ML20117D589
| ML20117D589 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 08/27/1996 |
| From: | Tuckman M DUKE POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| TAC-M90566, NUDOCS 9608280380 | |
| Download: ML20117D589 (3) | |
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kn uhesk Owlotte, NC2820!-1006 NuclearGeneration I
(IO4)382-22000Wice.
(704)3824360 Fat DiMWPOWER August 27, 1996 i
U. S. Nuclear Regulatory Commission l
Attention: Document Control Desk Washington, DC 20555 l
Subject:
Catawba Nuclear Station, Unit 1, Docket No. 50-413 Supplement to Replacement SG Proposed TS Amendment (TAC M90566)
By letter dated March 15, 1996, Duke Power Company submitted responses to the NRC Staff's Request for Additional Information.
Subsequent review of the steam generator tube l
rupture (SGTR) analysis has identified a minor error in the i
calculation of the initial break flow rate.
The revised l
offsite dose results (at the EAB) are summarized in.
These doses remain bounded by 10CER100 and the current FSAR Section 15.6.3 analysis.
The remaining discussion of the SGTR event presented'in the March 15, 1996 submittal remains valid.
l Doses for the locked rotor and rod ejection accidents were l
also provided'in the March 15, 1996 submittal.
As a result of modifications to the Auxiliary Feedwater System during
-the steam generator replacement outage, the dose analyses i
for these two accidents have been_ revised and are provided l
in Attachment-1.
The' March 15, 1996 submittal also provided the SGTR offsite dose.results for McGuire Units 1 and 2.
The identified error effects these offsite dose results, also.
The McGuire SGTR offsite dose results are being revised and will be provided in a future submittal.
Please contact R. O. Sharpe at (704) 382-0956 if you have
'any questions.
Very truly A06 i
K. 3. T1~
M. S. Tuckman 9608280380 960827 L
PDR ADOCK 05000413 I
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D. S: Nuclear Regulatory Commission August 27, 1996 Page 2 Attachment xc:
S.
D. Ebneter Regional Administrator, Region II U.
S. Nuclear Regulatory Commission 101 Marietta Street, NW, Suite 2900 Atlanta, GA 30323 R.
J.
Freudenberger Senior Resident Inspector Catawba Nuclear Station S. M.
Shaeffer Senior Resident Inspector McGuire Nuclear Station P.
S.
Tam Project Manager, ONRR V. Nerses Project Manager, ONRR L. N.
Tran Project Manager, ONRR l
t
.a l
Catawba Unit 1 Revised UFSAR Ch 15 Offsite Doses Catawba 1 Catawba 1 10CFR100 Current (3/15/96 (revised)
Limit UFSAR Letter)
S/G Tube Rupture (SGTR)
Whole body dose (Rem) 0.126 0.169 2.5 0.31 Thyroid dose (Rem):
-pre-existing iodine spike 53.4 63.4 300 91
-coincident iodine spike 20.1 22.4 30 26 Locked Rotor Whole body dose (Rem) 0.252 0.250 2.5 0.44 Thyroid dose (Rem):
-pre-existing iodine spike 8.294 5.632 30 3.7 Rod Ejection I
Total whole body dose (Rem) 1.127 1.119 6
0.094 Total thyroid dose (Rem):
l
-no iodine spike 60.23 69.558 75 1.069 l
t 1
Note: Current UFSAR dose analyses do not include the effect of possible S/G tube' bundle uncovery.
This effect has been added to Duke's dose calculation model for Westinghouse and BWI S/G's.
It was included in the dose analyses submitted on 3/15/96 and will be included in the next update to the Catawba UFSAR.
The percent failed fuel assumption for locked rotor was increased from 10% to 15% and for rod ejection was increased from 10% to 50%.
The source term assumptions for SGTR remain unchanged and are the pre-existing and coincident iodine spike as delineated in the SRP (NUREG-0800).
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