ML20205D333
| ML20205D333 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 09/13/1985 |
| From: | Carey J DUQUESNE LIGHT CO. |
| To: | Knighton G Office of Nuclear Reactor Regulation |
| References | |
| 2NRC-5-132, TAC-62898, TAC-62899, TAC-62900, TAC-62901, TAC-62902, TAC-62903, NUDOCS 8509230659 | |
| Download: ML20205D333 (7) | |
Text
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'Af Duquesne Lidit
"",T'53 Nuclear Construction Division Telecopy 41 )
N$u$n$' *is2Os' September 13, 1985 United States Nuclear Regulatory Commission Washington, DC 20555 ATTENTION:
Mr. George W. Knighton, Chief Licensing Branch 3 Office of Nuclear Reactor Regulation
SUBJECT:
Beaver Valley Power Station - Unit No. 2 Docket No. 50-412 Response to FDSER Confirmatory Issues 16 through 21 Gentlemen:
This letter transmits responses to Final Draft Safety Evaluation Report (FDSER) Confirmatory Items 16, 17, 18, 19, 20, and 21. The responses to these issues are attached.
DUQUESNE LIGHT COMPANY By
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J. W. 04 rey Vice President KAT/wjs Attachments cc:
Mr. B. K. Singh, Project Manager (w/a)
Mr. G. Walton, NRC Resident Inspector (w/a)
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ATTACHMENT Respon_se_s to FOSER,C_onfirmator,y, Issues 16 through 21
- 16. P_eak Pellet De, sign Basis (%4.2.1)
"The applicant should confirm that the peak pellet design basis burnup of 53,000 mwd /MTu shown in the second paragraph of FSAR Section 4.2.1 is consistent with the region discharge burnup of 33,000 mwd /MTu shown under ' Basis' in FSAR Section 4.3.1.1."
Response
The peak pellet burnup of 53,000 mwd /MTu referenced in Section 4.2.1 of the Beaver Valley Unit 2 FSAR bounds the maximu;n expected peak pellet burnup for. f uel operated to 33,000 mwd /MTu region average discharge burnup. Therefore, the peak pellet design basis burnup of 53,000 mwd /MTu is consistent with the region discharge burnup of 33,000 mwd /MTu refer-enced in Section 4.3.1.1.
- 17. Discrepencies in th_e FSAR ( 4.2.2)
"... there appear to be some OFA data rather than SFA data in several places in the FSAR.
In Figure 4.2-1, the fuel rod dianeter is shown as 0.360 inch [0FA size] rather than 0.374 inch-[SFA size], ~as indicated in Table 4.1-1), and in FSAR Tables 4.1-1 and 4.3-1, the Zircaloy weights are given as 41,415 and 38,230 pounds, respectively.... In Figure 4.2-1, 204 fuel rods are shown as required, rather than 264 as noted in Section 4.1.1 and Table 4.3-1; certain dimensions (e.g.,154.0 REF,133.4 REF, 112.8 REF, etc.) appear to be incorrectly shown in Figure 4.2-2; and FSAR Tables 4.1-1 and 4.3-1 give the fuel weight (as UO ) as 181,190 and 2
181,205 pounds, respectively.
The applicant should specify the correct values for Beaver Valley Unit 2 fuel'."
Response
Tables 4.1-1 and 4.3-1 and Figures 4.2-1 and 4.2-2 have been corrected by mark-up and are attached to this letter.
These will be incorporated into the FSAR.
- 18. Rod, Bowing Analysis _(94.2.3.1[6])
"The applicant must confirm that the rod bowing analysis has been perfonned."
Response
The rod bow analysis has been conpleted for Beaver Valley Unit 2 using the correlation in Revision 1 of WCAP-8691. The results of this analysis were provided in letter 2NRC-4-102 of July 12, 1984, and in FSAR 94.4.2.2.5, Amendment 8, Septenber 1984.
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- 19. Fuel Rod Internal Press _ur,els_4.2.3.1[8])
i "The applicant must confinn that the fuel rod internal pressure is consistent with the approved topical report, WCAP-8963 (Stolz, May 19, 1978)."
Response
Calculations performed for each fuel region confirm that the Rod Inter-nal pressure -criterion, described in Sectica 4.2.1.3 of the FSAR and referenced in WCAP-8963, is met.
- 20. Predicted Cladding Collapse Time (t4.2.3.2[2])
"The applicant has not yet confinned that the calculated cladding col-lapse time for Beaver Valley Unit 2 fuel using WCAP-8377 methods is nore than the expected residence of the fuel."
Response
Calculations perfonned with the NRC approved Westinghouse clad flatten-ing model (WCAP-8377) confinn that the predicted clad collapse time exceeds the expected residence time of the fuel.
21 Use of the Square-Root-of-the-Sum-of-the-Squares Method for Seismic and LOCA Load Calculations ( 4.2.3.3[4])
" Consequently,- the use of canbined LOCA and seismic loads using the SRSS method inust be confinned to satisfy SRP 4.2....
The applicant must provide these nongrid conponent forces so the staf f can complete its review."
Response
I This was provided by letter 2NRC-4-209 of December 18, 1984.
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BVPS-2 FSAR TABLE 4.1-1 (Cont)
Core Mechanical Virgil C. Summer Design Parameters BVPS-2 Nuclear Station Rod pitch (in) 0.496 0.496 overall dimensions (in) 8.426 x 8.426 8.426 x 8.426
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Fuel weight (as Uo ) (lb) 18)(f90/$l,200 101,170
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Zircaloy weight (lb) 41,41;L/f,Yd0 447415 f/,Yah Number of grids per assembly 8 - Type R 8 - Type R-Leading technique 3 region 3 region nonuniform nonunifera Fuel Rods' Number 41,448 41,448 Outside diameter (in) 0.374 0.374 Diametral gap (in) 0.0565 0.0065 Clad thickness (in)'
O.0225 0.0225 Clad material Zircalcy-4 Zircaloy-4 Fuel Pellets Material Uo sintered Uo, sintered a
Density (percent of theoretical) 95 95 Diameter (in) 0.3225 0.3225 Length (in) 0.530 0.530 Rod Cluster Control Assemblies Neutron absorber Hafnium Ag-In-Cd Cladding material Type 304 SS-Type 304 55-cold worked cold worked l
l Clad thickness (in) 0.0185 0.0185 Number of clusters 52 48 e
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TABLE 4.3-1 REACTOR CORE DESCRIPTION (First Cycle)
Active Core Equivalent diameter (in) 119.7 Core average active fuel height, first core (in) (nominal) 144 Height-to-diameter ratio, 1.20 Total cross section area (ftz) 78.14 H 0/U molecular ratio, lattice (cold) 2.43 2
Reflector Thickness and Composition Top - water plus steel (in) 10 Bottom - water plus steel (in) 10 side - water plus steel (in) 15 Fuel Assemblies Number 157 Rod array 17 x 17 Reds per assembly 264 Rod pitch (in) 0.496 overall transverse dimensions (in) 8.426 x 8.426 Fuel weight, as Co, (lb)
FSF-feS 184484 Zircaloy weight (1b) 23.220-yl, a/e o Number of grids per assembly 8-R Type Composition of Grids Inconel-718 Weight of grids, (effective in core) (Ib) 1885 Number of guide thimbles per assembly 24 Composition of guide thimbles Zircaloy-4 Diameter of guide thimbles, upper part (in) 0.450 I.D. x 0.482 0.D.
Diameter of guide thimbles, lower part (in) 0.397 I.D. x 0.429 0.D.
Diameter of instrument guide thimbles (in) 0.450 I.D. x 0.482 0.D.
Fuel Rods Number 41,448 Outside diameter (in) 0.374 Diameter gap (in) 0.0065 Clad thickness (in) 0.0225 Clad material Zircaloy-4 4
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