L-91-096, Application for Amend to License DPR-67,deleting Tech Spec 3/4.2.2, Total Planar Radial Peaking Factor - Ftxy
| ML17223B164 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 04/17/1991 |
| From: | Bohlke W Florida Power & Light Co |
| To: | NRC/IRM |
| Shared Package | |
| ML17223B165 | List: |
| References | |
| L-91-096, L-91-96, NUDOCS 9104240022 | |
| Download: ML17223B164 (6) | |
Text
ACCELERATED DISTRIBUTION DEMONPHWTION SYSTEM Sfg j~
4 REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR: 9104240022 DOC. DATE: 91/04/17 NOTARIZED: YES FACIL:50-335 St. Lucie Plant, Unit 1, Florida Power 6 Light Co.
AUTH.NAME AUTHOR AFFILIATION BOHLKE,W.H.
Florida Power
& Light Co.
RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
Application for amend to License DPR-67,deleting Tech Spec 3/4.2.2, "Total Planar Radial Peaking Factor Ftxy."
DISTRIBUTION CODE:
AOOID COPIES RECEIVED:LTR C ENCL +
SIZE TITLE: OR Submittal:
General Distribution NOTES DOCKET 05000335 R
I RECIPIENT ID CODE/NAME PD2-2 LA NORRIS,Z INTERNAL: ACRS NRR/DET/ESGB NRR/DST 8E2 NRR/DST/SICB 7E NUDOCS-ABSTRACT OGC/HDS3 RES/DSIR/EIB EXTERNAL: NRC PDR COPIES LTTR ENCL 1
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1 RECIPIENT ID CODE/NAME PD2-2 PD NRR/DET/ECMB 9H NRR/DOEA/OTSBll NRR/DST/SELB 8D NRR/DST/SRXB 8E 0
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NOTE TO ALL"RIDS" RECIPIENTS:
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PLEASE HELP US TO REDUCE WASTE! CONTACTTHE DOCUMENT CONTROL DESK, ROOM Pl-37 (EXT. 20079) TO ELIMINATEYOUR NAMEFROM DISTRIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
TOTAL NUMBER OF COPIES REQUIRED:
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P.O. Box14000, Juno Beach, FL 33408-0420 APRIL' 7
1991 L-91-096 10 CFR 50.90 U.
S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, D.
C.
20555 Gentlemen:
RE:
St. Lucie Unit 1 Docket No. 50-335 Proposed License Amendment Deletion of Total Planar Radial Peakin Factor F~
In accordance with 10 CFR 50.90, Florida Power
& Light Company (FPL) submits herewith a
request to amend Facility Operating License DPR-67 for St. Lucie Unit 1.
This is a request to delete the St. Lucie Unit 1 Technical Specification 3/4.2.2 "Total Planar Radial Peaking Factor F ~" and all of its references.
Advanced Nuclear Fuels Corporation (ANF) had performed the setpoint analysis for St. Lucie Unit 1 reloads ANF-1 through 4 using Axial Power Distributions (APDs) generated by using a one-dimensional (1-D) core model which required the presence of an FT~ limit (Reference 1).
For the ANF-5 reload (current cycle),
and future reloads the APDs were and will be generated using a
three-dimensional (3-D) core model (Reference 2).
The use of the APDs from the 3-D core model obviates the need for the FT~ parameter because a synthesis of the 1-D axial power distribution is no longer performed.
The Nuclear Regulatory Commission (NRC) has determined that the use of the 3-D core model does not constitute a methodology change (Reference 3).
Thus, the deletion of the F~~
Technical Specification limit is possible because ANF's 3-D power distribution methodology does not require it.
Attachment 1 to this letter includes the proposed St. Lucie Unit 1 Technical Specification changes.
Attachment 2 is a Safety Analysis in support of the proposed amendment.
Attachment 3
is a
"Determination of No Significant Hazards Consideration."
Attachment, 4 is a copy of Reference 3.
The proposed amendments have been reviewed by the St.
Lucie Facility Review Group and the Florida Power
& Light Company Nuclear Review Board.
9i04240022 9i04i7 PDR ADOCK 05000335 p
~ ap Fp[ Qfaup companY
U.
S. Nuclear Regulatory Commission L-91-096 Page two In accordance with 10 CFR 50.91 (b)(1),
a copy of the proposed amendments is being forwarded to the State Designee for the State of Florida.
Please contact us if there are any questions about this submittal.
Very truly yours, W. H. Bohlke Vice President Nuclear Engineering and Licensing WHB/JWH Attachments cc:
Stewart D. Ebneter, Regional Administrator, Region II, USNRC Senior Resident Inspector, USNRC, St. Lucie Plant Mr. Jacob D. Nash, Florida Department of Health and Rehabilitative Services
References:
Exxon Report, XN-NF-507, "ENC Setpoint Methodology for CE Reactors,"
dated July 1980.
2 ~
Advanced Nuclear Fuels
- Report, ANF-507 (P)
Addendum 1
"Advanced Nuclear Fuels Corporation Setpoint Methodology for CE Reactors:
Three Dimensional Axial Power Distribution Generation,"
dated June 1988.
3.
NRC Letter, M.W. Hodges (NRC) to R.A. Copeland (ANF), "ANF 3-dimensional Setpoint Methodology for Combustion Engineering Reactors,"
dated July 8, 1988.
STATE OF FLORIDA
)
)
COUNTY OF PALM BEACH
)
~
W. H. Bohlke being first duly sworn, deposes and says:
That he is Vice President, Nuclear Engineering and Licensing of Florida Power
& Light Company, the Licensee herein; That he has executed the foregoing document; that the statements made in this document are true and correct to the best of his knowledge, information and belief, and that he is authorized to execute the document on behalf of said Licensee.
W. H. Bohlke Subscribed and sworn to before me this
'/+1 aay of NOTARY PUBLIC, in a for the County of Palm Beach, State of Florida NotaIy Pubf!o State of Rottda My Comm. Exp. Feb. 18, 1985 My Commission expires Bow~ th
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