ML20210U244

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Provides Verification of Reactor Containment Fan Cooler (RCFC) Heat Removal Capability Per 870121 Telcon.Rcfc Heat Removal Capability Meets or Exceeds That Used for Containment Integrity Analyses.Supporting Data Encl
ML20210U244
Person / Time
Site: Byron 
Issue date: 01/23/1987
From: Hunsader S
COMMONWEALTH EDISON CO.
To: Harold Denton
Office of Nuclear Reactor Regulation
References
2636K, NUDOCS 8702180421
Download: ML20210U244 (5)


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, One First Nabonal Plaza, Chcago, minois s -. Address Reply to: Post Omco Box 767 CNcapo, Illinois 60890 - 0767 January 23 1987 Mr. Harold R. Denton, Director-Office of; Nuclear Reactor Regulation r U.S. Nuclear-Regulatory Commission Washington, DC.-20555

Subject:

Byron Station Unit 2 Initial Test Program Results Containment Ventilation System NRC Docket No. 50-455

Reference:

(a) January.13, 1987.K.A. Ainger letter to H.R. Denton (b) November 3, 1986'K.A. Ainger letter to H.R.:Denton

Dear Mr. Denton:

Reference (a) provid'ed.the reevaluation of test results for the containment ventilation system (VP, test 2.93.61) to support a-deferral presented in reference (b). This letter provides additional data as requested in a teleconference with a memberoof your staff on January 21, 1987. During that discussion, it was requested that'the Reactor-Containment Fan Cooler (RCFC) heat removal capability be verified at both a relatively high temperature and pressure, and a lower ~ temperature and pressure with the results being compared to the heat removal assumption used in the containment integrity analyses. As such, the following containment conditions were analyzed: 2710F, 50 psig and 2250F, 20 psig. The RCFC heat removal performance l data is shown on the attached load versus temperature curve supplied by the RCFC manufacturer (Attachment I). The solid line curve represents the RCFC performance with 66,000 ACFM air flow over the coils and 2950 gpm, 1000F essential service water flow. This data was used by Westinghouse in the containment integrity' analyses. As such, this value of flow rate was used and not the original' design volumetric flow rate value of 59,000 CFM presented in the FSAR.. The dotted curve represents the original S&L RCFC procurement specification requirements and is representative of Table 6.2-56 of the Byron /Braidwood FSAR. l 'Using the solid line curve, at.271 F the load per RCFC is 0 approximately 143 x 106 BTUH. The total RCFC heat removal assumed in the containment integrity analyses is twice this value of 286 x 106 BTUH. Similarly, at 2250F the load per RCFC is approximately 98 x 106 BTUH for a total RCFC heat removal value of i 196 x 106 BTUH. 8702180 fM$55 ht PDR A PDR I' 'g P E j

.A . The'RCFC heat removal capability was tested at Wyle labs and documented in Wyle test report 43810-1 Rev. B. Figure 3 from the Wyle test report (Attachment II) is used to determine RCFC heat removal capability at approximately 54,000 CFM (determined at the. fan), 2660 gpm and 1000F Essential Service Water System water. At 2710F, 50 psig one RCFC is capable of removing approximately 170 x 6 106 BTUH for a total heat removal rate of 340 x 10 BTUH. At 2250F, 20 psig one RCFC is capable of removing approximately 115 x 6 106 BTUH for a total heat removal rate of 230 x 10 BTUH. If this data is plotted on Attachment I.the resulting curve falls to the right of both the solid and dotted line curves. -Attachment III provides a table of this data and the applicable volumetric flow rates. The Wyle test data was obtained L at the indicated flow rate of 54,000 CFM, and the installed fan cooler flows (as determined by preoperational tests) were found to range from 54,992 CFM to 58,238 CFM at the fan. The flow rates from pre-operational test results have been corrected for air density since the test was performed at a lower pressure and temperature than that given in the containment integrity analyses. Consequently, the heat removal capability for the installed Byron Unit 2 RCFC's is greater than that determined by the Wyle acceptance test which in turn is greater than that used in the accident analyses. The above information demonstrates that the installed RCFC heat removal capability meets or exceeds that used for the containment integrity analyses. The manufacturer's design prediction (used as a basis for the analyses) was met or exceeded by actual installed RCFC demonstrated capability. Please address any questions concerning this matter to this office. One signed original and fifteen copies of this letter and the attachment are included for your review. Very truly yours, = e_: & S. C. Hunsader Nuclear Licensing Administrator /klj cc: L. Olshan J. Stevens 2636K j

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t t. ATTACHMENT III CONTAINMENT VENTILATION SYSTEM e Volumetric Flow Rate Heat (cfm) Containment Atmosphere Flow Rate x 106 Temp (OF) Press. (PSIG) (BTUH) Containment integrity 66,000 271 50 286 analysis (at the coils) 225 20 196 Wyle 54,000* 271 50 340 Test results 51,300* 225 20 230 Pre-op 54,992** approx. 80, 14.7 greater Test results 55,277** " 80 than-55,810** " 80 the 58,238** " 80 above-

    • Vol. flow rate values corrected for density change for test performed of lower temp./ press.
  • Values calculated from flow rate readings taken at the coils in the Wyle test.

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