ML17216A625

Proposed Tech Specs,Incorporating Revised Pressure/Temp Limits & Results of Low Temp Overpressure Protection Analysis

ML17216A625
Person / Time
Site:	Saint Lucie
Issue date:	07/15/1986
From:	FLORIDA POWER & LIGHT CO.
To:
Shared Package
ML17216A624	List: ML17216A623 ML17216A625
References
NUDOCS 8607220407
Download: ML17216A625 (37)

Text

ATTACHMENT 3 St.Lucie Unit 2 P/T Limits and LTOP Analysis Pro osed Tech'nical S ecification Chan es o Revise Specification 3.4.9.I o Replace Figure 3.4-2 through 3.4-4 with new Figures 3.4-2 through 3.4-I 5 o Revise Specification 4.4.9.l.2 o Revise Specification 3.4.9.3 o Add Table 3.4-3 o Revise the Bases for Specification 3/4.4.9 8b07220407 8b0715 8 PDR ADOCK 0500038'9 p'DRQ M AS3/026/7 F~e~~e 8'I V eel I e>>

REACTOR COOLANT SYSTEM 3/4.4.9 PRESSURE/TEMPERATURE LIMITS REACTOR COOLANT SYSTEM LIMITING CONDITION FOR OPERATION 3.4.9.1 The Reactor Coolant Sys m (except the pressurizer

)temperature and pressure shall be limited in a dance with Figures during heatup, cooldown, criticality, and inservice leak and hydrostatic testing,~k.

a 0 b.C.A m imum he up of 10 in any hour per od with R cold 1 te eratur less than F.A aximum he tup of 30 F in any-hour p riod wi RCS cold eg temp ature gr ter than 2'F but ss than 18 F.maximum h tup of F in an 1-hour p iod with CS cold leg tern erature gr ter tha 1184F bu less tha 3704F.maximum heatu of 100 F i any 1-ur perio with RCS old leg mperatur grea r than 370 F.A aximum coo down of 04F in an 1-hour p riod wit RCS cold eg mperature ess tha 754F.A aximum c ldown of 04F in a 1-hour eriod wit RCS col leg temp ature gr ter than 54F but ss than 864F.A ximum c oldown of 04F in a 1-hour er iod wit RCS col leg templature eater tha 864F bu less tha 974F.A aximum cooldow of 100'n any hour per'with R cold le temperat e great than 9 F.A m ximum t perature ange of ess than r equal 104F in ny 1-our per d during nservice ydrostati and lea testing erations ove the eatup an cooldown imit cur s.APPLICABILITY:

At al l times.ACTION: With any of the above limits exceeded, restore the temper ature and/or pressure to within the limit wi'thin 30 minutes;perform an engineering evaluation to determine the effects of the out-of-limit condition on the structural integrity of the Reactor Coolant System;determine that the Reactor Coolant System remains acceptable for continued operations or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and reduce the RCS T and pressure to less avg than 200 F and 500 psia, respectively, within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.SURVEILLANCE RE UIREMENTS I 4.4.9.1.1 The Reactor Coolant System temperature and pressure shall be determined to be within the limits at least once per 30 minutes during system heatup, cooldown, and inservice leak and hydrostatic testing operations.

ST.LUCIE-UNIT 2 3/4 4-29

~-.INSERVICE/HYDRO TEST..COO LDOWN~":~'EATUP~:: g 2000 g 1500 N I g 1000 A z 5~~--'OWEST SERVICE TEMP,:~172'F~~~5-)r::::.-:;.::

':..:~::::.'.'ORE CRITICAL::'INIMUM.BOLT UP:.'-." TEMP.62'F-'.: MIN.TEMP.:~:-..BOLTUP:: CORE.CRITICAL~~~~541 PSIA'52 100 SEE TECH, SPEC.3.4.$-1 FOR HEATUP AND COO RATE LIMITATIONS TRCS-INDICATED RCS TEMP,'F FIGURE 3.4-2 REACTOR COOLANT SYSTEM PRESSURE TEMPERATURE LIMITATIONS 0 TO 2 YEARS OF OPERATION ST;LUCIE-UNIT 2"3/4 4-31

'INSERVICE/HYDRO TEST'=.:-:." l~~~W~-2500 C IL N CC 8 I CJ D R 2000:: LOWEST:-'i SERVICE TEMP 1720 F I 1500 I I RE CRITICAL: 'OOLDOWN P f: 'SEE H.SPEC.3,4.9-1 FOR H TUP AND COOLDO LIMITATIONS

~~I i~'I'-"".:: j::.>::.:

.-.-'MIN TEMP'OLT UP: CORE.CRITICAL..

-82 100 200 TRCS~INDICATED RCS TEMP,'F FIGURE 3.44 REACTOR COOLANT SYSTEM PRESSURE TEMPERATURE LIMITATIONS 2 TO 10 YEARS OF OPERATION ST.LUCIE-UNIT 2 3/4 4-32 y1'"'NSERVICE/HYDRO TE..COOLDOWNi:" HEATUP'...

~~'CORE CRITICAL.i: Oa W N 9 a W 5 CL R 5 1600 1000...-..LOWEST""'::.:: SERVICE.TEMP"'172'F I I I I'.:~:~~HEATUP.:..'.~iOOLDOWN CSEE H.SPEC.3.4.8 1'.FOR H TUPAND COOLDO LIMITATIONS

.MIN.TEMP.BOLTUP'.:::: 'ORE CRITICA 0 62 100 200 300 400 TRCS~INDICATED RCS TEMP,'F FIGURE 3.44 REACTOR COOLANT SYSTEM PRESSURE TEMPERATURE LIMITATIONS 10 TO 40 YEARS OF OPERATION ST.LUCIE-UNET 2 3/4 4-33 ST.LUCIE-2 P/T LIMITS,5 EFPY HEATUP AND CORE CRITICAL 2600~4~I~I 60 F/HR~~~~~~2000 C Oe 1600 N I 1000 I CJ Q R 500~~~~.LOWEST SERVICE TEMP 168oF F/HR 636 PSIA'CORE CRITICAL NAf<Nu/fI QLLOuOASM H 0 mS HU, 4F/HR Temperature Uelt, 4F 0 0 MIN.BOLTUP TEMP.M 50 100<3C7 i3C7 TC INDICATED REACTOR COOLANT TEMPERATURE nJ~F~Zg-3 ST.LUCIE-2 P/T LIMITS, S EFPY COOLDOWN AND INSERVICE TEST 2500~~~'-"-INSERV ICE TEST 2000 1600 N a 1000 Q a 5 ERMAL-ISOTH: LOWEST SERVICE TEMP.168 F 680 PSIA 100 F/HR 8c ISO THE RM AL='0 30 SI 1$lM<<OC af-112 112-ill i12$NAXlfHLIM LLOtdA LE C 5 RATgg m, F/HR Temperature Umit, F 30 F/HR 100 0 0 MIN.BOLTUP TEMP.TC INDICATED REACTOR COOLANT TEMPERATURE<

F ST.LUCIE-2 P/7 LIMITS, 10 EFPY HEATUP AND CORE CRITICAL.~~t 504 F/HR't t~'~~I~t~~"'""i'~~i~t'I,*~~.~~~~~~~q~lOWEST SERVICE TEMP.1684F I I~~~~s'...".CORECR ITICA F/HR NAWlmuN AL.Lo+ASLE II U,RAT~>HU, F/HR Temperature List,~F 40 SI 100~3C7 i3C7 I MIN.BOlTUP TEMP.Q~1QO 2QO 30Q 400 TC INDICATED REACTOR COOLANT TEMPERATURE'F 0~-P

<V ST.LUCIE-2 P/T LIMITS, 10 EFPY COOLDOWN AND INSERVICE TEST I--"" INSERVICE TEST~~~~~~~~~2000 1600 1000 4 Q-ISO THER MA LOWEST SERVICE TEMP.168 F~~~L~~F/H R 5 ISOTH AlhQt RATES CD, 4F/HR Teaperature UmIt, 4F 0 0 660 PSIA SPF/HR 65 MIN BOLTUP TEMP.20 30$0 7$1N~~c1M 1Q-130 130-11C~1%TC INDICATED REACTOR COOLANT TEMPERATURE, F Table 1 ST.LUCIE-2-LTOP SYSTEM CHARACTERISTICS, 5 EFPY Relief Valve Ali nment Tem eratures (F)SOTS Relief VaLu,es HU'D PORV','HU CD<102<161 102-295 161-286 Maximum Allowable Heatu and Cooldown Rates HU, F/HR Temperature Llmi, F CD, F/HR Temperature Limit, F 00 50 100<367>367 20 30 50 75 100<86 86-112 112"128>128 LTOP S stem General Re uirements[Maximum I LTOP Temperatures:

For Heatup: For Coo!down: Maximum Secondary-to-Primary Temperature Differential for RCP Start: Maximum Calibration Interval for Pressurizer Pressure Transmitters:

Maximum Number of RCPs Allowed to Operate below 2004F: HPSI and Charging Pump-Combinations Allowed to be Aligned to the RCS: 'At T<200oF c At 2000F<T<295 F C-.At T->295oF c 2954F 286OF q0oF 18 months Two 2 Charging Pumps l 1 HPSI C 3 Charging Pumps 2 HPSI 6 3 Charging Pumps Table 2 ST;LUCIE-2 LTOP SYSTEM CHARACTERISTICS, 10 EFPY Relief Valve All nment Tem eratures (F)SOS Relief Valves HU CD HU PORV CD<156<179 156"313 179"304 Maximum Allowable Heatu and Cooldown Rates HU, F/HR Temperature Limit, F CD, F/HR Temperature I imit, F 40 50 100<367<<36?20 30 50 75 100<104 104"130 130-146>146 LTOP S stem Ceneral Re uirements[Maximum J LTOP Temperatures:

For Heatup: For Cooldown: Maximum Secondary-to-Primary Temperature Differential for RCP Start: Maximum Calibration Interval for Pressurizer Pressure Transmitters:

Maximum Number of RCPs Allowed to Operate below 200oF: HPSI and Charging Pump Combinations Allowed to be Aligned to the RCS: At T<200~F At200F<T<313F c-At T>313~F c 313oF 304OF 40oF 18 months Two 2 Charging Pumps 1 HPSI 6 3 Charging Pumps 2 HPSI 6 3 Charging Pumps

Table 3 ST.LUCIE-2 LTOP SYSTEM CHARACTERISTICS, 15 EFPY SQCS Relief VaLves HU CD<165~<190 165-324 190-315 Relief Valve Ali nment Tem eratures (oF)PORV'-HU CD Maximum Allowable Heatu and Cooldown Rates HU;F IHR Temperature, Limit, oF CD, FIHR Temperature Limit, F 40 50 100<89 89-367>367 20 30 50 75 100<115 115-141 141-157~157 LTOP S stem General Re uirements[Maximum]LTOP Temperatures:

For Heatup: For Cooldown: Maximum Secondary-to-Primary Temperature Differential for RCP Start: Maximum Calibration Interval for Pressurizer Pressure Transmitters:

Maximum Number of RCPs Allowed to Operate below 200 F: HPSI and Charging Pump Combinations Allowed to be Aligned to the RCS: At T<200oF At 200oF<T<324oF C-At T>324oF C 324oF 315oF 40oF 18 months Two ,2 Charging Pumps 1 HPSI 8 3 Charging Pumps 2 HPSI C 3 Charging Pumps Table 4 SJ.LUCIE-2 LTOP SYSTEM CHARACTERISTICS, 20 EFPY Relief Valve All nment Tem eratures ('F)SACS Relief Vabces HU CD PORV,.=-.HU CD<172<196 172-330 196-321 40 50 100<96 96"367>367 20 30 50 75 100 Maximum Allowable Heatu and Cooldown Rates HU, F/HR Temperature Limit, F CD, F/HR Temperature Limit,~F<121 121"147~1 47"'l63>163 LTOP S stem General Re uirements[Maximum)LTOP Temperatures:

~-For Heatup: For Cooldown: Maximum Secondary.-to-Primary Temperature Differential for RCP Start: Maximum Calibration Interval for Pressurizer Pressure Transmitters:

Maximum Number of RCPs Allowed to Operate below 200 F: HPSI and Charging Pump Combinations Allowed to be Aligned to the RCS: At T<2000F At 200 F<T<330 F At T>330~F c 3300F 3214F 400F 18 months Two 2 Charging Pumps 1 HPSI C 3 Charging Pumps 2 HPSI 6 3 Charging Pumps Table 5 ST.LUCIE-2 LTOP SYSTEM CHARACTERISTICS, 25 EFPY SIX;$Relief Valves HU CD Relief Valve All nment Tem eratures (OF)PORV.'U CD~<178<201 178-335 201-326 Maximum Allowable Heatu and Cooldown Rates HU, F/HR~Temperature Limit, F CD, F/HR Temperature Limit, F 40 50 100<102 109-367 367 20 30 50 75 100<83 83-126 126"152 152-168>168'LTOP S stem General Re uirements f Maximum)LTOP Temperatures:

For Heatup: For Cooldown: Maximum Secondary-to-Primary Temperature Differential for RCP Start: Maximum Calibration Interval for Pressurizer Pressure Transmitters:

Maximum Number of RCPs Allowed to Operate below 200 F: HPSI and Charging Pump Combinations Allowed to be Aligned to the RCS: At T<200~F At 200oF<T<335oF c-At T>335oF C 3350F 326oF 40oF 18 months Two 2 Charging Pumps 1 HPSI 6 3 Charging Pumps 2 HPSI C 3 Charging Pumps Table 6 ST.LUCIE-2 LTOP SYSTEM CHARACTERISTICS,'30 EFPY SM;S Relief Vaivqs HU CD Relief Valve All nment Tem eratures (~F)PORV.HU CD<1 82<205 182-339 205-330 Maximum Allowable Beatu and Cooldown Rates HU, F/HR Temperature Limit, F CD, oF/HR Temperature Limit, F 40 50 100<106 106-367>367 20 30 50 75 100<87 87-130 130-156 156-172>172 LTOP S stem General Re uirements[Maximum J LTOP Temperatures:

For Heatup: For Cooldown: Maximum Secondary-to-Primary Temperature Differential for RCP Start: Maximum Calibration Interval for Pressurizer Pressure Transmitters:

Maximum Number of RCPs Allowed to Operate below 2000F: HPSI and Charging Pump Combinations Allowed to be Aligned to the RCS: At T<200 F At 2000F<T<339oF c-At T>>339oF C 339~F 330~F 000F 18 months Two 2 Charging Pumps 1 HPSI 6 3 Charging Pumps 2 HPSI 6 3 Charging Pumps Table 7 ST.LUCIE-2 LTOP SYSTEM CHARACTERISTICS, 32 EFPY SDCS Relief Valv.es HU CD Relief Valve Ali nment Tem eratures (oF)PORV.HU CD<184<207 184-341 207-332 Maximum Allowable Heatu and Cooldown Rates HU, F/HR Temperature Limit, F CD, F/HR Temperature Limit, oF 40 50 100<108 108"367>367 20 30 50 75 100<89 89-132 132-158 158"174>174 LTOP S stem General Re uirements[Maximum]LTOP Temperatures:

For Heatup: For Cooldown: Maximum Secondary-to-Primary Temperature Differential for RCP Start: Maximum Calibration Interval for Pressurizer Pressure Transmitters:

Maximum Number of RCPs Allowed to Operate below 200'F: HPSI and Charging Pump Combinations Allowed to be Aligned to the RCS: At T<200 F c At 200 F<T<341oF c-At T>341~F C 341oF 3320F 40'F 18 months Two 2 Charging Pumps 1 HPSI 6 3 Charging Pumps 2 HPSI C 3 Charging Pumps 2500 2000 ca 1600 0 Q I CJ 0 R Ch CJ 4 1000 0 0 ST.LUCIE-2 P/7 LIMITS, 16 EFPY HEATUP AND CORE CRITICAL 60oF/HR LOWEST SERVICE TEMP.1684F CORE CRITICAL-60 F/HR NAXimum ALLotdA~H/Q~~F/HR HU, F/HR Tpepceature LImit, F 535 PSIA cia 85-3C7 i3C7 10 50'IOO MIN.SOLTUP TEMP.TC INOICATEO REACTOR COOLANT TEMPERATURE oF ST LUCIE.2 P/T LIMITS, 46 EFPY COOLDOWN AND INSERVICE TEST INSERVICE TEST g a.1600 CC M LC S 1000 I C7 A R CJ gl 4.600 LOWEST SERVICE TEMP.1684F ISOTHERMAL

-30 F/HR-F/H TH ERM R&ISO 20 30 50 75 100 c115 18-1e1 111-157~157 MAW~niwn ALLau)ABLE, 4 RAT CO, F/HR Teeperature umit, 1=0 MIN.BOLTUP TEMP.TC~INDICATED REACTOR COOLANT TEMPERATURE, F n/~Fogy g ST.LUCIE-2 P/T LIMITS, 20 EFPY HEAT UP AND CORE CRITICAL 2500 50 F/HR 2000 1500 N IL 1000 Q., K 500 LOWEST SERVICE TEMP.1684F 504 F/H 4PF/HR 535 PSI CORE CRITICAL tnt sieve A~up,a~'YSS HU, F/HR Teeperature Llmlt, 4F MIN.BOLTUP TEMP.40 50)00 c96 94-367 i367 TC INDICATED REACTOR COOLANT TEMPERATURE'I II ST.LUCIE-2 P/T LIMITS, 20 EFPY COOLDOWN AND INSERVICE TEST 2500 INSERVICE TEST a.1500 etc N tt;0 1N W CJ 4 a 5 500 LOWEST SERVICE TEMP 168oF ISOTHERMAL SO4F/HR SO 1004F/HR 8c ISOTHE AL-20 30 50 75 100 ct21'IS-147 117-163~Ni3 Mh tmcj~At.mesh~C O gAZgz I, OF/HR Temperature LImIt, OF 0 0 MIN.BOLTUP TEMP.TC-INDICATED REACTOR COOLANT TEMPERATURE, oF ST.LUC S,26 EFPY HEAT UP AND CORE CRITICAL 2500 60 F/HR 2000 g 1600 N K 1000 C7 z'0 LOWEST SERVICE TEMP 168oF 604F/HR F/HR 635 PSIA CORE CRITICAL Nhwimu~Ai<ouo p e.a.HU, FIHR Teeperature Umit, F 0 0 MIN.BOLTUP TEMP, 10 SO 100<102 1Q-3C7 367 TC INDICATED REACTOR COOLANT TEMPERATURE oF

ST.LUCIE-2 P/T LIMITS, 26 EFPY COOLDOWN AND INSERVICE TEST INSERV ICE TEST 2000 g cg.1600 N 1000 C 8: 5 CL LOWEST SERVICE.TEMP.1684F ISOTHERMAL

.:.304F/HR 100 HR 8c ISOTHERMAL 20 30 50 75 100 ce3 el-126 126-1$2 152-16e F168 NAWWunl Au.p+ABI.E, 4 D RNES'O, F/HR Temperature LImit, F 00 MIN.BOLTUP TEMP.TC INDICATED REACTOR COOLANT TEMPERATURE, F ST.LUCIE-2 P/T LIMITS, 30 EFPY HEATUP AND CORE CRITICAL 604 F/HR 2 000 Os 1500 N 1000 A R 4=LOWEST SERVICE~TEMP.1884F 50 F/HR F/HR 638 PSIA RE CRITICAL HU, F/HR Tamperature Limit, F 0 0 ININ.BOLTUP TEINP.IO 50 100<<106 1Q-367>367 TC INDICATED REACTOR COOLANT TElNPERATURE,4F ST LUCIE-2 P/T LIMITS, 30 EFPY COOLDOWN AND INSERVICE TEST INSERVICE TEST 2000 1600 N 4>000 C(J.R LOWEST SERVICE TEMP)B8oF ISOTHERMAL 30 F/HR 100 F/H 5 ISOT MAL~(hlU4 ALL~ABLE 0 RATES I, 4F/HR Temperature Umit, F 20 30 50 75 100 c 87 l7" 130 130-'I 56 156"172>172 0 MIN.BOLTUP TEMP.TC-INDICATED REACTOR COOLANT TEMPERATURE, F ST.LUCIE-2 P/T LIMITS, 32 EFPY HEATUP AND CORE CRITICAL QPF/HR 1600 N lC LOWEST SERVICE TEMP.1%I F CORE CRITICAL QPF/HR PA%(~v+~4~8M H 0 QATaS F/HR S35 PSIA HU, 4F/HR Tanperature LImlt, 4F 10 50 IOO clM lQ"367%367 Pp MIN.BOLTUP TEMP.TC iNDICATED REACTOR COOLANT TEMPERATURE' ST.LUCIE-2 P/T LIMITS, 32 EFPY COOLDOWN AND INSERVICE TEST INSERVICE TEST 1SOO 4 1000 I Q R 5 soo ISOTHER MAL 30 F/HR LOWEST SERVICE TEMP.1684F 100 F/HR8c I SOT Hf RMAL 20 30 50 75 100<dS 1%-1 32 132" 150 15d-171%171~%imam Au, a~n~s CO, 4F/HR Tenpec'ature Limit, 4F 0 0 N.BOLTUP TEMP.100 200 300 400 TC INDICATED REACTOR COOLANT TEMPERATURE, F REACTOR COOLANT SYSTEM SURVEILLANCE RE UIREMENTS Continued 4.4.9.1.2 The reactor vessel material irradiation surveillance specimens shall be removed and examined, to determine changes in material properties, at the intervals required by 10 CFR 50 Appendix H in accordance with the schedule i Table 4.4-5.The results of these examinations shall be used to update'ST.LUCIE" UNIT 2 3/4 4-30 REACTOR COOLANT SYSTEM OVERPRESSURE PROTECTION SYSTEMS LIMITING'CONOITION FOR OPERATION Moga4Oo sees 5'a JP soi'6 4<e readov-vessel lleU ovI I so>ow+ŽIs less f'4~ov uJ fo+<Qppr>plve,k v4<<g m<~I, e.3,+-3.3.4.9.3 At least one of the followin overpressure protection systems shall be OPERABLE:$7o a.Two power-operated reli valves (PORVs),~are-with a lift setting of less than or equal to psia>a~d t~o shut~coot~q syd~~r (i~F VnJVe5 DCSRVg)>AC COSY a lift Seft'in'f leSS f4~Orlq+SLl to$56 PSi<~b.The Reactor Coolant System depressurized with an RCS vent of greater than or equal to 3.58 square inches.APPLICABILITY:

ACTION: b.C.or ogi~Spt 5i'V og SbcSRV With one PORV inopera e, restore the inoperable PORV to OPERABLE status within 7 days or depressurize and vent the RCS through a greater than or equal to 3.58 square inch vent(s)within the next 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.beg sDcsRL(g With both POR s inoperable, depressurize and vent the RCS through a greater than or equal to 3.58 s uare inch vent(s)within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.SD CS Vs In the event either the POR s~or the RCS vent(s)are used to mitigate a RCS pressure transient, a Special Report shall be prepared and submitted to the Commission pursuant to Specific tion 6.9.2 within 30 days.The report shall describe the sbcsRVs circumstances initiating the transient, the effect of the POR s or vent(s)on the transient and any corrective action necessary to prevent recurrence.

d.The provisions of Specification 3.0.4 are not applicable.

SURVEILLANCE RE UIREMENTS 4.4.9.3.1 Each PORV shall be demonstrated OPERABLE by: a.In addition to the requirements of Specification 4.0.5, operating the valve through one complete cycle of full travel at least once per 18 months.ST.LUCIE-UNIT 2 3/4 4"36 TABLE 3.4-3 LOW TEMPERATURE OVERPRESSURE PROTECTION Maximum LTOP Tem erature (F)Time in Life (EFP)~Heatu Cooldown 0-5 5-l0 I 0-I 5 I5-20 20-25 25-30 30-32 295 3I3 324 330 335 339 34I 286 304 3I5 32I 326 330 332 M A 53/026/8 REACTOR COOLANT SYSTEM BASES 3/4.4.9 PRESSURE/TEMPERATURE LIMITS All components in the Reactor Coolant System are designed to withstand the effects of cyclic loads due to system temperature and pressure changes.These cyclic loads are introduced by normal load transients, reactor trips, and startup and shutdown operations.

The various categories of load cycles used for design purposes are provided in Section 5.2 of the FSAR.Ouring startup and shutdown, the rates of temperature and pressure changes are limited so that the maximum specified heatup and cooldown rates are consistent with the design assumptions and satisfy the stress limits for cyclic operation.

During heatup, the thermal gradients in the reactor vessel wall produce thermal stresses which vary from compressive at the inner wall to tensile at the outer wall.These thermal induced compressive stresses tend to alleviate the tensile stresses induced by the internal pressure.Therefore, a pressure-temperature curve based on steady state conditions (i.e., no thermal stresses)represents a lower bound of all similar curves for finite heatup rates when the inner wall of the vessel is treated as the governing location.The heatup analysis also covers the determination of pressure-temperature limitations for the case in which the outer wall of the vessel becomes the controlling location.The thermal gradients established during heatup produce tensile stresses at the outer wall of the vessel.These stresses are additive to the pressure induced tensile stresses which are already present.The thermal induced stresses at the outer wall of the vessel are tensile and are dependent on both the rate of heatup and the time along the heatup ramp;therefore, a lower bound curve similar to that described for the heatup of the inner wall cannot be defined.Consequently, for the cases in which the outer wall of the vessel becomes the stress controlling location, each heatup rate of interest must be analyzed on an individual basis.The heatup and cooldown limit curves Figures are composite curves which were prepared by determining t e most conserva sve case, with either the inside or outside wall controlling, for any heatup or cooldown rates of up to 100'F per hour.The heatup and cooldown curves were prepared based upon the most limiting value of the predicted adjusted reference p 0 h i g+he, Q pplicabl~/<au~~a~o~g Figures 9,9-2.w~ghz.+-<z.

The reactor vessel materials have been tested to determine their initial RTNOT the results of these test are shown in Table B 3/4.4-1.,, Reactor opera-tion and resultant fast neutron (E greater than 1 MeV)irradiation will cause an increase in the RT>OT.Therefore, an adjusted reference temperature, based upon the fluence and copper content of the material'in question, can be predicted using Figur 8 3/4.4-1 and the recommendations of Regulatory Guide 1.99, Revisio ,"Effects of Residual Elements on Predicted Radiation Oamage to eactor Vessel Materials." The heatup and cooldown limit curves Figures include predicted adjustments for this shift in RT>>at the end of the applicable service period, as well as adjustments for po45ible errors in the pressure and temperature sensing instruments.

ST.LUCIE-UNIT 2 B 3/4 4-8

REACTOR COOLANT SYSTEM BASES.PRESSURE/TEMPERATURE LIMITS Continued The actual shift in RTN>T of the vessel material will be established periodically during operation by removing and evaluating, in accordance with ASTN E185-73 and 10 CFR Appendix H, reactor vessel mCerial irradiation surveil-lance specimens installed near the inside wall of the reactor, vessel in the core area.The surveillance specimen withdrawal schedule is shown in Table 4.4-5.Since the neutron spectra at the irradiation samples and vessel inside radius are essentially identical, the measured transition shift for a sample can be applied with confidence to the adjacent section of the reactor vessel.The heatup and cooldown curves must be recalculated when the delta RTNOT determined from the surveillance capsule is different from the cal ul ted delta RTNOT for the equivalent capsule radiation exposure.The pressure-temperature limit lines shown on Figures for reactor criticality and for inservice leak and hydrostatic testing have been provided to assure compliance with the minimum temperature requiyements of Appendix G to 10 CFR 50.The maximum RTN>T for all Reactor Coolant System pressure-retaining mate-rials, with, the exception of the reactor pressure vessel, has been determ ed to 50 F.The Lowest Service Temperature limit line shown on Figures is based upon this RT since Article NB-2332 (Summer Ad enda of 1972)of Section III of the ASIDE Bo)Nr and Pressure Vessel Code requires the Lowest Service Temperature to be RTN>T+100 F for piping, pumps, and valves.Below this temperature, the system pressure must be limited to a maximum of 20K of the system's hydrostatic test pressure of 3125 psia.The limitations.

imposed on the pressurizer heatup and cooldown rates and spray water temperature differential are provided to assure that the pres-surizer is operated within the design criteria assumed for the t performed in accordance with th C 4a)cp>F+g wcsM iaaf vcsr e sore Qahm Ag The OPERABILITY of two PO s or an vent opening of grea er than 3.58 square inches ensures that the RCS will be protected from pressure transients which could exceed the limits of Appendix G to 10 CFR Part 50 when one or more of the RCS cold legs are less than or equal to 280F during cooldown and 320 F during heatup.has ade uate reliev capability to protect the RCS from overpressur zatson when t e transient is limited to either (1)a safety injection actuation in a water-solid RCS with the pressurizer heaters energized or (2)the start of an idle RCP with the secondary water temperature of the steam generator less than or equal to 4894 above the RCS cold leg temperatures with the pressurizer solid.ST.LUCIE-UNIT 2 B 3/4 4-11 0 a ej a t