Letter Sequence Other |
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Results
Other: ML19211C502, ML19225C629, ML19241B277, ML19242B871, ML19257A933, ML19274F296, ML19337A164, ML19351E408, ML20003H527, ML20008E280, ML20010A331, ML20030B943, ML20126H318
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MONTHYEARML19241B2771979-07-11011 July 1979 Forwards Revision 1 to Rept on Reanalysis of Safety-Related Piping Sys. Seven Piping Supports Will Be Modified & Two New Supports Will Be Installed.Requests Authorization to Begin Interim Operation Until Refueling Project stage: Other ML19274F2961979-07-18018 July 1979 Forwards Revision 2 to Rept on Reanalysis at Safety- Related Piping Sys Project stage: Other ML19225C6291979-07-27027 July 1979 Forwards Revision 3 to Rept on Reanalysis of Safety-Related Piping Sys. Change Reflects up-to-date Reanalysis & Mod Program Project stage: Other ML19242B8711979-08-0707 August 1979 Forwards Revision 4 to Rept on Reanalysis of Safety-Related Piping Sys Project stage: Other ML19257A9331980-01-0303 January 1980 Advises That Baseplate Evaluations Per IE Bulletin 79-02 Revealed Two & One half-inch to six-inch Piping Designed for Loads Derived from SHOCK-2 Computer Calculations Project stage: Other ML19211C5021980-01-0303 January 1980 Submits Corrections to 790803 Rept on Seismic Reanalyses of Safety-Related Piping Sys, Revision 4.Nine Computer Problems Exist for Which SHOCK-II Run Is Run of Record for Some Pipe Supports.Reanalyzing Problem Project stage: Other ML19337A1641980-08-14014 August 1980 Forwards Responses to IE Bulletin 79-14 & Suppls 1 & 2, Seismic Analysis for As-Built Safety-Related Piping Sys. W/Completion of Mods,All Piping Sys Will Be Able to Perform Required Safety Functions During Seismic Event Project stage: Other ML19331C6601980-08-14014 August 1980 Interim Deficiency Rept Re Linear Indications in Gib Gusset Welds in Reactor Vessel Structural Support(Neutron Shield Tank).Metallographic Analysis of Weld Samples & Addl Insps Being Conducted.Next Rept Will Be Issued on 801101 Project stage: Request ML20008E2801980-10-20020 October 1980 Identifies Status of Activities Re IE Bulletin 79-14.All Physical Insp of Piping & QC Records Completed.All Piping Reanalyzed.Mods to Supports to Be Completed Before Startup. Requests Extension Until 810331 for Full Completion Project stage: Other ML19339A1831980-10-20020 October 1980 Amend 34 to License DPR-66,removing Nine Hydraulic Snubbers from Table 3.7-4 of Tech Specs Project stage: Request ML19351E4081980-11-0303 November 1980 Immediate Action Ltr 80-43:discusses Util 800814,0911 & 1020 Ltrs Re IE Bulletin 79-14.Enumerates Actions Taken or Planned by Util.Requests Response If Actions Differ from Actions Described Project stage: Other ML20126H3181981-03-31031 March 1981 Requests Extension Until 810407 for Submittal of Final Rept Re IE Bulletin 79-14, Seismic Analysis for As-Built Safety- Related Piping Sys. Addl Time Required for Review of Info Re Reanalysis Effort Supplied by Ae Project stage: Other ML20003H5271981-04-0707 April 1981 Submits Rept Re IE Bulletin 79-14, Seismic Analysis for As- Built Safety-Related Piping Sys. Rept Not Final Since Equipment Nozzle Info Is Incomplete.Vendor Responses Outstanding Project stage: Other ML20010A3311981-07-31031 July 1981 Requests 2-wk Extension to Satisfy Requirements of IE Bulletin 79-14,per .Util Awaiting Vendor Concurrence for Seven Components Project stage: Other ML20030B9431981-08-14014 August 1981 Submits Final Response to IE Bulletin 79-14, Seismic Analysis for As-Built Safety-Related Piping Sys. Nozzle Load Evaluations Complete & Required Mods Installed,Except for Two Items.Status of Equipment Nozzles Encl Project stage: Other 1980-10-20
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August 14, 1981 15219 United States Nuclear Regulatory Commission Office of Inspection and Enforcement
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Attn: Boyce H. Grier, Regional Director p
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Reference:
Beaver Valley Power Station, Unit No. 1 (h
Docket No. 50-334, Lic' me No. DPR-66 h
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IE Bulletin 79-14 f
Gentlemen:
This le'.;ter is to inform you of the status of the equipment nozzle load evaluations being performed as indicated in attachment B of our report dated April 7, 1981.
All the IEB 79-14 nozzle evaluations have been completed and the required modifications installed except for two items. The subject equipment and other pertinent information is shown on attachment A to this letter.
The vendor of item 1, the control room air conditioning evaporator coils, has informed us that they can not quantify the load carrying capacity of the i
nozzle connections.
Since the units have operated satisfactorily since the plant start up and the calculated loads and seismic contributor are small, we do not categorize this as a safety problem, and we do not intend to perform any modificat 2n.
Item No. 2, the redundant river water control room air conditioning coils are not required for safety reasons due to the presence ofethe two 100% air conditioning units, which are safety grade.
These coils are normally isolated from the river water system and will remain isolated until piping modifications are installed to assure the structural adequacy of the cooling coils.
This equipment will be modified by the end of the next refueling.
We have completed the review and reanalysis in compliance with IEB 79-14 and consider this our final submittal.
If you have any questions concerning this response, please contact my office.
Very truly yours, J. J. Carey Vice President, Nuclear Attachment T0108250232 810814 hY PDR ADOCK 05000334 u
PDR SI l
Beaver Valley Power Station, Unit No. 1 Docket No. 50-334, License No. DPR-66 IE Bulletin 79-14 Page 2 cc:
Mr. D. A. Beckman, Resident Inspector U.S. Nuclear Regulatory Commission Beaver Valley Power Station Shippingport, PA 15077 U.S. Nuclear Regulatory Commission c/o Document Management Branch Washington, DC 20555
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DUQUESNE LIGHT COMPANY j
Beaver Valley Power Station - Unit 1 i
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i ATTACHMENT A Status of Equipment Nozzles August 14, 1981 4
EQUIPMENT EQUIPMENT CALCULATED LOADS SEISMIC LOAD AMT. OF 1
NAME MK. NO.
NO. CONN.
FORCE LBS. MOMENT FT. LBS.,
CONTRIBUTION OVERLOAD COMMENTS 1.
Control Room VS-AS-1A 12 27 min 14 min 17% min N/A No vendor i
Air Conditioning VS-AS-1B 76 max 46 max 38% max allowables; 1 a s are Evap. Coil j
minimal i
2.
River Water VS-E-14A 6
123 min 110 min 10% min 65 to Add pipe i
Cooling Coils VS-E-14B 244 max 187 max 29% max f,00%
support l
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