ML20211P667
| ML20211P667 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood  |
| Issue date: | 10/10/1997 |
| From: | Tulon T COMMONWEALTH EDISON CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| RTR-NUREG-1431 NUDOCS 9710210103 | |
| Download: ML20211P667 (4) | |
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'ItiHi% M M2 Hot October 10,1997 United States Nuclear Regulatory Commission Attre Document Control Desk Washington, D. C. 20555
Subject:
Clarifying Information on tiie improved Technical Specification (ITS)
Submittal Byron Nuclear Power Station, Units I and 2 Facility Operating Licenses NPF-37 and NPF-66 NRC Doqket Nos. 50-454 and 50-455 Braidwood Nuclear Power Station, Units I and 2 Facility Operating Licenses NPF-72 and NPF-77 NRC Docket Nos. 50-456 and 50 45.2
Reference:
G. Stanley and K. Graesser (Comed) letter to United States Nuclear Regulatory Commission Document Control Desk,
" Application for Amendment to Appendix A, Technical Specifications, for Facility Operating Licenses NPF 37, NPF-66, NPF-72, and NPF 77," dated December 13,1996.
The purpose of this letter is to transmit additional information related to Commonwealth Edison's (Comed) request to adopt the improved Technical Specifications of NUREG 1431 for Byron and Braidwood (B/B) Units I and 2. This information is provided to clarify a question raised by NRC Staff during the review of the"Beyond Scope Changes"in the ITS submittal.
The Staffs question was specific to their review of Limiting Conditions for Operation (LCO) 3.5.5 and its accompanying figure. The Comed response to the Stairs question is contained in the attachment to this letter.
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As discussed with NRC Stafron a September 4,1997 teleconference, Figure 3.5.5.1, Seal Injection Flow limits, is consistent with the method used and approved by the NRC for the Vogtle Units.
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Please address any comments or questions regarding this matter to our Nuclear Licensing Deparin ent.
Sincerely,
/
[ Mothy J. Tulon
' Site Vice President Braidwood Nuclear Power Station TJTTfb\\o:...nrc\\97119mt. doc Attachment :, Additionallnformation to Support the Seal injection Flow Limits Figure cc:
Regional Administrator-Rill Byron Project Manager NRR Braidwood Project Manager-NRR
- Senior Resident inspector Braidwood Senior Resident inspector-Byron Office of Nuclear SeMy IDNS
- D. Chrzanowski-Ndest Licensing e
9 4
'O Attachment Additional Information to Support the Seal Injection Flow Limits Figure As requested by NRC Staff, the following provides additional information on seal injection flow and worst case emergency core cooling system (ECCS) flows.
Figure 3.5.5-1 in the B/B ITS submittal was based on Comed's Nuclear Fuel Services Calculation Note RSA B 93-04 using the following limiting plant data:
Pr (discharge header pressure upstream of filter) = 2,340 psig Paes (average coldleg pressure) = 2,253.5 psig Q (scal injection flow rate) = 37.6 gpm The above values were the most conservative combination of plant data selected from all four Byron /Braidwood units. Based on these values the loss coeflicient (K) for the seal injection line must be greater than.062 psi /gpm', when calculated in accordance with the following equation:
K = (Pr-Paes)/Q' = AP/Q' Based on this equation, an acceptance formula for the ieal injection line loss coefficient was established as follows:
Q > (AP/K) * * (AP/.062)d = 4.02(AP)4 The above equation specifies the acceptable region of operation of the seal injection flow relative to the above referenced Calculation Note. Figure 3.5.5 1 in the B/B ITS submittal plots this equation over the range of anticipated operating conditions.
Byron /Braidwood UFSAR Figure 15.6-6 (attached) shows the minimum, worst case, ECCS flows used in the LOCA analysis. This worst case ECCS plot is a combination of flows from one Safety injection pump, one Residual lleat Removal pump, and one Centrifugal Charging pump, but does not include the contribution from seal injection.
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REVISION 6 DECEMBER 1996 500
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100 200 300 4I40 5lJO 6l10 RCS Pressure (psia)
BYRON /BRAIDWOOD STATION UPDATED FINAL SAFETY ANALYSIS REPORT FIGURE 15,6-6 MINIMUM SAFETY INJECTION FLOW RATES USED IN LARGE BREAK
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