ML20035F992
| ML20035F992 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 04/19/1993 |
| From: | Sieber J DUQUESNE LIGHT CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| TAC-M85819, TAC-M85820, NUDOCS 9304230187 | |
| Download: ML20035F992 (5) | |
Text
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Beaver Valley Power Station Shippingport. PA 15077-0004 I
JOHN D. DEBER (412) 393-5255 Senior Vice President and Fax (412) 643-8069 i
$*da*/PO.*Er $$[on April 19, 1993 U.
S.
Nuclear Regulatory Commission Attn:
Document Control Desk Washington, DC 20555 s
Subject:
Beaver Valley Power Station, Unit No. 1 and No. 2 BV-1 Docket No. 50-334, License No. DPR-66 l
BV-2 Docket No. 50-412, License No. NPF-73 i
Additional Information Supporting TSCR 208/74 (TAC Nos. M85819/M85820)
Attached are summaries of the Beaver Valley Unit No. 1 and No. 2 l
peak clad temperature determinations which support the reported i
values in our February 19, 1993 proposed operating license change request.
This information is provided in response to a telephone conversation between our respective staffs which occurred on April l
12, 1993.
If you have any questions regarding this submittal, please i
contact Mr. Steve Sovick at (412) 393-5211.
I Sincerely,
/
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D.
Sieber Attachment i
cc: Mr.
L.
W.
Rossbach, Sr. Resident Inspector Mr. T. T. Martin, NRC Region I Administrator Mr. G.
E.
Edison, Project Manager Mr. M. L.
Bowling (VEPCO) 7 23003G
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61 THE YEAR l'
5 9304230187 930419 PDR ADDCK 05000334 i
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Additional Information Supporting TSCR 208/74 (TAC Nos.-M85819/M85820)
'Page 1
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i 1.
Analysis of record:
BASH analysis described in UFSAR 14.3.2 and 14.3.2.1 (full-spectrum analysis).
l PCT for most limiting break (CD = 0.4) = 1918'F i
(UFSAR, page 14.3-8)
[ Key Assumptions: 10% steam generator tubes plugged UFSAR 14.3.2.2 first paragraph]
Partial BASH analysis described in UFSAR 14.3.2.2 i
(re-analyzed limiting break only) l t
PCT calculated as 2149'F.(UFSAR, page 14.3-10) [ Key l
Assumptions:
20%
steam generator tubes plugged -
UFSAR 14.3.2.2]
2.
Most recently reported change to 1 above prior to 2/19/93:
f None 3.
Specific changes since 2 above prior to 2/19/93:
i Fuel rod backfill initial pressure uncertainty (1) 2*F(2) l RCS Tavg uncertainty 2*F(3) i 9
l l
(1)
Letter ET-NRC-91-3647, 12/20/91, Interim Report No.91-021, l
S.R. Tritch (Westinghouse to NRC).
(2)
Interim issue under Westinghouse evaluation.
I (3)
Proposed license change request dated 2/19/93; plant specific uncertainty calculation.
l
i
' Add (tional-Information Supporting TSCR 208/74 f
.(TAC Nos. MB5819/M85820) l Page 2 l
Analysis of record:
NOTRUMP analysis described in UFSAR 14.3.1
[
PCT for most limiting break (3" break)'= 1802*F-(UFSAR, page 14.3-4) [ Key Assumptions: as described in UFSAR 14.3.1]
f l
2.
Most recently reported change to 1 above prior to 2/19/93:
-Annual 10 CFR 50.46 report dated July 20, 1992 j
PCT reported as 2010*F r
3.
Specific changes since 2 above prior to 2/19/93:
Auxiliary feedwater flow rate change
'175'F(2)
I I1)
Remove penalty for SBLOCA rod internal
-53*F
(
pressure initial condition assumption Auxiliary feedwater pump start signal 6aF assumption change l
Burst / Blockage SPIKE interim penalty 204*F(3)-
1
-Burst / Blockage SPIKE increase due to 10'F(3) 3 2/19/93 proposed license cnange request Non-cycle specific power shape /P-bar-HA
-118*F((4)
Cycle specific power shape /P-bar-HA
-42*F(4) 5*F 5)
RCS Tavg uncertainty (1)
This penalty is assigned as a contingency to accommodate a i
reduced auxiliary feedwater flow rate, if needed.'
No credit is currently taken for it.
i (2)
This issue is bounded by the Burst / Blockage SPIKE interim l
issue.
These two issues are mutually exclusive.
See letter i
ET-NRC-91-3647, 12/20/91, S. R. Tritch (Westinghouse to NRC),
l Interim Report No.91-021.
l (3)
This is an interim ' issue under. evaluation.
See letter i
ET-NRC-91-3647 (above), Interim Report No.91-005.
i (4)
Plant specific input values were used rather than the previous j
more
- generic, bounding values.
This'is not a change to the model.
j (5)
Proposed license change request dated 2/19/93; plant specific uncertainty calculation.
I
' Add (tional Information Supporting-TSCR 208/74 (TAC Nos. M85819/M85820)
'Page 3
[
i
~!
1.
Analysis of record:
j i
BART analysis described in UFSAR 15.6.5 I
f PCT for most limiting break (C
= 0.4) = 2120*F-l k5.6.5.3.3, page i
(UFSAR Table 15.C-9, UFSAR 15.6-18)
[ Key Assumptions: 5% steam generator tubes plugged - UFSAR Table 15.6-9]
I 2.
Most recently reported change to 1 above prior to 2/19/93*
i Annual 10 CFR 50.46 report dated July 20, 1992.
f i
PCT reported as 2191*F f
i 3.
Specific changes since 2 above prior to 2/19/93:
I WREFLOOD structural heat model
-25'F(1) i i
I l'
(1)
This change was identified by Westinghouse to us at i
approximately the same time our 2/19/93 submittal was issued i
and is, therefore, not reflected in item 2 above '2191'F)
.l 5
e I
i
)
i k
a
Additional Information Supporting TSCR 208/74 (TAC Noh. M85819/M85820)
[
I I
T 1.
Analysis of record:
t NOTRUMP analysis described in UFSAR 15.6.5 l
PCT for most limiting break (4" break) = 1399*F
{
(UFSAR 15.6.5.3.3, page 15.6-19 and Table 15.6-10)
[ Key Assumptions: as described in UFSAR 15.6.5]
i 2.
Most recent reported change to 1 above prior to 2/19/93:
Annual 10 CFR 50.46 report dated July 20, 1992 PCT reported as 2176*F(1}
3.
Specific changes since 2 above prior to 2/19/93:
None j
I l
l
?
'I (1)
The summary reported in our 2/19/93 submittal provides an itemization of this reported PCT.
I 6
-.