Letter Sequence Meeting |
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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
ML20210G8471987-02-0909 February 1987
Proposed Tech Specs,Incorporating Revised Proposed Snubber Visual Insp Schedule
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
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
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
ML20212C8781987-02-27027 February 1987
Forwards Info Re Plant Snubbers,Including Date of Failures & Current safety-related Snubber Population
Project stage: Other
ML20206G3561987-03-30030 March 1987
Safety Evaluation Supporting Amends 69 & 61 to Licenses NPF-2 & NPF-8,respectively
Project stage: Approval
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
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
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
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
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
ML20058L1891990-08-0101 August 1990
Dcrdr Human Engineering Discrepancy Repts 1988 Summary Addendum 1,Vol 1
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
1987-07-08
[Table View] |
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ESSEX rJc October 28, 1985 g jg
&SS.f5 Mr. Al De Agario U.S.
Nuclear Regulatory Commission 7920 NorfoIk Avenue Bethesda, Maryland 20814
Subject:
Davis-Btsse Nuclear Power Station DCRDR: follow-up on post avdii r4
Dear Al:
Ric h Morrison csked me to send you this. outline for loledo Edison's report summarising the presentation made at the 10/9/85 meeting.
If you have any questions or commtnts, if probably would be best to contact Rich at Davis-Besse (419/249-5000, X-692) or Jacque Lingenfelter, it is planned that the report will go out from Davis-Besse tomorrow evening.
I will also be glad to answer any questions or provide any further information that may be helpful.
Sincerely, e>-~
.i _,. (,., 7' i,
Barbara Paramore Program Manager Attachment ESSEX COR PO H ATION
- 333 North Fairfax Street. Alexandria, VA 22314 2691 * (703)548-4500 Telex 90-1901
910'3290039 831028 q
Pon
- cr zooos4e P
PDR D
p*v TOLEDO EDISON j
DAVIS-BESSE NUCLEAR POWER S1ATION OUTLINE OF SUBMITTAL TO NRC SUMMARIZING 10/9/85 MLE11NG 1.
Response to findings and recommendations in DCRDR sudit report:
a.
Present status of DCRDR b.
Specific DCRDR deficiencies (nine requirements identified in NUREG-0737, Supplement 1) c.
Near term programs:
Systems Review and Test Program and its coordination with the DCRDR
- Fixes prior to restart (including hardware, prucedural, and other changes)
Continuation of DCRDR work in preparation for the the 1986/87 outage (special study schedule, specification of HED corrections for implementation, plan for implemen-tation of paint-tape-label solutions) d.
Longer term programs Role of human factors in ongoing FCR process Close-out of the DCRDR project.
2.
Role of human factors in the overall Course of Action program pursuant to the June 9 event at Davis-Besse Notes:
The Totedo Edison report is scheduled to be sent to the NRC human factors staff on Tuesday 10,29/85.
Tim 0'Donahue.of SAIC prepared a draft report on the meeting for submittal to Ray Ramirez on Friday 10/25/85.
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