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MONTHYEARML19309H8111980-05-0808 May 1980 Forwards IE Info Notice 80-20, Loss of Decay Heat Removal Capability at Davis-Besse Unit 1 While in Refueling Mode. No Response Required Project stage: Other ML19318B8961980-06-0505 June 1980 Responds to IE Bulletin 80-12, Decay Heat Removal Sys Operability. Plant Design Does Not Provide for Automatic Actuation of ECCS Recirculation or Automatic Positioning of Containment Recirculation Sump Valves Project stage: Other ML20008E2951980-10-14014 October 1980 Responds to NRC Re Proposed Tech Spec Changes for All Facilities to Provide for Redundancy in Decay Heat Removal Capability.Plant Specs Already Address Concerns & Require No Changes Project stage: Other ML20010E8541981-08-14014 August 1981 Requests That Proposed Tech Specs for Redundancy of Decay Heat Removal Capability in All Modes of Operation & Related Safety Analysis Be Submitted within 60 Days.Model Tech Specs to Assist in Preparation of Submittal Encl Project stage: Other ML20038B1351981-11-16016 November 1981 Tech Spec Change Request 72 for Amend to License DPR-24 & DPR-27,changing Tech Specs 15.3.1,15.3.3 & 15.3.8 to Ensure Redundancy of Decay Heat Removal Capability Under All Operating Conditions Project stage: Other ML20038B1461981-11-16016 November 1981 Proposed Tech Specs Sections 15.3.1,15.3.3. & 15.3.8 to Ensure Redundancy of Decay Heat Removal Capability Under All Operating Conditions Project stage: Other ML20039C4011981-11-18018 November 1981 Comments on Util Tech Spec Change Request 72,proposing Revision to Tech Spec 15.3.1.A.2(a) Re Redundancy of Decay Heat Removal Sys.Elimination of Decay Heat Removal Capability Above 350 F Inappropriate Project stage: Other ML20039C4191981-12-0909 December 1981 Interim Deficiency Rept DER 81-39 Re Unit 1.Gas Stripper by C-E Has Undocumented Section of Pipe & Welds in Violation of ASME Code,Initially Reported 811112.Evaluation & Final Rept Expected by 820129 Project stage: Other ML20039C3981981-12-21021 December 1981 Forwards Region 3 Comments Re Util Tech Spec Change Request 72 Project stage: Other ML20040H0251982-01-22022 January 1982 Informs That 811116 Proposed Amend to Tech Specs Re Establishment of Redundancy of Decay Heat Removal Capability During All Modes of Operation Is Unacceptable.Application Should Be Modified Project stage: Other ML20052D8061982-05-0303 May 1982 Advises That Westinghouse Will Not File Reply Brief in Response to Wi Environ Decade Brief.Svc List Encl Project stage: Request ML20052E9091982-05-0303 May 1982 Revised Application for Amend to Licenses DPR-24 & DPR-27 Consisting of Changes to Tech Specs to Provide Addl Assurance of Availability of Redundant Reactor Decay Heat Removal Capabilities Project stage: Request ML20052E9201982-05-0303 May 1982 Proposed Changes to Tech Specs to Provide Addl Assurance of Availability of Redundant Reactor Decay Heat Removal Capabilities Project stage: Request ML20027D2131982-07-31031 July 1982 Tech Spec for Redundant DHR Capability,Point Beach,Units 1 & 2 Project stage: Other ML20069L7481982-11-0808 November 1982 Safety Evaluation Supporting Amends 66 & 71 to Licenses DPR-24 & DPR-27,respectively Project stage: Approval ML20069L7521982-11-0808 November 1982 Notice of Issuance & Availability of Amends 66 & 71 to Licenses DPR-24 & DPR-27,respectively Project stage: Other ML20069L7421982-11-0808 November 1982 Amend 66 & 71 to Licenses DPR-24 & DPR-27,respectively, Upgrading Tech Specs to Provide Redundancy of DHR Capability in All Modes of Operation Project stage: Other ML20081D3121983-10-25025 October 1983 Application to Amend Licenses DPR-24 & DPR-27,changing Tech Spec 15.3.1.A to Eliminate Provisions Beyond Basis for Required Operational Components of Rcs.Class II Fee Encl Project stage: Request ML20081D3241983-10-25025 October 1983 Proposed Changes to Tech Spec 15.3.1.A Eliminating Provisions Beyond Basis for Required Operational RCS Components Project stage: Request ML20086M6131984-02-0202 February 1984 Safety Evaluation Supporting Amends 82 & 86 to Licenses DPR-24 & DPR-27,respectively Project stage: Approval ML20086M6031984-02-0202 February 1984 Amends 82 & 86 to Licenses DPR-24 & DPR-27,respectively, Clarifying Limiting Condition for Operation of Steam Generators & Other DHR Equipment,Indicating Conditions Only Applicable When Fuel Loaded in Core Project stage: Approval 1981-12-09
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Docket Nos. 50-528/529/530 50 55(e) Report O
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pgot,m, y,,o,.,, u m December 9, 1981 ANPP-19646-GHD/BSK U. S. Nuclear Regulatory Commission P-g Region V 9
Creekside Oaks Office Park 1450 Maria 1.ane - Suite 210 S
RECEIVED Walnut Creek, California 94596-5368 2
h "DEC2 81981b Attention:
Mr. B. H. Faulkenberry, Chief Reactor Construction and p
[7 Engineering Support Branch Tsi;
Subject:
Interim Report - DER 81-39 g
A 50.55(e) Potentially Reportable Deficiency Relating to Unit 1 Cas Stripper by CE Has Undocumented Section of Pipe and Welds In Violation of ASME Code File:
81-019-026 D.4.33.2
Reference:
Telephone Conversation between J. Eckhardt and G. Duckworth on November 12, 1981 Pear Sir:
The NRC was notified of the potentially reportable deficiency in the referenced telephone conversation. At that time, it was estimated that determination of reportability would be made within thirty (30) days.
Due to the extensive investigation and evaluation required, an Interim Report is attached.
It is now expected that this information will be finalized by January 29, 1982, at which time a complete report will be submitted.
Very truly yours 3
G.L MLR E. E. Van Brunt, Jr.
APS Vice President Nuclear Projects ANPP Project Director EEVBJr/GHD:skc Attachment cc: See Attached Page 2 g :} /j 's13-V*3
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U. S. Nuclear Regulatory Commission Mr. B. H. Faulkenberry, Chief ANPP-19646-CHD/BSK December 9,1981 Page 2 cc:
Victor Stello, Jr., Director i
U. S. Nuclear Regulatory Commission Office of Inspection and Enforcement Washington, D. C.
20555 J. A. Roedel D. B. Fasnacht G. C. Andognini F. W. Hartley J. M. Allen A. C. Rogers B. S. Kaplan W. E. Ide J. Vorees J. A. Brand A. C. Gehr W. J. Stubblefield W. C. Bingham R. L. Patterson R. W. Welcher R. M. Grant D. R. Hawkinson L. E. Vorderbrueggen Ms. Patricia Lee Hourihan 6413 South 26th Street Phoenix, Arizona 85040 Mr. Charles Ferguson Combustion Engineering 1000 Prospect Hill Road Windsor, Connecticut 06095 l
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INTERIM REPORT - DER 81-39 POTENTIAL REPORTABLE DEFlcir.NCY ARIZONA PUBLIC SERVICE COMPANY (APS)
PVNGS UNIT 1 I.
Potential Problem Bechtel Nonconformance Report N-A-558 was initiated to correct unacceptable welds on the Gas Stripper Unit supplied by Combustion Engineering. The defective welds were on a 2" pup piece between column nozzle and 4
to 3" reducer; however, when the N-5 Code Data Report was checked, it was discovered that the pup piece was not accounted for as material meeting the requirements of the ASME Code.
II.
Approach To and Status Of Proposed Resolution Bechtel has requested assistance from Combustion Engineering in evaluating and dispositioning this item.
III.
Projected Completion of Corrective Action and Submittal of the Final Report The evaluation and final report are forecast to be completed by January 29, 1982.
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