Letter Sequence Approval |
|---|
|
Results
Other: ML19332D159, ML20058L182, ML20058L189, ML20101T359, ML20148L774, ML20148T448, ML20150E134, ML20154E847, ML20196E495, ML20206G334, ML20207D534, ML20210D237, ML20210G847, ML20211P569, ML20212C878, ML20212J766, ML20235C993, ML20235J455, ML20237L002, ML20244B799, ML20245B632, ML20245H985, ML20247C762, ML20247Q189
|
MONTHYEARML20101T3591985-01-31031 January 1985 Forwards Implementation Schedule for Detailed Control Room Design Review,In Response to Generic Ltr 82-33,Suppl 1 to NUREG-0737.Safety Significance Rankings of Human Engineering Deficiencies & short-term Corrective Actions Encl Project stage: Other ML20108D7451985-02-14014 February 1985 Forwards Safety Evaluation & Technical Evaluation Rept Based on Review of 840629 Detailed Control Room Design Review Summary Rept,Per Suppl 1 to NUREG-0737.Supplemental Rept Addressing Items Identified in Safety Evaluation Requested Project stage: Approval ML20112F6631985-03-22022 March 1985 Responds to NRC Re Schedule for Submitting Supplemental Summary Rept for Detailed Control Room Design Review & Status of Special Studies.Addl Info Will Be Discussed During Preimplementation Audit in Late Apr 1985 Project stage: Supplement ML20077D2221985-10-28028 October 1985 Forwards Outline of Submittal to NRC Summarizing 851009 post-audit Meeting Re Dcrdr Project stage: Meeting ML20214E3081986-02-28028 February 1986 Forwards Descriptions of Safety Significant Human Engineering Discrepancies (Heds) Identified During Dcrdr,Per Commitments Made in Util Comments on Draft Ser.Justification for Heds That Will Not Be Addressed Also Encl Project stage: Draft Other ML20209E9881986-09-0202 September 1986 Application for Amends to Licenses NPF-2 & NPF-8,changing Snubber Surveillance Requirements to Increase Allowable Time Interval Between Visual Surveillances When Snubber Sys Operating at High Level of Dependability.Fee Paid Project stage: Request ML20214D2161986-11-18018 November 1986 Notification of 861120 Meeting W/Util,Southern Co Svcs,Inc & Bechtel in Bethesda,Md to Discuss Proposed Change to Tech Specs Re Snubber Surveillances Project stage: Meeting ML20207D5031986-12-19019 December 1986 Application for Amends to Licenses NPF-2 & NPF-8,revising Tech Specs to Authorize Repair of Steam Generator Tubes W/Indications of Degradation as Alternative to Tube Plugging.Fee Paid Project stage: Request ML20236S4401986-12-30030 December 1986 Summary of 861120 Meeting W/Util Re Proposed Tech Spec Changes to Snubber Surveillance Insp Intervals Project stage: Meeting ML20207D5341986-12-31031 December 1986 Proposed Tech Specs Authorizing Repair of Steam Generator Tubes W/Indications of Degradation as Alternative to Tube Plugging Project stage: Other ML20212J7661987-01-13013 January 1987 Requests Relief from ASME Code,Section XI,1974 Edition Through Summer 1975 Addenda,Table IWB-2600,Item B3.2 & Table IWB-2500,Category B-D,permitting Visual Exam of Each Steam Generator Primary Side Nozzle.Fee Paid Project stage: Other ML20210F8011987-02-0909 February 1987 Application for Amends to Licenses NPF-2 & NPF-8,changing Tech Specs Re Snubber Surveillance Requirements.Request Suppls 860902 Tech Spec Submittal by Providing Requested Revised Proposed Snubber Visual Insp Schedule.Fee Paid Project stage: Request ML20210G8471987-02-0909 February 1987 Proposed Tech Specs,Incorporating Revised Proposed Snubber Visual Insp Schedule Project stage: Other ML20211P5001987-02-25025 February 1987 Application to Amend Licenses NPF-2 & NPF-8,revising Tech Specs to Allow Snubber Failures to Be Expressed as Percentage of Specific Snubber Population in New Snubber Visual Insp Schedule Project stage: Request ML20147F5041987-02-25025 February 1987 Forwards Comments on Licensee Training Performance During Period of INPO Accreditation Effort.Certification of Licensed Operator Training Program Encl Project stage: Request ML20211P5691987-02-25025 February 1987 Proposed Tech Specs Re Snubber Surveillance Requirements & Visual Insp Schedule Project stage: Other ML20212C8781987-02-27027 February 1987 Forwards Info Re Plant Snubbers,Including Date of Failures & Current safety-related Snubber Population Project stage: Other ML20206G3341987-03-30030 March 1987 Amends 69 & 61 to Licenses NPF-2 & NPF-8,respectively, Modifying Tech Specs Re Visual Insp Requirements for Snubbers on one-time Basis Project stage: Other ML20206G3561987-03-30030 March 1987 Safety Evaluation Supporting Amends 69 & 61 to Licenses NPF-2 & NPF-8,respectively Project stage: Approval ML20210D2371987-04-27027 April 1987 Requests That Proprietary Rev 1 to WCAP-11178, Steam Generator Sleeving Rept (Mechanical Sleeves), Be Withheld (Ref 10CFR2.790).Affidavit for Withholding Encl Project stage: Other ML20210D2281987-05-0404 May 1987 Revised Application for Amends to Licenses NPF-2 & NPF-8, Changing Tech Specs Re Repair of Steam Generator Tubes W/ Indications of Degradation.Ra Wiesemann & Revs 1 to WCAP-11179 & Proprietary WCAP-11178 Also Encl Project stage: Request ML20235K4211987-07-0808 July 1987 Forwards Safety Evaluation Granting Relief from ASME Section XI Volumetric Exam Requirements for Steam Generator Nozzle Inside Radiused Sections.Requirements Impractical & Alternative Methods Acceptable Project stage: Approval ML20235K4441987-07-0808 July 1987 Safety Evaluation Supporting Granting Licensee Relief from Volumetric Exam of Steam Generator Primary Side Noozles Inside Radiused Sections Project stage: Approval ML20235J4551987-07-10010 July 1987 Forwards Section 2.3 of Proprietary Version WCAP 11178,Rev 1 & Nonproprietary Version WCAP 11179,Rev 1 of Rept Applicability. Section Discusses Steam Generator Tube Repair.Encl for Insertion Into 870504 Tech Spec Change Project stage: Other ML20237L0021987-08-25025 August 1987 Forwards Replacement Pages for Proprietary Rev 1 to WCAP 11178 & Nonproprietary Rev 1 to WCAP 11179 Re Steam Generator Tube Repair & Tubesheet Region Plugging Criterion. Proprietary Pages Withheld (Ref 10CFR2.790) Project stage: Other ML20235C9931987-09-18018 September 1987 Amends 72 & 63 to Licenses NPF-2 & NPF-8,respectively, Revising Tech Spec 3/4.4.6 to Allow Use of Approved Steam Generator Tube Sleeving Technique in Lieu of Plugging Defective Tubes Project stage: Other ML20148T4481988-01-28028 January 1988 Proposed Revs to Tech Specs,Deleting Surveillance Requirement 4.4.10.1.2 & Table 4.4-5 Re Surveillance Specimen Withdrawal Times.Related Info Encl Project stage: Other ML20148L7741988-03-29029 March 1988 Requests Relief from Requirements of Second 10-yr Interval Inservice Testing Program for ASME Class 1,2 & 3 Pumps & Valves to Enable Use of Valve Disassembly & Installation of Instrumentation as Acceptable Test Alternatives Project stage: Other ML20150F3341988-03-30030 March 1988 Grants Revised Interim Approval for Reliefs for Inservice Testing Program for Second 10 Yr Interval Until NRC Final Action & Safety Evaluation Issued.Agrees That Remaining Two Valves Do Not Need to Be Included in Subj Program Project stage: Approval ML20154C9651988-05-12012 May 1988 Safety Evaluation Re Flaw Indications in Reactor Pressure Vessel Project stage: Approval ML20154C9601988-05-12012 May 1988 Forwards Safety Evaluation Re Util 880428 & 0505 Submittals of Results of Inservice Insp Exam.Flaw Indications Conditionally Acceptable for Svc.Augmented Inservice Insp Required During Next Three Insp Periods,Per ASME Code Project stage: Approval ML20154H9341988-05-20020 May 1988 Application for Amends to Licenses NPF-2 & NPF-8,retaining Portion of Paragraph 4.4.10.1.2 Which Reiterates 10CFR50, App H Requirement That Reactor Vessel Matl Irradiation Surveillance Specimens Shall Be Removed & Examined Project stage: Request ML20154L9331988-05-26026 May 1988 Application for Amends to Licenses NPF-2 & NPF-8,revising Ref of Senior Vice President to President - Nuclear to Reflect Organizational Titles Project stage: Request ML20196E4951988-06-22022 June 1988 Requests Exemption from Program Update Requirements of 10CFR50.55a(g)(4)(ii).Proposes to Update Unit 2 Program to ASME Code 1983 Edition Rather than Update Program to Code of Record on 910731 Project stage: Other ML20150E1341988-06-29029 June 1988 Submits Resolution Schedule for Human Engineering Discrepancy Identified as Part of 1984 Dcrdr.Based on Review of Hed 3.1.037, Annunciators W/Input from More than One Parameter, 14 of 207 Annunciators Should Be Modified Project stage: Other ML20207G1781988-08-18018 August 1988 Forwards Environ Assessment & Finding of No Significant Impact Re 880622 Request for Exemption from Certain 10CFR50.55a(g)(4)(ii) Requirements Project stage: Approval ML20154E8471988-09-0909 September 1988 Forwards Proposed Schedules for Completion of Licensing Items,Including Prioritized Listing of License Amend & Other Requests & Listing of NRC-related Submittals Project stage: Other ML20247C7621989-03-23023 March 1989 Forwards Rev 0 to FNP-2-M-068, Updated Inservice Insp Program for ASME Code Class 1,2 & 3 Components, Per NRC 890320 Conference Call Request.Addl Component Sketches Also Encl Project stage: Other ML20244B7991989-06-0808 June 1989 Proposes Listed Schedule for Completion of NRC Review of Util 881216 Updated Inservice Insp Program for ASME Code Class 1,2 & 3 Components.Approx 2 Yrs Left to Complete Remaining Exam Requirements Project stage: Other ML20245B6321989-06-19019 June 1989 Forwards Proposed Schedules for Submission & Requested Completion of Licensing Items Project stage: Other ML20245H9851989-08-0303 August 1989 Requests Responses to Encl Questions Re Requests for Relief from ASME Code Requirements of Second 10-yr Inservice Insp within 45 Days of Ltr Receipt Project stage: Other ML20247Q1891989-09-21021 September 1989 Advises That Util Will Submit Response to Inel Questions Re Inservice Insp Programs by 891006 Project stage: Other ML19332D1591989-11-22022 November 1989 Clarifies Util 880629 Submittal Re Schedule for Corrective Actions to Resolve 378 Hed Items Re Dcrdr Program Project stage: Other ML20058L1821990-08-0101 August 1990 Forwards Davis-Besse Dcrdr Human Engineering Discrepancy Repts 1988 Summary Addendum 1,Vol 1, Per NRC Audit Team Request Project stage: Other ML20058L1891990-08-0101 August 1990 Dcrdr Human Engineering Discrepancy Repts 1988 Summary Addendum 1,Vol 1 Project stage: Other 1987-07-08
[Table View] |
Text
E "M
0 3 1987 Docket Nos. 50-348 DISTRIBUTION:
and 50-364 Docket File E. Jordan NRC & Local PDRs J. Partlow Mr. R. P. Mcdonald PD21 r/f ACRS (10)
Senior Vice President S. Varga G. Johnson Alabama Power Company G. Lainas ARM /LFMB 1
Post Office Box 2641 E. Adensam GPA/PA j
Birmingham, Alabama 35291-0400 P. Anderson T. Barnhart (4) i E. Reeves (L)
T. Murley/
J. Sniezek
Dear Mr. Mcdonald:
OGC-B F. Miraglia
Subject:
Relief from ASME Section XI Volumetric Examination Requirements for Steam Generator Nozzle Inside Radiused Sections -
Joseph M. Farley Nuclear Plant, Units 1 and 2 (TACS 64435/64436)
By letter dated January 13, 1987, you requested additional relief from the volumetric examination requirements of ASME Code Class 1, 2 and 3 components.
l The specific relief requested is from the volumetric examination of the steam l
generator primary side nozzle inside radiused sections (Item No. B3.2, l
Category B-D).
I We previously granted certain reliefs for Unit 1 and 2 requirements, which you requested pursuant to 10 CFR 50.55a(g) in our letters dated December 7, 1979, August 24, 1983, February 10, and March 30, 1984 (one-time relief),
January 10, and December 27, 1985, June 19, and November 17, 1986.
This request, also pursuant to 10 CFR 50.55a(g), is for relief from ASME Code Section XI, as noted above. The enclosed Safety Evaluation delineates the relief, which we hereby grant to allow use of an alternate examination.
l l
The staff has determined that where stated the ASME Code requirements are impractical, the alternative methods to be performed will provide adequate assurance of the structural integrity of the components evaluated, and pur-suant to 10 CFR 50.55a(a)(3) and 10 CFR 50.55a(g)(6)(i) the grariting of this I
relief is authorized by law and will not endanger life or property or the common defense and security, and is otherwise in the public interest.
In l
making this determination, we have given due consideration of tie burden that could result if these requirements were imposed on your facility.
The request for relief complies with the standards and regulations of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules l
l l
8707160309 070703 PDR ADOCK 0500 0
P
Mr. R.P. Mcdonald and regulations. The Commission has made appropriate findings as required by the Act and the Commission's rules and regulations in 10 CFR Chapter I.
A copy of our Safety Evaluation for granting of the relief is enclosed.
Sincerely, Original Signed By Ober G.iide;s m Elinor G. Adensam, Director Project Directorate II-1 Division of Reactor Projects I/II
Enclosure:
As stated cc: w/ enclosure:
See next page
)h hllN)/
'$il
LA./
- D PI M:
1:DRPR *0GC
PAnderson EReev.es/ds f RFonner EAdensam
/Q/87 87 6/29/87 7/01/87
i
"'.l03 E7 Docket Nos. 50-348 DISTRIBUTION:
e and 50-364 Docket File E. Jordan NRC & Local PDRs J. Partlow Mr. R. P. Mcdonald PD21 r/f ACRS (10)
Senior Vice President S. Varga G. Johnson Alabama Power Company G. Lainas ARM /LFMB Post Office Box 2641 E. Adensam GPA/PA Birmingham, Alabama 35291-0400 P. Anderson T. Barnhart (4)
E. Reeves (2-)
T. Murley/
J. Sniezek OGC-B
Dear Mr. Mcdonald:
F. Miraglia
Subject:
Relief from ASME Section XI Volumetric Examination Requirements for Steam Generator Nozzle Inside Radiused Sections -
Joseph M. Farley Nuclear Plant, Units 1 and 2 (TACS 64435/64436)
By letter dated January 13, 1987, you requested additional relief from the volumetric examination requirements of ASME Code Class 1, 2 and 3 components.
The specific relief requested is from the volumetric examination of the steam generator primary side nozzle inside radiused sections (Item No. B3.2, Category B-D).
We previously granted certain reliefs for Unit 1 and 2 requirements, which you requested pursuant to 10 CFR 50.55a(g) in our letters dated December 7, 1979, August 24, 1983, February 10, and March 30, 1984 (one-time relief),
January 10, and December 27, 1985, June 19, and November 17, 1986.
This request, also pursuant to 10 CFR 50.55a(g), is for relief from ASME Code Section XI, as noted above. The enclosed Safety Evaluation delineates the relief, which we hereby grant to allow use of an alternate examination.
The staff has determined that where stated the ASME Code requirements are impractical, the alternative methods to be performed will provide adequate assurance of the structural integrity of the components evaluated, and pur-suant to 10 CFR 50.55a(a)(3) and 10 CFR 50.55a(g)(6)(1) the granting of this relief is authorized by law and will not endanger life or property or the common defense and security, and is otherwise in the public interest.
In making this determination, we have given due consideration of the burden that i
could result if these requirements were imposed on your facility.
The request for relief complies with the standards and regulations of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules
Mr. R.P. Mcdonald.
and regulations. The Comission has made appropriate findings as required by the Act and the Commission's rules and regulations in 10 CFR Chapter I.
A copy of our Safety Evaluation for granting of the relief is enclosed.
Sincerely, N
WW Elinor G. Adensam, Director Project Directorate 11-1 Division of Reactor Projects I/II
Enclosure:
As stated cc: w/ enclosure:
See next page
l Mr. R. P. Mcdonald Alabama Power Company Joseph M. Farley Nuclear Plant cc:
Mr. W. O. Whitt D. Biard MacGuineas, Esquire Executive Vice President Volpe, Boskey and Lyons Alabama Power Company 918 16th Street, N.W.
Post Office Box 2641 Washington, DC 20006 Birmingham, Alabama 35291-0400 Charles R. Lowman Mr. Louis B. Long, General Manager Alabama Electric Corporation Southern Company Services, Inc.
Post Office Box 550 Post Office Box 2625 Andalusia, Alabama 36420 Birmingham, Alabama 35202 Chai rman Regional Administrator, Region II Houston County Commission U.S. Nuclear Regulatory Commission Dothan, Alabama 36301 101 Marietta Street, Suite 2900 Atlanta, Georgia 30303 Ernest L. Blake, Jr., Esquire Shaw, Pittman, Potts and Trowbridge Claude Earl Fox, M.D.
2300 N Street, N.W.
State Health Officer Washington, DC 20037 State Department of Public Health l
State Office Building Montgomery, Alabama 36130 i
Robert A. Buettner, Esquire l
Balch, Bingham, Baker, Hawthorne, Mr. J. D. Woodard l
Williams and Ward General Manager - Nuclear Plant i
Post Office Box 306 Post Office Box 470 l
Birmingham, Alabama 35201 Ashford, Alabama 36312 Resident Inspector U.S. Nuclear Regulatory Commission Post Office Box 24 - Route 2 Columbia, Alabama 36319 I
l l