Text

Proposed Tech Specs,Incorporating Guidelines of NUREG-1431 Re PORV & Block Valve Operability & Correcting AOT Typos in 921117 Application
	ML18100A763
Person / Time
Site:	Salem
Issue date:	12/08/1993
From:	; Public Service Enterprise Group
To:	;
Shared Package
ML18100A762	List: ML18100A761; ML18100A763;
References
	RTR-NUREG-1431 NUDOCS 9312200155
	Download: ML18100A763 (23)
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Mlndmnt No. 39 J

9312200155 931208 PDR ADOCK 05000272 P - PDR _

.. eLCR 91-06 (Rev. 2)

NLR-N93163 Insert A for page 3/4 4-5:

a. With one or both PORVs inoperable and capable of being manually cycled, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months either restore the PORV(s) to OPERABLE status or close the associated block valve(s) with power maintained to the block valve(s); 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 HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b. With one PORV inoperable and not capable of being manually cycled, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months either restore the PORV to OPERABLE status or close its associated block valve and remove power from the block valve; restore the PORV to OPERABLE status within the following 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

c. With both PORVs inoperable and not capable of being manually I cycled, within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months either restore at least one PORV to OPERABLE status or close the associated block valves and remove power from the block valves and be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . Restore the remaining PORV to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months from failure of that valve to meet the Limiting Condition ~or Operation.

d. With one block valve inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months restore the block valve to OPERABLE status or place the associated PORV in manual control; restore the block valve to operable status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or 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 HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

e. With both block valves inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months restore the block valves to OPERABLE status or place the associated PORVs in manual control; restore at least one block valve to OPERABLE status within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months or 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 HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . Restore the remaining block valve to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months from failure of that valve to meet the Limiting Condition for Operation.

f. The provisions of Specification 3.0.4 are not applicable.

ATTACHMENT 2

e LCR 91-06 (Rev. 2)

NLR-N93163 Insert B for page 3/4 4-5:

4.4.3.1 In addition to the requirements of Specification 4.0.5, each PORV shall be demonstrated OPERABLE at least once per 18 months by:

a. Operating the PORV through one complete cycle of full travel during MODES 3 or 4, and

b. Operating solenoid valves, air control valves, and check valves on associated air accumulators in PORV control systems through one complete cycle of full travel, and

c. Performing a CHANNEL CALIBRATION of the actuation instrumentation.

4.4.3.2 Each block valve shall be demonstrated OPERABLE at least once per 92 days by operating the valve through one complete cycle of full travel unless the block valve is closed in order to meet the requirements of ACTION b, or c in Specification 3.4.3.

ATTACHMENT 2

REACT.QR COOLANT SYSTEM OVERPRESSURE PP.OTECTtON SYSTEMS LIMITING CONDITION FOR OPERATION 3.4.9.3 At least one of the following overpressure protection syst!~s sha11 be OPERABLE:

a. Two ?ressurizer Overi:iressure Protection System relier vai'les (POPs) with a lift setting of less tl'lan or equal to 375 osi;, er

b. A reactor coolant system vent of g'l"!ater than or eaual to 3. l~

square inches. of APPLICABILITY: When the tenll'trature of one or rnore'vth1 ~CS cold legs ~s '

1ess than or equa 1 to 312° F. except whtn tli1 rea.cto,. vessel he!d ; s i removed.

ACTION: in (Y/O'f E '/ olVl .:&,. f..;1".J.,._ of ont ,,r ""'" oj

~ l'ol~ y9s is lu' .J.ha..,.. Jl e~"cJ hi 31z ft -

0

~I

a. With one ?OPs inoperabl~ eitht1" re~tore tht inoperable ?C~s ~~

OPERABLE status within 7 days 01" d1pr9ssur1ze and vent the ~cs through a 3.14 square inch vent(s) within the next e !iour5; maintain the RCS in a vented condition until both POPs ha'la be~r:

restol"td to OPERABLE status.

With both POPs 1nope1"able, depressu,.ize and vent.the ~cs tnrcu;~

a 3.14 squal"t inch vent(s) within a hours; maintain the ~cs i~ a vented cond1t1n until both POPs have bun restored to OPE~.:.5L~

status.

In tht event either the POPs or the RCS vent(s) are ~sac ~~

m1t1gatt a RCS P1"tssure transient, a Special Report shall :e Pl"IPll"td and submitted to the Conm1ssion pursuant to Soe~i~-

1cat1on 6.9.2 within 30 days. ih1 report shall deseri:! t~e c1rctmtlnces initiating the transient, the effect of t~e ~c~s .....

v1nt(s) en trie tru1si1nt and &ny corrective action ne:usal'":: ::

Pl"IYtnt r1curl"'ence.

e Jt'. Tht provisions of Specification 3.0.4 art not applicable.

SURVEILLANCE REOU!REMENTS 4,4.9.3.1 Each ?OPS shall be demonstrated OPE~.ASL£ by:

SALEM

UNIT 1 3/4 4-30 Amendment ~o. 2!

~**-------..:....______ _______;

J IR 91-06 (Rev. 2)

NLR-N93163 Insert A for page 3/4 4-30

b. With one POPs inoperable in MODES 5 or 6 with the Reactor Vessel Head installed, restore the inoperable POPs to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , or complete depressurization and venting of the RCS through at least a 3.14 square inch vent(s) within the next 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months ; maintain the RCS in a vented condition until both POPs have been restored to OPERABLE status.

ATTACHMENT 2

-e ---

REACTOR COOLANT SY.STEM SURVEILLANCE REQUIREMENTS (Continued)

a. Performance of a CHANNEL FUNCTIONAL TEST on the POPS actuation channel, but excluding valve operation, withfn 31 days prior to entering a condition in which the POPS is required OPERABLE. _

b. Pel'"fonnance of a CHANNEL CALIBRATION on the POPS actuation .

channel at least once per 18 months.

c. Verifying the POPS isolation valve is open at least once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months whtn the POPS is btin~ used for overprtssure prot1ction.

p~r-s1.1a...,,,f to 5pec.;.*cqf,-o.,, "l~o.s. *

d. Testing ift aeea"'9aAat w1i~ t~* in111"v1;1 t11t r1quirtR11nt1 f~

"ASE S.tegepY s valves puJ!'SwaAi a Sp1eifi;1~i;A 4.Q.5.,...Z<

4.4.9.3.2 The RCS vent(s) shall be v1rffitd ~o bt open at least once per 12 hou"* when tht vents ( s) is being used for. *ov1rpressure protection.

. 1 ~

~ !

\:.. ~.!.

Eicept when tht vent pathway is provfded with a v1lv1 which f s locked, sealed, or othtNiSt secured in the open pasition, then verify these valves open at least once per 31 days.

SALEM ~ UNIT 1 3/4 4-31 Amendment No. 24

E:?iDGE?iCY Ci9'" COOLr~G S't'S'!'~S ECCS SUBSYSTE1S * ! 408 <JSO*F LD1IIIHG CONDITION FOR OPERATION 3.S.3 ~ a miniJllWll, one ECCS subsyst~ollll)risad of the follovin1 shall be OP!R.UL!:

a. One OP!RA!L! centrifu1al char1in1 pump\.-(nd associated flov path capable of takin1 suction from the refuelin1 water stora1* tank and transferrin1 suction to th* residual heat removal pump discharge pipin1 and;

l. Oischar1in1 into each Reactor Coolant System lRCS) cold Leg.

b. On* OP!RAJL! residual heat removal pump and associated resid\Ul ,eac remcv:l hc~t Q&CNarli~~ and Elov path capable of takin1 suction from th* refuelin1 water stora1* tank on a. safety injection si1nal and tran1ferrin1 suction to th* containment sump durin1 th*

recirculation phase of operation and;

l. Dischar1in1 into each RCS cold l*1, and; upon manual initiation,

2. Di~c~r;in; into two RCS h@t 181**

APPLICABILITY.: MODI 4. ,

t ACTION:

a. With no !CCS sub1y1t* OP!LULI becaus* of tbs inoperability of

ith*r the centrifu1al char1in1 pU!ip or the flow patft from th*

refuelini water 1tora1* tank, re1tore at l ...t on* !CCS subsystam ~o OP!IABLI 1tatua within l hour or be in COLD SBUTDOWN within the next 20 hours2.314815e-4 days 0.00556 hours 3.306878e-5 weeks 7.61e-6 months .

b. Within no !CCS 1ub1y1t.. OP!IABLI bec:aua* of th* lnop*rability of either the ruidual h..t removal hut exchan1*r or ruidual heat r..aval pump, rutore at l ...t on* !CCS sub1y1t.. to OP!RA!LI status or *intain the Reactor Coolant Syst.. Tavs lu* than 3.5Q*p by use of altaTnat* hut r..aval mathod9.

c*. wtllrcowt tlw KC$ i* ~and- inj<<t* *ta* into. th&* Reactor Coolaat S19t.. , a Special Report 1hall be prepared and submittt-i :o th9 Commi11ion pursuant to Spscifieation 6.9.2 within 90 day1 cla8cribtn1 the circUlll9tanc** of the actuation and th* total

~tecl actuation cycl** to data.

ftl pump I U

~I

~es SAUM

UNIT l 3/4 5*6

IR 91-06 (Rev. 2)

NLR-N93163 Insert A for page 3/4 5-6

A maximum of one safety injection pump or one centrifugal charging pump shall be OPERABLE in MODE 4 when the temperature of one or more of the RCS cold legs is less than or equal to 312°F, Mode 5, or Mode 6 when the head is on the reactor vessel.

ATTACHMENT 2

EP1ERGEHC Y CORE COOL I NG SYSTEMS ECCS SUISYSTEMS

Tavg < 3SO*F SURVEILLANCE RE QJIREMENTS 4.5.3.1 The ECCS subsyst1111 shall be deaanstratld OPERABLE per applicable Survetll1nc1 Requfre1111nts of 4.5.2.

1. By ver"1fy1ng th1t th* natar c1rcu1t bl"Hkert h1v1 been r111Dvtd fro* their 1lectrfc1l powtr suppl1 circuits or,

b. For tntf "' purposes, by verifyf ng thlt the pu., 1s 1n a rte1 rculltfon flow path and th1t: the *nual dt1ct11rg1 valve is clos.a8

SALEM - UNIT 1 Allllnmnent No. 66

.... . R 91-06 (Rev. 2)

NLR-N93163 Insert A for page 3/4 5-6a 4.5.3.2 All safety injection pumps and centrifugal charging pumps, except the above required OPERABLE pump, shall be demonstrated to be inoperable at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months while in MODE 4 and the temperature of one or more of the RCS cold legs is less than or equal to 312°F, MODE 5, or MODE 6 when the head is on the reactor vessel by either of the following methods:

ATTACHMENT 2

. r.

.REACTOR COOLANT SYSTEMe BASES 3/4.4.2 SAFETY VALVES The pr-essuri zer code safety valves oper-ate to prevent the RCS from being pressurized above its Safety Limit of 2735 psig. Each safety valve is designed* to r-elieve 420,000 pounds per hour- of saturated stealT'I at the valve setpoint. The relief capacity of a single safety valve is adequatP.

to relieve any overpressure condition which could occur during shutdown.

In the event that no safety valves are OPERABLE, an operating RHR loop,

connected to to the RCS, pMvides overpressure relief capability and will prevent RCS overpressurization. In addition, the Overpressure Protection*

System provides a diverse rreans or protection against RCS overpressurization at low temperature. Ii.hi le in Mode S the safety valve requirement may be met by establishing a vent path of equivalent relieving capacity when no code safety valves are OPERABLE.

During operation, al 1 pressurizer code safety valves rrust be OPERABLE to prevent the RCS from being pressurized above its safety lim;t of 2735 psig. The combined relief capacity of all of these valves is greater than the maxirrum surge rate resulting from & complete loss of load assuming no reactor trip until the first Reactor Protective System trip setpoint is reached (i.e., no credit is taken for a direct reactor trip on the loss of load) and also assuming no operation of the* power operated relief valves or steam.dump valves.

De1TOnstration of the safety valves lift settings will occur only during shutdown and wi 11 be perforrred in accordance with the provisions of Section XI of the ASME Boiler and Pressure Code.

3/4.4.3 RELIEF VALVES

{ PoRV)

The power operated relief val v. sAand am bubble function ti> relieve RCS pressure during all design tran up to and including the design step load decrease with steaM dump. Operation of the power operated relief valves m;nimizes the undesirable opening of the spring-loaded pressurizer cod~ safety valves. Each power operated relief valve has a re1TOtely operated block valve to provide positive shutoff capability should a relief valve become inoperable.

SALEM - UNIT l B 3/4 4-la Amendment No. 74

IR 91-06 (Rev. 2)

NLR-N93163 Insert A for page B 3/4 4-la Although a PORV may be inoperable, it may be able to be manually opened or closed, and therefore, able to perform its intended design function. PORV inoperability may be due to excessive seat leakage, instrumentation problems, automatic control problems, or other causes that do not prevent manual use, and do not create a possibility for a small break LOCA. The Action Statement requires that the block valve be closed, and power maintained to the valve in those circumstances when the PORV is still capable of being manually cycled.

ATTACHMENT 2

J REACTOR COOLANT SYSTEM 3/4.4.5 RELIEF VALVES LIMITING CONDITION FOR OPERATION 3.4.5 Two power relief valves (PORVs) and their associated block valves shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTION:

SURVEILLANCE REQUIREMENTS SALEM - UNIT 2 3/4 4-8

IR 91-06 (Rev. 2}

NLR-N93163 Insert A for page 3/4 4-8:

a. With one or both PORVs inoperable and capable of being manually cycled, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months either restore the PORV(s} to OPERABLE status or close the associated block valve(s} with power maintained to the block valve(s}; 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 HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b. With one PORV inoperable and not capable of being manually cycled, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months either restore the PORV to OPERABLE status or close its associated block valve and remove power from the block valve; restore the PORV to OPERABLE status within the following 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

c. With both PORVs inoperable and not.capable of being manually cycled, within6 hours either restore at least one PORV to OPERABLE status or close the associated block valves and remove power from the block valves and be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and'in HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . Restore the remaining PORV to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .from failure of that valve to meet the Limiting Condition for Operation.

d. With one block valve inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months restore the block valve to OPERABLE status or place the associated PORV in manual control; restore the block valve to operable status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or 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 HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

e. With both block valves inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months restore the block valves to OPERABLE status or place the associated PORVs in manual control; restore at least one block valve to OPERABLE status within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months or 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 HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . Restore the remaining block valve to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months from failure of that valve to meet the Limiting Condition for Operation.

f. The provisions of Specification 3.0.4 are not applicable.

ATTACHMENT 2

l \ IR 91-06 (Rev. 2)

NLR-N93163 Insert B for page 3/4 4-8:

4.4.5.1 In addition to the requirements of Specification 4.0.5, each PORV shall be demonstrated OPERABLE at least once per 18 months by:

a. Operating the PORV through one complete cycle of full travel during MODES 3 or 4, and

b. Operating solenoid valves, air control valves, and check valves on associated air accumulators in PORV control systems through one complete cycle of full travel, and

c. Performing a CHANNEL CALIBRATION of the actuation instrumentation.

4.4.5.2 Each block valve shall be demonstrated OPERABLE at least once per 92 days by operating the valve through one complete cycle of fulL travel .unless* the block valve is closed in order to meet the.requirements.of ACTION:b, or c .in Specification 3.4.5.

ATTACHMENT 2

e REACTOR COOLANT SYSTEM OVERPRESSURE PROTECTION SYSTEMS LIMITING CONOITIOM FOR OPERATION 3.4.10.3 At least one of the following overpressure protection systems shall be OPERABLE:

a. Two Pressurizer Overpressure Protection System relief valves (PO~Ss) with a lift setting of less than or equal to 375 ps1g, or

b. The Reactor Coolant Syste* (RCS) depressurized with an RCS vent o'.f greater than or equal to 3. 14 square 1n~hes.

APPLICABILITY: When the temperature of one or llOre of *the RCS cold legs is less than or equal to 312°F, except when the reactor vessel head is removed.

ACTION:

hltJllE L/ o.nd. ~ h.-.jltra.-lvr&- ~ ont o-r "MOr~ o-e ~ ecs

' 11 eokt ~f i.5 lt6s ~ or eq1111.I +o 31Z"F"

+ A \fee\ a. With one POPS inoperabl~ restore the 1r,operable POPS to OPERABLE

i;~~e~ ~+-" status within 7 days or depressurhe and vent the RCS through a I

"' 3. 14 square in<:h vent( s) within the next a* hours,, 3 ~.** .,__;.,, 1'1e lfes i.,

f/d.. >- ct .,* ..,~<!ti ~* .,J,**nu... "'.,~,*/ "-"" ,.,,.., "'*~ ...... ,.~5'1:0,.~d f* o-Pe~-ldl.E' 1hc.J.vs .

c }L With both POPSs inoperable, depressurize and ve~ the RCS thrqugh a J *,

3. 14 square inch vent(s) within 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months s_;,.,.,,..,~.... '""~ sec' ,*., ' ~~"'91eo "1 ..J,'t-.** ., ..... 1-.*1 1..1'1 ~~ ""*lie w"" ~-,,".Jo,.,.J "'- ()t?~lf.-ldl.~ sJ.'(J.~s.

d. ~- In the event either the POPSs or the RCS vent(s) are used to mitigate a RCS pressure transient, a Special Report shall be prepared and subllitted to the Ca11mission pursuant to Specification 6.9.2 within

.30 days. Th9 report shall describe the circU111tances initiating the.

transient, the effect of the POPSs or vent(s) on the transient and any corrective action necessary to prevent recurrence.

e,I. The provisions of Specification 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS

4. 4.10. 3. 1 Each POPS* shall be demonstrat,FJd OPERABLE by:

SALEM - UNIT 2 3/4 4-31

\'

IR 91-06 (Rev. 2)

NLR-N93163 Insert A for page 3/4 4-31

b. With one POPs inoperable in MODES 5 or 6 with the Reactor Vessel Head installed, restore the inoperable POPs to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , or complete depressurization and venting of the RCS through at least a 3.14 square inch vent(s) within the next 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months ; maintain the RCS in a vented condition until both POPs have been restored to OPERABLE status.

ATTACHMENT 2

=\(ERG~'ic: :::R:: ::c~:.sc .:*:*;-:-2-':s ECCS SU!.SYSTa- 1' <JSO"F aug LIMITING CONDITION FOR OPERATION 3.5.3 A* a minimum. one ECCS subsyst~omprised of the following shall be OP!IAIL!:

=;

a. One OP!RABL! centrifugal charging pump~nd associated flow path capable of takin1 suction from the refualin1 water stora1* tank and transferrin1 suction to th* residUAl heat removal pump discharge pipin1 and;

l. Dischargin1 into each Reactor Coolant System (RCS) cold leg.

b. One OPERABLE residual heat removal pump and associated residual heat removal heat exchanger and flow path capable of takina suction from the refuelin1 water stora1* tank on a safety injaetion sianal and tran*f*rrina suction to thQ eontainment sump durin1 the recireulation phase of operation and;

1. Dischar1in1 into each RCS cold le1, and; upon manual initiation,

2. Dischar1in1 into two RCS hat l*1s.

APPLICABILITY: MODI 4.

ACTION:

a.

With no !CCS *ubsyst .. OP!RABLI because of the inaperability of either th* centrifu1al char1in1 pump or the flov path from the refuelin1 water stora1* tank, r .. tare at l ... t on* !CCS 5ubsystem to OP!RAILI status within 1 hau!!' or be in COLD SlltJTDOWN within the next 20 hOU!!'S *.

b. With no !CCS sub*Y*t.. OPDABLI because of th* inoperability of either the r .. idual hut r..oval hut uchan1er or residual heat r..oval pump, r .. tore at leut one ICCS sub*y*t* to OPERABLE status or maintain the Reactor Coolant Syat* Tavi l ..* than 350*1 by use of alternate heat r..aval methoda.

c. IA tlla.~ ti.~ a actuated and injects vat* into cm R*actor Cool.mt S,wtm. a Special Report shall be prepared and subllitud to the ea..i**ian pursuant to Specification 6.9.2 within 90 days da8cribifta the circum.tances of the actuation and the total ac:c:am&lat9d actuation cycl.. to dat&. TM currmt ftlua of th*

U9&.. factor tor each affected 1afety-injec:tia11 nozzle shall be provided in this Special Repar~ vbaaeftr its value exceeds 0.70.

SAL!J4

UNIT 2 3/4 5*7 Amendment No. 70

t (.. :.

IR 91-06 (Rev. 2)

NLR-N93163 Insert A for page 3/4 5-7

A maximum of one safety injection pump or one centrifugal charging pump shall be OPERABLE in MODE 4 when the temperature of one or more of the RCS cold legs is less than or equal to 312°F, Mode 5, or Mode 6 when the head is on the reactor vessel.

ATTACHMENT 2

tJ ( (~, '{,I EMERGEMCY . E COOLING SYSTEMS ECCS SUBSYSTEMS* T1 vg < 3509F SURVEILLANCE REQJIREMENTS 4.5.3.1 The ECCS subsyst1111 shall bl d1nanstr1tt<i OPERABLE per

.,~ app11c1bl1 Surveill1nc1 R1quirelftlnts of 4.5.2 *

~""e ~ &~ 4.5.3.Z All s ety 1nject1on ~s, exctpt th OPERABLE pu,,.,

/,.ef ~ ~~ 1llowed abov , shall bl dlfta tr1tld 1nopera

at least one 11

':!fl' '"" per 12 ho whenever th* 1r1ture of o or ..,,.. of t

)

cold 11 1s less t111n o 1q1i11l to 312., iy the fo11ow1 *

~(.!' ~ 1. By verifying that the nator circuit weu1rs have been reaavld .fro* their 1l1etrf c1l pow.,- suppt1 circuits or,

b. For t11ting purposes, by verifyf 111 that the .,.,., ts tn 1 rect rculat1on flow path and that the *nu1l dtldlarge valve* ts closed.

SALEM

UNIT 2 3/4 5-8 Amendment No. 41.

IR 91-06 (Rev. 2)

NLR-N93163 Insert A for page 3/4 5-8 4.5.3.2 All safety injection pumps and centrifugal charging pumps, except the above required OPERABLE pump, shall be demonstrated to be inoperable at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months while in MODE 4 and the temperature of one or more of the RCS cold legs is less than or equal to 312°F, MODE 5, or MODE 6 when the head is f on the reactor vessel by either of the following methods:

ATTACHMENT 2

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REACTOR COOLANT SYSTEM BASES 3/4.4.2 and 3/4.4.3 SAFETY VALVES

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The pressurizer code safety valves operate to prev.ent the RCS from being prsssurized above its Safety Limit of 2735 psig. Each safety valve is designed to relieve 420,000 pounds per hour of saturated steam at the valve setpoint. The relief capacity of a single safety valve is adequate to relieve any overpressure condition which could occur during shutdown.

In the event that no safety val v<:?s are OPERABLE, an operating RHR loop, connected to to the RCS, provides overpressure relief capability and will prevent RCS overpressurization. In addition, the Overpressure Protection System provides a diverse 111eans of protection against RCS overpressuri zation at low temperature. li.tli 1e in Mode 5 the safety valve requirement may be met by establishing a vent path of equivalent relieving capacity when no code safety valves are OPERABLE.

During operation, al 1 pressurizer code safety valves rrust be OPERABLE to prevent the RCS from being pressurized above its safety limit of 2735 psi g. The combined relief capacfty of al 1 of thes~ valves is greater than the maximum surge rate resulting from a co1:1pl ete loss of load assuming no reactor trip untii the first Reactor Protective System trip setpoint is reached (i.e., no credit is taken for a direct reactor trip on the loss of load) and also assuming no operation of the power operated relief valves or steam dump valves.

De1TDnstration of the safety valves lift settings will occur only during shutdown and will be perforrred in accordance with the provisions of

_ Section XI of the ASME Boiler and Pressure Code.

3/4.4.4 PRESSURIZER The limit on the maximum water volune in the pressurizer assures that the parar.eter is maintained within the normal steady-state envelope of operation assumed in the SAR. The limit is consistent with the initial SAR assumptions. The 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months periodic surveillance is sufficient to ensure that the parameter is restored to within its limit following expected transient operation. T"e maximum water volume also ensures that a steam bubble is formed and thus the RCS is not a hydraulically solid system. The requirement that a mini murn number of pressur*i zer heaters be OPERABLE enhances the capability of the plant to control RCS pressure and establish natural circulation.

3/4.4.5 RELIEF VALVES Cl':'~

The power operated relief val ve~am bubble function to relieve RCS pressure during all *design transients up to and including the d~si gn step load decrease with steam dump. Operation of the power operated relief valves minimizes the undesirable opening of the spring-loaded pressurizer code safety valves. Each power operated relief valve has a renntely operated block valve to provide positive shutoff capability should a relief valve become inoperable.

I

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- SALEM - UNIT 2 B 3/4 4-2 Amendment No. 49

e LCR 91-06 (Rev. 2)

NLR-N93163 Insert A for page B 3/4 4-2 Although a PORV may be inoperable, it may be able to be manually opened or closed, and therefore, able to perform its intended design function. PORV inoperability may be due to excessive seat leakage, instrumentation problems, automatic control problems, or other causes that do not prevent manual use, and do not create a possibility for a small break LOCA. The Action Statement requires that the block valve be closed, and power maintained to the valve in those circumstances when the PORV is still capable of being manually cycled.

ATTACHMENT 2

ML18100A763

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