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MONTHYEARML18113A9681979-03-30030 March 1979
Responds to NRC 790313 Show Cause Order.Dynamic Analysis of Affected Piping Involves Use of Original Amplified Response Spectra & Spectra Incorporating Soil Structure for Pipes Showing Overstress.W/Three Positions for Resolution of Order
Project stage: Request
ML18114A4301979-04-0202 April 1979
Notification of 790404 & 05 Meeting W/Va Electric & Power Co & S&W in Boston,Ma to Discuss Pipe Stress Analyses & Results of Hanger Evaluation Performed Up to Time of Meeting Date
Project stage: Request
ML18114A4441979-04-13013 April 1979
Forwards Update Rept on Plan for Verification of Dynamic Analysis Codes
Project stage: Request
ML18114A5921979-05-24024 May 1979
Submits Response to 790518 Request for Info Concerning Review of Methodology in Use of Oil Structure Interaction
Project stage: Request
IR 05000280/19790431979-08-0101 August 1979
IE Insp Repts 50-280/79-43 & 50-281/79-63 on 790718-20.No Noncompliance Noted.Major Areas Inspected:Const Status, Licensee Action on Previous Insp Findings,Nonconformance Rept Review & safety-related Work Activities
Project stage: Request
ML19208A8301979-08-22022 August 1979
Safety Evaluation of Results of Seismic Reanalysis of Pipe Stress.Reanalysis Indicates Stress & Equipment Loads Satisfy FSAR Allowables & manufacturer-specified Load Criteria.Plant May Resume Operation
Project stage: Approval
ML19208A8231979-08-22022 August 1979
Forwards NRC 790822 Order Lifting 790313 Order to Show Cause.Earlier Order Suspended Due to Reanalysis & Mod of Piping Deficiencies in safety-related Sys.Unit Can Withstand Seismic Event
Project stage: Other
ML19208A8291979-08-22022 August 1979
Orders Lifting of NRC 790313 Order to Show Cause.Licensee Has Completed Analysis & Mod of Pipe Support Sys.Public Health & Safety Does Not Require Continued Shutdown of Facility.Forwards SER
Project stage: Approval
ML20079P8701983-05-0404 May 1983
Application to Amend Licenses DPR-24 & DPR-27,consisting of Tech Spec Change Request 91 Re Limiting Conditions for Operation Requiring Both RHR Loops Be Operable Unless Reactor Sys Is in Refueling Shutdown Condition
Project stage: Request
ML20080J9901984-02-0606 February 1984
Requests Repeal of 791130 & 800103 Confirmatory Orders Re Provisions for Operation Pertaining to Steam Generator Tubes.Steam Generator Lower Assemblies Replaced
Project stage: Other
ML20081C1531984-03-0505 March 1984
Advises That,Due to Delays in Delivery & Installation of Auxiliary Safety Instrumentation Panels (Asips),Installation of Six Accident Monitors Addressed in NUREG-0737,Items II.F.1.1 Through II.F.1.6 Will Not Be Completed by 840630
Project stage: Other
ML20092N6521984-06-26026 June 1984
Advises That,Due to Delays in Final Fabrication & Delivery of Auxiliary Safety Instrumentation Panels,Per , Panels Will Be Delivered in Sequence Which Best Enables Installation to Proceed
Project stage: Other
ML20092P3341984-06-29029 June 1984
Lists Measures Implemented to Minimize Schedule Delays of post-TMI NUREG-0737,Items II.F.1.1 - 6,per 840626 Request, Including Timely QA Insps of Panel Welding & Detailed pre- Installation Plans & Preparation Procedures
Project stage: Other
ML13308A8541984-11-21021 November 1984
Advises That Commission Reviewed SECY-84-434 Re Restart of Facility.Order Dtd Aug 1982 Merely Suspended Authority to Operate Pending Mods to Facility & NRC Approval of Restart
Project stage: Other
ML20101M5831984-12-26026 December 1984
Confirms Position That Application for Amend to License Concerning Request for Mod of Dates Contained in Commission 830712 Confirmatory Order Unnecessary,Because of Ruling That Confirmatory Order Conditions Not License Conditions
Project stage: Request
ML20101M4101984-12-28028 December 1984
Informs That Accident Monitors Addressed by NUREG-0737,Items II.F.1.3 - II.F.1.6 Installed on Panels in Control Room, Powered by Interim Safety Grade Power Supplies & Accepted for Use by Plant Operations as of 841228
Project stage: Other
1983-05-04
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[
l%sconsin Electnc eowcacouranr 231 W. MICHIGAN, P.O. BOX 2046, MILWAUKEE, WI 53201 February 6, 1984 Mr.
H.
R.
Denton, Director Office of Nuclear Reactor Regulation U. S. NUCLEAR REGULATORY COMMISSION Washington, D.
C.
20555
Dear Mr. Denton:
DOCKET 50-266 REPEAL OF CONFIRMATORY ORDER FOR MODIFICATION OF LIs.SNSE POINT BEACH NUCLEAR PLANT, UNIT 1 During inservice inspections of the Point Beach Nuclear Plant Unit 1 steam generators performed during the August 1979 and October 1979 outages, eddy current and destructive examinations of steam generator tubes indicated intergranular attack and stress corrosion cracking originating from the secondary side of steam generator tubes within the tubesheet crevice.
Although Wisconsin Electric concluded that continued safe operation of Point Beach Unit 1 was not jeopardized, additional operating conditions were proposed to provide further assurance of the continued safe operation of Unit 1 in our letters dated November 23, Noveinber 29, and December 31, 1979.
These operating conditions were formally imple-mented for Point Beach Unit 1 in the NRC's Confirmatory Order for Modification of License dated November 30, 1979 and in the Order Modifying Confirmatory Order of November 30, 1979 dated January 3, 1980.
As you know, the Point Beach Unit 1 steam generator lower assemblies have bcen replaced during the current refueling and maintenance outage.
The integrity and design parameters of the steam generators have been or will be verified by the performance of shop, post-installation, and return-to-service tests and inspections as outlined in the Point Beach Nilclear Plant, Unit 1, Steam Generator Repair Report, Revision 1, dated March 1983.
Since the degraded Unit 1 steam generator lower assemblies have been replaced and the integrity and performance of the repaired steam generators will be verified prior to or during the course of returning to service, the provisions of the Confirmatory Order for Modification of License dated November 30, 1979 and the Order -
fl 8402150261 840206 "
M ADOCK 05000266
\\-
0 p
PM
,o Mr. H.
R.
Denton February 6, 1984 l-Modifying Confirmatory Order of November 30, 1979 dated January 3, 1980 are no longer appropriate.
In addition, those provisions from the Orders regarding reactor coolant sampling and~ primary system operating pressure have been incorporated into the plant Technical Specifications.
Accordingly, there is no longer any need for these Orders, and we request that they be formally rescinded.
Very truly yours, 0
i/
e O #
/
Vice President-Nuclear Power C. W. Fay Copy to NRC Resident Inspector
.
