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 MAS3/026/7

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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.

a0 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.

b. 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 temp l ature 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.

C. 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~::

~

~~

) r::::.-:;.:: ':..:

5-

~::::.'.'ORE

~

CRITICAL:

g 2000

-- 'OWEST SERVICE TEMP,

~ 172'F g 1500 N

'INIMUM

. BOLT UP

.'-." TEMP. 62'F -'.:

I ~ ~

1000 g

A z

5 541 PSIA '

CORE ~ ~ ~ ~

CRITICAL MIN. TEMP.:

BOLTUP

~: -..

SEE TECH, SPEC. 3.4.$ -1 FOR HEATUP AND COO RATE LIMITATIONS 52 100 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

' '=.:-:." l INSERVICE/HYDRO TEST

~ ~ ~ W ~-

2500 C RE CRITICAL:

2000::

IL N LOWEST CC

-'i SERVICE TEMP 1720 F 8 I 1500 I

I CJ D I R

'OOLDOWN

'SEE H. SPEC. 3,4.9-1 FOR H TUP AND P f COOLDO LIMITATIONS

~ ~

I i ~ 'I '-"".:: j::.>::.: .-.-'  : CORE MIN TEMP'OLT

. CRITICAL..

UP

-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

...-.. LOWEST ""' '

SERVICE '::.::

W . TEMP N "' 172'F I I

1600 9 I aW 5

CL R

5 1000 HEATUP .: .. '.~ ~

i'

~

I CSEE FOR H TUPAND

~:

H. SPEC. 3.4.8 1

'OOLDOWN COOLDO LIMITATIONS

'ORE CRITICA MIN. TEMP. BOLTUP '.::::

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 I ~

~ 4 I

~

~ ~ ~ ~ ~ ~

60 F/HR

~ ~ ~ ~

2000 C

Oe 1600 N . LOWEST SERVICE TEMP 168oF I '

1000 I

CJ Q CORE CRITICAL R

F/HR NAf<Nu/fI QLLOuOASM H 0 mS 636 PSIA 500 HU, 4F/HR Temperature Uelt, 4F MIN. BOLTUP TEMP.

M 50 <3C7 100 i3C7 0

0 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 100 F/HR 8c ISO THE RMAL 1600 N  : LOWEST SERVICE a TEMP. 168 F

='0 NAXlfHLIM LLOtdA LE C 5 RATgg m, F/HR Temperature Umit, F 1000

- ISOTH ERMAL 30 <<OC Q SI af-112 a 1$ 112-ill lM i12$

5 680 PSIA 30 F/HR 100 MIN. BOLTUP TEMP.

0 0

TC INDICATED REACTOR COOLANT TEMPERATURE< F

ST. LUCIE-2 P/7 LIMITS, 10 EFPY HEATUP AND CORE CRITICAL.

~ ~

t 504 F/HR

't

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t ~

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~ ~ .

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'I,*

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lOWEST SERVICE TEMP. 1684F ~ ~

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~s'...".CORECR ITICA NAWlmuN AL.Lo+ASLE II U,RAT~>

HU, F/HR Temperature List, ~F F/HR 40 SI ~3C7 100 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 ~ ~ ~ L ~ ~

1600 LOWEST SERVICE TEMP. 168 F F/H R 5 ISOTH 4 1000 AlhQt RATES ISO THER MA CD, 4F/HR Teaperature UmIt, 4F Q

20 30 c1M

$0 1Q-130 660 PSIA 7$ 130-11C 1N ~1%

SPF/HR 65

~ ~

MIN BOLTUP TEMP.

0 0

TC INDICATED REACTOR COOLANT TEMPERATURE, F

Table 1 ST. LUCIE LTOP SYSTEM CHARACTERISTICS, 5 EFPY Relief Valve Ali nment Tem eratures ( F)

HU 'D SOTS Relief VaLu,es

'HU PORV',

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 20 00 30 <86 50 <367 50 86-112 100 >367 75 112"128 100 >128 LTOP S stem General Re uirements

[Maximum I LTOP Temperatures:

For Heatup: 2954F For Coo!down: 286OF Maximum Secondary-to-Primary Temperature Differential for RCP Start: q0oF Maximum Calibration Interval for Pressurizer Pressure Transmitters: 18 months Maximum Number of RCPs Allowed to Operate below 2004F: Two HPSI and Charging Pump-Combinations Allowed to be Aligned to the RCS:

'At T < 200oF 2 Charging Pumps c

l At 2000F < TC .

< 295 F 1 HPSI C 3 Charging Pumps At Tc -> 295oF 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 PORV HU CD HU 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 20 40 30 <104 50 <367 50 104 "130 100 <<36? 75 130-146 100 >146 LTOP S stem Ceneral Re uirements

[Maximum J LTOP Temperatures:

For Heatup: 313oF For Cooldown: 304OF Maximum Secondary-to-Primary Temperature Differential for RCP Start: 40oF Maximum Calibration Interval for Pressurizer Pressure Transmitters: 18 months Maximum Number of RCPs Allowed to Operate below 200oF: Two HPSI and Charging Pump Combinations Allowed to be Aligned to the RCS:

At T < 200~F 2 Charging Pumps At200F< Tc-<313F 1 HPSI 6 3 Charging Pumps At Tc > 313~F 2 HPSI 6 3 Charging Pumps

Table 3 ST. LUCIE-2 LTOP SYSTEM CHARACTERISTICS, 15 EFPY Relief Valve Ali nment Tem eratures (oF)

SQCS Relief VaLves PORV'-

HU CD HU CD

<165 ~ <190 165-324 190-315 Maximum Allowable Heatu and Cooldown Rates HU; F IHR Temperature, Limit, oF CD, FIHR Temperature Limit, F 20 40 <89 30 <115 50 89-367 50 115-141 100 >367 75 141-157 100 ~157 LTOP S stem General Re uirements

[Maximum] LTOP Temperatures:

For Heatup: 324oF For Cooldown: 315oF Maximum Secondary-to-Primary Temperature Differential for RCP Start: 40oF Maximum Calibration Interval for Pressurizer Pressure Transmitters: 18 months Maximum Number of RCPs Allowed to Operate below 200 F: Two HPSI and Charging Pump Combinations Allowed to be Aligned to the RCS:

At T < 200oF ,2 Charging Pumps At 200oF < TC-< 324oF 1 HPSI 8 3 Charging Pumps At TC > 324oF 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 PORV, . =-.

HU CD HU CD

<172 <196 172-330 196-321 Maximum Allowable Heatu and Cooldown Rates HU, F/HR Temperature Limit, F CD, F/HR Temperature Limit, ~F 20 40 <96 30 <121 50 96"367 50 121 "147 100 >367 75 ~

1 47"'l63 100 >163 LTOP S stem General Re uirements

[Maximum) LTOP Temperatures:

~ For Heatup: 3300F For Cooldown: 3214F Maximum Secondary.-to-Primary Temperature Differential for RCP Start: 400F Maximum Calibration Interval for Pressurizer Pressure Transmitters: 18 months Maximum Number of RCPs Allowed to Operate below 200 F: Two HPSI and Charging Pump Combinations Allowed to be Aligned to the RCS:

At T < 2000F 2 Charging Pumps At 200 F < T < 330 F 1 HPSI C 3 Charging Pumps At Tc > 330~F 2 HPSI 6 3 Charging Pumps

Table 5 ST. LUCIE-2 LTOP SYSTEM CHARACTERISTICS, 25 EFPY Relief Valve All nment Tem eratures (OF)

SIX;$ Relief Valves PORV.'U HU CD 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 20 <83 40 <102 30 83-126 50 109-367 50 126"152 100 367 75 152-168 100 >168

'LTOP S stem General Re uirements f Maximum) LTOP Temperatures:

For Heatup: 3350F For Cooldown: 326oF Maximum Secondary-to-Primary Temperature Differential for RCP Start: 40oF Maximum Calibration Interval for Pressurizer Pressure Transmitters: 18 months Maximum Number of RCPs Allowed to Operate below 200 F: Two HPSI and Charging Pump Combinations Allowed to be Aligned to the RCS:

At T < 200~F 2 Charging Pumps At 200oF < T c-< 335oF 1 HPSI 6 3 Charging Pumps At TC > 335oF 2 HPSI C 3 Charging Pumps

Table 6 ST. LUCIE-2 LTOP SYSTEM CHARACTERISTICS, '30 EFPY Relief Valve All nment Tem eratures (~F)

SM;S Relief Vaivqs PORV.

HU CD 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 20 < 87 40 <106 30 87-130 50 106-367 50 130-156 100 >367 75 156-172 100 > 172 LTOP S stem General Re uirements

[Maximum J LTOP Temperatures:

For Heatup: 339~F For Cooldown: 330~F Maximum Secondary-to-Primary Temperature Differential for RCP Start: 000F Maximum Calibration Interval for Pressurizer Pressure Transmitters: 18 months Maximum Number of RCPs Allowed to Operate below 2000F: Two HPSI and Charging Pump Combinations Allowed to be Aligned to the RCS:

At T < 200 F 2 Charging Pumps At 2000F < T c-< 339oF 1 HPSI 6 3 Charging Pumps At T>>C 339oF 2 HPSI 6 3 Charging Pumps

Table 7 ST. LUCIE-2 LTOP SYSTEM CHARACTERISTICS, 32 EFPY Relief Valve Ali nment Tem eratures (oF)

SDCS Relief Valv.es PORV.

HU CD 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 20 <89 40 <108 30 89-132 50 108"367 50 132-158 100 >367 75 158"174 100 >174 LTOP S stem General Re uirements

[Maximum] LTOP Temperatures:

For Heatup: 341oF For Cooldown: 3320F Maximum Secondary-to-Primary Temperature Differential for RCP Start: 40'F Maximum Calibration Interval for Pressurizer Pressure Transmitters: 18 months Maximum Number of RCPs Allowed to Operate below 200'F: Two HPSI and Charging Pump Combinations Allowed to be Aligned to the RCS:

At Tc < 200 F 2 Charging Pumps At 200 F < T c- 341oF

< 1 HPSI 6 3 Charging Pumps At TC > 341~F 2 HPSI C 3 Charging Pumps

ST. LUCIE-2 P/7 LIMITS,16 EFPY HEATUP AND CORE CRITICAL 2500 60oF/HR 2000 ca 1600 LOWEST SERVICE TEMP. 1684F 0

Q 1000 I

CJ 0 CORE CRITICAL R

60 F/HR 4

Ch CJ F/HR 535 PSIA NAXimum ALLotdA~ H/Q ~~

HU, F/HR Tpepceature LImit, F 10 cia 50 85-3C7

'IOO i3C7 MIN. SOLTUP TEMP.

0 0

TC INOICATEO REACTOR COOLANT TEMPERATURE oF

ST LUCIE.2 P/T LIMITS, 46 EFPY COOLDOWN AND INSERVICE TEST INSERVICE TEST g

a. 1600 CC LOWEST SERVICE M TEMP. 1684F F/H R& ISO TH ERM LC S

1000 I

MAW~niwn ALLau)ABLE, 4 RAT C7 ISOTHERMAL A CO, F/HR Teeperature umit, 1=

R

-30 F/HR 20 CJ 30 gl c115

4. 600 50 18-1e1 75 111-157 100 ~157 MIN. BOLTUP TEMP.

0 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 LOWEST SERVICE N TEMP. 1684F IL 1000 Q ., CORE CRITICAL K

504 F/H 4PF/HR tnt sieve A~up,a~ 'YSS 535 PSI 500 HU, F/HR Teeperature Llmlt, 4F 40 c96 50 94-367

)00 i367 MIN. BOLTUP TEMP.

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 LOWEST SERVICE N TEMP 168oF tt; 0

1004F /HR 8c ISOTHE AL W

1N ISOTHERMAL CJ At.mesh~

a4 SO4F/HR Mh tmcj~ C O gAZgz 5

SO I, OF/HR Temperature LImIt, OF 500 20 30 ct21 50 'IS-147 75 117-163 100 ~Ni3 MIN. BOLTUP TEMP.

0 0

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 LOWEST SERVICE TEMP 168oF 1000 C7 z' CORE CRITICAL 604F/HR Nhwimu ~ Ai<ouo p e.a.

0 635 PSIA F/HR HU, FIHR Teeperature Umit, F 10 <102 SO 1Q-3C7 100 367 MIN. BOLTUP TEMP, 0

0 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

HR 8c ISOTHERMAL LOWEST SERVICE

. TEMP. 1684F 1000 C ISOTHERMAL NAWWunl Au.p+ABI.E, 4 D 8:

RNES'O, F/HR Temperature LImit, F

.:. 304F/HR 5 20 ce3 CL 100 30 el-126 50 126-1$ 2 75 152-16e 100 F168 MIN. BOLTUP TEMP.

00 TC INDICATED REACTOR COOLANT TEMPERATURE, F

ST. LUCIE-2 P/T LIMITS, 30 EFPY HEATUP AND CORE CRITICAL 604 F/HR 2000 Os 1500 N

1000

= LOWEST SERVICE TEMP. 1884F

~

A RE CRITICAL R

50 F/HR 4 638 PSIA F/HR HU, F/HR Tamperature Limit, F IO <<106 50 1Q-367 100 >367 ININ. BOLTUP TEINP.

0 0

TC INDICATED REACTOR COOLANT TElNPERATURE,4F

ST LUCIE-2 P/T LIMITS, 30 EFPY COOLDOWN AND INSERVICE TEST INSERVICE TEST 2000 1600 N

LOWEST SERVICE TEMP )B8oF 100 F/H 5 ISOT MAL 4

>000 C ISOTHERMAL (J.

~(hlU4 ALL~ABLE 0 RATES R 30 F/HR I, 4F/HR Temperature Umit, F 20 c 87 30 l7"130 50 130-'I 56 75 156"172 100 > 172 MIN. BOLTUP TEMP.

0 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 HU, 4F/HR Tanperature LImlt, 4F S35 PSIA 10 clM 50 lQ"367 IOO %367 MIN. BOLTUP TEMP.

Pp TC iNDICATED REACTOR COOLANT TEMPERATURE'

ST. LUCIE-2 P/T LIMITS,32 EFPY COOLDOWN AND INSERVICE TEST INSERVICE TEST 1SOO LOWEST SERVICE TEMP. 1684F 100 F/ HR8c I SOT HfRMAL 4

I 1000 ISOTHER MAL ~%imam Au, a~ n ~s Q CO, 4F/HR Tenpec'ature Limit, 4F R 30 F/HR 20 <dS 5 30 1%-1 32 50 132" 150 soo 75 15d-171 100 %171 N. BOLTUP TEMP.

0 0 100 200 300 400 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

Moga4Oo sees 5'a JP soi'6 4<e readov- vessel lleU ovI I so>ow +'

REACTOR COOLANT SYSTEM OVERPRESSURE PROTECTION SYSTEMS Is less f'4~ ov uJ fo +< Qppr>plve,k LIMITING'CONOITION FOR OPERATION 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 less than or equal to valves (PORVs),~are-with a lift setting of psia>

t~o shut~ coot~q syd~~ r (i~ F VnJVe5 DCSRVg)> AC COSY a lifta~dSeft'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:

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

b. 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 C. 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 0-5 295 286 5-l0 3I3 304 I 0- I 5 324 3I5 I5-20 330 32I 20-25 335 326 25-30 339 330 30-32 34I 332 MA53/026/8

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

+he, p

Q 0

pplicabl~ /<au~ ~ h i g 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 equivalent capsule radiation exposure. cal ul ted delta RTNOT for the 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 performed in accordance with th t

C 4a) cp>F+

g wcsM iaaf vcs r 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