ML18096A087

Proposed Tech Specs Incorporating Requirements of Generic Ltr 90-06 Re Power Operated Relief Valve & Block Valve Operability & low-temp Overpressure Protection for LWRs

ML18096A087
Person / Time
Site:	Salem
Issue date:	06/20/1991
From:	Public Service Enterprise Group
To:
Shared Package
ML18096A086	List: ML18096A085 ML18096A087
References
GL-90-06, GL-90-6, LCR-91-06, LCR-91-6, NLR-N91095, NUDOCS 9106260305
Download: ML18096A087 (28)

Text

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SALEM LCR 91-06 NLR-N91095 TECHNICAL SPECIFICATION PAGES WITH PEN AND INK CHANGES The following Technical Specifications are affected by this requested amendment:

Facility Operating License No. DPR-70 (Unit 1)

Technical Specification Page 3.1.2.3 3/4.1-10 3.1.2.4 3/4 1-11 3/4.4.3 3/4 4-5 3.4.9.3 3/4 4-30 3/4 4-31 3.5.3 3/4 5-6 3/4 5-6a Facility Operating License No. DPR-75 (Unit 2)

Technical Specification 3.1.2.3 3/4 1-9 3.1.2.4 3/4 1-10 3/4.4.5 3/4 4-8 3.4.10.3 3/4 4-31 3.5.3 3/4 5-7 3/4 5-8 ATTACHMENT 2

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REACTIVITY CO NTROL SYSTEMS CHARGING PUMP - SHUTDOWN LIMITING CONDITION FOR OPERATION 3.1 . 2~3 At least one charging pump in the boron injection flow path required by Specification 3.1 . 2.l shall be OPERABLE.:IJt.

APPLICABILITY: MODES 5 and 6.

ACTION:

With no charging pump OPERABLE. suspend all operations involving CORE ALTERATIONS or positive reactivity changes until one charging pump is restored to OPERABLE status.

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"t-\1.e. SURVEILLANCE REQUIREMENTS )

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ALEM - UNIT l 3/4 1-10 )

• l SALEM LCR 91-06 I NLR-N91095 I I

Insert A for page 3/4 1-10 4.1.2.3 In addition to the requirements of Specification 4.0.5, 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 <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> while in MODE 5 or MODE 6 and the head is on the reactor vessel by either of the following methods:

a. By verifying that the motor circuit breakers have been removed from their electrical power supply circuits, or

b. For testing purposes, by verifying that the pump is in a recirculation flow path and that the manual discharge valve is closed.

Insert B for page 3/4 1-10

1. A maximum of one safety injection pump or one centrifugal charging pump shall be OPERABLE while in MODE 5 or MODE 6 and the head is on the reactor vessel.

ATTACHMENT 2

REACTIVITY CONTROL SYSTEMS CHARGI NG PUMPS - OPERATING LIMITING CONDITION FOR OPERATION 3.1.2.4 At least two charging pumps shall be OPERABLE . .tf::

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

With only one charging pump OPERABLE, resto*re at least two charging pumps to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY and borated to a SHUTDOWN MARGIN equivalent to at least l~ ~ k/k at 200°F within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; restore at least two charging pumps to OPERABLE" status within the next 7 days *or be in COLO SHUTDOWN within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

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SURVEILLANCE RE UIREMENTS I .

ALEM - UNIT 1 3/4 1-11

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SALEM LCR 91-06 NLR-N91095 Insert A for page 3/4 1-11 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 <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> while in MODE 4 and the temperature of one or more of the RCS cold legs is less than or equal to 312*F by either of the following methods:

a. By verifying that the motor circuit breakers have been removed from their electrical power supply circuits, or

b. For testing purposes, by verifying that the pump is in a recirculation flow path and that the manual discharge valve is closed.

Insert B for page 3/4 1-11

1. 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.

ATTACHMENT 2

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• UNli I J/4 4-5 .a.nendment No. 39

SALEM LCR 91-06 NLR-N91095 Insert A for page 3/4 4-5:

a. With one or both PORVs inoperable because of excessive seat leakage, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 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 <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

b. With one PORV inoperable due to causes other than excessive seat leakage, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 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 7 days or be in 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 HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

c. With both PORVs inoperable due to causes other than excessive seat leakage, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> either restore at least one PORV to OPERABLE status or close the associated block valves and remove power from the block valves; restore at least one PORV to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in 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 HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

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

e. With both block valves inoperable, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 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 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-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 HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

f. The provisions of Specification 3.0.4 are not applicable.

ATTACHMENT 2

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SALEM LCR 91-06 NLR-N91095 Insert B for page 3/4 4-5:

4.4.3.l 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

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REACTOR COOLANT SYSTEM OVERPRESSURE PROTECTION SYSTEMS LIMITING CONDITION FOR OPERATION 3.4.9.3 At least one of the following overpressure protection syst2ms shall be OPERABLE:

a. Two Pressurizer Overpressure Protection System relief va lves (POPs) with a lift setting of less than or equal to 375 psig, er

b. A reactor coolant system vent of greater than or eQual to 3. 1~

square inches. of APPLICABILITY: When the temperature of one or more\lfhe RCS cold l egs is less than or equal to 312°F, except when the reactor vessel head is removed.

ACTION: in .;>?oO E L/

a. With one POPs inoperabl ~ either restore the inoperab l e ?O~s ~o OPERABLE status within 7 days or depr!ssuri ze and vent th e ~cs through a 3.1 4 square inch vent(s) within the next 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />; maintain the RCS in a vented condition until both PQPs have been .)

restored to OPERABLE status.

With both POPs inoperable, depressurize and vent the RCS thrcu~~

a 3.14 square inch vent(s) within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />; maintain the qcs ir. a vented conditin until both POPs have been restored to OPE~~5LE status.

In the event either the POPs or the RCS vent(s) are wsec :o mitigate a RCS pressure transient, a Special Report shall :e prepared and submitted to the Coll'lllission pursuant to Soec if-ication 6.9.2 within 30 days. The report shall descr i:e the circumstances initiating the transient, the effect. of the ' Ocs .., ..

vent(s) on the transient and any corrective act ion ne:essary ::

prevent recurrence.

The provisions of Specification 3.0.4 are not appl i cab l e.

SURVEILLANCE REQUIREMENTS 4.4.9.3 .1 Each POPS sha ll be demonstrated OPE~ASLE by:

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

SALEM LCR 91-06 NLR-N91095 Insert A for page 3/4 4-30

b. With one POPs inoperable in MODES 5 or 6, restore the inoperable POPs to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, 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 <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />; 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. Pe-rfonnance of a CHANNEL FUNCTIONAL TEST on the POPS actuation channel, but excluding valve operation, within 31 days prior to entering a condition in which the POPS is required OPERABLE . _

b. Perfonnance 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 <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> when the POPS is being used for overpressure protection.

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d. Testing iA accordance witl:! tl:!e insen<ica tast requirements f~

' ASME Category C valves pursuant to Specification 4. 0.5,..'2<

4.4.9.3.2 The RCS vent(s) shall be verified to be open at least once per 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />s* when the vents(s) is being used for overpressure protection.

• Except when the vent pathway is provided with a valve which is locked, sealed, or otherwise secured in the open position, then verify these valves open at least once per 31 days.

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

EMERGENCY cl COOLING SYSTEMS ECCS SUBSYSTEMS - T <350°F LIMITING CONDITION FOR OPERATION 3.5.3 As a minimum, one ECCS subsyst ~ omprised of the following shall be OPERABLE:

a. One OPERABLE centrifugal charging pump~nd associated flow path capable of taking suction from the refueling water storage tank and transferring suction to the residual heat removal pump discharge piping and;

1. Di scharging i nto each Reactor Coolant System lRCS ) co l d l eg .

b. One OPERABLE residual heat removal pump and associated res i dua l heat removal heat exchanger and fl9w path capable of taking suction from the refueling water storage tank on a safety injection signal and transferring suction to the containment sump during the recirculation phase of operation and;

1. Discharging into each RCS cold leg, and; upon manual initiation,

2. Discharging into two RCS hot legs.

APPLICABILITY.: MODE 4.

ACTION:

a. With no ECCS subsystem OPERABLE because of the inoperability of either the centrifugal charging pump or the flow path from the refueling water storage tank, restore at least one ECCS subsystem to OPERABLE status within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or be in COLD SHUTDOWN within the next 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br />.

b. Within no ECCS subsystem OPERABLE because of the inoperability of either the residual heat removal heat exchanger or residual heat removal pump, restore at least one ECCS subsystem to OPERABLE status or l'D&intain the Reactor Coolant System T less than 350°F by use of alternate heat removal methods. avg

c. Ia .. the.. f f Wt , th* *UCS. is- ~uac.O* and- inJect*s wate?' in*to- th&* Reactor Coolant System, a Special Report shall be prepared and submitted to the Co1111lission pursuant to Specification 6.9.2 within 90 days describing the circumstances of the actuation and the total acc\111\llated actuation cycles to date.

g1ng pump SALEM - UNIT 1 3/4 5-6 Amendment No. 94

. SALEM LCR 91-06 NLR-N91095 Insert A for page 3/4 5-6

1. 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

EMERGENCY CORE COOLING SYSTEMS ECCS SUBSYSTEMS - Tavg < 350°F SURVEILLANCE REC:UIREMENTS 4.5.3.l The ECCS subsystem shall be de111>nstrated OPERABLE per applicable Surveillance Requirements of 4.5.2.

4.5.3~2 All safety nject1on pu , except the RABLE pu~

above, sh 1 be de111>nst ted 1noperab1 at least on per hours wh ever the te rature of one r 111>re of t .RCS tJ . legs is st than or al ta 312-F b the fo 11ow1

• a. By ver1 fyi ng that th* 111>tor c1 rcu1t breakers have been ren>ved fro* their electrical power supply circuits or,

• b. For testing purposes, by verifying that the pu~ is 1n a rec1rcu1at1on flow path and that the 111nual discharge valve is closed.

SALEM

• UNIT l 3/4 S-6a Amendment No. 66

SALEM LCR 91-06 NLR-N91095 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 <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 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

REACTIVITY CONTROL SYSTEMS CHARGING PUMP - SHUTDOWN LIMITING CONDITION FOR OPERATION 3.1.2. 3 At least one charging pump

• In the boron injection flow path required by Specification 3. 1.2. 1 shall be OPERABLE. 1;l:=

APPLICABILITY : MODES 5 and 6.

ACTION:

With no charging pump OPERABLE, suspend all operations involving CORE ALTERA-TIONS or positive reactivity changes until one charging pulllJ> is restored to OPERABLE status.

SURVEILLANCE REQUIREMENTS SALEM - UNIT 2 3/4 1-9

SALEM LCR 91-06 NLR-N91095 Insert A for page 3/4 1-9 4.1.2.3 In addition to the requirements of Specification 4.0.5, 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 <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> while in MODE 5 or MODE 6 and the head is on the reactor vessel by either of the following methods:

a. By verifying that the motor circuit breakers have been removed from their electrical power supply circuits, or

b. For testing purposes, by verifying that the pump is in a recirculation flow path and that the manual discharge valve is closed.

Insert B for page 3/4 1-9

1. A maximum of one safety injection pump or one centrifugal charging pump shall be OPERABLE while in MODE 5 or MODE 6 and the head is on the reactor vessel.

ATTACHMENT 2

i 1 REACTIVITY CONTROL SYSTEMS J CHARGING PUMPS - OPERATING LIMITING CONDITION FOR OPERATION

3. 1.2.4 At least two charging pumps shall be OPERABLE . tJ:"

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

With only one charging pump OPERABLE, restore at least two charging pumps to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY and borated to a SHUTDOWN MARGIN equivalent to at least 1% delta k/k at 200°F within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; restore at least two charging pumes to OPERABLE status within the next 7 days or be in COLD SHUTDOWN within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

rveillance equirement other than ose require y SALEM - UNIT 2 3/4 1-10

SALEM LCR 91-06 NLR-N91095 Insert A for page 3/4 1-10 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 <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> while in MODE 4 and the temperature of one or more of the RCS cold legs is less than or equal to 312*F by either of the following methods:

a. By verifying that the motor circuit breakers have been removed from their electrical power supply circuits, or

b. For testing purposes, by verifying that the pump is in a recirculation flow path and that the manual discharge valve is closed.

Insert B for page 3/4 1-10

1. 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.

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

SALEM LCR 91-06 NLR-N91095 Insert A for page 3/4 4-8:

a. With one or both PORVs inoperable because of excessive seat leakage, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 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 <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

b. With one PORV inoperable due to causes other than excessive seat leakage, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 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 7 days or be in 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 HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

c. With both PORVs inoperable due to causes other than excessive seat leakage, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> either restore at least one PORV to OPERABLE status or close the associated block valves and remove power from the block valves; restore at least one PORV to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in 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 HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

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

e. With both block valves inoperable, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 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 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-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 HOT SHUTDOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

f. The provisions of Specification 3.0.4 are not applicable.

ATTACHMENT 2

SALEM LCR 91-06 NLR-N91095 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

REACTOR COOLANT SYSTEM OVERPRESSURE PROTECTION SYSTEMS LIMITING CONDITIOK 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 (POPSs) with a lift setting of less than or equal to 375 psig, or

b. The Reactor Coolant System (RCS) depressurized with an RCS vent of greater than or equal to 3. 14 square inches.

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

ACTION: /n t1/0{)! 'I

+ A \fe~ a. With one POPS inoperabl ~ restore the inoperable POPS to OPERABLE

I:"..,_~er -l't~" status within 7 days or depressurize and vent the RCS through a . I C). 3.14 square inc;:h vent(s) within the next 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />)t j rn-...*.,fq.i.., tJ.te tfcs '"

.(.(()""  ?" ct 11t1..,f<icl e1>*nl1'fio-1 ..,.., ;..,"/ bofl.t ft.it'S' hqve beh ~~<. ft;r-c:;d 'fo OY'c>e-41/!ll! st4~S _

c JI.. With both POPSs inoperable, depressurize and vent the RCS through a J j

3. 14 square inch vent(s) within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />,. _; ,,,.,q,* ~Joc,'., t-ire ~~' ,*,, "- ve..,re co~r1.*;.,*o.., ..,...,f,*1 h,,J41 ~"~s h"ve ~""l!'-9 .,-,. 1 /.o;ot-J fo oPc~4dl.E s-J.'<J.~s .

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 submitted to the Commission pursuant to Specification 6.9.2 within 30 days. The report sh~ll describe the circumstances 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 demonstrated OPERABLE by:

SALEM - UNIT 2 3/4 4-31

SALEM LCR 91-06 NLR-N91095 Insert A for page 3/4 4-31

b. With one POPs inoperable in MODES 5 or 6, restore the inoperable POPs to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, 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 <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />; maintain the RCS in a vented condition until both POPs have been restored to OPERABLE status.

ATTACHMENT 2

. ') EMERGENCY CORE COOLING SYSTEMS

.. ECCS SUBSYST~ - T <350°F LIMITING CONDITION FOR OPERATION 3.5.3 As a minimum, one ECCS subsyste~omprised of .t he following shall be OPERABLE:

~

a. One OPERABLE centrifugal charging pump'V{nd associated flow path capable of taking suction from the refueling water storage tank and transferring suction to the residual heat removal pump discharge piping and;

1. Discharging into each Reactor Coolant System (RCS) cold leg .

b. One OPERABLE residual heat removal pump and associated res i dua l heat removal heat exchanger and flow path capable of taking suction fr om the refueling water storage tank on a safety injection signal and transferring suction to the containment sump during the recirculation phase of operation and;

1. Discharging into each RCS cold leg, and; upon manual initiation,

2. Discharging into two RCS hot legs.

APPLICABILITY: MODE 4.

ACTION:

a. With no ECCS subsystem OPERABLE because of the inoperability of either the centrifugal charging pump or the flow path from the refueling water storage tank, restore at least one ECCS subsystem to OPERABLE status within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> or be in COLD SHUTDOWN within the next 20 hours2.314815e-4 days <br />0.00556 hours <br />3.306878e-5 weeks <br />7.61e-6 months <br />.

b. With no ECCS subsystem OPERABLE because of the inoperability of either the residual heat removal heat exchanger or residual heat removal pump, restore at least one ECCS subsystem to OPERABLE status or maintain the Reactor Coolant System T less than 350°F by use of alternate heat removal methods. avg c *. In tba . event the ECCS-is actlUlted and injects water into the Reactor Coolant System. a Special Report shall be prepared and submitted to the Commission pursuant to Specification 6.9.2 within 90 days describina the circumstances of the actuation and the total accumulat*d actuation cycles to date. The current value of the usage factor for each affected safety-injection nozzle shall be provided in this Special Report whenever its value exceeds 0.70.

one sa e th temperature 12°F. NOTE :

SALEM - UNIT 2 3/4 S-7 Amendment No. 70

--- - - - - - -- -

. SALEM LCR 91-06 NLR-N91095 Insert A for page 3/4 5-7

1. 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 I

I J

• .. .. e EMERGENCY CORE COOLING SYSTEMS ECCS SUBSYSTEMS - Tavg < 350°F SURVEILLANCE REOJIREMENTS 4.5.3.1 The ECCS subsystem shall be denonstrated' OPERABLE per applicable Surveillance Requirements of 4.5.2.

-~~

~*

~<t'-e. "" e~ 4.5.3.Z A11 s ety 1nject1on ~s. except th OPERABLE puq>

1-ef ,~ ~""\.1 allowed abov

• shall be de111> trated 1nopera t at least one

e. ,1 per 12 hou whenever the erature of o or nore of th CS 1-"'l ,. cold le 1s less than o eq~al to 312-W: y th* fo11ow1n *

\(II"' ~ a. By ver1fy1ng that the notor circuit breakers h1v1 been renaved from their electrical pow1r supply circuits or,

b. For testing purposes, by verifying th1t the pu.,.. is fn 1 recfrculat1on flow pith and that the nanu1l discharge v1lv1 *1s closed.

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

, SALEM LCR 91-06 NLR-N91095 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 <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 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