W3P85-1441, Forwards marked-up FSAR Pages 14.2-129 & 3.9-109,reflecting Change to Test Subsection 14.2.12.3.17, Piping Thermal Growth,Vibration & Shock, Allowing Evaluation of Piping Stresses in Main Steam Piping After Revised Test

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Forwards marked-up FSAR Pages 14.2-129 & 3.9-109,reflecting Change to Test Subsection 14.2.12.3.17, Piping Thermal Growth,Vibration & Shock, Allowing Evaluation of Piping Stresses in Main Steam Piping After Revised Test
ML20126L194
Person / Time
Site: Waterford Entergy icon.png
Issue date: 07/29/1985
From: Cook K
LOUISIANA POWER & LIGHT CO.
To: Knighton G
Office of Nuclear Reactor Regulation
References
W3P85-1441, NUDOCS 8507310102
Download: ML20126L194 (4)


Text

{{#Wiki_filter:. Louisiana / ,..o.-e.1.... . co.o-.co. P O W E R & L i G H T / N.w onceANa Louiew ros744cos e geo4 see-es4s $1uSN0Yab July 29, 1985 W3P85-1441 A4.05 Director af Nuclear Ronctor Regulation Attentim Mr. G. W. Knighton, Chief 1,1 censing Branch No. 3 Division of 1,1 censing U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Dear Mr. Knighton

Subject:

Waterford 3 SES Docket No. 50-382 Licenne No. NPF-38 TNTTIAI, TEST PROGRAM

Reference:

Waterford 1 FSAR, Chapter 14 This nubmittal in made in accordance with 10 CFR 50.59(b) and the licenne condition in Section 2.C.10 of the subject licenne. Reported horowith in a change made to the Waterford 3 Initial Tent Program, as doncribed in reference 1. nn amended through Amendment No. 36 The attached marked-up pagen 14.2-129 (Amendment 34) and 3.9-109 (Table 3.9-19 Amendment 14) of the Waterford 3 FSAR reflects the changn made for tent subncetion 14.2.12.3.17 Piping Thermal Crowth, Vibration, and Shock. A natinfactory evaluation of piping stronnen in main stonm piping after the revined tent will be acceptabla fantend of nn actual inntrumented level 4, trannient monitoring of the main stonm syntem during turhinn trip from 100% power. The vibration tenting constatn of n vinunt innpoetion of the nopportn/ rentraintn on thn main utcam piping nfter turbine trip from 85% power and a connorvativo ovaluntion of the piping ntrannon using thn renults of tho vinunt innpoetion. Thn osaluation of thn renults of the visual innpoetion will alno dotarmfnn if nduttional trannient vihrntion monitoring of the main ntuam lino in required. An additional tranninnt vihrntion monitoring of the ntonm line will be performed if required. Thin change to the initial tent program doen not involvo a changn in the license technical speciftentions or nn unroviewed anfety question. I,P AI, han conlucted and doeur.cnted the required 10 CFR 50.59 nif aty evnluntion. Og;fK U$o00:,q;y Il I 2 0 01.vt

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Mr. G. W. Knighton W3P85-1441 Page 2 LP&L will provide the FSAR change in accordance with 10 CFR 50.71(c) requirements. The original plus 39 copies of this report transmittal are provided in accordance wfth 10 CFR 50.59(b). Very truly yours, K.W. Cook Nuclear Support & Licensing Manager KWCtGEWrams Attachment cc R.D. Martin, D.M. Crutchfield, J.H. Wilson, NRC Resident Inspectors Office INPO Records Center (J.T. Wheelock), B.W. Churchill, W.H. Stevenson

N I-/MY/ WSES-FSAR-UNIT-3 14.2.12.3.17 PIPIFC THERMAL GROVIF, VIERATION, AND SFOCK 34 14.2.12.3.17.1 Objectives To demonstrate that the essential Fuclear Stear Supply Syster (FSSS) and g balance of plant corponents reet acceptable limits for therral expansion, vibration, and dynamic response in accordance with design parameters during l steady-state and transient conditions.* l8 34 14.2.12.3.17.2 Prerequisites ~ 18 A. Construction activities on the systers to be tested are complete. B. Terporary instrurentation is installed where required. 15 C. Baseline positions and alignrent are recorded. D. Preservice inspection of the snubbers identified in the Technical Specifications (Chapter 16, Section 3/4.7.9) has been completed 18 within 6 ronths of the start of the individual syster preoperational tests. 14.2.12.3.17.3 Test Method 34 A. Expansion will be sonitored during plant heatups, cooldowns, and 8 operation at various power levels. l 'L. B. Piping vicration will be ronitored during steady-state and transient operation. C. Deronstrate that the ynamic respo se during' transient o ra lon meets 15 design parareters. t //724df; 42*v 2 Lf)etmtACriCLa6 cv psr 77d6. 3.9-/9. D. On original syster liestup and cooldown, verify snubber operability by corparing actual and expected therral rovement at specified terperature intervals. Also verify by observation and/or ressure-rent that adequate swing clearance exists. 18 E. For systers that do not attain design operating terperature, verify by observation and/or calculation that the snubbers will accorrodate the predicted therral rovement. LP&L W-3 RECORDS ,Q-O U \\lCONTROL_ED COPY f ,h.' CO NOT USE !N n NY !?AFETY -RELATED TEST!NG. t:j;: - MAINTENANCE. OR OFEHATIONAL ACTIVITY 34

  • If additional restraints are installed as a result of the preoperational piping test, the NBC will be advised of the change.

In addition, any ( stress analysis required to verify the change will be raintained on 8 file for FRC review. 14.2-129 Amendment No. 34, (1/84) D ^

[ ) . r.., WSES-FSAR-IP.41T 3 TABLE 3.9-19 VIBRATION TESTING MODES Flow Modes for Freoperational Vibration Testing Piping Systems Steady State Test Level Transient Test. Level Instrumentation Required Main Steam from !^^' *:-:: Turbine trip at (".'! i .?

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Steam Cenerators E4 PE WW" A ggg4) go/Jeg to MSIV's Full flow through 1 None None atmospheric dump valves, all valves open Main Steam to Run at full pump flow 1 AFW turbine trip 1 None Auxiliary Feed-at full pump flow water Pump Tur-b2 bine UO 2 -1 Feedwater and Single AFW Pump 1 Pump start, recircu-1 None _g g 14 Auxiliary Feed-Operation for Fumps lation mode FW res valve m water 2A, 25, 2C; recircu-2 lation p _ "*/ Intake Cooling Pump (s) Operating 1 None None g o Water Pumps Dis-7:4. " su== 2 'l I

  • charge Piping "U

g.4 e.v m Component Cooling Pump (s) Operating i None None

  • 11 ; 3

.e4 O s Diesel Oil Trans-gm fer Pump Dis-Fump(s) Operating 1 None None 8 U charge Pipang p< -1 i ~U Steam Cenerator Flow at normal 1 Initiate flow, 1 Mone M h"*y O Blowdown rate system cold gu s-r-O Flow at'maxisma 1 None None Mb 7) g e rate I -{ O N it p' m (n o E n ? 5 -l 4 -t - t t M g -< 2 ? ?, (7 P1 g* 3 a 4,p o s -}}