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 01 60 DOC ~ DATE! 83/06/ 17 NOTAR IZED NO

~ DOCKET ¹ FAOIL:50 38% St.Lucie Planti. Unilt 2< Flor ida Power L Light Co+ 05000389 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:

RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME L'TTR ENCL A/0 LICENSNG 1 0 LIC BR ¹3 BC 1 0 LIC BR ¹3 LA 1 0 NERSESiV ~ 01 1 1 INTERNAlo ElD/HDS2 1 0 IE FILE 1 1 IE/DEPER/KPB 36 3 IE/DEPER/IRB 35 1 1 IE/DEQA/QAB 21 j. 1 NRR/DE/AEAB 1 0 NRR/DE/CKB 11 1 1 NRR/DF/EHEB 1 1 NRR/DE/EQB 13 2 2 NRR/DE/GB 28 2 2 NRR/DE/MEB 18 1 1 NRR/DE/MTEB 17 1 1 NRR/DE/SAB 2A 1 1 NRR/DE/SGEB 25 1 1 NRR/DE/SGEB 30 1 1 NRR/DHFS/HFEB40 1 1 NRR/DHFS/LQB 32 1 1 NRR/DHFS/PSRB 1 1 NRR/DL/SSPB 0 NRR/DS I/AEB 26 1 NRR/DS I/ASB 1 1 NRR/DSI/CPB 10 1 1 NRR/DSI/CS8 09 1 1 NRR/DS I/ICSB 16 1 1 NRR/DSI/METB 12 1 NRR/DS I/PSB 19 1 1 NRR D AB 22 1 1 NRR/DSI/RSB 23 1 1 I OQ 1 1 RGN2 3 3 I/MIB 1 0 EXTERNAL: ACRS 01 6 -6 BNL(AMDT'S ONLY)

DMB/DSS (AMDTS) 1 1 FEMA~REP DIV "39 LPDR 03 1 1 NRC PDR 02 NSIC 05 1 1 NTIS

'TOTAL NUMBER OF COPIES REQUIRED+ LTTR 54 ENCl 07

'I,, y. I) J ' 'n

>>n hr M<<MM er f ') ~ X Mi!I, Ir

) )h 1 4 ~

I r<<l > l ll I' >> ~ hi'l f)Mf I "I')  !

l)t f

,<<)4 r rh]f If I $ .. M,,pl-ME,I I I li, ~ I ll )

Mfr>>>g>) M>f I gg<<M n>> fe1 fhhepilh >>1 ~ 1>

~ f >>>> ni i rr f rQ'>'1 >L~ Mhli ' li ~ ii 'I I> f JIM )f I In, I; n 'Men I 4'Ml ) 7'If' MM'1'1.' 'e "It>> if 4') "IM)

>)nrl>>1 I>> ') I 'M

) Mi} i I j( I I I>>>'I I ' e)> i Eg 4

hh >>1I

~ I )< 1 1 4 ') eil>>> 4 ni, '9>>

w m>>a:i < I,.l ". << I r, '",

ll hll i<< I n Mif fl 3n) fM PILHMQ 4 LO "1 ) I 'If h I >}'I fMI) l f,i ill rf >Chef

x1I ir I

,hf I I iI 'li<<>> i f knb il II I I, M- II r ),

I ii I hf I,, <<

I i

4 I lf I 'h N ~

I fl ft I

>4 >>

k 'ili'MM, f I A>> ii))

MMhn >If lf r f f><<'f if>, r r >>'I "lt I hh gg 1 f ,,r 'hhf

'nl IM III ~ i<< I "h,l M. e',

I Il. f

OX 14000, JUNO BEACH, FL 33408 FLORIDA POWER & LIGHT COMPANY June l7, l983 L-83-349 Office of Nuclear Reactor Regulation Attention: Mr. Darrell G. Eisenhut, Director Division of Licensing .

U. S. Nuclear Regulatory Commission Washington, D.C. 20555

Dear Mr. Eisenhut:

Re: St. Lucie Unit No. 2

~

Docket No. 50-389 Proposed License Amendment Steam Generator Pressure/Temperature Limitation and Administrative/Editorial chan es In accordance with IO CFR 50.90, Florida Power & Light Company submits herewith three signed originals and forty copies of a request to amend Appendix A of Facility Operating License NPF- I 6.

This amendment is submitted to revise the requirement for both primary and secondary -coolants in the steam generator to be greater than IOOOF when the pressure in either coolant is greater .than 200 psig. This change is necessary to allow heatup of the primary coolant w'ith fhe Reactor Coolant Pumps. This change is a revision to the like change submitted as part of FPL letter L-83-248 dated

.April 20, l 983, and therefore, supercedes that part of the April 20th submittal.

This amendment is also submitted to.make several administrative/editorial changes.

These changes have been identified as a result of continuing review of the Technical Specifications by both NRC and FPL.

The proposed amendment is described below and shown on the accompanying Technical Specif ication pages.

~P3/3 A-1 In the footnote, delete "and 3. I0.6". There is no Special Test Exception 3. I0.6.

~33/3 3-13 Change the "5.6" and the "5.35" in Specification 4.7. I.6 b. to "4.2".

Pa e 3/4 7-I2 Revise Specification.3.7.2 to apply only to the secondary coolant in the steam generator. Also, change the "275" in Specifications 3.7.2, 3.7.2 a. and 4.7.2 to "200".

Pa e 3/4 7-30 Change the "3.7.I I.4 and 3.7.I I.5" in Specification 3.7.I I.I c. to "3.7.11.3 and 3.7.I l.4".

Il PEOPLE... SERVING PEOPLE

Page 2 Office of Nuclear Reactor Regulation Mr. Darrell G. Eisenhut, Director i

Pa e B 3/4 7-4 Change the>>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

SAFETY EVALUATlON, Pa e 3/44-I 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.