ML20012G597
| ML20012G597 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 03/05/1993 |
| From: | SOUTHERN CALIFORNIA EDISON CO. |
| To: | |
| Shared Package | |
| ML20012G595 | List: |
| References | |
| NUDOCS 9303090550 | |
| Download: ML20012G597 (23) | |
Text
{{#Wiki_filter:1 i l t I ATTACHMENT A I i Existing Specifications and Bases Unit 2 I f l t l l l 9303090550 930305 , PDR ADOCK 05000361 I PDR \ P
3/4.7 8LANT SYSTEMS 3/4.7.1 TURBINE CYCLE SAFETY VALVES LIWITING CCNCITICN :CR CPERATICN 3.7.1.1 All main steam safety valves shall ha CPERABLE with lift settings as l specified in Table 3.7-1. APPLICABILITY: MODES 1, 2 and 3. ACTICN:
- a. With both reactor coolant loops and associated steam generators in operation and with one or more main steam safety valves ino:erable, l cperation in MODES 1, 2 and 3 may proceed providec, that witnin 4 hours, either the inoperable valve is restored to OPERABLE status or the Power Level-High trip setpoint is reducee per Table 3.7-2; otherwise, ce in at least HOT STAND 8Y within the next 6 hours and in COLD SHUTDOWN within the following 30 hours.
- b. The provisions of Specification 3.0.4 are not applicable.
SURVEILLANCE REQUIREMENTS 4.7.1.1 No additional Surveillance Recuirements other than those required by Specification 4.0.5. SAN ONOFRE-UNIT 2 3/4 7-1 AMENDMENT NO. 91 i
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2 i A a4 i a aiJ , SAN ONOFAE - UNIT 2 3/4 7-2 AMEN 0 MENT N0.91'. l l
TABLE 3.7-2 MAXIwuM ALLOWASLE_VALUE LINEAR DOWER LEVEL-dIGH TRIP WITH INOPERABLE MA;N 5 TEAM 5AFETY VALVE 5 DURING CFERAT;0N wiTm BCTM 5 TEAM 5ENERATCR5 l Maximum Allowable Valce Linear Maxima- Nu-:er of Inceerabia Safety Power Level Hign Tri: , Valves :n A y C: erat'n; Stea.m Gere-ater (8ercent of RATED TMERMAL DOWER) l l 1 38.6 2 86.3 3 -74.0 4 61.6 9 i SAN CNCFRE - UNIT 2 3/4 7-3 AMENDMENT No. 91
l l 3/a.7 DLANT SYSTEMS BASES ? 3/a.7.1 T;;iBINE CYCLE 4 3/4.7.1.*. SAFETY VALVES The OPERABILITY cf the main steam safety valves (MSSVs) ensures inat the seccreary system pressure will not exceed 110% (1210 psia)ofitscesign pressure of 1100 psia curing the m:st severe anticipated system 0; erat.:nal transient. The total relief capacity available is greater than the maxt:cm steam flew requirac after a turci. e trip from 102% RATED THERMAL PCWER ceincident with an assumed loss of condenser heat sink. The MSSV lift setpcints are staggered, as shown in Table 3.7-1, such snat only tnese valves neeced for pressure relief will actuate. The MSSV lift settings and relieving capacities meet the requirements of Section III of tne ASSE Beiler and Pressure vessel C ce, 1974 Editi:n, as described in the Overpressure Protection Report (UFSAR Appencix 5.2A). The total available relieving capacity f:r 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 generater ensures that sufficient relieving capacity is availacle for removing decay heat. STARTUP and/or PCWER OPERATION is allcwable with safety valves ine:eratie within the limitations of the ACTION requirements en the basis of the reduc-tion in secondary system steam flew and THERMAL POWER required my the reducac react:r trip settings of tne Pcwer Level High channels. The recuced reacter trip allownele values are datived on the following bases:
$p ,(X) - (Y)(V) x 111.0 X
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. 4 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 (859,646 lbs/hr at 1190 psia), SAN ONOFRE UNIT 2 8 3/4 7-1 AMENDMENT NO. 91 l l 1 i
I i ! 6 , I i l 1 l 1 l l i i i, a 4 I i 1 i 4 l- ATTACHMENT B 4 f
- Existing Specifications l and Bases.
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3/4.7 PLANT SYSTEuS 3/4.7.1 TURBINE CYCLE SAFETY VALVES i 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. 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 i 4 hours, 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 STAN08Y within the next 6 hours and in COLD SHUTDOWN within the following 30 hours. '
- b. The provisions of Specification 3.0.4 are not applicable. ,
4 SURVEILLANCE REQUIREMENTS 4.7.1.1 No additional Surveillance Requirements other than those required by Specification 4.0.5. e l l l l SAN ONOFRE-UNIT 3 3/4 7-1 AMENDMENT NO.31
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J J 7ABLE 3.7-2 a wax! MUM ALLCWA8LE VALL[ LINEAR PCW[R LEVEL *HIGH IRIP WITH IhCPERA8L{
*A;% 5TgAM SAFtry VALVE 5 ;LRING ;FERAT;CN *ITM 50Th~ 5 TEA # GEhERA!0R5 Maximum A11cwable Value Li ear Waxt um .% .?:er of I.c:eracle Safety Power Level nig.5 Trip valves :n Ary :eratico Steam Generat:r (8ercent Of RATED ?WERMAL 3Cw!?)
1 98.6 2 66.3 3 74.0 .. 4 61.6 ! 4 5 i L e 3AN ONOFRE - UNIT 3 1/4 7 3 AMENDef No. 81
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) 3/4.7 DLANT Sv57E*85 i i j BASES j 3/4.7.; *URBINE CYCLE
- 3/1.7.1.; SAF UY VALVES
) The OPE 8. ABILITY of the main steam safety valves (MSSVs) ansures snat tse I sec ncary systes pressure will not exceed 110% (1210 psia) of its casign j pressure of 1100 psia curing the aest severe anticipated system peratiensi
; transient. The total relief capacity available is greater than the max h m l steam flow required after a tureine trip from 1025 RATED THERMAL POWER i coincident with an assumed loss of condenser heat sink. l The MSSV lift setpoints are staggered, as shown in Table 3.7-1, such that only these valves needed for pressure relief will actuate. The MSSV lift settir;s and relieving capacities meet the requirements of Section III of the ASME Sciler as described in the overpressure Protect ce i
and Pressure Repcet vessel Code, (UFSAR Appendix 5.2A). 1974 TheEdition,l tota available relieving capacity for all valves on all of the steen lines is 15,473,628 lbs/hr at lito psia. A minimus of one OPERA 8LE safety valve per steen generator ensures that sufficient relieving capacity is availaale for removing decay heat. STARTUP and/or POWER OPERATION is allowable with safety valves inoperable ; within the limitations of the ACTION requirements on the basis of the reduc- ' tion in secondary systaa steam flow and THERMAL POWER required by the recucee
- reac+or trip settings of the Power Level-Nigh channels. The reduced reacter trio :
allewable values are derived on the following bases: SP = (X) - (Y)(V) ,gyy,g l X l' l where: l SP = reduced reactar trip allowable value in percent of RATED THERMAL J POWER. V = maximum number of inoperable safety valves per steam line. 111.0 e power Level High- Trip alloweble value from Table 2.2-1. X = Total relieving capacity of all safety valves per steen line in 1be/ hour (7,736,814 lbs/hr at 1190 psia). Y = Maximum relieving capacity of any one safety valve in 1bs/ hour (859,646 lbs/hr at 1190 psia). l SAN ON0FRE-UNIT 3 3 3/4 7-1 AMENDMENT W. 8I i
i I i i I t ; i I t I 1 , i i t l i I ATTACHMENT C i Proposed Specifications and Bases , i Unit 2
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l l 1 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 asJfound lift settings as specified in Table 3.7-1. APPLICABILITY: MODES 1, 2 and 3. L 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 hours, eWter the inopeeble-valve is restored to OPERABLE status or the Power Level High trip setpoint is reduced per the Maximum Allowable Steady State Power Level is reduced-per Table 3.7-2; ,
otherwise, be in at least HOT STANDBY within' the~ next 6 hours and in ' GGb9 HOT SHUTDOWN within the following 3012 hours.
- b. With one or more Steam Generators havingilbs~s than fivelmainisteam l safety valves OPERABLE, be in at least .H0T STANDBY within the1next 6 hours and'in HOT SHUTDOWN within the following-12 hours.
b c. The provisions of Specification 3.0.4 are not applicable. SURVEILLANCE RE0VIREMENTS 4.7.1.1 No additional Surveillance Requirements other than those required by Specification 4.0.5. .
- Following testing according to Specification:4.0.5,'MSSVf will be r'eturned to within +/-1% of the lift setting specified in Table 3.7-1. .
SAN ONOFRE-UNIT 2 3/4 7-1 AMENDMENT NO. I r
TABLE 3.7-1 m E MAIN STEAM SAFETY VALVES o 5 2 m i VALVE NUMBER LIFT SETTING f:/ 1%)* ORIFICE SIM
.E
- Line No. 1 Line No. 2 w
- a. 3PSV-8401 3PSV-8410 1100 psia M-4n 2
- b. 3PSV-8402 3PSV-8411 1107 psia 4Mn 2
- c. 3PSV-8403 3PSV-8412 1114 psia M-4n!
- d. 3PSV-8404 3PSV-8413 1121 psia 4 M n!
- e. 3PSV-8405 3PSV-8414 1128 psia 16-4n 2
{ [ f. 3PSV-8406 3PSV-8415 1135 psia M-4n!
- g. 3PSV-8407 3PSV-8416 1142 psia 4Mn 2
- h. 3PSV-8408 3PSV-8417 1149 psia M -in'
- i. 3PSV-8409 3PSV-8418 1155 psia M -in!
5 9 E *The lift setting pressure shall correspond to ambient conditions of the valve at nominal operating 9 temperature and pressure. f Each' MSSV h~asTan as-found toleran'ce of +2%/-3%. Following ' testing:according to
- Specification 4.0.5,'MSSVs will. be set within +/-1% of, the specified lift setting.
5 ** Valves 3PSV-8401: and 3.PSV-8410 have an...as-found lift setting of Il00' psia with'a tolera~nce of,+/1%/-3%.
TABLE 3.7-2 l
\
MAXIMUM ALLOWABLEVAWE-MNEAR-POWER LEVEL H]CH TRIPSTEADY -STATE ~ POWER LEVEL WITH ! 4NOPERABLE MAIN STEAM SAFETY VALVES DURING OPERATION WITH BOTH STEAM GENERATORS ) Maximum Allowable Vclue Lincer Madmum Minimum Number of Power Lc/cl High Trip 4++ operable Operable Safety Valves on Stehdy State Power Any-Opere +nt per Operable Steam Generator (Percent'of' RATED THERMAL' POWER) i 48 98A 97.0 27 86-3 84.0 , i
&6 744 72.0 45 6h4 58.0 l l
l l SAN ONOFRE - UNIT 2 3/4 7-3 AMENDMENT NO. i
3/4.7 PLANT SYSTEMS BASES 3/4.7.1 TURBINE CYLLE 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 operational 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 tho:;e valves needed for pressure relief will actuate. ColumnL 3 ' and footnotes I and 2 of Table 3.7-1 specify the setpoints 'and ~ tolerances 1hich meet valve operability requirements consistent with the safety analysis ' assumptions. The MSSVs lift set 44+es-and relic +4g-espacitic:, meet were constructed .in accordance with the requirements of Section 111 of the' ASME Boiler and Pressure Vessel Code,1974 Edition, as described in the Overpressure Protection Report (UFSAR Appendix 5.2A). The valves are tested-under ASME Section XI per Technical Specification 4.0.5 The total available relieving capacity for all valves on all of the steam lines is 15,473,628 lbs/hr at '.90 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 allowable with safety valves inoperable within the limitations of the ACTION requirements on the basis of the reduction in secondary system steam flow and steady state THERMAL POWER. required by the r+duced react +r trip set-t4fes-+f-the Power Level High channch. The reduced reactor tP4p-alkwat4e-vakes are der 4ved on the following bases: Allowable Steady State Power Levels / Operating Modes with inoperable MSSVs are based on. analysis of primary and secondary system pressures' following loss .of Condenser Vacuum and Feedwater Line Break events ' initiated from' the-allowable power limit, conservatively biased for power measurement--errors. -Operation at or below the allowable power will ensure the design over-pressure limits.will'
~
not be exceeded. The lowest allowable lift setting of 1067 psia (1100 psia:-3%) ist bounded by existing analyses. The radiological release -assumptions used -.in the Steam Generator. Tube Rupture dose assessment bound the source terms which arelbased'on a low MSSV setpoint of 1100 psia with 15% MSSV blowdown.-'Moreover,Tsteam generator releases and integrated primary to secondary mass leakage with.15% MSSV blowdown from the lowest allowable lift setting of 1067; psia:wou?d not be significantly different from those assuming 15% blowdown from 1100Lpsia. SAN ONOFRE-UNIT 2 B 3/4 7-1 AMENDMENT NO.
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l i i t t 1 i I i 4 ; i i l t t t b ATTACHMENT D . J 1 Proposed Specifications I and Bases Unit 3 f 4 t i , t
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3/4.7 PLANT SYSTEMS i l 3/4.7.1 TURBINE CYCLE i SAFETY VALVES LIMITING CONDITION FOR OPERATION 3.7.1.1 All main steam safety valves shall be OPERABLE with as^-fo~und 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, l operation in MODES 1, 2 and 3 may proceed provided, that within 4 i hours, st4 tee-t4+e-4*epecable-va4ve is restered to CPERABL4-shhs-ee - Ge-fower Levcl H4 9 h-t+4p-setpehtweduced per the Maximum : Allowable Steady State Power Level is reduced per. Table 3.7-2; i otherwise, be in at least HOT STANDBY within' the next 6 hours and in GGL-D HOT SHUIDOWN within the following 3012 hours. t
~
- b. With one or more Steam Generators having.less thanLfive main steam safety valves OPERABLE, be in at.least HOT STANDBYJ within the next 6 '
hours and-in HOT SHUTDOWN within the'following'12 hours', b c. The provisions of Specification 3.0.4 are not applicable. SURVEILLANCE REQUIREMENTS 4.7.1.1 No additional Surveillance Requirements other than those required by Specification 4.0.5. I i l
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' Tollowing' testing according to Specification 4.0.5, MSSVs will:be returned'to within .+/-l% of the' lift setting specified in Table 3.7-1.
I i SAN ONOFRE-DNIT 3 3/4 7-1 AMENDMENT NO.
TABLE 3.7-1 MAIN STEAM SAFETY VALVES
?
A
, VALVE NUMBER LIFT SETTING 4-#-Mf OR4FICE SIZE E.
Line No. 1 Line No. 2 N
- a. 2PSV-8401 2PSV-8410 1100 psia? 46-491
- b. 2PSV-8402 2PSV-8411 1107 psia 46-in!
- c. 2PSV-8403 2PSV-8412 1114 psia 46-4n'
- d. 2PSV-8404 2PSV-8413 1121 psia 46-4n!
- e. 2PSV-8405 2PSV-8414 1128 psia 46-4n3
)$
[, f. 2PSV-8406 2PSV-8415 1135 psia 16-in 2
- g. 2PSV-8407 2PSV-8416 1142 psia 46-4n!
- h. 2PSV-8403 2PSV-8417 1149 psia F6-in 2
- i. 2PSV-8409 2PSV-8418 1155 psia 46-+n' 3!
E2 E *The litt setting pressure shall correspond to ambient conditions of the valve at nominal operating 7 52 temperature and pressure. Each1 HSSV has lan? as'-found ~ tolera'nce 'of 42?,/-3%; ;Following testing 1according to
- Specification'.4.0.5',iMSSVs willLbe set within +/-l% of~the.specified liftisetpoint.
,8 ** Valves;2PSVt8401 and- 2PSV-8410' have :an; as foundllif t setting 'of' 1100-.psiafwith :'a tolerance of +1%/-3%.
TABLE 3.7-2 I MAXIMUM ALLOWABLEVAWE4H4E44-POWER-44VR-44G4-TMPSTEADY STATE POWER ~ LEVEL WITH H40PERABLE MAIN STEAM SAFETY VALVES DURING OPERATION WITH BOTH STEAM GENERATORS l l Maximum Allowable Lir.ccr Power Ma*4eum Minimum Number of Level High Trip
~
4ftsper+t4e Operable Safety Valves en Steady;StatelPower Any--Doereife per Operable St eam Generator (Percent ~of RATED THERMAL POWER) l 48 & 6 97 0 27 86d 84.0 36 74-0 72.0 45 64-6 58.0 i i SAN ONOFRE - UNIT 3 3/4 7-3 AMENDMENT NO.
3/4.7 PLANT SYSTEMS l i BASES 344.7.1 TURBINE CYCLE ! 3/4.7.1.1 SAFETY VAtVES ( i 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 operational ! transient. The total relief capacity available is greater than the maximum > steam flow required af ter a turbine trip fron 102% RATED THERMAL POWER i 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 3 and footnotes I and 2:of Table 3.7-1 specify the setpoints and' tolerances which meet valve operability requirements consistent with the safetyianalysis assumptions. ' The MSSVs Mf+-set-14ngs-end-reMevhg ccpacitics mect 'were constructed in : accordance with the requirements of Section 111 of the ASME' Boiler'and Pressure Vessel Code,' 1974 Edition, as described in the Overpressure Protection Report (UFSAR Appendix 5.2A). The valves are tested.under ASME1Secti~onjXITper Technical Specification 4.0.5 The total available relievin~g' capacity 'for all i valves on all of the steam lines is 15,473,628 lbs/hr at 1190 psia. A minimum ; of one CPERABLE safety valve per steam generator ensures that sufficient relieving capacity is available for removing decay heat. STARTUP and/or POWER OPERATION is allowable with safety valves inoperable within the limitations of the ' TION requirements on the basis of the reduction , in secondary system steam flos sad steady state THERMAL POWER; required by the l reduced reccter-+v4p settings of the Power Level High chennels. The redueed reaetee-t+4p-aMewalde-values cre der 4+cd on the follov.ing bcses: Allowable Steady State Power Levels / Operating Modes lwithLinopepable MSSVs7are based'on analysis of primary'and secondary system'pressuresifollowing1 Loss 7of Condenser Vacuum and Feedwater Line Break events initiatedt from thedallowable power limit, conservatively biased for power measurementMerrors. L0perationfat , or below the allowable power will ensure the design over-pressure limits will
~ ' '
not be exceeded. , l The lowest allowable lift setting of 1067. psia (1100'psiai-3%)sisibounded by existing analyses. The radiological release assumptions;used in the Steam - Generator Tube Rupture dose' assessment bound the: source oterms whichiareibasedson
~
a low MSSV setpoint of'1100 psia with 15% MSSV blowdown. iMoreoverissteam generator releases and integrated primary to secondary ~ mass leakage withil5% MSSV blowdown from the lowest allowable lift setting of 1067 psia would not be significantly different from those assuming- 15% blowdown :from' 1100 psia. I SAN ON0FRE-UNIT 3 B 3/4 7-1 AMENDMENT NO. i
e 1 l l l i i h On -- Y ., 11 5 Di n n sa . i en :- , , , , . ,,u,- . , , , , , - :- ___-- . _c nnTrn vi __uud i
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