Letter Sequence Request |
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Results
Other: ML19309H811, ML19318B896, ML20008E295, ML20010E854, ML20027D213, ML20038B135, ML20038B146, ML20039C398, ML20039C401, ML20039C419, ML20040H025, ML20069L742, ML20069L752
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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 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 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 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 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 ML20069L7521982-11-0808 November 1982 Notice of Issuance & Availability of Amends 66 & 71 to Licenses DPR-24 & DPR-27,respectively Project stage: Other ML20069L7481982-11-0808 November 1982 Safety Evaluation Supporting Amends 66 & 71 to Licenses DPR-24 & DPR-27,respectively Project stage: Approval 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 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 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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q Westinghouse ta oepanrnent Electric Corporation
.a NW -6 ra 1 westinghouse Buitaing Gateway Center PittsburghPennsylvania 15222 P. O. Box,355 Pittsburgh, PA 15230 (412) 373-4558 Peter B.
Bloch, Esq., Chairman May 3, 1982 Atomic Safety and Licensing Board Panel N
U.
S. Nuclear Regulatory Commission f
D Washington, D.C.
20555 d'
Re:
Wisconsin Electric Power Company gr [
Point Beach Nuclear Plant, Units 1 and 2 Docket Nos. 50-265-OLA and 50-301-OLA
+
gr
Dear Judge Bloch:
/y'~
Westinghouse Electric Corporation has studied caref briefs submitted in the above-captioned proceeding reg the nature of balancing tests demanded by 10 CFR S2.790 as applied to the facts of this case.
The brief submitted by Wisconsin's Environmental Decade, Inc.
(Decade) raises again points which the parties other than Decade have anticipated, faced, and rebutted in their testimony and briefs.
Therefore, Westinghouse will not file a Reply Brief in response to the Decade Brief.
We again respectfully call to the Board's attention that Westinghouse has requested the Board plan and order a view of the Westinghouse research and testing facilities in Pittsburgh as it relates to this issue.
Very truly yours, l
~
Francis X. Davis Attorney for Westinghouse Electric Corporation, l
Appearing Specially l
FXD:mjl cc:
Service List l
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8205070227 920503 DRADOCK05000$I O
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. SERVICE LIST Wisconsin Electric: Power Company.
(Point Beach Nuclear Plant, Units 1 and 2)
Peter B. Bloch, Chairnan Atomic Safety & Licensing. Appeal Board Administrativ.e Judge U.S. Nuclear Regulatory Commission Atomic Safety & Licensing Board Panel Washington, D.C.
20555 U. S. Nuclear Regulatory Commission Washington, D.C.
20555 Atomic Safety & Licensing Board Panel U.S. Nuclear Regulatory Commission Dr. Hugh C..Paxton Washington, D.C.
20555 Administrative Judge 1229 - 41st Street Docketing and Service Section Los Alamos, New Mexico 87544 Office of the Secretary (3 copies)
'U.S. Nuclear R.egulatory Commission Dr. Jerry R. Kline Washington, D.C.
20555 Administrative Judge.
Atomic Safety & Licensing Board Panel Bruce Churchill, Esq.
U.S. Nuclear Regulatory Commission Lisa Ridgway, Esq.
Washington, D.C.
20555 Gerald Charnoff, Es'q.
Shaw, Pittman, Potts & Trowb' ridge Kathleen M. Falk, Esq.
1800 M Street N.W.
Wisconsin's Environmental Decade Washington, D.C.
2003.6 114 North Carroll Street Madison, Wisconsin 53703 Barton Z. Cowan, Esq.
John R. Kenrick, Esq.
Richard Bachmann, Esq,.
Eckert, Seamans, Cherin & Mellott.
Stuart A. Treby, Esq.
42nd Floor, 600 Grant Street Office of the Executive Legal Director Pittsburgh, PA 15219 U.S. Nuclear Regulatory Commission Washington, D.C.
20555 Francis X. Davis, Esq.
Westinghouse Electric Corporation, Appearing Specially P. O. Box 355 Pittsburgh, PA 15230 e
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