube Degradation Mechanisms (8 pages) i
12. Undated Tube Plugging Criteria for Axial and Circumferential Cracks in the Tubasheet Area (13 pages)
13. Undated Swedish Experiences of a Revised Plugging Criterion for Steam Generator Tubes - A Regulatory View ( 7 pages)

. l

14. Undated Regulatory Practices and Experiences on Steam Generators - CNRA '

Special Issue Meeting, Paris, June 25-26,1992, Swedish Presentation (3 pages)

15. Undated Steam Generator Tube Cracks at Dampierre 1 EDF PWR Plant impact on Plant Safety (16 pages) l l

i 16. Undated Stability Analysis of a Cracked Steam Generator Tube, G/F 4/4 (7 pages)

17. Undated integrity Analysis of Cracked Steam Generator Tubes, G 6/5 (5 pages) 1 l \

! 18. Undated NDE Qualification Methodology: A Combined Effort (7 pages) i j 19. Undated Steam Generator Tubes, LBRB Studies (2 pages) l

20. Undated Session 4.7, Characteristics of Roll Transition Cracks in Steam Generator l Tubes (8 pages) )
21. Undated Steam Generator Secondary Side Corrosion Problems in DOEL 4 (6 i pages)
22. Undated Nickel Electroplating as a Remedy to Steam Generator Tubing PWSCC (8 l pages)

I l 23. Undated is OD Peening of Alloy 800 SG Tubes Desirable? (8 pages) l

24. Undated SCC Testing of Steam Generator Tubes Repaired by Welded Sleeves (8 pages) l 25. Undated Synthesis of the Belgian Experience in Nickel Electroplating of Steam l Generator Tubes (14 pages)
26. Undated Validation of Leak Before Break Analysis for Steam Generator Tubes (7 Pages)
27. 3/92 On the Steam Generator Tube Break at Mihama Unit No. 2 of the Kansai Electric Power Co., Inc. (82 pages)
28. 5/96 Advanced ECT Probe for Steam Generator Tube inspection (3 pages)
29. 5/22-23/96 The Ninth Regular Meeting on Nuclear Safety Regulatory Matters Between NRC and MITI, Japanese Side Presentation (4 pages) l 30. 5/22-23/96 The Ninth Regular Meeting on Nuclear Safety Regulatory Matters l Between USNRC and MITI, Stats of High Burnup Fuel (13 pages) l 31. 12/3/96 Fax to Ornstein from Kishida (5 pages) l l

1

! I

! 1

4

32. 7/31/90 Memo for J Lee from C Cheng,

Subject:

Allegation Review - Furnas .

(Brazil) Lawsuit Against Westinghouse (1 page)

33. 11/94 ORNL/NRC/LTR-94/40,

Subject:

Leakage Monitoring Assessment Support for Steam Generator Rule Making (26 pages) ' '

34. 6/15/94 Press Release Information, Manual Shutdown of Unit 1 of the Mihama Nuclear Power Station, Kant,ai Electric Power Company (2 pages)
35. 3/27/91 Memo for E Jordan et al., from J Shea,

Subject:

Kansai's Mihama Unit-2 Event (2/9/91) (55 pages)

36. 7/18/97 Memo to E Sullivan from G Hornseth et al.,

Subject:

Trip Report - May Meeting with Ontario Hydro, in Toronto, Canada to Discuss Canadian

, Experiences with Electrosleeves (2 pages)

. . . - . -.. .. _ - - . _ - . . _. ..

Retrieved from "https://kanterella.com/w/index.php?title=ML20155F315&oldid=3348625"