ML17338A639

Forwards Results of Seismic Reanalysis for Reactor Coolant Loop,Pressurizer Surge Line & Pressurizer Spray Line. Concludes Results Are Essentially Unchanged from FSAR

ML17338A639
Person / Time
Site:	Turkey Point
Issue date:	04/12/1979
From:	Anderson T WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
To:	Case E Office of Nuclear Reactor Regulation
Shared Package
ML17338A638	List: ML17338A637 ML17338A639
References
NS-TMA-2066, NUDOCS 7904160162
Download: ML17338A639 (8)

Text

Yi'estingh ouse'i";ctric Corporation Water Reactor Divisions 0 PVN Sysiems 0;"rem Box 355 Pil t&~l gh Paasy"re'315230 April 12, 1979 NS-TMA-2066 Edson G.Case Deputy Director Office of Nuclear Reactor Regulation U.S.Nuclear Regulatory Commission 7920 Norfolk Avenue Bethesda, Maryland 20014

Dear Mr.Case:

TURKEY POINT SEISMIC ANALYSIS At: the request of Florida Power and Light, a detailed file search was conducted of piping analyses performed by'Westinghouse for the Turkey Point Units.Three anaylses were performed by Aestinghouse including a seismic analysis of the reactor coolant loop, the pressurizer surge line, and the pressurizer spray line.The analysis of the loop was performed using the algebraic summation technique for intramodal responses.

The analyses of the pressurizer surge and spray lines were performed using the absolute summation technique.

I C/A reanalysis of the Turkey, Point loop has been performed incorpor-ating the absolute, summation of intramodal responses.

The results are presented in the attached table.The results from the previous analysis, which were reported in Revision 9 of the FSAR, page 5A-20, are also shown for comparison.

As with the original analysis, both horizontal and vertical components of the seismic response spectrum were input simultaneously.

Two different directions of the horizontal component were chosen and the results reported were for the most severe loading condition.

As can be seen from the table, the magnitude of the stresses are essentially unchanged, and stresses are well below allowables.

The method of combination has little effect on the pipe stresses due to the lack of coupling between the horizontal and vertical modes of the v 904160 l6%

Mr.Edson G.Case-2-April 12, 1979 main loop piping.The results of this comparison were reported to Florida Power and Light on April 12, 1979.V truly y rs, r T., M.Anderson, Manager Nuclear Safety COMPARISON OF SEISMIC STRESSES Location Maximum Stress, si Previous.Analysis Reanalysi s Reactor Coolant Pump Inlet Reactor Coolant Pump Outlet 10 Inch Accumulator Line Steam Generator Outlet Reactor Vessel Inlet Reactor Vessel Outlet Pressurizer Surge Line Connection Steam Generator Inlet 4085 3616 3201 2274 1289 182 78 71 4100 3700 3300 2300 1300 200 100 100 Maximum allowable seismic stress=13,125 psi I REGULATORY IN(RMATION DISTRIBUTION SYST (RIDS)ACCESSION NBR~7904160162 DOC~OATEN'9/00/12 NOTARIZED~NO DOCKET FACILe50 250 TURKEY POINT PLANT<UNIT 3F FLORIDA POWER AND LIGHT C 50"251, TURKEY POINT PLANTF UNIT 0F FLORIDA POWER AND LIGHT C 05000251 AUTH~NAME AUTHOR AFFILIATION ANDERSONF T~M~WESTINGHOUSE ELECTRIC CORP~REC IP~NAME RECIPIENT AFF IL IAT ION CASEFE~G~OFFICE OF NUCLEAR REACTOR REGULATION

SUBJECT:

FORWARDS RESULTS OF SEISMIC REANALYSIS FOR REACTOR COOLANT LOOP PRESSURIZER

'SURGE LINE 5 PRESSURIZER SPRAY LIPE, CONCLUDES RESULTS ARE ESSENTIALLY UNCHANGED FROM FSAR~DISTRIBUTION CODE: ASSIS COPIES RECEIYED:LTR

~ENCL L SIZE:~TITLE: GENERAL DISTRIBUTION FOR AFTER ISSUANCE OF OPERATING LIC NOTES: RECIPIENT ID CODE/NAME ACTION: 05 BC INTERNAL: 0 F ILF'1 I 5 15 CORE PERF BR 17 ENGR BR 19 PLANT SYS BR 21 EFLT TRT SYS EXTERNALS 03 LPDR 23 ACRS COP IES LTTR ENCL 7 7 1 1 2 2 1 1 1 1 1 1 1 1 1 ib 16 RECIPIENT ID CODE/NAME 02 NRC PDR 1.0 TA/EDO ie AO SYS/PROJ 18 RKAC SFTY BR 20 KEB 22 BR INKMAN OQ NSIC COPIES LTTR ENCL NAY pg yg TOTAL NUMBER OF COPIES REQUIRED: LTTR 38 ENCL 38 r PP RKcfy'Ip 0 cs QX'P**dt+i UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C.20555 OK4%3UM FOR: TERA Corp.FROM:

SUBJECT:

US i'/TIDC/Distribution Services Branch Special Document Handling Requirements 1.Please use the following special distribution list for the attached document.0 2.The attached document requires the following special considerations:

g Do not send oversi ze enclos.ure to the KtC PDR.g Only one oversize enclosure was received-please return for Regulatory File storage.Q Proprietary information

-send affidavit only to the NRC PDR ther: (specify)cc: DSB Files TTDC/DSB Authorized Signature Westinghouse Eiectric Corporation

~/pi.R<<~~~~~,p~~(~/7e.KWate f BeaCter gC.TlJ++~PYFRSYstems0NIkn Divisions...

Ri~Pi1tsbufghPtmnsylYaAIa 15230 April 12, 1979 NS-TMA-2066~Edson G.Case Deputy Director Office of'uclear Reactor Regulation U.S.Nuclear Regulatory Commission 7920 Norfolk Avenue Bethesda, Maryland 20014

Dear Mr.Case:

TURKEY POINT SEISMIC ANALYSIS At the request of Florida Power and Light, a detailed file search was conducted of piping analyses performed by llestinghouse for the Turkey Point Units.Three anaylses were performed by Westinghouse including a seismic analysis of the reactor coolant loop, the pressurizer surge line, and the pressurizer spray'iine.The analysis of the loop was performed using the algebraic summation technique for intramodal responses.

The analyses of the pressurizer surge and spray lines were performed using the absolute summation technique.

A reanalysis of the Turkey Point loop has been performed incorpor-ating the absolute summation of intramodal responses.

The results are presented in the attached table.The results from the previous analysis, which were reported in Revision 9 of the FSAR, page 5A-20, are also shown for comparison.

As with the original analysis, both horizontal and vertical components of the seismic response spectrum were input simultaneously.

Two different directions of the horizontal component were chosen and the results reported were for the most severe loading condition.

As can be seen from the table, the magnitude of the stresses are, essentially unchanged, and stresses are well below allowables.

The method of combination has little effect on the pipe stresses due to the lack of coupling between the horizontal and vertical=modes of the Hr.Edson G.Case April 12, 1979 main loop piping.The results of this'comparison were reported to Florida Power and Light on April 12, 1979.V truly y rs, r T;H.Anderson, Hanager Nuclear Safety COMPARISON OF SEISMIC STRESSES Location Maximum Stress, si Ptevious Analysis Reanalysis Reactor Coolant Pump Inlet Reactor Coolant Pump Outlet 10 Inch Accumulator Line Steam Generator Outlet Reactor Vessel Inlet Reactor Vessel Outlet Pressurizer Surge Line Connection Steam Generator Inlet 4085 3616 3201 2274 1289 182 78 71 4100 3700 3300 2300 1300 200 100 100 Maximum allowable seismic stress=13,125 psi