L-82-335, Responds to 820513 Request for Addl Info Re Responses to IE Bulletin 80-04, Analysis of PWR Main Steam Line Break W/ Continued Feedwater Addition. No Further Calculations Re Magnitude of Peak Pressure Necessary
| ML17213A336 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 08/09/1982 |
| From: | Robert E. Uhrig FLORIDA POWER & LIGHT CO. |
| To: | Clark R Office of Nuclear Reactor Regulation |
| References | |
| REF-SSINS-6820 IEB-80-04, IEB-80-4, L-82-335, NUDOCS 8208170203 | |
| Download: ML17213A336 (3) | |
Text
REGULATO lNFORMA'TION DISTRIBUTION TEM (RIDS)
ACCESSION NBR:8208170203 DOC ~ DA'TE: 82/08/09 NOTARIZED; NO FACIL:50"335 St, Lucie Pl anti Uni1t ii Florida -Power 8 Light Co.
AUTH~ NAME AUTHOR AFFILIATION UHRIGg R ~ E ~
Florida 'Power 8 Light Co,
'R EjC IP ~ NAME RECIPIENT AFFILIATION CLARKPR,AD Operating Reactors Branch
-3
SUBJECT:
Responds to 820513 request for addi info Ire responses'to IE Bulletin 80 04'"Analysis of PNR Main Steat'ine Break N/
Continued Feedwater Addiition," No further calculations re magnitude of peak pressure necessary'ISTRIBUTION
'CODE:
ASSIS,:COPIES
'RECEIVED:LTR g ENCL j SIZE:.
TITLE: General Distribution for after Issuance of.Operating License NOTES:
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P OX 14000, JUNO BEACH, FL 33408 Office of Nuclear Reactor Regulation Attention:
Mr. Robert A. Clark, Chief Operating Reactors Branch g3 Division of Licensing U.S.
Nuclear Regulatory Commission Washington, D.C. 20555 FLORIDAPOWER & LIGHT COMPANY August 9, 1982 L-82-335
Dear Mr. Clark:
Re:
St. Lucie Unit 1
Docket No. 50-335 Main Steam Line Break (MSLB)
With Continued Feedwater Addition Florida Power 8 Light has reviewed your letter dated May,13, 1982 concerning our response to IE Bulletin 80-04, "Analysis of a PWR Main Steam Line Break with Continued Feedwater Addition," for St. Lucie Unit l.
Your letter requested additional information concerning the effect of proposed Auxiliary Feedwater (AFW) modifications on containment pressure and on core reactivity.
These modifications will allow the AFW system to feed only the steam'enerator unaffected by a Main Steam Line Break.(MSLB).
We have evaluated the effect that the "smart" AFW system will have on containment pressure.
Because the system will not open the valves to the faulted steam generator, the automatically initiated AFW flow will not reach it.
There will be no AFW contribution to the containment pressure calculation.
This will increase the margin between the design pressure and the maximum pressure in the containment during the postulated event.
We do not see the need to submit further calculations to provide the magnitude of the peak pressure, because it will be below that which we have previously described in our response to the Bulletin.
'tem 2 of your letter concerned core reactivity response to a
MSLB.
We have contracted with our new fuel vendor to perform a
MSLB analysis using the parameters of the "smart" AFW system as input.
This analysis is due to be completed in December 1982, at which time we will provide a response to your concern.
This schedule is justified by the fact that the system is not scheduled to be completely installed until our next refueling outage which is presently scheduled for triarch 1983.
Very truly you s
Rober
. Uhrig Vice President Advanced Systems 8 Technology 8208170203 820809 REU/PLP/mbd PDR ADOCK 05000335 8
PDR cc:
Mr. J.P. O'Reilly, Region II Harold F.
Rei s, Esquire o<i PEOPLE... SERVING PEOPLE