ML18101A622

Proposed Tech Specs,Eliminating Defined Term Controlled Leakage Flow from RCS Operational Leakage LCO & Establishing New Seal Injection Flow LCO

ML18101A622
Person / Time
Site:	Salem
Issue date:	03/30/1995
From:	Public Service Enterprise Group
To:
Shared Package
ML18101A621	List: ML18101A620 ML18101A622
References
NUDOCS 9504110065
Download: ML18101A622 (22)

Text

DEFINITIONS

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SECTION 1.0 DEFINITIONS DEFINED TERMS ACTION AXIAL FLUX DIFFERENCE

• CHANNEL CALIBRATION * *

• CHANNEL CHEClt * * *

• CHANNEL FUNCTIONAL TEST

• CONTAINMENT INTEGRITY eeN'!'RebbED bEA:ltAGB CORE ALTERATION * * *

• ROSE EQUIVALENT I-131,

• E-AVERAGE DISINTEGRATION ENERGY ENGINEERED SAFETY FEATURE "RESPONSE TIME *

• FREQUENCY NOTATION FULLY WITHDRAWN * * * * *. *..

• 1-1

• 1-1

• 1-1

• 1-1

• *

• 1-1

• 1-1

• 1-2

• l 2

• 1-2 1-2

• 1-3

• 1-3 1-3 1-3 GASEOUS RADWASTE TREATMENT SYSTEM.

IDENTIFIED LEAKAGE

........

• 1-3

, 1-3 MEMBER(S) OF THE PUBLIC....

OFFSITE DOSE CALCULATION MANUAL (ODCM)

OPERABLE - OPERABILITY OPERATIONAL MODE PHYSICS TESTS PRESSURE*BOONDARY LEAKAGE.*

PROCESS CONTROL PROGRAM (PCP)

• PURGE-PURGING QUADRANT POWER TILT RATIO.

• RATED THERMAL POWER * * *.. *

• 1-4

• 1-4

• 1-4

• 1-4

• 1-5

• 1-5

• !-5

• 1-5

• 1-5

• 1-5 RE~CTOR TRIP SYSTEM RESPO?>SE TIME *

• 1-6 REPORTABLE EVENT * * * * *... * * * * * * * * * * * *

• 1-6 SHUTDOWN MARGIN

• SITE BOUNDARY

• SOLIDIFICATION SOURCE CHEClt STAGGERED TEST BASIS THERMAL POWER * * *

• UNIDENTIFIED LEAKAGE UNRESTRICTED AREA * *

• VENTILATION EXHAUST TREATMENT SYSTEM VENTING * * *

~ *

• SALEM -

UNIT 1

(

9504110065 950330 PDR ADOCK 05000272 p

PDR I

• 1-6

• 1-6

• 1-6

• 1-6

• 1-6

• 1-7

• • 1-7

• 1-7

• 1-7 1-7 Amendment No. 133 I,

LIMITING CONDITIONS FOR OPERA,TION AfU) SUR.VEil.lANCE REOU!REMENIS SECTION

~

3/4.5 EHERGENCX COBE CQQLING SYSTEHS (ECCS) 3/4.5.1 3/4.5.2 3/4.5.3" 3/4.5.4 3/4.5.5 ACCUMUI.ATORS ECCS SUBSYSTEMS - T

> 35o*F avg -

ECCS SUBSYSTEMS - T

< 350*F a*Tg DELE'i'EB _STAL JAJ-:fEC.T10AJ,CLow REroELING YATER STORAGE TANK 3/4.6 CONIAINMENI SYSiEHS 3/4.6.1 PRIMARY CONTAINMENT Containment Integrity Containment Leakage Containment Air Loclt.s Intern&l Pressure Air Temperature Containment Structural Integrity Containment Ventilatio~ System

• *3/4. 6. 2 DEPRESSURIZATION AND COOLING SYSTEMS Containment Spray System Spray Additive System Containment Cooling System 3/4.6.3 CONTAINMENT ISOU\\TION VALVES 3/4.6.4 COMBUSTIBLE GAS CONTROL Hydrogen Analyzers Electric Hydrogen Recombiners SALEM - UNIT l VI 3/4 5-1 3/4 5-3 3/4 5-6 3/4 5-&t I 3/4 5-9 3/4 6-1 3/4 6-2 3/4 6-5 3/4 6-6 3/4 6e7 3/4 6-8 3/4 6-8a 3/4 6-9 3/4 6-10 3/4 6-11 3/4 6-12 Amendment No. 101

DEF IN IT IONS CONTAINMENT INTEGRITY 1.7 CONTAINMENT INTEGRITY shall exist when:

1.7.l All penetrations required to be closed during accident conditions are either:

a. Capable of being closed by an OPERABLE containrrent automatic isolation valve system, or

b. Closed by manual valves, blind flanges, or deactivated j

automatic valves secured in their closed positions, except as provided in Table 3.6-1 of Specification 3.6.3.l.

1.7.2 All equiprrent hatches are closed and sealed, 1.7.3 Each air lock is OPERABL: pursuant to Specification 3.6.l.3, 1.7.4 The containrrent leakage rates are within the limits of Specification 3.6.l.2, and 1.7.5 The sealing mechanism associated with each penetration (e.g.,

welds, bellows or 0-rings) is OPERABLE.

. CONTROLLED LEAKAGE

/UOT USED 1.8 CONTROLLED LEAKAGE slta11 be that seal wat!r flow 1'relft tfle reaeter eeelaR-t:

pu~ seals.

CORE ALTERATION 1.9 CORE ALTERATION shall be the rroverrent or manipulation of any C01'1ponent within the reactor pressure vesse*l with the vessel head rernved and fuel in the vessel.

Suspension of CORE ALTERATION shall not preclude completion of rmverrent of a co~nent to a safe conservative position.

DOSE EOJIVALENT I-131 1.10 DOSE ECl.JIVALENT I-131 shall be that concentration of I-131 (rTticrocuries per gram) which alone would produce the sal"'e thyroid dose as the quantity and isotopic mixture of I-131, I-132, l-133, I-134, and I-135 actually present. The SALEM - UNIT 1 1-2 Amendment No. 64

(_

DEFINITIONS thyroid dose conversion factors used for this calculation shall be those listed in Table III of TID-14844 "Calculation of Distan~e Factors for Power anc!. Test Reactor Sites."

E - AVERAGE DISINTEGRATION ENERGY 1.11 E shall be the average (weighted in proportion to the concentration of each radionuclide in the reactor coolant at the time of sampling) of the sum of the average beta and gaana energies per disintegration (in MeV) for isotopes, other than iodines, with half-lives greater than 15 minutes, making up at least 95% of the total non-iodine activity in the coolant.

ENGINEERED SAFETY FEATURE RESPONSE TIME 1.12 The ENGINEERED SAFETY FEATURE ~SPONSE TIME shall be that time interval from when the monitored parameter exceeds its ESF actuation setpoint at the channel sensor until the ESF equipment is capable of performing its safety function (i.e., the valves travel to their required positions, pump discharge pressures reach their required values, etc.). Times shall include diesel generator starting and sequence loading delays where applicable.

FREQUENCY NOTATION 1.13 The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 1.2.

FULLY WITHDRAWN 1.13a FULLY WITHDRAWN shall be the condition where control and/or shutdown hanks are at a position which is within the interval of 222 to 228 steps withdrawn, inclusive.

FULLY WITHDRAWN will be specified in the current reload analysis.

GASEOUS RADWASTE TREATMENT SYSTEM 1.14.A GASEOUS RADWASTE TREATMENT SYSTEM is any system designed and installed to reduce radioactive gaseous effluents by collecting primary coolant system off gases from the p~i.mary system and providing for delay or holdup for the purpose of reducing tha total radioactivity prior.. to.. r.alusa.. to.. the..

en~-

IDENTIFIED L!AIAGE 1.15 IDENTilI!D LEAUGI shall be:

REAc...,-O{l. Coot_wvr fvM/l Sk"AL f,PA-r.E,( /,,v:J/£.c,r/'o,-J (),/!-tftAKo.t=F

a.

Leakage (except CON'fROLLEf) LE*lEl\\6!) into closed systems, such as pump seal or valve packing leaks that are* captured and conducted to a sump or collecting tank, or SALEM - UNIT 1 1-3.-

Amendment No. 91

DEFINITIONS

b.

The testing* of one system, subsystem, train, or other designated component at the beginning of each subinterval.

THERMAL POWER l.33 THERMAL POWER shall be the total reactor core heat transfer rate to the reactor coolant.

UNIDENTIFIED LEAKAGE

/exc£.Pr £cne.w!l Ci::oLA.-.,-r fJ,;,,.,,,,f' S&q 1.A...1Ar~) I

~; JA.Y:fe.t!..rw-v v..e L.15.A;~F_F-

l. 34 UNIDENTIFIED LEAKAGE shall be all leakageAwhich is not IDENTIFIED LEAKAGE or C0NTROLLE8 LEAKAGE.

UNRESTRICTED AREA 1.35 An UNRESTRICTED AREA shall oe any area at or beyond the SITE BOUNDARY, access to which is not controlled by the licensee for purposes of protection of individuals-from exposure to radiatjon and radioactive materials, or any area within the SITE BOUNDARY used for residential quarters or industrial, commercial, institutional, and/or recreational purposes.

VENTILATION EXHAUST TREATMENT SYSTEM 1.36 A VENTILATIDN EXHAUST TREATMENT SYSTEM shall be any system designed and installed to reduce gaseous radioiodine and radioactive material in particulate fonn in effluents by passing ventilation or vent exhaust gases through charcoal adsorbers and/or HEPA filters for the purpose of removing iodines or particulates from the gaseous exhaust stream prior to the release to the environment (such a system is not considered to have any effect on noble gas effluents).

Engineered Safety Feature (ESF) atmospheric cleanup systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components.

VENTING 1.37 VENTING shall be the controlled process of discharging air or gas from a confinement to maintain temperature, pressure, humidity, concentration, or other operating condition, in such a manner that replacement air or gas is not provided or required during VENTING.

Vent, used in system names, does not imply a VENTING process.

SALEM -

UN IT 1 1-7 Amendment No. 59

REACTOR COOLANT SYSTEM OPERATIONAL LEAKAGE LIMITING CONDITION FOR-OPERATION

~..;...__~~~~~~~~~~~~~~~~-

3.4.6.2 Reactor Coolant System leakage shall be limited to:

a.

No PRESSURE BOUNDARY LEAKAGE,

b.

l GPM UNIDENTIFIED LEAKAGE,

c.

l GPM total primary-to-secondary leakage through all steam generators and 500 gallons per day through any one s~2am generator,

d.

10 GPM IDENTIFIED LEAKAGE from the Reactor Coolant System, and

• e.

40 GPM CONTROLLED LEAKAGE at a Reaeter Coolant System pressuree-f 2230 _I_ 20 ~s~

APPLICABILITY:

MODES 1, 2, 3'and 4 ACTION:

a.

With any PRESSURE BOUNDARY LEAKAGE, be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and

~ COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

b.

With any Reactor Coolant System leakage greater than any one of the above limits, excluding PRESSURE BOUNDARY LEAKAGE, reduce the leakage rate to within limits within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

SURVEILLANCE REQUIREMENTS 4.4.6.2 Reactor Coolant System leakages shall be demonstrated to be within each of the above limits by;

a.

Monitoring the containment atmosphere particulate rad~oactivity monitor at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

b.

Monitoring the containment sump inventory at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

SALEM - UNIT 1 3/4 4-15

11 REACTOR COOLANT SYSTEM SURVEILLANCE REWIREMENTS (Continued)

NoT us~o

c.

• Measurement of tf1e CONTROLLED LEAKAGE fFern tne 1 ~a:eter cool arit 19um19 seals at least a-flee pel" 31 day!! wl9e"1'l tl'le Reaeto1 Coolant

~rn 13ress1:1re is 2230 1 20 !'Sig and "Vahe 1GV71 is fully

~

d.

Performance of a Reactor Coolant System water inventory balance at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

The water inventory balance shall be perforrred with the plant at steady state conditions.

The provisions of specification 4.0.4 are not applicable for entry into MJde 4, and

e.

MJnitoring the reactor head flange leakoff system at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

SALEM - UNIT 1 3/4 4-16 Amendment No. 58

SALEM - UNIT 1 (SECTION 3.5.4 HAS-BEEN RENIJM~EREO TIJ 3.5.5) 3/4 5-6b

REACTOR COOLANT SYSTEM

• s*ASES 3/4.4.6.2 OPERATIONAL LEAKAGE (Continued)

The CONTROLLEB LEAKAGE limitatieA restFiets eperatieR wAeR tAe tetal flow from the reactor coolant p~mp seals exeeeas 40 GPM with wal~e 1CV71 f~lly elosed at a nemin1l RGS ppess~re ef 223Q psig. TAis limitatie~

-ens~res that in the e¥eAt af a LOCA, the safety iAjeetien flaw w;11 not be.less thaA ass~med in the aeeident aAalyses.

The total steam generator tube leakage limit of 1 GPH for all steam generators (but not more than 500 gpd for any steam generator) ensures that the dosage contribution from the tube leakage will be limited to a small fraction of Part 100 limits in the event of either a steCtm genera-tor tube rupture or S'team line break.

The 1 G'PH limit is consistent with the as!umpUons *u~~c.i in *tht! analysis nf these accidents.

The* 500 gpd leakage l_imi"t*;p~r stearu gene1 ator *e*n~.u:res that steam generator tube integrity is ru.=\\ ir.-Le_in~ in the ev~nt of a main steam 1 i ne rupture or,

under LOCA coud it. fens.

PRESSURE BOUNl*ARY LEAKAGE of any magnitude is unacceptable since it may be indicative of an impending gross failure of the pressure boundary.

Therefore, the prest:nce of any PRESSURE BOUNDARY LEAKAGE requires the unit to be pro.mrri;l y p 1 ar.-ed in COLD SHUTDG:..lN.

3/4.4.7 CHEM-ISTRY" The 11~itations* on Reactor Coolant System chemistry ensure that corrosion of the Reactor Coolant System is minimized and reduces the potential for Reactor Coalant System Leakage or failure due to stress corrosion. Maintaining the chemistry within the Steady Stace Limits provides adequate* corrosion protection to ensure the structural integrity of the Reactor Coolant System over the life of the plant. The associated effects of exceeding the oxygen, chloride and fluoride limits are time and temperature dependent.

Corrosion studies show that operation may be continued with contaminant concentration levels in excess of the Steady State Limits, up to the Transient Limits, for the specified limited time intervals without having a significant effect on the structural integ*rity of the Reactor Coolant System.

The time interval permitting continued operation within the restrictions of the Transient Limits provides time for taking corrective actions to restore the contaminant concentrations to within the Steady State Limits.

The surveillance requirements provide adequate assurance that con-centrations in excess of the limits will be detected in sufficient time to take corrective action.

SALEM - UNIT 1 B 3/4 4-4

EffERGENCX CORE COOLING SYSTEMS BASES ECCS SUBSYSIEHS (Continued)

With the RCS temperature below 350°F, one OPERABLE ECCS subsystem is acceptable without single failure consideration on the basis of the-stable reactivity condition of the reactor and the limited core cooling requirements.

The surveillance requirements, which are provided to ensure the OPERABILITY of each component, ensure that, at a minimum, the assumptions used in the safety analysis. are met and that subsystem OPERABILITY is maintained.

The safety analyses make assumptions with respect to:

1) both the maximum and minimum total system resistance, and 2) both the maximum and minimum branch injection line resistance.

These resistances, in conjunction with. the ranges of potential pump performance, are used to calculate the maximum and minimum ECCS flow assumed in the safety analyses.

The maximum and minimum flow surveillance requirements in conjunction with the maximum and minimum pump performance curves ensures that the assumptions of total system resistance and the distribution of that system resistance among the various paths are met.

The maximum total pump flow surveillance requirements ensure the pump runout limits of 560 gpm for the centrifugal charging pumps and 675 gpm for the safety injection pumps are not exceeded. -

The surveillance requirement for the maximum difference between the maximum and minimum individual injection line flows.ensure that the minimum f

individual injection line resistance assumed for the spilling line following a LOCA is met.

.~

t.

B 3/4 5-l:a-Amendment No. 143 SALEM - UNIT 1 I I

EMERGENCY CORE COOLING SYSTEMS BASES s

3/4.5.+-REFUELING WATER STORAGE TANK The OPERABILITY of the RWST as --part of the ECCS ensures that a sufficient supply of borated water is available for injection by the ECCS in the event of a LOCA.

The limits on RWST minimum volume and boron concentration ensure that:

(1) sufficient water is available within containment to permit recirculation cooling flow to the core, (2) the reactor will remain subcritical in the cold condition following a small LOCA assuming complete mi~ing of the RWST, RCS, and ECCS water volumes with all control rods inserted except the most reactive control assembly (ARI-1), and (3) the reactor will r~~ain subcritical in the cold condition following a large break LOCA (break flow area > 3.0 sq. ft.)

assuming complete mixing of the RWST, RCS, and ECCS water and ct.her sources of water that may eventually reside in the sump following a LOCA with all control rods assUBed to be out (ARO).

The limits on contained water volume and boron concentration also ensure a pH value of between 8.5 and 11.0 for the solution recirculated within containment after a LOCA.

This pH band minimizes the evolution of iodine and minimizes the effect of chloride and caustic stress corrosion on mechanical systems and components.

The contained water volume limit includes an allowance for water not usable because of tank discharge line location or other physical characteristics.

SALEM - UNIT 1 3

B 3/4 5-~

Amendment No. 83

INDEX DE!'INITIO~S SECTION PAGB 1.0 DEFINITIONS DEFINED TERMS.......................................... **** 1-1 ACTION................................................. **** 1-1 AXIAL FLUX DIFFERENCE * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * * *

• 1-1 CHAN'NEL CALIBRATION **************************************** 1-1 CHAN'NEL C!IECK. ********************************************** 1-1 CHAN'NEL FUNCTIONAL TEST ************************************1-1 CONTAINMENT INTEGRITY **************************************1-2 CONT.ROLLE!) LZ1'KACB ***************** * ************************ 1 2 CORE ALTERATION ******************************************** 1-2

~CSE EQUIVALENT I-131 *****************~********************1-2 E-AVERAGE DISINTEGRATION ENERGY ****************************l-3 ENGINEERED SAFETY FEATURE RESPONSE TIME ******************** 1-3 FREQUENCY NOTATION ***************************************** 1-3 FULLY WITHDRAWN *...*.*****.*****.************************** 1-3 GASEOUS RADWASTE TREATMENT SYSTEM. ************************** 1-3 IDENTIFIED LEAKAGE *********

MEMBER(S) OF THE PUBLIC

• • • • • • • • • • • • • • • • • ~ ********* 1-3

• .*.******.*.************** l-4 OFFSITE DOSE CALCULATION MANUAL (ODCK)

OPERABLE - OPERABILITY

• • • • • • • • • • • • • • • • • • • • . 1-4

• • • • • • • 1-4 OPERATIONAL MODE PHYSICS TESTS

• • • • • • • • • • ...*****.**.*.******************* 1-4

• • • • • • • • • • • • • • • • • ..*************************** 1-5

.................................. 1-s PRESSURE BOUNDARY LEAKAGE PROCESS CONTROL PROGRAM (PCP)

PURGE-PURGING ********.********..*

QUADRANT POWER TILT RATIO ******

RATED THERMAL POWER ************

REACTOR TRIP SYSTEM RESPONSE TIME

• * *******.i-S

.1-s

.1-s

.1-s

.1-6 REPORTABLE EVENT********************************************l-6 SHUTDOWN' MA.RGIN ******************************************** 1-6 SITE BOUNDARY ********************************************** l-6 SOLIDIFICATION ********************************************* l-6 SOURCE CHECK ******************************** "' o ************* 1-6 STAGGERED TEST BASIS *************************************** 1-6 THERMAL POWER *************************** ~ **** * ************** 1-7 UNIDENTIFIED LEAKAGE ***************************************1-7 UN'RESTRICTED AREA ****************************************** 1-7 VENTILATION EXHAUST TREATMENT SYSTEM ***********************1-7 VENTING **************************************************** 1-7 SALEM -

UNIT 2 I

Amendme"'.t No. 1121

. INDEX.

L!MITING'"coNJ)tTIONS FQR OP£RATION AND SURVEILI.ANCE REOUIREMENIS SECIIOH

~

3/4,5 EMQGENCX COSE COOLING SYSTEMS CECCS>

3/4.5.l ACCUMULATORS............... ;,,,,...................... 3/4.5:-l 3/4.5.2 3/4.5.3 3/4.5.4 ECCS SUBSYSTEMS - T

> 35o*r avg -

ECCS SUBSYSTEMS - T

< 35o*r avg f)~!I) SEAL 1..v-:rs.c..710,v FL.Ow

....... *................ -.3/4 5-3

........................ 3/4 5-7

¥1 s--S7~\\. I J:

3/4.5.5 R.EFUi:LING YATER. STORAGE TANK..*........*.............. 3/4 5-9 3 /4. 6 CONIAINMENI SYSTF.MS 3/4.6.l PRIMARY CONTAINMENT Containment Integrity.............*................... 3/4 6-1

• Containment 1.Aakage................................... 3/4 6*2 Containment Air Locks................................. 3/4 6 e 4 Internal Pressure...............,...................., 3/4 6-6 Air Temperature........................*.............. 3/4 6-7 Containment Structural Integrity...................... 3/4 6-8 Containment Ventil&tion System.............,.......... 3/4 6-~

3/4.6.2 OEPRESSUR.IZATION AND COOLING SYSTEMS Containment Spray System...,.~.................,,..... 3/4 6-10 Spray Additive System................................. 3/4 6-11 Containment Cooling System........................ ~... 3/4 6-12 3/4. 6. 3 CONTAINMENT ISOLATION VALVES................. *....,..... 3/4 6-14 3/4.6.4 COMBUSTIBLE GAS CONTROL Hydrogen Analyzers.................................... 3/4 6-21 Electric Hydrogen Recombiners........".. *............... 3/4 6-22 SALEM

• UNIT 2 VI Amendment No. 78

DEFINITIONS CONTAINMENT INTEGRITY 1.7 CONTAINMENT INTEGRITY shall exist when:

1.7.1 All penetrations required to be closed during acr.ident conditions are either:

a. Capabie of being closed hy an OPERABLE containrrent automatic isolation valve system, or

b. Closed by manual valves, blind flanges, or deactivated automatic valves secured fn their clo-sed positions, except as provided in Table 3.6-1 ~f Specification 3.6.3.1.

1.7.2 All equipment hatches are closed and sealed, 1.7.3 Each air lock is OPERABLE pursuant to Specification 3.6.1.3, 1.7.4 The containment leakage rates are within the limits of Specification 3.6.1.2, and 1.7.5 The sealing rechanism assoc;ated with each penetration (e.g.,

welds, bellows or 0-rings) is OPERABLE.

CONTROLLED LEAKAGE

/Jo} USED 1.8 CONTROLLEEl LEAKAGE shall be that seal water flow fr 0111 the reactor coola"t

!)ti,.,, seal !!l.

CORE ALTERATION 1.9 CORE ALTERATION shall he the mvel'l@nt or manipulation of any component within the reactor pressure vessel with the vessel head rermved and fuel in the vessel. Suspension *of CORE ALTERATION shall not preclude COMPletio11 of rmver.ent of a component to a safe conservative position.

DOSE EQJIVALENT I-131 1.10 DOSE EQJIVALENT I-131 shall be that concentration of I-131 (microcuries per gram} which alone would produce the same thyroid dose as the* quantity and isotopic mixture of I-131, I-132, I-133, I-134, and I-135 actually present. The SALEM - UN IT 2 1-2 Amendment No. 36

DEFINITIONS

• thyroid dose conversion factors used for this calculation shall be those listed in Table III of TID-14844 "Calculation of Distance Factors for Power and Test Reactor Sites."

E - AVERAGE DISINTEGRATION ENERGY 1.11 E shall be the average (weighted in proportion to the concentration of each radionuclide in the reactor coolant at the time of sampling) of the sum of the average beta and gamma energies per disintegration (in MeV) for isotopes, other than iodines, with half-lives greater than 15 minutes, making up at least 957. of the total non-iodine activity in the coolant.

ENGINEERED SAFETY FEATURE RESPONSE TIME 1.12 The ENGINEERED SAFETY FEATURE RESPONSE TIME shall be that time interval from when the monitored parameter exceeds its ESF actuation setpoint at the channel sensor until the ESF equipment is capable of performing its safety function (i.e., the valves travel to their required positions, pump discharge pressures reach.their required values, etc.).

Times shall include diesel generatcr starting and sequence loading delays where applicable.

FREQUENCY NOTATION 1.13 The FREQUENCY NOTATION specified for the performance of Surveillance Requirements shall correspond to the intervals defined in Table 1.2.

FULLY WITHDRAWN l.13a FULLY WITHDRAWN shall be the condition where control and/or shutdown banks are at a position which is within the interval of 222 to 228 steps withdrawn, inclusive.

FULLY WITHDRAWN wLll be established by the current reload analysis.

GASEOUS RADWASTE TREATMENT SYSTEM 1.14 A GASEOUS RADWASTE TREATMENT SYSTEM is any system designed and installed to reduce r~dioactive gaseous effluents by collecting primary coolant system off gases from the primary system and providing for delay or holdup for the purpose of reducing the total radioactivity prior to release to the environment.

IDENTIFIED LEAKAGE 1.15 IDENTIFIED LEAKAGE shall be:

a.

REM..A<J(l coouv.Jr P()'"'-f' S£AL W.<W".isl. /AJ4'~£JN o,< V-.Ako{+

Leakage (except CON'i'ROLLEtl L!1dCAG!) into closed systems, such as pump seal or valve packing leaks that are captured and conducted to a sump or collecting tank, or SALEM - UNIT 2 1-3 Ar11endmen t No. 66

DEFINITIONS

b.

The testing of one system, subsystem, train, or other designated component at the beginning of each subinterval.

THERMAL ?OWER.

l.33 THERMAL ?OWER shall be the total reactor core heat transfer rate to the reactor coolant.

UNIOENTIFIEO LEAKAGE (t:><:cljf) /.-611<.:;-of-Coo<-.4.A.J'/ PJ~<A/.564L \\

A *t.l.4t\\'<~ IAJ'J"£c.no.J o.- t-6'.4k4 &.5.

.J 1.34 UNIOENTIFIED LEAKAGE shall be all leakage which is ryot IDENTIFIED LEAKAGE er COHTRQLLED LEAKAGE.

UNRESTRICTED AREA l.35 An UNRESTRICTED AREA*sha11 be any area at or beyond the SITE BOUNDARY, access to which 1s not controlled by the 11censee for purposes of protection of individuals from exposure to radiation and radioactive materials, or any area within the SITE BOUNOARY used for residential quarters or industrial, commercial, inst1tutiona1, and/or recreational purposes.

VENTILATION EXHAUST TREATMENT SYSTEM 1.36 A VENTILATION EXHAUST TREATMENT SYSTEM shall be any system designed and installed to r9duce gaseous radioiodine and radioactive material in particulate form 1n effluents by passing ventilation or vent exhaust gases through charcoal adsorbers and/or HEPA filters for th~ purpose of removing iodines or particulates from the gaseous exhaust stream prior to the release to the environment (such a system 1s not considered to have any effect on noble gas effluents). Engineered Safety Feature (ESF) atmospheric cleanup systems are not considered to be VENTILATION EXHAUST TREATMENT SYSTEM components.

VENTING l.37 VENTING shall be the controlled process of discharging air or gas from a confinement to maintaio temperature, pressure, humidity, concentration, or other operating condition, in such a manner that replacement air or gas is not provided or required during VENTING.

Vent, used in system names, does not imply a VENTING process.

SALEM

• UNIT 2 1-7 Amendment No. 28

REACTOR CJOLANT SYSTEM OPERATIONAL LEAKAGE LIMITING CONDITION FOR OPERATION

z====***c=================================~===============*=============

3.4.7.2 Reactor Coolant System leakage shall be limited to:

a.

No PRESSURE BOUNDARY LEAKAGE,

b.

1 GPM UNIDENTIFIED LEAKAGE,

c.

1 GPM total primary-to-secondary leakage through all steam generators and 500 gallons per day through any one stea~ generator,

d.

10 GPM IDENTIFIED LEAKAGE from the Reactor Coolant System, and

/i.drff usf..D

e.

46 6PM CONTROLLEB LEAKAGE at a Reactor Coolant System press~re ef 2239 +/- 29 ~Si§.

f.

1 GPM leakage at a Reactor Coolant System pressure of 2230 +/- 20 psig from any Reactor Coolant System Pressure Isolation Valve specified in Table 3.4-1.

APPLICABILITY:

MODES 1, 2,* 3 and 4 AC'rION:

a.

With any PRESSURE BOUNDARY LEAKAGE, be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

b.

With any Reactor Coolani System leakage greater than any one of the above limits, excluding PRESSURE BOUNDARY LEAKAGE and leakage from Reactor Coolant System ~ressure Isolation Valves, reduce the leakage rate to within limits within 4 hou~s or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

c.

With any Reactor Coolant System Pressure Isolation Valve leakage greater than the above limit, isolate the high pressure portion of the affected system from the low pressure portion within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> by use of at least two closed manual or deactivated automatic valves, or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

SURVEILLAMCE REQUIREMENTS

=~m=~*====*=======================================================

4.4.7.2.1 Reactor Coolant System leakages shall be demonstrated to be within each of the above limits by:

a.

Monitoring the containment atmosphere particulate radioa~tivity monitor at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

b.

Monitoring the containment sump inventory at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

SALEK - UNIT 2 3/4 4-17 Amendment No. 106

REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued)

========================================================z=========

c.

d.

e.

J.Jor {)U..D

• !fuas u1 emeu t of the CON'fROLL:EB L:E:AKA:S:E from the rea:e to I eoolant pttm' seals at _east enee per 31 days 1Fhen the Reaetor Coolant System pressttre is 2230 ! ao psi~ aftd valve 2CV71 is fttlly elesed, Performance of a Reactor Coolant System water inventory balance at least once per 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. The water inventory balance shall be performed with the plant at steady state conditions. The provisions of specification 4.0.4 are not applicable for entry into Mode 4, and Mc' ~toring the react:r head flange leakoff system at least once pe::- 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

4.4.7.2.2 Each Reactor Coo:ant :ystem Pressure Isolation Valve specified in Table 3.4-1 shall be demonstr~:!i OPERABLE pursuant to Specification 4.0.5, except that in lieu of any le*' i;!e testing required by Specification 4.0.5, each valve shall be demonstr111i OPERABLE by verifying leakage to be within its limit:

a.

At least once per t& £onths.

b.

Prior to entering MODE 2 whenever the plant has been in COLD SHUTDOWN for 72 hourc or more and if leakage testing has not been performed in the prrv~ous 9 months.

c.

Prior to ~eturninq *~e valve io service following maintenance repair or replacem~~~ work on the valve.

d.

For the Residual

~~ Removal and Safety Injection Systems hot and cold leg inJ~ct1on valves and accumulator valves listed in Table 3.4-1 the tesling will be done within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> following valve actuation due to automatic or manual action or flow through the valve.

For all other systems testing will be done once per refueling.

The provisions of specification 4.0.4 are not applicable for entry into MODE 3 or 4.

SALEM - UNIT 2 3/4 4-18 Amendment No. 106

UACTQR CQQLAfL, __ SYSTEM BAS BS 3/4.4.E STEAM ;EN!iRATQBS <Continued>

Wh1n1v1r th* r**ult* of any *t*am g1n9rator tubing in*1rvic1 in*pection fall into category c-3, th*** r**ult* 'will be evaluated for reportability to th*

Commi**ion pur*uant to the applicable *ections of 10CFRS0.72 and lOC!'RS0.73.

3/4.4.7 RIACTQR COOLANT SXSTIM LIAXAGI 314.4.7.1 LEAJ)AG!i pETICTION SYSTEM§ Th* RCS l1aka91 detection *Y*tmll9 required by thi* *pecif ication are provided to monitor and detect leakage from t~* Reactor coolant Pr***ur* Boundary.

Th*** detection *y*tem* are con*i*t*nt with the reconmendation* of Regulatory Guide 1.45, *Reactor Coolant Pr***ur1 Boundary Leakage Detection Sy*tema,*

May 1973.

3/4.4.7.2 OPEBATIONAL LEAgAG!i Industry 1xperi1nc1 ha* *hown that while A iimited amount of leakage i*

expected from the RCS, the unid*ntified portion of thi* leakage can be reduced to a thr**hold value of l*** than 1 GPM.

Thi* thr**hold value i* *µfficiently lr-.*w to *n*ur1 early detection of additional leakage.

Th* 10 GPM IDENTIFIED LEAXAGE limitation provide* allowance for a limited amount of l1akag9 from known *cure** who** pr***nc* will not interfere with the detection of UNID!iNTIFI!iD LEAJtAGE by th* leakage detection *y*tllll8.

Th* CC!ft'ROLLZD f;ZllcDCZ limitation z**tzict* opezatiou when the total flow frem

-t=h* reae~er eeelant pump ***l* 1xe11d* *o GPM with valve 2ev71 fully eleaed at a nominal Res i,>re**ure of 223e p*ig.

'l'lix* limitation *n*1.1r** that in the event of a lieel"... th* **f*ty injaction flow will not be l*** 1than ***um*d i.Rx the aecident analy*e*r Th* *urv1illanc1 requirement* for RCS Pr***ur1 I*olation V~lv** provide added

• • • uranc1 of valve integrity thereby reducing th* probability of 9ro** valve

~ailu~* and con*equent inter*y*tem LOCA.

Leaka9* from the RCS Pr***ur*

l*olation Valvea i* IDBRTIFIBD LEAJCAGB and will be con*idered a* a portion of th* allowed limit.

SALEM - UNIT 2 B 3/4 4-4 Amendment No. 112

• ;AJS&T '(

SALEM -

UN IT 2 (SECTION 3.5.4 HAS

~EEN RENUMBERED TO 3.5.5) 3/4 5-8a

... \\...-

r *

,. EHERGENCY CORE COOLING SYSTEMS BASES

**=*****a*=======~s==========================*=======a~========3=====

ECCS SUBSYSTEMS (Continued!

With the RCS temperature below 350°F; one OPERABLE ECCS subsystem is acceptable without single failure consideration on the basis of the stable reactivity condition of the reactor and the limited core cooling requirements.

The limitation for a maximum of one safety injection pump or one centrifugal charging pump to be OPERABLE and the surveillance Requirement to verify all safety injection pumps except the allowed OPERABLE safety injection pump to be inoperable below 312°F provides assurance that a mass addition pressure transient can be relieved by the operation of a single POPS relief valve.

The surveillance requir~ments, which are provided to ensure the OPERABILITY of each component, ensure that, at a minimum, the assumptions used in the safety analyses are met and that subsystem OPERABILITY is maintained.

The safety analyses make the assumption* with respect to:

1) both the maximum and minimum total system resistance, and 2) both the maximum and minimum branch injection line resistance.

These resistances, in conjunction with the ranges of potential pump performance, are used to calculate the maximum and minimum ECCS flow assumed in the safety analyses.

The maximum and minimum flow surveillance requirements in conjunction with the maximum and minimum pump performance curves ensures that the assumptions of total system resistance and the diatribution of that system resistance among the various paths are met.

The maximum total pump flow surveillance requirements ensure the pump runout limits of 560 gpm for the centrifugal charging pumps and 675 gpm for the safety injection pumps are not exceeded.

The surveillance requirement for the maximum difference between the maximum and minimum individual injection line flows ensure that the minimum individual injection line resistance assumed for th~ spilling line following a LOCA is met.

SALEM -

UNIT 2 B 3/4 5-2 Amendment No. 118

( ;

" EMERGENCY CORl!i COOLING SYSTEM$

BASES s

3 /4. 5 *"i=

REFUELING WATER STORAGE TANK The OPERABILITY of the RWST as a part of the ECCS ensures that a sufficient supply of borated water is available for injection by the ECCS in the event of a LOCA.

The limits on RWST minimum volume and boron concentrations ensure that:

(1) sufficient water is available within containment to permit recirculation cooling flow to th* core, (2) the reactor will remain subcritical in the cold condition following a small LOCA assuming complete mixing of the RWST, RCS, and ECCS water volumes with all control rod* inserted except the most reactive control aa*ambly (ARI-1), and (3) the reactor will remain subcritical in the cold condition following a large break LOCA (break flow area> 3.0 sq. ft.)

assuming complete mixing of the RWST, RCS, and ECCS water and other sources of water that may eventually reside in the sump following a LOCA with all control rods assumed to be out (ARO).

The limits on contained water volume and boron concentration also ensure a pH value of between 8.5 and 11.0 for the solution recirculated within containment after a LOCA.

Thia pH band minimize* the evolution of iodine and minimizes the effect of chloride and caustic stress corrosion on mechanical systems and components.

Th* contained water volume limit include* an allowance for water not usable because of tank discharge line location or other physical characteristics.

SALEM -

UNIT 2 B 3/4 5-3 Amendment No. 118