ML20104B161
| ML20104B161 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 09/09/1992 |
| From: | SOUTHERN CALIFORNIA EDISON CO. |
| To: | |
| Shared Package | |
| ML20104B156 | List: |
| References | |
| NUDOCS 9209150014 | |
| Download: ML20104B161 (35) | |
Text
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ATTACHHENT A-EXISTING TECHNICAL SPECIFICATIONS AND BASES UNIT 3 4
1 9209150014 920909 PDR ADOCK 05000362 P PDR
~
INDEX LIMITING CON 0! TION FOR OPERATION AND SURVEILLANCE REQUIREMENT 5 SECTION PAGE r07 5 HUT 00VN.. . . . . . . . . . . ........ .. ................ 3/4 4-3 COLD SHUT 00WN - LOOPS FILLEO.. .... ... ..... ... 3/4 4-5 COLD SHUTDOWN - LO^PS NOT FILLEO. . . ...... . ........ 3/4 4-5 3/4.4.2 SAFETY VALVES - 0PERATING............................... 3/4 4-7 3/4.4.3 PRE 550RIZER......................................... ,
. 3/4 4-8 3/4.5.4 STEAM GENERATOR 5........................................ 3/4 4 9 3/4.4.5 REA'CTOR COOLANT SYSTEM LEAKAGE.
LEAKAGE DETECTION SYSTEMS. . . . . . . . . . . . . . . . . . . . . . . . . 3/4 4-17.
O P E R AT IO NA L L EA KAG E . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3/4 4-18 3/4.4.6 CHEMISTRY............. . ............................... 3/4 4-21 3/4.4.7 SPECIFIC ACTIVITY.................... .................. 3/4 4-24 3/4.4.8 PRES 5URE/ TEMPERATURE LIMITS-
'-~
REACTOR COOLANT SYSTEM. . .................... ...... 3/4 4-29 PRE 55URIZER - HEATUP/C00LOOWN....... .......... .... 3/4 4-32 CVERPRESSURE PROTECTION SYSTEMS ACS TEMPERATURE < 302*F.'.................... .... . 3/4 4-33 t RCS TEMPERATURE I 302*F. ................... ...... 3/4 4-35 !
3/4.4.9 STRUCTURAL INTEGRITY................................ ... 3/4 4-36 3/4.4.10 REACTOR COO LANT GAS VENT SYSTEM. . . . . . . . . . . . . . . . . . . . . . . . . 3/4 4-37 3/4.5 EMERGENCY CORE COOLING SYSTEMS 3/4.5.1 .
SAFETY INJECTION TANKS.................................. 3/4 5 3/4.5.2 ECCS SUBSYSTEMS - T,yg > 350'F..........................
3/4 5-3 3/4.5.3 ECCS SUBSYSTEMS - T,yg < 350*F..........................
3/4-5-7.
3/4.5.4 REFUELING WATER STORAGE TANK............................ 3/4 5-3
(
A 5AN ONCFRE. ; UNIT 3 ,
V .. . . , . AMEN 0 MENT NO. 71 h
.2.,
)
_- _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ . _ _ . _ . _ . _ . _ . J
4 INDEX LIST OF FIGURES J
PAGE l FIGURE 4
3.1-1 MINIMUM BORIC ACID STORAGE TANK VOLUME AND TEMPERATURE
- AS A FUNCTION OF STORED BORIC ACID CONCENTRATION........ 3/4 1-13 b 3.1-2 CEA INSERTION LIMITS VS FRACTION OF ALLOWABLE THERMAL 3,4 1 24 e0wtR...................................................
c 3.2-1 DNBR MARGIN OPERATING LIMIT BASED ON C0LSS. . . . . . . . . . . . . . 3/4 2-7 3.2-2 DNBR MARGIN OPERATING LIMIT BASED ON CORE PROTECTION CALCULATORS (COLSS OLP' 0F. SERVICE).......... ........... 3/42-8 l
I 3.3-1 DEGRADED BUS VOLTAGE TRIP SETTING....................... 3/4 3-40 4.4-1 TUBE WALL THINNING ACCEPTANCE CRITERIA.......... ........ 3/4 4-16 i 3. 4- 1 00SE EQUIVALENT I-131 PRIMARY COOLANT SPECIFIC ACTIVITY 3
LIMIT VERSUS PERCENT OF RATED THERMAL POWER WITH THE PRIMARY COOLANT SPECIFIC ACTIVITY >1.0 pC1/ GRAM DOSE EQUIVALENT I-131...............*........................ 3/4 4-27 i
, 3.4-2 HEATUP RCS PRESSURE / TEMPERATURE LIMITATIONS FOR 0-5 YEARS- 3/4 4-30 4
] ,
3.4-3 C00LDOWN RCS PRESSURE / TEMPERATURE LIMITATIONS FOR 0-5 YEARS............................................... 3/4 4-30a 1
. 3.4-4 RCS PRESSURE / TEMPERATURE LIMITATIONS FOR 4-8 EFPY....... 3/4 4-31 3.4-5 RCS PRESSURE / TEMPERATURE LIMITS MAXIMUM ALLOWABLE
. C00 LDOWN RATES (4-8 EFPY). . . . . . . . . . . . . . . . . . . . . . . . . . . . . , . 3/4 4-31a f
l 3.7-1 MINIMUM REQUIRfD FEEDWATER INVEhl0RY FOR TANK:T-121 FOR .
MAXIMUM POWER ACHIEVED TO 0 ATE.......................... 3/4 7-7
~
5.1-1 EXC LUS ION MEA. , . . . . . . . . . . . . . . . . . . . . . . . . . . . . . l;.l. . . . . . . . 5-2 l ~
5.1-2 tow POPULATf0N 10NE............................~....... 5-3 5.1-3 SITF. B0UNDARY FOR GASEGUS EFFLUENTS........ 1Jr.......... 5-4 5.1-4 SITE SOUNDARY FOR LIQUID EFFLUENTS...................... 5-5 5.6-1$ UNITS 2 AND 3 FUEL MINIMUM BURNUP VS. INITIAL ENRIQMENT FOR REGION 11 RACKS.......................... 5-12 5.6-2 ~ UNIT 1 FUEL MINDEM BURMUP VS. INITIAL i
. ENRICINENT FOR REGION II RACKS.......................... 13 5.6-3' RACKS................ 5-14, -
, FUEL
. . S.TORAGE PATTERNS FOR REGION II SAN'dNOFRE '.. ...ntUNIT~7= 3- = # XVII
~ ~
AMEN 0 MENT NO.i 77 l g- ;
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, ,, - ,se-- v.,-,m~~e --n.---+w- - , - --r--, s-- t m--r- v -- -
m e
4 INDEX LIST OF FIGURES _
?
s t
i FIGURE PAGE
! 5.6-4 FUEL STORAGE PATTERNS FOR REGION II RACKS RECONSTITUTION STATION.................................. 5-15 6.2-1 0 F F S ITE O RGAN I ZATION. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-3 a
, 6.2-2 UNIT ORGANIZATION....................................... 6-4 6.2-3 6-6 C O NTRO L ROOM AREA. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
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- SAN OhuFRE - UNIT ~ ~ ** XVIIa AMENDMENT NO.' 77'
. . - . - . - - -. -.- . ~ . .. .- - . - . - . _ - . - . . -
i i j.
l 1 REACTOR COOLANT SYSTEM 3/4.4.8 PRESSURE /TENPERATURE LIMITS-s ,
(. .
- -t l LIMITING CONDITION FOR UPERATION 4
3.4.8.1 With the reacter. vessel head bolts tensioned *,-the-Reactor Coolant i System (except the pressurizer) temperature and pressure shall-be limited in l
- accordance with the limit lines-shnwn on Figures- 3.4-2, 3.4-3, 3.4-4, and
! 3.4-5 during heatup, cocidown, criticality, and inservice leak and hydrostatic '{
i
' testing with:
i i l a. A. maximum heatup as specified by Figure 3.4-3 in any 1-hour period l- with RCS cold leg temperature less'than 153*F. 'A maximum heatup.of.
- 60'F. in any 1-hour period with RCS cold leg temperature-greater j- than 153*F.
I
! b. A maximum cooldown as_specified by Figure 7.4-5 in any_1-hour period :
with RCS cold leg temperature less"than lic'F. A maximum cooldown- F
- of 100*F in any-1-hour period with-RCS cold leg temperature greater than 126'F. ,
A maximum temperatu o change _of: 10*F in any 1-hour period during
- c. I
- inservice-hydrostatic and leak testing operations above the heatup-i: _
and cooldown limit curves.
I 1 .
! ) d. A minimum temperature of:86'F to-tension reactor vessel head bolts. ",
i ..
i With the reactor vessel head bolts detensioned, the Reactor Coolant System F (except the pressurizer)-temperature shall_be limited to a maximum heatup or i cooldown of 60*F in any 1-hour period.
i
. APPLICABILITY: At all-times.
i -ACTION:
-With any of the above limits exceeded, restore the: temperature and/or-pressure j to within the limit within 30 minutes; perform an engineering evaluation to
<- determine the effects of the out-of-limit condition on the structural i tegrity n of the , Reactor: Coolant Systes; determine that;the Reactor. Coolant System e remains-acceptable:for continued operations or-be in'at least HOT STANOBY and pressure to-less than i
withinthenext-6hoursandreducetheRCS'T*Y8llowing30 200*F and 500 psia, respectively, within the hours, p
i
) "With the reactor vessel head bolts detensioned.-RCS' cold leg temperature may-t s be less than'86*F.
b -SAN ONOFRE - UNIT 3 '3/4 4-28 AMEN 0 MENT N0.71 4
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, . , .-. . . - - . - _ - - - . . . . - - . . - . ...-.a.-..
V RE.aC*;R C00'. ANT SYS?!M -
(5 d"'ws 3 _3/4.4.3 :# ESSURE / TEMPERATURE LIMITS REACTOR COOLANT SYSTEM L:9?T!NG CONDITION FOR OPERATION SURVE!LLANCE RECUIREMENTS 4.4.8.1.1 The Reactor Coolant System temoerature and pressure shall be determined to be within the-limits at least once per 30 minutes during system hectup, cocidown, and inservice-leak and hydrostatic testing operations, ,
4.4.8.1.2 The reactor vessel material irradiation surveillance specimens snall te removed and examined, to determine enanges in material properties,'at the intervals required by 10 CFR 50 Appendix.H in accordance with the schedule.
in Taele 4.4-5, The results of these examinations snall be used to uocate-Figures 3.4-2 and 3.4-3, Recalculate the Adjusted Reference Temperature based on the greater of the-following:
- a. The actual shift in reference temperature for plate C-6802-1 as determined by impact testing, or
- b. The predicted shift in reference temperature for weld seams 2-203A,
-'N 2-2038, or 2-203C as determined.by Regulatory Guide 1.99,
) Revision 2," Radiation Embrittlement of Reactor. Vessel Materials,
May 1988.
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w a SAN ONOFRE - UNIT.3- 3/4 4-28a AMENOMENT NO. 71
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NOCATE RCS TUPERA11)RE (- F)
FIGURE 3.4-2 SONGS 3 RCS PRESSURE / TEMPERATURE LIMITATION FOR 4-8 EFPY a,
SAN ONOFRF. - UNIT 3 3/4 4-30 AMENCMENT NO. 71 d
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i INDICATED RCS TEMPO 4ATIAqE N l NC11: A MAXnMi HEANP IETE OF' 00'F 5
- ALLOWED AT #ff TDdPE3ATulqE A80WE 1 4
FIGURE 3.4-3 4
.SGHGS'3 RCS PRESSURE /TEMFERATURE LIMITS-i MAXIMUM ALLOWABLE HEATUP- UTES (4-8 EFPY) w}
i he SAN ONOFRE - UNIT 3 3/4 4-30a AMENOMENT NO: n
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- 0 50 100' 150 200: -250 300 350 400-INDICATED RCS TDdPERATURE-(*F) l FIGURE:3.4-4 SONGS 3 RCS PRESSURE / TEMPERATURE LIMITATIONS FOR 4-8 EFPY L b SAN ONOFRE - UNIT 3. 3/4 4-31 AMEN 0 MENT NO. 71
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100 - c 90 -
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40 -
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10 -
0 ' ' ' ' ' '
80 30 100 110 120
. 130 .140 150
- INDICATED MC31EWPCIAM4E ('P)
NQ17.: A MAXWUW COOLDOWN MATE OF 100'F/HM 5 ALIDNED AT ## TGPDETURE ABOVE 128'F FIGURE 3.4-5 SONGS 3 RCS PRESSURE / TEMPERATURE T LIMI'S Sd 6 3AN ONOFRE - UNIT 3 MAXIMUM All0WABLE C00LOOWN RATES (4-8 EFPY)
% ?/4 4-31a MENOMENT NO. 71 s=
$ I
Tablc 3.4-3 k
Low Temeerature RCS Overeressure Protection Rance 0:eratino Pe-icd, EFPY Cold Leo Temcerature, 'F Ouring During Heatup, Coolcewn 4 to 8 < 302 < 267
'd i- SAN CNOFRE - UNIT 3 3/4 4-31b AMEN 0HENT NO. 71 I, 4
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REat'OR 2:0LAN' 5VSTEM !
? Ov!RPRE55URE PROTECTION SYSTEMS RCS TEMPERATURE 1 302*F L!9? TING CCN0! TION 80R OPERATION 3.4.3.3.1 At least one of tne following overpressure protection systems snill be OPERABLE:
- a. The Shutdown Cooling System Relief Valve (PSV9349) with:
- 1) A lift setting of 406 2 10 psig", and
- 2) Relief valve isolation valves 3HV9337, 3HV9339, 3HV9377, anc 3HV9378 open, or, _
- b. The Reactor Coolant System depressurized with an RCS vent of greater than or equal to 5.6 square-inenes.
APDLICABILITY: MODE 4 when the temocrature of any one RC5 cold leg is less
- nan or equal to that specified in Table 3.4-3; H00E 5; MODE 6 witn tne react:r 1 vessel nead on.
ACTION:
a.
With the 50C5 Relief Valve inoperable, reduce T,yg to less than 200*F, decressurize and vent the RCS through a greater than or equal to 5.6 square inch vent within the next 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, j b. With one or both SOC 5-Relief-Valve isolation valves in a single s,_) SOCS Relief Valve isolation valve pair (valve pair 3HV9337 and 3HV9339 or valve pair 3HV9377 and 3HV9378) closed, open the closec valve (s) within 7 days or reduce T to less than 200*F, depres-surize and vent the RCS tnrougn a %ater than or equal to 5.6 inen vent witnin the next 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
, c. In the event either tr.e 50C5 Relief Valve.or an RCS vent isiused to l mitigate an RCS pressure transient, a Special Report snall be precarec and submitted to the Commission pursuant to Specification i 9.2 within'30 days. The report shall describe the circumstances initi-ating the transient, the effset.of the SOCS Relief v lve a or RCS vent on the transient and any corrective action necessary to prevent recurrence, j d. The provisions of Specification 3.0.4 are not applicable. .
SURVEILLANCE REQUIREMENTS 4.4.8.3.1.1 The SOCS Relief Valve shall be demonstrated OPERABLE by:
- a. Verifying at least ence per. 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> when the SOCS Relief Valve is being used for overpressure protection that SOCS Relief Valve-
- l. isolation valves 3HV9337, 3HV9339, 3Hv9377,*and 3HV9378.are open.
"The lift setting pressure applicable to valve temperatures of less than or I equal to 130*F.
.J SAN ONOFRE - UNIT 3 3/4 4-33 AMENOMENT NO. 71 V
] ..
. , - - - . . , - . - , , - , , , , , , , - . , - ,-. ., ~ , . . . .
REACTCR ::C'. ANT Sf 57EM
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OVERPRE55uRE PROTECTION SYSTEMS-i RCS TEypERATURE > 302'?
LIMITING CCNOITION FOR OPERATION
- 3. 4. 3. 3. 2 At least one of the following overpressure protection systems snall
- e OPEAAOLE:
- a. The Shutdown Cooling System Pelief_ Valve (PSV9349) with:
- 1) A lift setting of 406 e 10 psig*, and-
- 2) Reitef valve isolation valves 3HV9337, 3HV9339, 3HV9377, and 3HV9378 open, or,_
- b. A minimum of one cressurizer code tafety valve with 4 iift setting of_2500 psia 1%**.
APPt.IC ABILITY: MODE 4 with RCS temperature sbove that specified in Table 3.4-3.
] ,
, t.CTION:
- a. With no safety or relief valve OPERABLE, be in COLD SHUT 00VN and: .; '
vent the RCS tnrough a greater than or equal to 5.6 square inch vent--
within the next a hours.
- b. In the event. the SOCS Relief Valve or an RCS vent is used to-e mitigate an RCS pressure . transient, a Special Report shsil' be
~ prepared and submitted.to .the Commission pursuant.to-Specifica-
,). tion 6.9.2 witnin 30 days. . The : report shall . describe the'
, circumstances initiating-the transient, the effect of the 50C5
, Relief Valve code safety valve or RCS vent on the transient and any corrective action necessary to prevent recurrence.
i SURVEILLANCE REQUIREMENT 5 .
b 4.4.8.3.2.1 TheSOCS-Relief-ValveshalibedemonstratedOPERABLEby:
- a. Verifying at least once-per-72 hours-that the SOCS Rollef Valve isolation valves 3HV9337,' 3HV9339,_3HV9377 and 3HV9378 are open when the SOCS Rehef Valve-is being used for overpressure protection,
- b. Verifying relief valve satpoint at least"once per 30 months when tested pursuant to Specification-4.0.5.
4.4.S.3.2.2- The pressurizer code safety, valve.has-.no additional surveillance-requirements other that. those required by Spacification 4.0.5.
4.4.8.3.2.., The RC5 vent shall be verified to be open at least once-per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when the vent is being used 'for ovorprassure protection, except when the . vent -
-pathway is provided with aLvalve which is.-locked,isealeo, or otherwise secured in the open-position,- then verify these valvss cpen at least.once _per 31 days.
"The lif t setting pressure applicable to valve tempe'ratures ef 1:ss- than'or equal to 130*F.
- The lift setting pressure shall.correscend to ambient conditions of'the valve at nominal-operating temperature and, pressure, k
^ it :
SAN ONOFRE-- UNIT 3 3/4.4-35' AMENOMENT-NO.71_
k;
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1
RE AC-"R C:CLaNT SYSTEM BASES l
- RE55LRE/ TEMPERATURE _ LIMITS (Continued)
Tne heatup and cooldown limit curves (Figures 3.4-2 and 3.4-3) are composite :urves .ni:n were prepared by determining the most conservative
- ase, 1 n e1trer tne insice or outsice wall controlling, for any heatup rate of up to 50'F/hr or cooldown rate of up to 100*F/hr. The heatup and cooldown curves .ere precared cased uoon the most limiting value of the predicted adjusted reference temperature at the end of the service ,:eriod indicated on Figures 3.4-2 and 3.4-3.
The reactor vessel materials have been tested to determine their initial RT y ; tne results of these tests are shown in Tacle B 3/4.4-1. Reactor opeNtion and resultant fast neutron (F veater than 1 Mev) irradiation will cause an increase in the RT Therefore, an acjust-d reference temcerature, cased ucon the fluence and $ c.er and nickel content of the material in i question, can be prudicted using FSAR Table 5.2-5 and tne recommencations of Pegulatory Guide 1.99, Revision 2, " Radiation Emerittlement of Reactor vessel Materials." The heatup and cooldown limit curves, Figures 3.4-2 and 3.4-3, include predicted adjustments for this shift in RT y at the enc 0; the applic-able service period, as well as adjustments for posk ble errors in t.*e pressure and temperature sensing ir.struments.
The actual shif*,in RT of the vessel material will be established periodir.allyduringoperatigTby removing and evaluating, in accordance with ASTM E185-73 and 10 CFR Appendix H, reactor vessel material irradiati;n sur-7 veillar.ce specimens installed near the inside wall of the reactor vessel in f tre core area. The surveillance specimen withdrawal schedule is st.own in Tac!e 4.4-5. Since the neutron spectra at the irradiation samples and vessel insice radius are esser.tially identical, the measured transition snif t for a l samole. can be applied with confidence to the adjacent section of the reactor sessel taking into account the location of tne sample closer to the core than the vessel wall by means of the Lead Factor. The heatup and cooldown curves i must be recalculated when the delte RT determined from the surveillance caosuleisdifferentfromthecalculatEdelt=RTg7 for the equivalent capsule radiation exposure. -
l The pressure-temperature limit lines shown on Figures 3.4-2 and 3.4-3 for I reactor criticality and for inservice leak and hydrostatic testing have eten provided to assure compliance with the mininm temperature requirements of Apcendix G to 10 CFR 50.
The maximum RT for all Reactor Coolant System pressure-retaining materials, with the NEIception of the reactor pressure vessel, has been deter-mined to bu 90*F. The t.owest Service Temperature limit line shown on Figures 3.4-2.and 3.4-3 it 'ased c upon this H since Article W8-2332 (Summer Accenda of 1972) of Section III of the ASME Sb er and Pressure Vessel Code recuires the Lowest Service Temperature to be RT 100'F for piping, pumps and valves. Below this temperature, t"e syst m pbs+ure must be limited to a maximum of 20'l; of the system's hydrostatte test press.ure 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 aparated within the design criteria assumed for the fatigue analysis performri in accordance with the ASME Code requirements.
w.
)
SAN ONOFRE-UNIT 3 8 3/4 4-7 AMEN 0 MENT NO. 71 a *
.. . _. . . . . . . .. . - .. -~ . - - .
8 lABLE B 3/4.4-1
- x. -
REAC10R VESSEL TOUGilNESS O Temperature of Minimum Upper E Drop Charpy V-Motch Shelf Cv energy
/- Weight e 30 e 50 for. Longitudinal 5 Vessel Location Results it - Ib - f t - :;, Direction-ft Ib Piece No. Code No. Material
] Upper Shell P1 ate -20 28 64 115 235-01 C-6801-1 A53 MRBCL1 106
'C-6801-2 A533GR8CLI Upper Shell Plate -20 -6 34 215-01 16 115 C-6801-3 A533GRBCL1 Upper Shell Plate' -20 10 215-01 L6wer Shell Plate -30 32 62 16 215-02 C-6802-4 A533GR8CL1 64 140 A533GRBCLI -Lower Shell rlate 0 36 215-02 C-6802- 5 90 Lower shell Plate -'O 32 100 215 C-6802-6 A533GR8CL1 C-6802-1 A533GASCL1 Intermediate Shell -20 56 100 95.
215-03 40 66 113 5" 215-03 .0-6802-2.. A533GRBCL1 Intermediate Shel2 -20 44 80 101 t' 215-03 C-6802-3 A533GRBCLI Intermediate Shee -10 C-6823 A508CL2 Vessel flange forging 0 -30 -15 NA 203-02 A508Cl2 Closure itead flange -40 -100 -100 NA 209-02 C-6824-1 forging..
Inlet Nozzle forping 10 -35 -5 109 205-02 C-5829-1 A508CL2 156 C-6829-2 A508CL2 Inlet Nozzle forg!ng 0 -55 -35 20 -25 35 112 C-6829-3 A508CL2 It;let Nozzle forging 10
- 20 JJ C-6829-4' A50BCl2 InleL Nozzle Forgiag 10 -30 25 108 20' ffl2 z
Outlet Nozzle forging -10 -30 -15 125 20 M --. 1 C-6830-1 A508Cl2
-10 -5 131 2Cr-f46 -
S z-.
C-6830-2 A500CL2. ' Outlet Nozzle forging -20'
-50 -10 0 107 r
- ' 2: kl r
O C-6840-1 A533GitBCL1 Bottom flead focus
- g Bottog ilead Dome -40 10 20 99'
"' 2 3 02 3 C-6841-1 'A533GRBCl1 G --e ~
I"> 6 a:
l'
4 T
4 4
i ATTACHMENT B PROPOSED TECHNICAL SPECIFICATIONS AND BASES t
i UNIT 3 f
d k
I
+
w- ~
1 1
It(REX !
l I
, LIMITING CONDITION FOR ODERATION AND SURVEILLANCE REQUIREMENTS J SECTION EAGE l HOT _SHUTD0WN........................................... 3/4 4-3 i COLD SHUTDOWN - LOOPS FILLED........................... 3/4 4-5
~
COLD SHUTDOWN - LOOPS NOT FILLED....................... 3/4 4-6 3/4.4.2 SAFETY VALVES - 0PERATING.............................. 3/4 4-7
- 3/4.4.3 PRESSURIZER............................................ 3/4 4-8
- 3/4.4.4 STEAM GENERATORS....................................... 3/4 4-9 i 3/4.4.5 REACTOR COOLANT SYSTEM LEAKAGE LEAKAGE DETECTION SYSTEMS........................ 3/4 4-17
. OPERATIONAL LEAKAGE.............................. 3/4 4-18 3/4.4.6 CHEMISTRY.............................................. 3/4 4-21 3/4.4.7 SPECIFIC ACTIVITY...................................... 3/4 4-24 3/4.4.8 PRESSURE / TEMPERATURE LIMITS REACTOR COOLANT 5YSTEM........................... - 3/4 4-28 PRESSURIZER -'HEATUP/C00LD0WN.................... 3/4 4-32 OVERPRESSURE PROTECTION SYSTEMS
. -RCS TEMPERATURE $ 302 265aF................... 3/4 4-33 RCSTEMPERATURE>302g6)*F....................3/44-35 3/4.4.9 STRUCTURAL INTEGRITY................................... 3/4 4-36 3/4.4.10 REACTOR. COOLANT GAS VENT SYSTEM........................ 3/4 4-37 3/4.5 EMERGENCY CORE C00 LING SYSTEMS 3/4.5.1 SAFETY INJECTION TANKS................................. 3/4 5-1 3/4.5.2 ECCS SUBSYSTEMS - T,y a'350aF......................... 3/4 5-3 3/4.5.3 ECCS. SUBSYSTEMS - T,y < 350aF......................... 3/4 5-7
- 3/4.5.4 REFUEL 1NC WATER STORAGE TANK........................... 3/4 5-8 SAN ON0FRE-UNIT 3 V AMENDMENT NO.
4 g .
- ,, . m . ,- r ,-~rw- s,
I INDEX LIST OF FIGURES FIGURE PAGE 3.1-1 MINIMUM BORIC ACID STORAGE TANK VOLUME AND TEMPERATURE AS A FUNCTION OF STORED BORIC ACID CONCENTRATION...... ... 3/4 1-13 3.1-2 LEA INSERTION LIMITS VS FRACTION OF ALLOWABLE THERMAL 4 P0WER..................................................... 3/4 1-24 j 3.2-1 DNBR MARGIN OPERATING LIMIT BASED ON C0LSS................ 3/4 2-7 ,
3.2-2 DNBR MARGIN OPERATING LIMIT BASED ON CORE PROTECTION CALCULATORS (COLSS OUT OF SERVICE)............ ........... 3/4 2-8 3.3-1 DEGRADED BUS V0LTAGE TRIP SETTING......................... 3/4 3-40 I
4.4-1 TUBE WALL THINNING ACCEPTANCE' CRITERIA.................... 3/4 4-16 3.4-1 DOSE EQUIVALENT I-131 PRIMARY COOLANT SPECIFIC ACTIVITY 4
LIMIT VERSUS PERCENT OF RATED THERMAL POWER WITH THE THE PRIMARY COOLANT SPECIFIC ACTIVITY >1.0 pCi/ GRAM DOSE EQUIVALENT I-131.......................................... 3/4 4-27 3.4-2 SONGS;3 HEATUP RCS PRESSURE / TEMPERATURE LIMITATIONS FOR
, ^ 0 ~ S YE a,P.S 8.1EFPYj -T NORMAL': 0PERATION. . . . . . . . . . . . . . . . . . . . . . 3/4 4-30 3.4-3 COOLDOWN SONGSi3 RCS PRESSURE / TEMPERATURE LIMITSRAT40H 0 5 YEARS ^MAXIMUMfALLOWABLE-HEATUPiRAT NORMAI!0PERATION.~......................ESf(81EFPY)r '- 3l ~
3.4-4 SONGS 73;C00LDOWN RCS PRESSURE / TEMPERATURE LIMITATIONS FOR' T ' 8' EFPYMNORMAl': 0PERATI_0N. . . . . . . . . . . . . . . . . . . . . . . . 3/4 4-31 3.4-5 SONGS ~3 RCS PRESSURE / TEMPERATURE LIMITS MAXIMUM ALLOWABLE C00LDOWN RATES ( i 8EFPY)pNORMAl20PERAT10N........... 3/4 4-31a 3[4F6T
" *~7sONGSf3EC00LDOWN RCSEPRESSURE/TEMPERATUREfLIMITATIONS "FOR18EFPYi-REMOTE 1 SHUTDOWN _0PERATIONE..'.J....c........... [3/4 A 31b 3:457f ;~ ? SONGS?37 RCS PRESSURE /TEMPERATUREiLIMITS
- MAXIMUM: Alt.0WABLEJC00LDOWN; RATES (8 EFP.Y)%
l REMOTEL SHUTDOWN !0PERAT ION. . . . . . . . . . . :.r.^.7. . '. . . . . . . . . . . . . . . . . . 3/4?4-31c 3.7-1 MINIMUM REQUIRED FEEDWATER INVENTORY FOR TANK T-121 FOR MAXIMUM POWER ACHIEVED TO DATE........... ................ 3/4 7-7 5.1-1 EXCLUSION AREA............................................ 5-2 i 5.1-2 LOW POPULATION Z0NE....................................... 5-3
. 5.1-3 SITE BOUNDARY FOR GASE0US EFFLUENTS....................... 5-4 l
5.1-4 SITE BOUNDARY FOR LIQUID EFFLUENTS........................ 5-5 l
I SAN ON0FRE-UNIT 3 XVII AMENDMENT.NO.
I
- . - . . . . ~ ..
e f
- INDEX IIST OF FIGURES FIGURE. PAGE a
l 5!621? 5*17 UNITS!2'AND7EFUEliMINIMUMiBURNUPIVSMINITIAU
~ ~'~ ~ " ENRICHMENT!FORfREGIONilleRACKS?S 3 smh 5 k -W-M_...~ M w'. . . .- L5-12
_ . ,_ _ _ .,m__,. _ .,_._ .,._
.516:25"f"SKUNIT71? FUEL" MINIMUM? BURNUPZVS yINITI AU i _ . ~ "
ENRICHMENTd f._0R?R..E.G..I_ON
&m ~ ~~m . ?.l. lf_ R_ACK_SWA_.sWMEMM._
. m- .s. AM.
.- .m .,. 4 15f13
n;.-namn. F GIONc - I..I? R_ACKS_M. ~~ . ???N.1.. . . . . . r, 75;14
, x .- ; ~~ . ; -..
j 6.2-1 0FFSITE ORGANIZATION...................................... 6-3 s . .
6.2-2 UNIT ORGANIZATION......................................... 6-4
^
- - 6.2-3 CONT RC '. ROOM A R E A . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 6-6 c
s i
?:
- . J e
f i.
i-E t
T F
d I
i-I e
l
- l. SAN ON0FRE-UNIT:3- XVIIa AMENDMENT-N0.
e
- s. -.m.. <
. , . . . , . m .. vw, si n - w- , y 9 - e, i y _ +, -wr
REACTOR COOLANT SYSTEM 3/4.4.8 PRESSVRE/ TEMPERATURE LIMITS
l t1MITING CONDITION FOR OPERATION 3.4.8.1 With the reactor vessel head bolts tensioned ~, the Resctor Coolant
- System (except the pressurizer) temperature and pressure shall be limited in accordance with the limit lines shown on Figuras 3.4-2, 3.4-3, 3.4-4, and 3.4-57 3f406 Fan ~d73.427 during heatup, cooldown, criticality, and inservice leak
- and hydro" static ~' testing with
- a. A maximum heatup as specified by figure 3.4-3 in any 1-hour period
". with RCS cold leg temperature less than M F 180*F. A maximum heatup l of 60*F in any 1-hour period with RCS cold leg ~ temperature grever than 4 M1180*F. !
- b. A maximum cooldown as specified by figure 5.4-5 in any 1-hour period
- with RCS cold leg temperature less than 4K175'F. A maximum l .
cooldown of 100*F in any 1-hour period with"RCS cold leg temperature greater than 446 175af. l
- c. A maximum temperature change of 10*F in any 1-hour period during inservice hydrostatic and leak testing operations above the heatup and cooldown limit curves.
- d. A minimum temperature of 86*F to tension reactor vessel head bolts.
- With the reactor vessel head bolts detensioned, the Reactor Coolant System i (except the pressurizer) temperature shall be limited to a maximum heatup or cooldown of 60*F in any 1-hour period.
- APPLICABILITY: At all times.
ACTION _1 With any of the above limits exceeded, restore the temperature and/or pressure to within the limit within 30 minutes; perf:rm 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 i
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 than 200*F and 500 psia, respectively,withinthefo1Nwing30 hours.
- With the reactor vessel head bolts detensioned, RCS cold leg temperature may be less than 86*F.
SAN ON0FRE-UNIT 3 3/4 4-28 AMENDMENT NO.
REACTOR COOLANT SYSTEM 3/4.4.8 PRESSURE / TEMPERATURE LIMITS REACTOR COOLANT SYSTEM E441-T44Cr-CGN0!T!0" FOR OPERATION SURVEllLANCE REQUIREMENTS 4.4.8.1.1 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.
4.4.8.1.2 The reactor vessel material irradiation surveillance specimens shall be removed and examined, to determine chbnges in material properties, at the intervals required by 10 CFR 50 Appendix H in accordance with the schedule in Table 4.4-5. The results of these examinations shall be used to update Figures 3.4-2_cnd 3.4 3 .through*374;7. Recalculate the Adjusted Reference _ Temperature bem!-en the grchtsf of~ the"fellowingfin"accoFdanceWithTRegulatoryTGuide' l.99 Revisian~ 2{l" Radiation"" Embrittlement of Reactor Vessel!Matirials," May 1988;
- a. The acts:1 shift in ref+rence tempeeature fcr platW80M-as detennhed -by impact te:W9r-se
- b. The predicted shif t in reference temperat-uee-for .-;cid scam: 2 203Ar B-203B, or 2 203C ;; determined-by-Regtdat+ey-Guide 1.99, Revis4en-GT
- Radiatien Embrittlemaat-of-Resetor Vc :cl Material;," May 1988r I
i i
I SAN ON0FRE-UNIT 3 3/4 4-28a AMENDMENT NO.
t 4
T t
3500 , , , , , , , , , , , , , , , , , , , , , , , , , , , , , , , , . , , ,,,,,
HEATUP i
J LOWEST SERVICE MRE 3A 3 < 180*O (60*F/HR *> 180*F)
TEMP - 208T 3000 N\ 't 1 i
I !' '
, ... . . . l. I l .I ...I. ._ .,
.l._
dlN] SERVICE - - - - -
- -._._.. .p..
....J .J Tests -
j I _
. <C y \ --
- 55 2500 -
3 g. 3
- Q _ p .a .a. _
l..- ...% .
' I '
y.
, g_
m
_J._b_.
- j. l
.. ..... l.f .L.[..._..-. [-.___
1 M t j;i <
tu 2000 - - - + -~r-I j ---- - --- "- -
3- g .
I
- . . ...p . . .} ....... . . ~ ..d .. -.- - ..-. ...
LU j!
N_
_ p 2
( .. ..'./
~
< T- l ? i 1500
--)
_. ... .J.. 4. 4_._ [.. . a . ... . . . .. ....
LU C l .ji..1 .i CORE -
a i
.....[. CRITICAL -
a i L..F
._j.q_...i . 7 . j ik 7J
- l. --
! 3000
.. 76'..
7 9
a i , ).q ,-
.T l... ......
3' 1_.
g ).. V
_._ . _. . g . .._
5% 1 i i ! i i i,y, y p.. .t . .L. . :
i
~
MINIMUM -
. 5 i j i,
BOLTUP TEM A - 86'F N
~ .- --
. I. l . +. 4 . 1' .i 7.+..++{+. . + -+. .I--
! r i
__ liiilill l i iI t I t il' t > L l ! l i I
! i i I i
-0 50- 100 150 200< 250_' '300 350- 400
. INDICATED RCS TEMPERATURE ( F) .
t e
. FIGURE 3.4-2 SONGS 3 HEATUR RCS: PRESSURE / TEMPERATURE LIMITATIONS FOR- i 8 EFPY Normal.10peration 3/4 4-30 AMENDMENT N0.
SAN ONOFRE-UNIT 3'
- _ ._. .. . _ ~ . _ _ _ _ . . .
1 i
4, i
i-
- j. 70 .
i-f I
l.
l- so - ,
i-I L
! 50 -
e i r
- . X C
1 .t j
w <a -
c
!. 1 2 -
! H. 30 -
w :
i
- 1 4
20 -
i i
i
- i. -
10 -
1 i
4-
. i p
i i i i i i
.o i i i i 80 90- 100 110- 120' 130 140 -150 160 170 .180' 190 200' 210 i
j-
- j. INDICATED RCS TEMPERATURE (*F)_
!- NOTE: A MAXIMUM'HEATUP RATE--0F 60*F/HR IS ALLOWED-AT ANY TEMPERATURE:ABOVE M PF 180*F F .
j FIGURE 3.-4-3
-SONGS 3 RCS PRESSURE / TEMPERATURE LIMITS d
MAXIMUM ALLOWABLE HEATUP-RATES ( .:8 EFPY) j Normali;0peration - -!
l 1 i j i SAN-0N0FRE-UNIT 3 3/4 4-30a -AMEN 0 MENT NO. J i
l l
}
- ^ - .. ,4.-,4..c.-w- # - ,,w. e . , . . . . ,,4-~E.--..,,,ud,- .,4E . e, ., y --
p-. vvw-, ,#y3 q , . - ---
4 1
a
- 3500 i i i i i , ii iiie i ii iiii i ii iii,i. iiiii,i
_ COOLDOWN
- (FIGURE 3.65 < 175'F) ~
- LOWEST SERVICE- (3o0.F/HR > 175"F) ,
3000 TEM P - 208'F i;
g^' -
\l i
i i i Ni. !- !
_. .i a...a . --. L. p_. . . . .Lj.. .
I ! ! ! ! I' I
.4.g. f ...._.
.7..
... .. 7. ;_[. p..f . .
- . . .h- . . . ..._
2500 - i L 4-4-4-+ +4 4-. 4-4-4I i
! -- u- --
W 3
- i. l I'.-.-j -- i
] .[ ..p . L. _ .. .. _ _ ..
m -
w
[
! i i!
i
/
t t . j p' Q- 2000 - -+- 4. l + -.. --. . - j.3- - 4..J -
C w I!
7: -+ ..+-+ 7- +- 4 t. .+ - ! -
g _ .. 4 t .i. . - . 1... .._..
14 gi I .. .
_. t... .. . . _
.e 7 ., 7.. _
D i il /
m .
- i j.
m 1500 _._.L.
. .. 7 . 7 7 .-....j ..q_. .._. .._7-g_.
e -
- a. -
i : !i ./
a i 9 m _._.. t.. . . .2 ,_
'T.-
r . i, -r. h i.
a 3000 __....;.._....
i i 4_._._4 e
._ ..i . .; . .. i >
r _
5 i
!!I i
! ! /
z i i li / [ }
II
- i ' / i
=
l
. ... -.f- a : - .[- . . .; . . . _
_i uiniuuu j H- ~
5% -
nmp , ,
g; f
..i TEMP - 86*F ...--
j-+~ j- -+-4 +-- 4.-y -+ m v , i r ! i
~,-.~.. - ,,,
.f
' L r- : 4 4 .. .
15 I i l i- l - l +i~'I o ji 0 50 . 100 150 >200 250 300' 350 400 INDICATED RCS TEMPERATURE ( F)
FIGURE 3.4 ,
-1 SONGS 3 C001.00WN RCS PRESSURE / TEMPERATURE 1 LIMITATIONS FOR i 8 EFPY l Normal?0pe.ratiori .
j SAN ON0FRE-UNIT 3 3/4 4-31 AMENDMENT NO.
120 . ,_ . .. .i,,,,. .
.i i. .i.
110 -
100 -
90 -
E -
I 80 - l 2 .
L
-y 70 -
E- -
g' 60 -
3 -
o- -
o
.J 50 -
~
O O 4o .
- g 30 -
p 20 -
10 -
' '*I ' ' ' ' ' ' ' ~' ' ' ' ' I '
0
-80 90 100 110 120 130 140 150 160 170 180 190= 200 210 INDICATED RCS TEMPERATURE '( F) t NOTE: A MAXIMUM COOLDOWN RATE OF 100?F/HR IS ALLOWED AT ANY TEMPERATURE AB0VE M64175'E-FIGURE 3.4-5 SONGS 3-RCS PRESSURE / TEMPERATURE LIMITS
'. MAXIMUM ALLOWABLE-C00LDOWN RATES (
i 8 EFPY)
Normalf 0peration.
SAN-0N0FRE-UNIT 3 3/4-4-31e AMENDMENT N0.
3500 , ,,,,,,,,,,,,,i,_,,,,,,_,,,,,,,,,,,,,,,,, _ _
COOLDOWN .
LOWEST SERVICE (FIL. lE 3.4 7 < 184*F) "
TEMP - 208'F - (100*F/HR > 184*F) .
3000 I I--- I- d-- - 1-- 11 ll L
l_i.
i d ..._... I. . . .. _ . ..
il .j._i..p
< ...L r-- i
.i .....a. i. .i i_ .i i ...
g --a a.
l t 1 w
2500 - . - . . . . . ..- -
.i r . ... .. l.i: t,
,...)
. . + . . . ....-
[ d. .! 3 . _.l .d .. [.llt - .I . .
D I
' jj - [- }-
u> . , - t ,
O ...k, .. k. .._ } ..!
w .-.
I Z ! L! ! ._ I Q.
2000
}
' 3 q
I/ l -
C ; , ;; jL _{
w - _4 ..g1 -.,.. . i..
_N ! .! I. -n i-c i:
,f 2 -
-I.
.. . q W 1500 ;' -
1/
c ; i : 'i I t O-g . . ~ .
l .
j
.. l .
i i ' .. .,i!
.. 9 . _._,
~ 7, . 7, .
w
. 1
-d .I
/
4 .... . h.
O 1000 y
! l a
lI
+' l l'i
/. 1 .+l 3
L 4...+l 3 i
- 4. . .
-O i } l- i - li - f ! j l' i z '
- +- --
l
.. I. i. . j_. ...! I i g'!. ...
[- !
},_, . , ,
._t ..... a_..., . .: . e ,_. .....
! ! II I -!
i i i
-] ;l i
500
?.-- j 4.
t.+.,.. j --
ggp ... i. .
4 ; ..i . .
.. !. } . ..... . ,; t..A. ;
I I i
-TEMP - 86*F -
-.i i '
j_% .. l. ..... t - -
b + -+ + -
^
I r
!i 15
' l ' '
II O 50- ~100 150 200 250 300 , W, 400 INDICATED RCS TEMPERATURE ( F)
FIGURER 3:4-6 SONGS;3?COOLDOWNTRCSIPRESSURE/ TEMPERATURE
" " LIMITATIONS?FOR::'8tEFPT ~ ~
Remote 1 Shutdown (0peratied
, - 4
\ SAN 10_NOFRE-UNIT *3) . .,
3/47431b(_', m 3: AMENDMENT l N0.
J
i-i i
1
} 120 .
i .i.i.T i .
i .
i .
i i.i.
! l
! 110 !
i 100 -
i
(~ l 90 - l
- B0 5L l
i -
- y 70 -
l W -
l C 80 a z '
1
'g i O 50 - -
+ O ,
!. J h 40 - -
4 i
0 .
! 30 - .-
L j 20 - -
l- -
10 --
V s
$ 8 8 e a i t e i ' t i i t 's a ! i 80 90. 100 110 120 :130 140 150 160 170 180 190 200 210 l l INDICATED RCS TEMPERATURE ('F) i
!. NOTE:PALMAXIMUN C00LDOWN: RATE OF?lofF/HRiIS' All.0WED-F
' ' " AT.3 ANY ' TEMPERATURE 1 A80VEd84*s
- m. 1 '
FIGURE @42?
SONGS 13; RCSi PRES SURE/T EMPE RATURE"' LIMITS i --
e"MAXIMUMfALLOWABLE-tC00LDOWNRATES)(8EFPY)
' ' ' Remote 3 Shutdown'0per'ation
/ SAN l.O.NOFRE;UNITT,3 V ~
, 2~
M 3/4:4.231c; ~' "'~ *
~ . . .
/AMENDMENTiN0k 4
,v-r. .- , ,-. se, ,* - ,. - - , , . . , ,,m, .....,+4,.,.m,. + ..~.,,.__,.....,,,r-, .m . . ., . + , .._,%,r.. ...,,.y
TABLE 3.4-3
! 1qg Jemperature RCS Overpressure Protection Ranae Qgetalina Period. EFPY Cold Leo Temperature. 'F During During Heatuo Cooldown 4 Up to 8 Ojormal' Operation) s 30 ( 265 5 29 249 Up1 tot 8V(Remote,.ShutdoWniOp6Fation)J,a , ; *J ' s 249 l .
- Heatupfoperations"are notlnormally perfor.medifrcim the Remote Shutdown panels'.
SAN ON0FRE-UNIT 3 3/4 4-31b--d AMENDMENT NO.
i I PMCYOR COOL ANT SYSTEM i
OVERPRESSURE PROTECTION SYSTEMS a i
- RCS_,T.EMPER'TURE s BOB 265*F LiHITING CONDITION FOR OPERATION _
3.4.8.3.1 At least ot.e of the following overpressure protection systems j{ shall be OPERABLE:
- a. The Shutdown Cooling System Relief Valve (PSV 9349) with:
t
-l 1) A lift setting of 406 i 10 psig*, and 3 2) Relief valve isolation valves 3HV9337, 3HV9339, 3HV9377, and j 3HV9378 open, or, i b. The Reactor Coolant System depratsurized with an RCS vent of greater
- than or equal to 5.6 square ir.nzs.
! APPLICABillTY: Mode 4 when the temperature of any one RCS cold leg is less i
than or equal to that specified in Table 3.4-3; MODE 5; MODE 6 with the reactor vessel head on.
ACTION:
4
- a. With the SDCS Relief Valve inoperable, reduce T,9 to less than
! 200*F, depressurize and vent the RCS through a greater than or equal
! to 5.6 square inch vent within the next 8 hocrs,
- b. With one or both SDCS Re;ief Valve isolation valves in a singie SDCS
, Relief Valve isolation valve pair (valve pair 3HV9337 and 3HV9339 or valve pair 3HV9377 and 3HV9378) closed, open the closed valve (s) i M @in 7 days or reduce T,y to 'iess than 200*F, depressurize and-Vent the RCS through a greater than or equal to 5.6 inch vent within j the next 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
- c. In the event either the SDCS Relief Valve or an RCS vent is used to
. prepared and submitted to the Commission pursuant to Specification 6.9.2 within 30 days. The report shall describe the circumstances 1 initiating the transient, the effect of the SDCS Relief Valve or RCS vent on the transient and any corrective action necessary to prevent
, recurrence.
- d. The provisions of Technical Specification 3 0.4 are not applicable.
l SURVEltLANCE RE0VIREMENTS _
4.4.8.3.1.1 The SDCS Relief Valve shall be demonstrated OPERABLE by:
- a. Verifying at'least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> when the SDCS Relief Valve is being used for overpressure protection that SDCS Relief Valve isolation valves 3HV9337, 3HV9339, 3HV9377 and 3HV9378 are open.
'The lift setting' pressurn applicable to valve temperatures of less than or
! equal to 130*F.
SAN ONOFRE-UNIT 3 3/4 4 AMENDMENT NO.
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OVERPRESSURE PROTECTION SYSTEMS !
j FIS TENKRATURE >302 265*E .
l
- LIMITING CONDITION FOR OPERATION
{ 3.4.8.3.2 At least one of the following overpressure protection systems
, shall be OPERABLE:
j a. The Shutdown Cooling System Relief Valve (PSV 9349) with:
i
} 1) A lift setting of 406 i 10 psig*, and 1
i 2) Relief valve isolation valves 3HV9337, 3HV9339, 3HV9377, and
. 3HV9378 open, or,
! b. A minimum of one pressurizer code safety valve with a lift setting of 1 2500 psia i 1%".
- APPLICABillTY: Mode 4 with RCS temperature above that specified in Table 3.4-3.
! ACTION:
j a. With no safety or relief valve OPERABLE, be in COLD SHV100WN and vent the RCS through a greater than or equal to 5.6 square inch vent i within the next 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, i
l b. In the event the SDCS Relief Valve or an RCS vent is used to mitigate
- an RCS pressure transient, a Special Report shall bs prepared and i submitted to the Commission pursuant to Specification 6.9.E within 30 l days. The report shall describe the circumstances initiating the :
t transient, the effect of the SDCS Relief Valve code safety valve or RCS vent on the transient and any corrective action necessary to j prevent recurrence.
SURVElllANCE RE0VIREMENTS l
! 4.4.8.3.2.1 The SDCS Relief Valve shall be demonstrated OPERABLE by:
i a. Verifying at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> that the SDCS Relief Valve i isolation valves 3HV9337, 3HV9339, 3HV9377 and 3HV9378 are open when the SDCS Relief Valve is being used for overpressure protection.
f b. Verifying relief valve setpoin't at least once per 30 months when
! tested pursuant to Specification 4.0.5 4.4.8.3.2.2 The pressurizer code safety valve has no additional surveillance requirements other than those requir.ed by Specification 4.0.5.
, 4.4.8.3.2.3 The RCS vent shall be verified to be open at least once per-12 hours when the vent is being used for cverpressure protection, except when the
- vent pathway is provided with a valve which is locked sealed, or other<ise-
! secured in the open position,- then verify these valves open at least once-per 31-days.
' ' The lift setting pressure applicable to_ valve temperatures of'less than or
- equal.to-130*F.
"The lift setting pressure shall correspond to ambient conditions of the valve
- at nominal opere. ting temperature and pressure.
SAN ON0FRE-UNIT 3 3/4.4-35 AMENDMENT N0.
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REACTOR COOLANT SYSTEM BASFS PRESSURE / TEMPERATURE LIMITS (Continued)
The heatup and cooldown limit curves forl normal ~ operation (Figures 3.4-2 ,
and 3.4-34) and the cooldown limit ~ curve ~ for- remote shutdown operation (Figure 3.4l-6) are composite ~ curves ihichlere~ prepared by determining the most conservative case, with either the inside or outside wall controlling, for any heatup rate of up to 60*F/hr or cooldown rate of up to 100'F/hr. The limit curvesEforRemote Shutdown ~ operation"are' determined'using;the: Total Loop Uncertaintias (TLUs)- foritemperature;and pressuretfor;the: Remote Shutdown Panel ,
instruments 91n which the pressure:TLUsiare higher than;those for the Cont <ol Room shutdown ~1nstruments. 'The'heatup and~cooldown' cur:Ves"were~ prepared based upon the mo'st' limiting Value of the predicted adjusted reference temperature at the end of the service period indicated on Figures 3.4-2 and 3.4-3.4f for^ normal operatioli and: Figure 3:4;61for Remote Shutdownloperation?
The reactor vessel materials have-been Were tested p'rior to reactor startup i
to determine Generic their initial RT,21 01,'"The results'of'these tests ~and the. updates in responseTto" 3 etter192 Reactor" Vessel / Structural Integrity," Revision '
1~are shown in~ Table ~B 3/474-1. Reactor' operation ~ arid resultant fast neutron :(E' greater than 1 MeV) irradiation will cause an increase in the RT,37 Therefore, an adjusted reference temperature based upon the fluence and copper and nickel content of the material in question, can be predicted using UFSAR Table 5.2-6 6
, and the recor,eendations of Regulatory Guide'l.99, Revision 2, " Radiation Embrittlement of Reactor Vessel Materials." The heatup limit: curve (Figure 3.4-
- 2) and th'e cooldown limit curves, Figt res 3.4-241 and 3.4-36, include predicted' at the end of the applicable service period, adjustments for this shift as well as adjustments in RT,'e errors in the pressure and temperature for possibl sensing instruments.
lne actual snift in RTg3 of the vessel material will be established periodically during operation by removing and evaluating, in accordance with ASTM E185 73 and 10 CFR 50 Appendix H, reactor _ vessel material irradbtion sur-veillance 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.
l Since the neutron spectra at the irradiation samales and vessel inside radius are essentially identical, the measured transition siift for a sample can be applied
+
with confidence to the adjacent section of the reactor vessel taking into account the location of the sample closer to the core than the vessel wall by means of-
< the Lead Factor. The heatup and cooldown curves must be recalculated when the-determined from the surveillance capsule is different from the deltaRT,3deltaRTnt calculate for the equivalent capsule radiation exposure.
The pressure-t2mperature limit lines shown on Figures 3.4-2 and 3.4 -3 for reactor criticality and for. inservice leak and_ hydrostatic testing have been provided to assure compliance with the minimum temperature requirements of Appendix G to 10.CFR 50.
l l
l SAN ON0FRE-UNIT 3 8 3/4 4-7 AMENDMENT NO.
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-7
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BASES ,,
PRESSVRE/ TEMPERATURE LlHITS (Continued)
The maximum RT,31 for all Reactor Coolant System pressure-retaining materials, with tha exception of the reactor pressure vessel, has been determined to be 90*F. The lowest Service Temperature limit line shown on Figures 3.4-2, 3.4-47 and 3.4-36 is based upon this RT or since Article NB-2332 (Summer Addenda of ~1972) of Section III of the ASME Boiler and Pressure Vessel Code requires the Lowest Servica Temperature to be RT,o1 + 100*f for piping, pumps and valves.
Below this temperature, the system pressure must be limited to a maximum of 20%
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 pressurizer is operated within the design criteria assumed for the fatigue analysis performed in accordance with the ASME Code requirements.
The low Temperature ~0verpressure: Protection 1(LTOP): enable' temperatures are based upon the recommendations of HUREG 0800 Branch Technical' Position (BTP):RSB 5-24 Revision 1,i'0verpressurization Protection of Pressurized Water Reactors While Operating at Low Temperatures;" -BTP RSB 5-2, Revision 1 defines the enable temperature asL"the water temperature corresponding to'a metal temperature of at i
least:RTu$"ix the1Appen G limit calculations."+190*F at the beltlinn location (1/4t or 3/4t)1that is cont
~ ' " ~
l i
L i
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SAN;0NOFRE! UNIT;3' B'3/4c4;7a?
~ >
' AMENDMENT NO.
TABLE B 3/4.4-1 s:
'r REACTOR VESSEL TOUGHNESS E
g Temperature of Minimum Upper j", Drop Charpy V-Notch Shelf Cv energy
& Weight 0 30 0 50 for longitudinal
= Piece No. ~ Code No. Material Vessel Location Results ft - lb - ft - lb Direction-ft lb 215-01 C-6801-1 A533GRBCL1 Upper Shell Plate -20 28 64 115 215-01 C-6801-2 A533GRBCLI Upper Shell Plate -20 -6 34 106 215-01 C-6801-3 A533GRBCLI Upper Shell Plate -20 18 36 115
!!5-02 C-6802-4 A533GRBCLI Lower Shell Plate -30 3240 6270 1158 215-02 C-6802-5 A533GRBCLI Lower Shell Plate 0 3640 6470 1106
'215-02 C-6802-6 A533GRBCLI Lower Shell Plate -40 3240 M080 9092 215-03 C-6802-1 A533GRBCLI Intermediate Shell - 2010 56110 M0135 9594 c, 215-03 C-6802-2. A533GRBCLI Intermediate Shell -20 40 6670' 1135 w 215-03 C-6802-3 A533GR8CLI Intermediate Shell -10 4460 80 1015 p '203-02 C-6823 A508CL2 Vessel Flange Forging 0 -30 -15 NA 209-02 C-6824-1 A508CL2 Closure Head Flange -40 -100 -100 NA Forging 205-02 C-li829-1 A508Cl2 . Inlet Nozzle Forging 10 -35 -5 109 205-02 C-li829-2 A508CL2 Inlet Nozzle Forging 0 -55 -35 156 205-02 C-li829-3 A508Cl2- . Inlet Nozzle Forging 10 -25 35 112 205-02 C-6829-4 A508CL2 Inlet Nozzle Forging 10 -30 25 108 205-06' C-6830-1 A508CL2 Outlet Nozzle Forging -10 -30 -15 125 M 203-06 C-6830-2 A508CL2- Outlet Nozzle Forging -10 -23 -5 131 9
SE 232-01 C-6840-1 A533GRBCLI Bottom Head Torus -50 -D 0 107 9 232-02 C-6841-1 A533GRBCLI Bottom Head Dome -40 10 20 99 5
b O e
ENCLOSURE-2 CHANGES TO 15.3.4.8.3.1 PAGES WHICH WERE PREVIOUSLY REQUESTED IN AMENDMENT APPLICATION NO. 97 (PCN 358) DATED DECEMBER 20, 1991 AND ARE BEING REQUESTEC IN PCN-359 SAN ONOFRE UNIT 3
't
OVERPRESSURE PROTECTION SYSTEMS RCS TEMPERATURE s 303 265*F g LIMITING CONDITION FOR OPERATION 3.4.8.3.1 Nimore than two high-pressure'safetyYin,lection pumps shall be PdN OPERABLE'ind at least one 'of'the' follcwing ~ overpressure protection systems s'iall 358 be OPERABLE:
- a. The Shutdown Cooling System Relief Valve (PSV9349) with:
- 1) A lift setting of 406 i 10 psig*, and
- 2) Relief valve isolation valves 3HV9337, 3HV9339, 3HV9377, and 3HV9378 opent-+er fdN or,_
ggg
- b. Tb Reactor Coolant System depressurized with an RCS vent of greater t .n or eaual to 5.6 square inches.
APPLICABillTY: MODE 4 when the temperature of any one RCS cold leg is less than or equal to that the enable temperatures specified in
~
peg Table 3.4-3; MODE 5; and MODE 6 w4e when th'e reac-tor-vesse head is on the reactor vess61'and the RCSLis1not' vented. 95 eCTION:
- a. With the SDCS Relief Valve inoperable, reduce T.,, to less than 200*F, depressurize and vent the RCS through a greater than or equal to S.6 square inch vent within the next 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />,
- b. With one or both SDCS Relief Valve isolation valves in a single SDCS Relief Valve isolation valve pair (valve pair 3HV9337 and 3HV9339 or valve pair 3HV9377 and 3HV9378) closed, open the closed valve (s) or power-lock open th'e~other SDCS Relief ValvbHsolationivalve~ pair RN within Mayi 24 hourb "or reduc'e T '[to less"than 200*F,
~
- 359 depressurize and vent the RCS througfi a greater than or equal to 5.6 inch vent within the next 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, v
cb " With1more thanntwo high; pressure shfetirinjection' pumps 10PERABLE, secure the'. third' high-pressure; safety 31njection' pum) by racking;out N
- its? motor circuit brea(er ~or locking;close!1tsJdisc1arge-valve ~ 3gg within
- 8 hours.
- The lift setting pressure applicable to valve temperatures of less than or equal to 130*F.
-SAN ON0FRE-UNIT 3 3/4 4-33 AMENDMEt:T N0.
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