ML18127B104
| ML18127B104 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie |
| Issue date: | 02/25/1977 |
| From: | Robert E. Uhrig Florida Power & Light Co |
| To: | Ziemann D Office of Nuclear Reactor Regulation |
| References | |
| L-77-60 | |
| Download: ML18127B104 (6) | |
Text
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0 U.S. NUCLEAR REGULATORY CO MISSION tcC DISTRIBUTION FoR PART 50 DOCKET MATERIAL DOCKET NUMBER 50-335 FILE NUMBER I.ETTE R ABORIGINAL ClcoP Y ONOTORIZED IRUNCLASSIFIE D TO: Mr, D. L. Ziemann PROP INPUT FORM FROM:FPL Miami, Fla.
33101 R E Uhrig DATE OF DOCUMENT 2-25-77 DATE RECEIVED 2-28-77 NUMBER OF COPIES RECEIVED 3 signed 37 CC DEscRIPTIoN Ltr furn info on pressure-temperatur limits for the X9a~Mz firstz 2 effective years of full power operation
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1P gure 3/4 4-23a entitled "Reacto Coolant System Pressure Temperature Limit-ations for up to 5 Years of Full Power Ope ation. ". ~ 1P (40 cys encl rec'.d)
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FOR ACTION/INFO RMATION RO ECT NAQ LIC ASST VL4 PROJECT MANAGER'IC ASST NRC PDR OELD GOSSXCK & STAFF, MIPC CASE HARLESS PROJECT MANAGEMENT BOYD PE COLLINS HOUSTON PETERSON MELTZ HELTEMES SKOVHOLT LPDR tc.~
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INTERNALD SYSTEMS SAFETY HEINEMAN SCHROEDER ENGINEERING MACARR BOSNAK SD5lEIL PAWLICK REACTOR SAFE ROSS NOVAK ROSZTOCZY CHECK AT&I SALTZMAN RUTBERG EXTERNAL DISTRIBUTION NAT LAB REG V.IE LA PDR CONSULTANTS:
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ISTRI BUTION PLANT SYSTEMS TEDESCO XPPOLXTO OPERATING REACTORS STELLO OPERATING TECH EISENHUT B 0 ULR KSON OR S TE SAFE ERNST BALLARD SPANGLER SITE TECH GAMMILL STEPP HULMAN SXTE ANALYSIS VOLLMER BUNCH J ~ COLLINS
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. O. BOX 013100, MIAMI, FL 33101
<<y9 i/i FLORIDAPOWER 8c LIGHTCOMPANY February 25, 1977 L-77-60 Office of Nuclear Reactor Regulation Attention:
Mr. Dennis L. Ziemann, Chief Operating Reactors Branch g2 Division of Operating Reactors U.
S. Nuclear Regulatory Commission Washington, D.C.
20555
Dear Mr. Ziemann:
Re:
St. Lucie Unit 1 Docket No. 50-335 Pressure-Tem erature Limits Your letter of February 15, 1977 requested that we revise our pressure-temperature limits for the first, 2 effective years of full power operation (Technical Specification Figure 3.4-2a) to provide additional margin to assure compliance with Appendix G to 10 CFR Part 50.
More specifically, you requested that we commit to using Figure 3.4-2b as our present limit, and to submit a subsequent application for license amend-ment to formally change the Technical Specifications in a manner to assure compliance with Appendix G.
We have studied several references (SRP 5.3.2, BTP MTEB No. 5-2, and Appendix G to 10 CFR Part,
- 50) dealing with fracture toughness requirements and have developed a new curve with which to replace Figure 3.4-2a.
We feel that our new curve conservatively depicts operating conditions for,up to 5 effective years of full power operation, and that it will not. be necessary for us to commit in the interim to using Figure 3.4-2b. (see attached)
To allow for an orderly transition to our new curve, we plan to begin using it by March 4, 1977.
. We will then -submit an application for license amendment to replace the present Figure 3.4-2a with our new curve by March 18, 1977.
Very t y yours, Robert E. Uhrig Vice President REU/MAS/ms cc:
Norman C. Moseley, Region II Robert Lowenstein, Esquire QOQ'EOPLE...
SERVING PEOPLE
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LUCIE UNIT
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REACTOR COOLANT SYSTEM PRESSURE TEMPERATURE LIMITATIONS FOR UP TO 5 YEARS OF FULL POWER OPERATION I
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