ML17301A044

Application to Amend License NPF-16 Revising Tech Spec Requirement for Primary & Secondary Coolants in Steam Generator to Be Greater than 100 F When Coolant Pressure Greater than 200 Psig.Ser Encl

ML17301A044
Person / Time
Site:	Saint Lucie
Issue date:	06/17/1983
From:	Robert E. Uhrig FLORIDA POWER & LIGHT CO.
To:	Eisenhut D Office of Nuclear Reactor Regulation
Shared Package
ML17214A236	List: ML17214A234 ML17301A044
References
L-83-349, NUDOCS 8306210160
Download: ML17301A044 (6)

Text

rr REGULATORY ORMATION DISTRIBUTION S M (RIDS)AOCBSSI'ON NBR 83062 1 0 1 60 DOC~DATE!83/06/17 NOTAR IZED~NO FAOIL:50 38%St.Lucie Planti.Unilt 2<Flor ida Power L Light Co+AUTH~NAME AUTHOR AFFILIATION UHRIGiRiE, Florida Power 3 Light Co, RECIP, NAME RECIPIENT AFFILIATION EISENHUTiD

~G.Division of Licensing

SUBJECT:

Application to amend License NPF 16 revising Tech Spec requirement for primary L secondary coolants in steam generator to be greater than 100 F when coolant pressure greater than 200 psig,SER encl.DISTRIBUTION"CODE!8001S COPIES RECEIVED:LTR ENCl'SIZE,-TITLE: Licensing"Submittal:

PSAR/FSAR Amdts 8 Related Correspondence NOTES: DOCKET¹05000389 RECIPIENT ID CODE/NAME A/0 LICENSNG LIC BR¹3 LA INTERNAl o ElD/HDS2 IE/DEPER/KPB 36 IE/DEQA/QAB 21 NRR/DE/CKB 11 NRR/DE/EQB 13 NRR/DE/MEB 18 NRR/DE/SAB 2A NRR/DE/SGEB 30 NRR/DHFS/LQB 32 NRR/DL/SSPB NRR/DS I/ASB NRR/DSI/CS8 09 NRR/DSI/METB 12 NRR D AB 22 I OQ I/MIB EXTERNAL: ACRS 01 DMB/DSS (AMDTS)LPDR 03 NSIC 05 COPIES LTTR ENCL 1 0 1 0 1 0 3 j.1 1 1 2 2 1 1 1 1 1 1 1 1 0 1 1 1 1 1 1 1 1 1 1 0 6-6 1 1 1 1 1 1 RECIPIENT ID CODE/NAME LIC BR¹3 BC NERSESiV~01 IE FILE IE/DEPER/IRB 35 NRR/DE/AEAB NRR/DF/EHEB NRR/DE/GB 28 NRR/DE/MTEB 17 NRR/DE/SGEB 25 NRR/DHFS/HFEB40 NRR/DHFS/PSRB NRR/DS I/AEB 26 NRR/DSI/CPB 10 NRR/DS I/ICSB 16 NRR/DS I/PSB 19 NRR/DSI/RSB 23 RGN2 BNL(AMDT'S ONLY)FEMA~REP DIV"39 NRC PDR 02 NTIS COPIES L'TTR ENCL 1 0 1 1 1 1 1 1 1 0 1 1 2 2 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 3 3'TOTAL NUMBER OF COPIES REQUIRED+LTTR 54 ENCl 07

>>n hr M<<MM'I,, y.I)J'er f')))h 1 4~I r<<l>l ll I'>>f)Mf I"I')!'l)t f ,<<)4 r rh]f If I$..M,,pl-ME,I I I Mfr>>>g>)M>f I gg<<M n>>fe1 fhhepilh'n~X'Mi!I, I r~hi'l li,~I ll)>>1~1>~f>>>>ni i>)nrl>>1 w m>>a:i 3n)fM PILHMQ rr f rQ'>'1>L~Mhli'li~ii I>>')I'M n'Men I 4'Ml))Mi}i 7'If'MM'1'1.'I j(~I)<1 1<I,.l."<<Ir, 4LO"1)I'If h I>}'I'e"It>>if 4')"IM)I I I>>>'I I'e)>i 4')'I I>f JIM)f I Eg 4 hh>>1I eil>>>4 ni,'9>>'", ll hll i<Chef In, I;x1I ir ,hf I I il II r iI'li<<>>i f knb I), I I, M-II r I I I f r f'h N~I fl ft A>>',,r'hhfI>4 f><<'f ,'nl k 4 I hh I ii I,, lf>>'ili'MM, f ii))MMhn>If lf if>, r"lt gg 1 I hf<>'I IM III~i<>275>>to>>2QQ>>and the>>3Q>>to>>20>>jn BASES 3/4 7 2 Pacae 6-20 Delete the words"first half year" in the first line of the double-asterisk footnote.In accordance with I 0 CFR 50.9I(b)(l), a copy of this proposed license amendment is being forwarded to the State Designee for the State of Florida.In accordance with IO CFR 50.9I(a)(I), we have determined that this amendment does not involve any significant hazards considerations pursuant to IO CFR 50.9I(c)in that the amendment is administrative in nature and therefore does not: I)'nvolve a significant increase in the probability or consequences of an accident previously evaluated; or 2)create the possibility of a new or different kind of accident from any accident previously evaluated; or 3)involve a significant reduction in a margin or safety.*el~~I The proposed amendment has been reviewed by the St.Lucie Facility Review Croup and the Florida Power&Light Compariy Nuclear Review Board.In that this amendment is administrative in nature, it has been determined to be a Class II amendment, in accordance with IO CFR I 70.22.A check for pl,200.00 will follow short I y.Very truly yours, Robert E.Uhrig Vice President Advanced Systems&Technology REU/R JS/cab Attachments cc: J.P.O'Reilly, Region II Harold F.Reis, Esquire Ulray Clark, Administrator Radiological Health Services Department of Health and Rehabilitative Services I 323 Winewood Boulevard Tallahassee, Florida 3230I Pa e 3/44-I SAFETY EVALUATlON, This change is administrative/editorial, and therefore of no safety concern.P~3/4 7-14 This change is administrative/editorial (the actual valve closure time is 4.2 seconds, not 5.6 seconds or 5.35 seconds), and therefore of no safety conern.Pa e 3/4 7-I2 and B 3/4 7-4 Limiting Condition for Operation 3.7.2 for Technical Specification 3/4.7.2 requires that the temperatures of both primary and secondary coolants in the steam generators shall be greater than l00oF when the pressure of either coolant in the steam generator is greater than 275 psig.Our NSSS vendor has indicated that the 275 psig limit is incorrect and should be 200 psig.Furthermore, our startup procedures call for initial heating of the primary coolant to be performed utilizing pump heat from the reactor coolant pumps (RCP).However, the pump curve received from the vendor indicates that operation of the RCPs within these primary coolant system pressure limits will cause reduction in life of the RCP seals.Since the temperature of the secondary coolant in the steam generator is at ambient, about 80 to 90oF, this Technical Specification would preclude the use of RCPs to heat up the primary coolant without reducing seal life.\4 4~The bases for this Technical Specification is that by placing limits on the pressure and',temperature of both;the primary and secondary coolants, the pressure induced stresses in the steam generators do not exceed the maximum allowable fracture toughness stress limits.The current limits are based on a steam generator RTNDT of 20oF.However, Technical Specification 3/4.4.9 also contains pressure and temperature limitations for the reactor coolant system (RCS).The bases for these limits is the same as that for Technical Specification 3/4.7.2, i.e., to ensure that the maximum pressure induced stresses do not exceed the maximum allowable fracture toughness stress limits for the RCS pressure retaining components.

Bases 3/4.4.9 states that these curves were developed assuming the maximum RTNDT for all RCS pressure-retaining materials, with the exception of the reactor pressure vessel, of 50oF.Therefore, the pressure/temperature curves for Technical Specification 3/44.9 are appropriate for use for the primary coolant in the steam generator as well, since they are based on a more conservative basis (higher RTNDT)than those in Technical Specification 3/4.7.2.The pressure temperature limits in Technical Specification 3/4.7.2 are clearly more conservative and restrictive than required.Due to the potential problems of the RCP seals being operated at the low pressure currently required, the existing limits of 3/4.7.2 may cause the system to be operated in a condition less safe than desired.Based on the above, it is our determination that removal of the pressure temperature limits for the primary coolant from Technical Specification 3/4.7.2 does not pose a risk to health and safety of the public.This is due to the fact that the secondary pressure boundary remains protected by this Technical'pecification and that the primary pressure boundary is protected by'echnical Specification

~3/4.4.9.Our NSSS vendor concu'rs with this conclusion.

SAFETY EVALUATION (continued)

Pa e 3/4 7-30 Ths change is administrative/editorial, and therefore of no safety concern.Pacee 6-20 This change is administrative/editorial, and therefore of no safety concern.