Text

Proposed TS 3/4.7.1, Turbine Cycle, Increasing as-found Setpoint Tolerance of MSSVs
	ML20073D529
Person / Time
Site:	San Onofre
Issue date:	09/22/1994
From:	; SOUTHERN CALIFORNIA EDISON CO.
To:	;
Shared Package
ML20073D497	List: ML20073D492; ML20073D502; ML20073D515; ML20073D529;
References
	NUDOCS 9409270261
	Download: ML20073D529 (24)
	v • d • e

. .

I ATTACHMENT A Existing Specifications and Bases Unit 2 9409270261 940922 PDR ADOCK 05000361 P PDR

g..

I INDEX 7 LIST OF TABLES

PAGE TABLE G 3/4 3-52 i 3.3-10 ACCIDENT MCNITORING INSTRUMENTATION......................

[ 4.3-7 ACCIDENT HONITORING INSTRUMENTATION SURVEILLANCE 3/4 3-54 REQUIREMENTS.............................................

3/4 3-57 4 3.3-11 FIRE DETECTION INSTRUMENTS - MINIMUM INSTRUMENTS OPERABLE

3.3-12 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION --

DELETED

.! 4.3-8 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS - DELETED 3/4 3-55 3.3-13 RADICACTIVE GASEQUS EFFLUENT MONITORING INSTRUMENTATION..

4.3-9 RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION 3/4 3-67 SURVEILLANCE REQUIREMENTS................................

4.4-1 MINIMUM NUMBER OF STEAM GENERATORS TO BE INSPECTED 3/4 4-14DURING INSERVICE INSPECTION.....................................

3/4 4-15 4.4-2 STEAM GENERATOR TUBE INSPECTION..........................

3/4 4-19 3.4-1 REACTOR COOLANT SYSTEM PRESSURE ISOLATION VALVES. . . . . . . . .

q 3/4 4-21 V 3.4-2 REACTOR COO LANT SYSTEM CHEMISTRY. . . . . . . . . . . . . . . . . . . . . . . . .

3/4 4-30a 3.4-3 LOW TEMPERATURE RCS OVERPRESSURE PROTECTION RANGE........

4.4-3 REACTOR COOLANT SYSTEM CHEMISTRY LIMITS SURVEILLANCE 3/4 4-22 1

REQUIREMENTS.............................................

4.4-4 PRIMARY C0OLANT SPECIFIC ACTIVITY SAMPLE AND ANALYSIS 3/4 4-25 PR0 GRAM..................................................

4.4-5 REACTOR VESSEL MATERIAL SURVEILLANCE PROGRAM - 3/4 4-28 WITH0RAWAL SCHEDULE......................................

3/4 6-12 Y 4.5-1 T ENDON SURVEI LLANCE. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

I 3/4 6-12a 4.6 2 TENDON LIFT-0FF F0RCE....................................

3/4 6-20 3.6-1 CONTAINMENT ISOLATION VALVES. . . . . . . . . . . . . . . . . . . . . . . . . . . . .

3/4 7-2 3.7-1 MAIN STEAM SAFETY VALVES.................................'

[

3.7-2 MAXIMUM ALLOWA8LE VALUE LINEAR POWER LEVEL-HIGH TRIP .

t INOPERABLE MAIN STEAM SAFETY VALVES OURING OPERATION 3/4 7-3 1 WITH BOTM STEAM GENERATORS...............................

i b

Q SAN ON0FRE-UNIT 2 XIX AMENDMENT NO. 91

. at( .

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1.

1 i I

., 3/4.7 PLANT SYSTEMS

}

3/4.7.1 TURBINE CYCLE SAFETY VALVES LIMITING CONDITION FOR OPERATION 3.7.1.1 All main steam safety valves shall be OPERABLE with lift settings as specified in Table 3.7-1. l APPLICABILITY: MODES 1, 2 and 3.

ACTION:

a. With both reactor coolant loops and associated steam generators in operation and with one or more main steam safety valves inocerable, l operation in MODES 1, 2 and 3 may proceed provided, that witnin 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , either the inoperable valve is restored to OPERABLE status or the Power Level-High trip setpoint is reduced per Table 3.7-2; otherwise, be in at least HOT STANOBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the fo11cwing 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

, . . , b. The provisions of Specification 3.0.4 are not applicable.

. .]I SURVEILLANCE REQUIREMENTS 4.7.1.1 No additional Surveillance Requirements other than those required by .

Specification 4.0.5.

U.g s.

SAN ON0FRE-UNIT 2 3/4 7-1 AMENOMENT NO. 91

7 _

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E o TABLE 3.7-1 5

2 m

InlN STEAM SAFETY VALVES I g VALVE IE85ER LIFT SE1 TING (1 1%)* ORIFICE SIZE' 4

m Line No. 1 Line ato. 2

a. 2PSV-M01 2PSV-8419 1100 psia 16 ina

b. 2PSV-M82 2PSV-8411 1107 psia 16 in2

c. 2PSV-8403 2PSV-8412 1114 psia 16 in2

d. 2PSV-8404 2PSV-8413 1121 psia 16 in2

, e. 2PSV-8405 2PSV-8414 1128 psia 16 in2 s

[ f. 2PSV-8406 2PSV-8415 1135 psia 16 inz

g. 2PSV-8487 2PSV-8416 1142 psia 16 inz

h. 2PSV-8400 2PSV-8417 1149 psia 16 in2

1. 2PSV-8489 2PSV-8418 1155 psia 16 inz ;

2x E

$ The lift setting pressure shall correspond to ambient' conditions of the valve at nominal operating temperature and pressure.

E

.h

?

i

- . - _ - - _ - _ _ _ _ _ . . - _ - _ _ - . _ - _ - _ - _ _ - - . _ - - - _ _ . - . --._.-._____---___-_--_--_-_2--.--. - - - - - - _ - - . _ - _ - - - _ _ -, _ ,

c..- . . . .. - -

I TABLE 3.7-2 L /

MAXIMUM ALLCWABLE__VALUE LINEAR POWER LEVEL HIGH' TRIP VITH_ INOPERABLE P.AIN 51EAM SAFETY VALVE 5 00 RING OPERATION WITH EOTM STEAM GENERATORS Maximum Allowable value Linear Maximu.- Nuecer of Incperable Safety Power Level-Hign Trip Valves en Any Oceratino Steam Generator (Percent of RATED THERMAL POWER) 1 98.6 2 86.3 3 -74.0 4

61.6 A

$) .,

SAN ON0FRE - UNIT 2 3/4 7-3 AMEN 0 MENT NO. 91 a 5' -

- - - - - - . . - . _ - -1

i . . _ . . _ . _

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f 3/4.7 PLANT SYSTEMS BASES 3/4.7.1 TURBINE CYCLE 3/4.7.1.1 SAFETY VALVES The OPERABILITY of the main stea:n safety valves (MSSVs) ensures that the sacer.cary system pressure will not exceed 110% (1210 psia) of its cesign pressure of 1100 psia during the mest severs anticipated system Operational transient. The total relief capacity available is greater than the maxt:um steam flew requirac af ter a turbine trip from 102% RATED THERMAL POWER coincident with an assumed loss of cendenser heat sink.

The M55V lift setpoints are staggered, as shown in Table 3.7-1, such trat only tnose valves neeced for pressure relief will actuate. The M55V lift settings and relieving capacities meet the requirements of Section III of tne ASME Boiler and Pressure Vessel C:de, 1974 Edition, as described in the Overpressure Pretection Report (UFSAR Appendix 5.2A). The total available relieving capacity for all valves on all of the staam lines is 15,473,628 lbs/hr at 1190 psia. A minimum of one OPERABLE safety valve per steam generator ensures that sufficient relieving capacity is available for removing decay heat.

'( ) STARTUP and/or POWER OPERATION is allevable with safety valves ineparabie within the limitations of the ACTION requirements on the basis of the reduc-tion in sacendary system steam flew and THERMAL POWER required by the recuced reactor trip settings of the Pcwer Level-High channels. The reduced reactor trip allowable values are derived on the folicwing bases:

SP = (X) X- (Y)(V) x 111.0 where:

SP = reduced reactor trip allowable value in percent of RATED TXERMAL POWER.

V = maximum number of inoperable safety valves per steam line.

111.0 = Power Level-High Trip allowable value from Table 2.2-1.

X = Total relieving capacity of all safety valves per steam line in 1bs/ hour (7,736,814 lbs/hr at 1190 psia).

Y = Maximum relieving capacity of any one safety valve in 1bs/ hour l

'(859,646 lbs/hr at 1190 psia), j i

SAN ONOFRE-UNIT 2 8 3/4 7-1 AMENDMENT NO. 91

ATTACHMENT B Existing Specifications and Bases Unit 3 1

l 9

w

XNC EX' 5

{$ LIST OF TABLES .

TABLE PAGE 1

1- 4.3-7 Acc!0ENT MCNITCRING INSTRUMENTATION SURVEILLANCE l j' REQUIREFENTS............................................... 3/4 3 55 !

.....t.

p 3.3-11 FIRE !TECTICN INSTRUMENTS................................. 3/4'3 58 '

i l 3.3-12 RADICACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION -

d OELETED pt h 4.3-6 RA010 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION

$ SURVEILLANCE REQUIREMENTS -- DELETED 3.3-13 RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION.... 3/4 3-66 4.3-9 RADI0 ACTIVE GASECUS EFFLUENT MONITORING INSTRUMENTATION l k SURVEILLANCE REQUIREMENTS.................................. 3/4 3-68 l

3 Y 4.4-1 MINIMUM NUMBER OF STEAM GENERATORS TO BE INSPECTED OURING .

i INSERVICE INSPECTION....................................... 3/4 4-14 4.4-2 STEAM GENERATOR TU8E INSFECTI0N............................ 3/4 4-15 i 3.4-1 REACTOR COOLANT SYSTEM PRESSURE ISOLATION VALVES........... 3/4 4-20 V4'4-22 b]. : 3.4-2 REACTOR COOLANT SYSTEM CHEMISTRY.........................:.

? 4.4-3 REACTOR COOLANT SYSTEM CHEMISTRY LIMITS SURVEILLANCE REQUIREMENTS............................................... 3/4 4-23 f.

h 4.4 4 PRIMARY C00LANT SPECIFIC ACTIVITY SAMPLE................... 3/4 4-26 L

[9 4.4 5 REACTOR VESSEL MATERIAL SURVEILLANCE PROGRAM - WITHORAWAL .

SCHEDULE................................................... 3/4 4-29 F

3.4-3 LOW TEMPERATURE RCS OVERPRESSURE PROTECTION RANGE.......... 3/4 4 31b

+ .

3/4 6-12 4.6-1 TENDON SURVEILLANCE........................................

u 3/4 6-13 7 4.6-2 TENDON. LIFT 0FF F0RCE.......................................

g p 3.6-1 CONTA} MENT'ISCLATIONVALVES............................... 3/4 6-21 P 3/4 7-2 9, 3.7-1 MAIN STEM SAFETY VALVES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

s.

D 3.7 MAXIMUM ALLOWA8LE VALUE LINEAR POWER LEVEL HIGH TRIP -

' WITH INOPERABLI MAIN STIAN SAFETY VALVES DURING CPERATION

- . WITH BOTH STEAM GENERATOR $. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. 3/4 7-3

~

., 1 8' a 8

',< e -SAN'ON0FRE - UNIT.3 XIX AMENOMENT NO. B1 9 ,

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f 3/4.7 PLANT SYSTEMS C)

F 3/4.7.1 TURBINE CYCLE

'ih SAFETY VALVES p

LIMITING CONDITION FOR OPERATION

>;t

? 3.7.1.1 All main steam safety valves shall be OPERABLE with lift settings as t.

specified in Table 3.7-1.

p f APPLICABILITY: H0 DES 1, 2 and 3.

N k ACTION:

O I a. With both reactor coolant loops and associated steam generators in f operation and with one or more main steam safety valves inoperable, .

y operation in MODES 1, 2 and 3 may proceed provided, that within l

? 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , either the inoperable valve is restored to OPERABLE status is or the Power Level-High trip setpoint is reduced per Table 3.7-2; 1 otherwise, be in at least HOT STANOBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

b. The provisions of Specification 3.0.4 are not applicable.

J.

\:'< - } SURVEILLANCE REQUIREMENTS 4.7.1.1 No additional Surveillance Requirements other than those required by i Specification 4.0.5.

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SAN ONOFRE-UNIT 3 3/4 7-1 AMENDMENT NO. 81 i l

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E TABLE 3.7-1 o

5 MIN STEM SMEIY VRW5 l m

~

onligCl 5t2[

.5 UAL% W LIFT SETIIIIG (11%)*

l n Line Ilm. 1 Line Bee. 2-j ,

a. WSW-Mel 3PSV-M10 1100 psia 16 in2

b. 3P5W-MSt 3P5W-M11 1107 psia 16 int

c. 3P5W-MM WSW-M12 1114 psia 16 in2

d. WSW-MM . 3PSW-M13 1121 psia 16 in2

e. 3PSU-ME5 3P5W-M14 1128 psla 16 in*

w J. f. 3P5V-M06 3PSW-M 15 1135 psia 16 in2 3PSW-M07 3PSU-M16 1142 psia 16 in2 3

h. 3PSU-M OS 3PSV-M17 1149 psia 16 int

1. 3PSW-M09 3PSV-Mla 1155 psia 16 in8 E

9

1em litt settles pressure shall correspond te ambient conditions of the valve at' nominal operaties temperature and pressure.

E suuS

p.

s .

d 0 l TABLE 3,7-2 k MAX!PUM ALLCWABLE VALLE LINEAR POWER LEVEL.HIGH Trip WITH INOPERABLE AT" ..A;N w 5 TEAM SAFETI VALVE 5 QURING CPERATICN WITM 30TK STEAM GENEAA!0R5 g Maximum Et:er of Inceerable Safety Maximum Allowable Value U rear Pcwer Level Mign Trip ' '

6 N Valves en Ary Caeratino Steam Generater (Percent of RAIED THERMAL CWEO y.

i 1 98.6 g

s

~

h 2 86.3 h

k 3 74.0 -

g.

4 61.6 m

~

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z w

c( vp i

o 4

8 9

f:

4.

4 E

6 kY ,

R

$5

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!{J 1' 5 3AN ON0FRE - UNIT 3 3/4 7 3 AMDi0 LENT M. 81 4

kY mi

h y

k 3/4.7 DLANT SYSTES h

4{i: s) BASES ~

k, p-3/a.7.1 TUR5INE CYCLE f, 3/a.7.1.1 SAFETY VALVES h The OPERABILITY of the main steam safety valves (MSSVs) ensures that the !

$ secondary system pressure will not exceed 110% (1210 psia) of its design 6 pressure of 1100 psia during the most severe anticipated system operational '

{'l, transient. The total relief capacity available is greater than the maximum l steam flow required after a tureine trip from 102% RATED THERMAL POWER f- coincident with an assumed loss of condenser heat sink. j u

The MSSV lift setpoints are staggered, as shown in Table 3.7-1, such that l

f. only those valves needed for pressure relief will actuate. The MSSV lift setti.gs 9 1 I and relieving capacities meet the requirements of Section III of the ASME Boiler and Pressure Vessel Code, 1974 Edition, as described in the Overpressure Protecticq Report (UFSAR Appendix 5.2A). The total available relieving capacity for all i

i valves on all of the staan lines is 15,473,628 lbs/hr at 1190 psia. A minimum of r one OPERABLE safety valve per steam generator ensures that sufficient relieving capacity is available for removing decay heat.

7 STARTUP and/or POWER OPERATION is allowable with safety valves inoperable 0,~ within the limitations of the ACTION requirements on the basis of the reduc-

) tion in secondary systes steam flow and THERMAL POWER required by the reduced The reduced reactor trip

[i i

reactee trip settings of the Power Level High channels.

allowable values are derived on the following bases:

T SP = (*I ~ IY)fYI x 111.0

- X y where:

b

SP = reduced reactor trip allowable value in percent of RATED THERMAL

POWER.

y -

V = maximum number of inoperable safety valves per steam line.

g 111.0 = Power Level-High Trip allowable value from Table 2.2-1.

N' X=TotalrelieviN,capacityofallsafetyvalvespersteamlinein 1be/ hour (7,7 814 lbs/hr at 1190 psia).

w Y = Maximum relieving capacity of any one safety valve in 1bs/ hour gJ (859,646 lbs/hr at 1190 psia),

g O

B 3/4 7 1 AMENDMENT NO. 8I SAN ON0FRE-UNIT 3

. = . -

. . l l

l l

l i

ATTACHMENT C Proposed Specifications and Bases Unit 2

JNDEX LIST OF TABLES l TABLE PAGE 3.3-10 ACCIDENT MONITORING INSTRUMENTATION , . . . . . . . . . . . . 3/4 3-52 4.3-7 ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE '

REQUIREMENTS .......... . ... . . . . . .... 3/4 3-54 3.3-11 FIRE DETECTION INSTRUMENTS - MINIMUM INSTRUMENTS OPERABLE .

3/4 3-57 3.3-12 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION -- !

DELETED 4.3-8 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS -- DELETED 3.3-13 RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION . . . 3/4 3-65 4.3-9 RADIDACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS . . . . . . . . . . . . . . . . . . 3/4 3-67 4.4-1 MINIMUM NUMBER OF STEAM GENERATORS TO BE INSPECTED DURING J INSERVICE INSPECTION .................... 3/4 4-14 4.4-2 STEAM GENERATOR TUBE INSPECTION . . . . . . . . . . . . . . . 3/4 4-15 3.4-1 REACTOR COOLANT SYSTEM PRESSURE ISOLATION VALVES . . .... 3/4 4-19 3.4-2 REACTOR COOLANT SYSTEM CHEMISTRY . . . . . . .. . ... .. 3/4 4-21 3.4-3 LOW TEMPERATURE RCS OVERPRESSURE PRbTECTION RANGE . .. . . . . 3/4 4-30a 4.4-3 REACTOR COOLANT SYSTEM CHEMISTRY LIMITS SURVEILLANCE REQUIREMENTS ........................ 3/4 4-22 l 4.4-4 PRIMARY COOLANT SPECIFIC ACTIVITY SAMPLE AND ANALYSIS PROGRAM . . . ...... . . . . . . . . . .. 3/4 4-25 4.4-5 REACTOR VESSEL MATERIAL SURVEILLANCE PROGRAM -

WITHDRAWAL SCHEDULE . . . . . . . . . . . . . . . . . . . . . 3/4 4-28 i

4.6-1 TENDON SURVEILLANCE . ... . . . . . . .. ... 3/4 6-12 i l

4.6-2 TENDON LIFT-0FF FORCE . . . . . . . . . . . . . . . . . . . . 3/4 6-12a i 3.6-1 CONTAINMENT ISOLATION VALVES ................ 3/4 6-20 3.7-1 MAIN STEAM SAFETY VALVES .................. 3/4 7-2 3.7-2 MAXIMUM ALLOWABLE VALUE LINEAR POWER LEVEL-HIGH TRIP WITH 4NOPERABLE MAIN STEAM SAFETY VALVES DURING OPERATION l 5sg.1 WITH BOTH STEAM GENERATORS ................. 3/4 7-3 i

i SAN ON0FRE - UNIT 2 XIX AMENDMENT N0 l l

l

3/4.7 PLANT SYSTEMS l 3/4.7.1 TURBINE CYCLE SAFETY VALVES LIMITING CONDITION FOR OPERATION 3.7.1.1 All main steam safety valves settings as specified in Table 3.7-1.,shall be OPERABLE with as found lift l APPLICABILITY: MODES 1, 2 and 3.

ACTION:

a. With both reactor coolant loops and associated steam generators in i operation and with one or more main steam safety valves inoperable, -

operation in MODES 1, 2 and 3 may proceed provioed, that within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , either the ir. per:ble valve i: re:tered t OPEPf3!.E :tatus cr ,

the Power Level-High trip setpoint is reduced per Table 3.7-2; otherwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in l%f1 f

GOLD @ TjSHUTDOWN within the following 30 12s. hours. , ,

b? y' ^Wi thToheTof! aopel Ste aW Gehira torsDh aV16g71 esEthan';fi ve'mai h Ts te ss safety, valv~es:0PERABLEbbe[in~ atileast1HOTESTAND8Y within the nextL6 !

hoursLand.;inlHOTgSHUTDOWN;within1th,elfollowingf. l2 hours;'-

.,..>.c t

be. The provisions of Specification 3.0.4 are not applicable.

1 SURVEILLANCE REQUIREMENTS l 4.7.1.1 No additional Surveillance Requirements other than those required by ;

Specification 4.0.5. i r

i l

P R Fol l osi6f tes ti ngiaccordi ng7 tRSpki fi sti on'4 :015"MSSVsisillXretiirnsdLt6 ~ [

k.ithin +/..tl% ofJthe,~li_fti:settin.g lspecified,::i.nlTable13_;7,-1 ^'~ ' " " ' ' '

- . - _ ~ . - .

l SAN ONOFRE UNIT 2 3/4 7-1 AMENDMENT NO. (

i i

TABLE 3.7-1 .

z MAIN STEAM SAFETY VALVES E

8 5 VALVE NUMBER LIFT SETTING ' 16 ORIFICE SIZE 1

C 5,

Line No. 1 Line No. 2

" 1100 psia'* M-inE

a. 2PSV-8401 2PSV-8410 -

b. 2PSV-8402 2PSV-8411 1107 psia M-+n!

c. 2PSV-8403 2PSV-8412 1114 psia M -ini

d. 2PSV-8404 2PSV-8413 1121 psia M-in!

w e. 2PSV-8405 2PSV-8414 1128 psia M-m!

l M-inE y f. 2PSV-8406 2PSV-8415 1135 psia t'a

g. 2PSV-8407 2PSV-8416 1142 psia M-in!

h. 2PSV-8408 2PSV-8417 1149 psia M-ini

i. 2PSV-8409 2PSV-8418 1155 psia M-m!

E E *The lift setting pressure shall correspond to ambient conditions of the valve at nominal operating E temperature and pressure. Each MSSV has'-an as-found: tolerance 70f?+2%/-3%2 .Following1testin(according'?:to E 5pecificationT4:0:51:i.MSSVsTwil15 be set :within}+/;1% of': thel..specifiedilift ;setpointii'.

[ ;* Val vesf 2PSVsB4012 and ' 2PSV?.84.10.: hsve lanj as 2found.0 i f t):setti ngf.of:' 110.0:@ s i alwi thj.aQb] srancelo fi+1%g 3%{

. , . . . _ . _ . _ , . - . . _ . ~ _ . . _ . . _ . . , . . . . . _ . . . _ - . . -, . _ . , . . - . - - . _ - - . . . _ . _ _ _ . , ,.

TABLE 3.7-2 MAXIMUM ALLOWABLE VALUE LINEAR POWER LEVEL-HIGH TRIP WITH 4#0PERABLE MAIN STEAM SAFETY VALVES DURING OPERATION WITH BOTH STEAM GENERATORS t

";xt::: Number of Maximum Allowable Value Linear In:per:ble OperableiSafety Valves en Power Level-High Trip An; 0:cratihiner'Doerable75 team Generator (Percent of RATED THERMAL POWER) ;

+8 98.6 hppl B7 86.3 1

3p 74.0 4 ,5 61.6 '

i t

i 1

l t

h 1

I SAN ON0FRE - UNIT 2 3/4 7-3 AMENDMENT NO. l 1

l

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3/4.7 PLANT SYSTEMS BASES 3/4.7.1 TURBINE CYCLE 3/4.7.1.1 SAFETY VALVES The OPERABILITY of the main steam safety valves (MSSVs) ensures that the secondary system pressure will not exceed 110% (1210 psia) of its design pressure of 1100 psia during the most severe anticipated system eperational transient. The total relief capacity available is greater than the maximum steam flow required after a turbine trip from 102% RATED THERMAL POWER coincident with an assumed loss of condenser heat sink.

The MSSV lift setpoints are staggered, as shown in Table 3.7-1, such that only those valves needed for pressure relief will actuate. Columnt3[and i footnote's '11 and " 2 L o f1Tabl e a 3 ; 7-1 ? speci fy s the :setpoi nts? and Ltol erances /whi ch? me'et i valve operability! requirements consistent with thelsafetyJanalysistassumptions....

~

(

The'MSSVs'lif t' cettingnnd FelicVing' d:pacitief =ct were: constructed 'in~

accordanceLwithsthe requirements of Section III of the"ASME Boiler"ahd' Pressure Vessel Code,1974 Edition, as described in the Overpressure Protection Report (UFSAR Appendix 5.2A). The?:valvesTareitested under:ASMEtSectionTXIsp~e r TechnicaltSpecification?4.015btThstotal'availablerelissingcapacity'forall valves 'on~al1~6f ~ths ^ steam"liriss is 15,473,628 lbs/hr at 1190 psia. A minimum of one OPERABLE safety valve per steam generator ensures that sufficient ]

relieving capacity is available for removing decay heat.

l Theilowest!allowablesliftis'ettingiof r1067 psia': (1100l: psia 13%)Tisiboundedjby exi;stingianalysest:Mhe tradiological release lassump.tions .used intthe; 3 Steam ~~

Generator Tube Rupture' dose assessmentibound the source; terms which areibasedion ~

a low MSSV setpoint ofjl100gpsia with115% MSSV; blowdown'.7 Moreover,; steam gene rato rd rel ea ses; and ii nteg rated Lprimaryi to : secondary:: ma ssil ea kage "wi th L15%

MSSVT: blowdown: from1thellowestiallowibleilift3 settingioffl067/ psia wouldLnot be s.i gni fi cantly[di.ffe rent i from : thos e s s.s.umi ng[15%f b.l owdownj ffanJ1100 l psia i STARTUP and/or POWER OPERATION is allochla with safety valves inoperable within the limitations of the ACTION requirements on the basis of the reduction in secondary system steam flow and THERMAL POWER required by the reduced reactor trip settings of the Power Level-High channels. The reduced reactor trip allowable values are derived on the following bases:

(X) - (Y}(V)

SP = X x 111.0 where:

SP = reduced reactor trip allowable value in percent of RATED THERMAL POWER.

V= maximum number of inoperable safety valves per steam line.

111.0 = Power Level-High Trip allowable value from Table 2.2-1.

X= Total relieving capacity of all safety valves per steam line in lbs/ hour (7,736,814 lbs/hr at 1190 psia).

Y= Maximum relieving capacity of any one safety valve in lbs/ hour (859,646 lbs/hr at 1190 psia).

SAN ON0FRE-UNIT 2 B 3/4 7-1 AMENDMENT NO.

i ATTACHMENT D Proposed Specifications and Bases Unit 3 h

t

) b l

i l

1 INDEX LIST OF TABLES TABLE PAGE ,

[ 4.3-7 ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE i

REQUIREMENTS ....................... 3/4 3-55 3.3-11 FIRE DETECTION INSTRUMENTS ................ 3/4 3-58 3.3-12 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION --

DELETED 4.3-8 RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS -- DELETED ,

3.3-13 RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION .

3/4 3-66 4.3-9 RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS . . . ............. 3/4 3-68 4.4-1 MINIMUM NUMBER OF STEAM GENERATORS TO BE INSPECTED DURING INSERVICE INSPECTION ................... 3/4 4 14 4.4-2 STEAM GENERATOR TUBE INSPECTION . . . . . . . . . . . . . . 3/4 4-15 3.4-1 REACTOR COOLANT SYSTEM PRESSURE ISOLATION VALVES ..... 3/4 4-20 3.4-2 REACTOR COOLANT SYSTEM CHEMISTRY ............. 3/4 4-22 4.4-3 REACTOR COOLANT SYSTEM CHEMISTRY LIMITS SURVEILLANCE REQUIREMENTS ....................... 3/4 4-23 4.4-4 PRIMARY COOLANT SPECIFIC ACTIVITY SAMPLE ......... 3/4 4-26 4.4-5 REACTOR VESSEL MATERIAL SURVEILLANCE PROGRAM - WITHDRAWAL SCHEDULE ..... . .. ........... 3/4 4-29 3.4-3 LOW TEMPERATURE RCS OVERPRESSURE PROTECTION RANGE . . . . . 3/4 4-31b 4.6-I TENDON SURVEILLANCE . . . ................ 3/4 6-12 4.6-2 TENDON LIFT-0FF FORCE . . . . .............. 3/4 6-13 3.6-I CONTAINMENT ISOLATION VALVES ............... 3/4 6-21 3.7-1 MAIN STEAM SAFETY VALVES ................. 3/4 7-2 3.7-2 MAXIMUM ALLOWABLE VALUE LINEAR POWER LEVEL-HIGH TRIP WITH 4N0PERABLE MAIN STEAM SAFETY VALVES DURING OPERATION lStr.1 ,

WITH BOTH STEAM GENERATORS ................ 3/4 7-3 SAN ONOFRE-UNIT 3 XIX AMENDMENT N0.

o I

I 3/4.7 PLANT SYSTEMS 3/4.7.1 TURBINE CYCLE !

\

SAFETY VALVES LIMITING CONDITION FOR OPERATION 3.7.1.1 All main steam safety valves,shall be OPERABLE with as-found lift settings as specified in Table 3.7-1.

APPLICABILITY: MODES 1, 2 and 3.

ACTION:

a. With both reactor coolant loops and associated steam generators in operation and with one or more main steam safety valves inoperable, operation in MODES 1, 2 and 3 may proceed provided, that within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , the Power either the inoperable Level-High valve trip setpoint is restored is reduced to OPERABLE per Table 3.7-2; status otherwise, be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in GOLD HOT SHUTDOWN within the following 30 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

b. 'With one or more1 Steam Generators havingLless?than five main (steam safety valves OPERABLE,- be in at11 east . HOTS STANDBY. withinltheinexth6

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hours-and in' HOT-SHUTDOWN withinLthe.1followingE12l.hoursi b c. The provisions of Specification 3.0.4 are not applicable.

SURVElltANCE REQUIREMENTS 4.7.1.1 No additional Surveillance Requirements other than those required by Specification 4.0.5.

Following'testingfaccording"to'Specificationi4.0.52 MSSVs willlbelreturIiedlt'o within' +/pl%;of the: lift' setting specified in: Table. 3.7-1;

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SAN ON0FRE-UNIT 3 3/4 7-1 AMENDMENT N0.

a TABLE 3.7-1 ,

m E MAIN STEAM SAFETY VALVES E

.o

" LIFT SETTING ':/ 1%)* ORIFICE SIZE VALVE NUMBER E

Z Line No. 1 Line No. 2 w

a. 3PSV-8401 3PSV-8410 1100 psia ** M -in 2 2

b. 3PSV-8402 3PSV-8411 1107 psia M-m 2

c. 3PSV-8403 3PSV-8412 1114 psia M-m

d. 3PSV-8404 3PSV-8413 1121 psia M-4n 2 1128 psia M -in g e. 3PSV-8405 3PSV-8414 y f. 3PSV-8406 3PSV-8415 1135 psia M-in z ro

g. 3PSV-8407 3PSV-8416 1142 psia M -in2

h. 3PSV-8408 3PSV-8417 1149 psia M -inz

i. 3PSV-8409 3PSV-8418 1155 psia M-m m

N 5 *The lift setting pressure shall correspond to ambient conditions of the valve at nominal operating 5 temperature and pressure. Each :.MSSV;hastanias-found1toleranceTofi+2%/-30 LFollosi.ncj'ftsstingfaccordingito ^

Specifibati6n?4.0! SUMS $Vf will? bc7 set'withiR+/-1% ofLthe EspecifiedJ.. l iftisettincj. ~~ ~

2 s J an asifoun'd fl i ft/se tti ng ! o f41.1.00f.ps i alki th; altbl ePancel?o.fR.../1%.$3$0

- Val vess 3 PSV-84013a_n.d_( 3 PSV y 8410 / have ._ ._ s . _ .

,a . ..

1

. ~ .

TABLE 3.7-2 MAXIMUM ALLOWABLE VALUE LINEAR POWER LEVEL-HIGH TRIP WITH IN0PERABLE MAIN STEAM >

SAFETY VALVES DURING OPERATION WITH BOTH STEAM GENERATORS Ma*4 mum Number of Maximum Allowable Linear Power 4eoper-able Operable Safety Valves en Level-High Trip Any Or,crat4e4 Der Operable Steam Generator (Percent of RATED THERMAL POWER) 48 98.6 5 4 (. L 1 27 86.3 36 74.0 45 61.6 i

B SAN ON0FRE - UNIT 3 3/4 7-3 AMENDMENT NO.

3/4.7 PLANT SYSTEMS BASES j

1 3/4.7.1 TURBINE CYCLE l l

3/4.7.1.1 SAFETY VALVES The OPERABILITY of the main steam safety valves (MSSVs) ensures that the secondary system pressure sill not exceed 110% (1210 psia) of its design pressure of 1100 psia during the most severe anticipated system operational transient. The total relief capacity available is greater than the maximum steam flow required af ter a turbine trip from 102% RATED THERMAL POWER coincident with an assumed loss of condenser heat sink.

The MSSV lift setpoints are staggered, as shown in Table 3.7-1, such that only those valves needed for pressure relief will actuate. Column 131and footnotef1Eand 2Lof Table 3.7-ir:specifylthe' setpointstandTtolerances%hichimeet valve operability requirements: consistent- with'the safety. analysis asssinptions.

The MSSys' lift settings and reliesing' capacit4cs 'dect were~ constructedLin" accordance ~with the requirements of Section III of the ASME Boiler ~and' Pressure Vessel Co'de,1974 Edition, as described in the Overpressure Protection Report (UFSAR Appendix 5.2A). The" valves are tested under ASME?Section' XI'per Technica115pecification-'4.0.5z The total available relieving" capacity for all

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valves on~ all of the steam lines is 15,473,628 lbs/hr at 1190 psia. A minimum of one OPERABLE safety valve per steam generator ensures that sufficient relieving capacity is available for removing decay heat.

The lowest 'allowableel_iit settirig'of 1067 psia ~(110_0. psia 1:-3%)is bounded by existing analyses.. The:radi01ogical: release-' assumptions;usediin the) Steam Generator < Tube" Rupture doseiassessment' bound the sourceLterms"which'are based on a low MSSV setpoint"ofel100: psia with 15% MSSV-blowdown. LMoreoverJsteam generator releasas and integrated primary to secondary mass leakage with 15%

MSSV blowdown from the lowest allowable lift' setting.:of?10673 psia:wouldinot be significantly differentffrom;those' assuming 15% blowdown from:1100 psia.

STARTUP and/or POWER OPERATION is allowable with safety valves inoperable within the lit.itations of the ACTION requirements on the basis of the reduction in secondary system steam flow and THERMAL POWER required by the reduced reactor trip settings of the Power Level-High channels. The reduced reactor trip allowatle values are derived on the following bases:

(X) - (Y)(V)

SP = X x 111.0 where:

SP = reduced reactor trip allowable value in percent of RATED THERMAL POWER. g'ffl V= maximum nsaber of inoperable safety valves per steam line.

111.0 = Power Level-High Trip allowable value from Table 2.2-1.

X= Total relieving capacity of all safety valves per steam line in lbs/ hour (7,736,814 lbs/hr at 1190 psia).

Y= Maximum relieving capacity of any one safety valve in ;

ibs/ hour (859,646 lbs/hr at 1190 psia).

SAN ONOFRE-UNIT 3 8 3/4 7-1 AMENDMENT N0.

ML20073D529

Text

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