ML18228A435
| ML18228A435 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point |
| Issue date: | 05/08/1978 |
| From: | Robert E. Uhrig Florida Power & Light Co |
| To: | Stello V Office of Nuclear Reactor Regulation |
| References | |
| Download: ML18228A435 (5) | |
Text
REGULATORY INFORMATION DISTRIBUTION SYSTEM
< RIDS)
DISTRIBUTlON FOR INCOMING MATERIAL 50-250 REC:
STELLO V NRC ORG:
UHRIG R E FL PWR 8c LIGHT DOCDATE: 05/08/78 DATE RCVD: 05/17/78 DOCTYPE:
LETTER NOTARIZED:
NO COPIES RECEIVED
SUBJECT:
LTR 3 ENCL 0 FURNISHING INFO AND APPLlCANT"S PLANS FOR ANALYZING OPERATION OF SUBJECT FACILITY WITH GREATER THAN 19/ PLUGGED STEAM GENERATOR TUBES.
PLANT NAME: TURKEY PT 03 REVIEWER INITIAL:
XJM DISTRIBUTOR INITIAL:~
++>w+sl%>>+wmw+w++ DISTRIBUTION OF THIS MATERIAL IS AS FOLLOWS GENERAL DlSTRIBUTION FOR AFTER ISSUANCE OF OPERATING LICENSE.
<DISTRIBUTION CODE A001)
FOR ACTION:
INTERNAL:
EXTERNAL:
BR C
F SCHWENCER44LTR ONLY(7)
REG 4LTR ONLY(i)
E+>LTR ONLY(2)
HANAUER44LTR ONLY<i)
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ACRS CAT 8++LTR ONLY(16)
NRC PDR44LTR ONLY(i)
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DISTRIBUTION:
LTR 40 ENCL 0 SIZE:
2P CONTROL NBR:
781370030 THE END 4%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%%
Jt
Director of Nuclear Reactor Regulation Attention:
Mr. Victor Stello, Director Division of Operating Reactors U. S. Nuclear Regulatory Commission Washington, D.
C.
20555
Dear Mr. Stello:
CD C~ tTg rq<
May 8"g8'-1
~Cn
>~A Dy
(
LQ mc-R CD CO CA Re:
Turkey Point. Unit 4 Docket No.
50-250 ECCS Anal s'is
Turkey Point Unit 4,is presently authorized to operate with up to 19% plugged steam gener'ator tubes'.
Following the next Unit 4 steam generator'nspection and preventive tube plugging outage, the percentage of plugged steam generator tubes may exceed 19%.
We ha've, therefore, decided to analyze for operation of Turkey Point Unit 4 with greater than 19% plugged steam generator tubes.
The results of this analysis, as well. as any necessary license amendments, will be submitted to you for review.
Our plans for analyzing operation with greater than 19%
plugged steam generator tubes are summarized below.
We would appreciate receiving any comments.which you might have on our planned analysis by May 31, 1978 so as not to impact our schedule.
Operation of Turkey Point Unit 4 will be evaluated assuming 25% plugged steam generator tubes and a reactor coolant flow rate of 95% design flow.
The evaluation will include the effect of 95% design flow on the DNBR related accidents analyzed in Chapter 14 of the Turkey Point FSAR and will also include a large break ECCS re-evaluation for the presently identified limiting break size.
An ECCS re-evaluation will be performed for the specific fuel loading and burnup of Unit 4, Cycle 5 using the currently approved Westinghouse evaluation model, corrected for the Zircaloy/
water coding inconsistency.
After the NRC has approved recent model'mprovements submitted by Westinghouse, the i 78l370030 Y~'p PEOPLE... SERVING PEOPLE
II W
h t i't i
Mr. Victor Stell irector IJ.
S. Nuclear Regulatory Commission Page Two ECCS will be again re-evaluated.
The DNBR related accidents will be based on Unit 4, Cycle 5 and Unit 3, Cycle 6
operating parameters and NRC approved correlations,
- codes, and methods.
Very truly yours, Ro rt E. Uhrig, Vice, President REU:MAS:GDN:sl cc:
Mr. James P. O'Reilly, Region lX Robert Lowenstein, Esquire