ML18092B268

From kanterella
Jump to navigation Jump to search
Proposed Tech Specs Correcting Minor Typos Re Reactor Trip Sys Instrumentation,Esfas,Rcs & ECCS
ML18092B268
Person / Time
Site: Salem  PSEG icon.png
Issue date: 08/29/1986
From:
Public Service Enterprise Group
To:
Shared Package
ML18092B266 List:
References
NUDOCS 8609040139
Download: ML18092B268 (18)


Text

--- --- - - - - - - ---

TABLE 3.3-1 (Continued)

Vl REACTOR TRIP SYSTEM INSTRUMENTATION

)::o f;i 3:

c: MINIMlJ.t

z TOTAL NO. CHANNE l5 CHANNE l5

...... APPLICABLE

-I FUNCTIONAL UNIT OF CHANNELS TO TR IP OPERABLE MOlES ACTION

11. Pressurizer Water Leve 1--Hi gh
12. Loss of Flow - Single Loop 3

~/loop 2

2/loop in 2 1. 2 71 e 2/loop in 1 71 (Above P-8) any in oper- each oper-ating loop ating loop

13. Loss of Fl ow - Two Loops 3/loop 2/1 oop in 2/loop 1 7#

(Above P-7 and below P-8) two oper- each oper-ating loops ating loop w

~

w w

I

14. Steam Generator Water

. Level--Low-Low 3/loop 2/loop in any oper-ating loops 2/1 oop in each oper-ating loop 1, 2 71

15. Steam/Fee<Mater Flow 2/1 oop-1eve1 l/l oop-1 eve l l/loop-level 1, 2 Mismatch and Low Steam 71 and coincident and Generator Water level 2/l.oop-fl ow with 2/loop-flow mismatch 1I loop-fl ow mismatch or mismatch in 2/loop-level same loop and l/loop-flow mismatch

):IO i 16. Undervoltage-Reactor Coolant

I 0..

Pumps 4-1/bus 1/2 twice 3 1 61 ffi

I 17. Underfrequency-Reactor Coolant r+

Pu~s 4-1/bus 1/2 twice 3 1

z 0

61

  • 8609040139 860829 \

J POR ADOCK 05000272 p __ f>D.R____ __ _,

, __, I

..:.__:__ __ ~ *~_:

TAB LE 3.3-3 (Continued)

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION V>

i:;;

i:

MIN IMtJ.1

. c:

z TOTAL NO. CHANNELS CHANNELS APPLICABLE

-i FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERAS LE MOIES ACTION

8. AUXILIARY FEE llrlATER
a. Automatic Actuation Logic ** 2 1 2 1, 2. 3 20
b. Manual Initiation 1/pump 1/pump 1/pump 1, 2, 3 22
c. Steam Generator Water Level--Low-Low

-N 0

w

~

w I

i

  • Start Motor Driven Pumps 3/stm. gen. 2/stm. gen. 2/stm. gen. 1, 2. 3 14*

Ill ii

  • Start Turbine-Dri ve*n Pumps 3/stm. gen. 2/stm. gen. 2/stm. gen. 1, 2, 3 14*
d. Undervoltage - RCP Start Turbine-Driven Pu~ 4(1/bus) 1/2 x2 3 1, 2 19
e. S. I.

Start Motor-Driven m Pumps See 1 above (All S.I. initiating functions and requirements)

I 11.

m f. Emergency Trip of Steam

I M- Generator Feedwater Pumps Start Motor Driven Pumps 2(1/pump) 2 2(1/pump) 1, 2 21
z 0
g. Station Blackout See 6 and 7 above (SEC and U/V Vital Bus)
    • Applies to* items c and d *.

TABLE 4.3-2 (Continued)

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS SURVEILLANCE REQUIREMENTS .

c:

z

-i CHANNEL MOrES IN WHICH CHANNEL CHANNEL FUNCTIONAL SURVE I LlANCE FUNCT IONA L UN IT CHECK CA LI BRAT ION TEST REQUIRED

8. AUXILIARY FEEllrlATER
a. Automatic Actuation Logic N.A. N.A. M(2) 1, 2, 3
b. Manual Initiation N.A. N.A. M(4) 1, 2, 3
c. Steam Generator Water s R M 1, 2, 3 Level--low-Low w

""'w" d. Undervoltage - RCP s R M(2) 1, 2 I

w w e. S. I. See 1 above (All S.I. surveillance requirements)

f. Emergency Trip of Steam N.A. N.A. R 1, 2 Generator Feedwater Pumps
g. Station Blackout See 6b and 7 above (SEC and U/V Vital Bus) e 3

II)

I 0...

3 II)

I

":z 0

REACTOR *cOOlANT SYSTEM SURVE I LlANCE REQUIREMENTS (Continued)

2. Tubes in those areas where experience has indicated potential problems.
3. A tube inspection (pursuant to Specification 4.4.5.4.a.8} shall be performed on each selected tube. If any selected tube does not permit the passage of the eddy current probe for a tube inspection, this shall be recorded arid an adjacent tube shall be selected and subjected to a tube inspection.
c. The tubes selected as the second and third samples (if required by Table 4.4-2) during each inservice inspection may be subjected to a partial tube inspection provided:
1. The tubes selected for these samples include the tubes from those areas of the tube sheet array where tubes with imperfections were previously found.
2. The inspections include those portions of the tubes where imperfections were previously found.

The results of each sample inspection shall be classified into one of the following three categories:

Category Inspection Results C-1 Less than 5% of the total tubes inspected are degraded tubes and none of the inspected tubes are defective.

C-2 One or more tubes, but not more than 1% of the total tubes inspected are defective, or between 5%

and 10% of the total tubes inspected are degraded tubes.

C-3 More than 10% of the*total tubes inspected are degraded tubes or more than 1% of the inspected tubes are defective.

Note: In all inspections, previously degraded tubes must exhibit significant (greater than 101) further wall penetrations to be included tn the above percentage calcu)ations.

SALEM - UNIT 1 3/4 4-8 Amendment No.

REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued) 4.4.5.3 Inspection Frequencies - The abov~ required inservice- inspections ~f steam generator tubes sha 11 be perf armed at the following frequencies:

a. The first inservice inspection shall be performed after 6 Effective Full Power Months but within 24 calendar months of initial criticality. Subsequent i nservi ce inspect i ans sha 11 be perf armed at intervals ot not less than 12 nor more than 24 calendar months after the previous inspection. If two consecutive inspections following service under AVT conditions, not including the preservice inspection, result in all inspection results falling into the C-1 category or if two consecutive inspections demonstrate that previously observed degradation has not continued and no additional degradation has occurred, the inspection interval may be extended to a maximum of once per 40 months.
b. If the results of the inservice inspection of a steam generator conducted in accordance with Table 4.4-2 at 40 month intervals fall in Category c~3, the inspection frequency shall be increased to at least once per 20 months. The increase in inspection frequency shall apply until the subsequent inspections satisfy the criteria of Specification 4.4.5.3.a; the interval may then be extended to a maximum of once per 40 months.
c. Additional, unscheduled inservice inspections shall be performed on each steam generator in accordance with the first sample inspection specified in Table 4.4-2 during the shutdown subsequent to any of the following conditions:
1. Primary-to-secondary tubes leaks (not including leaks originating from tube-to-tube sheet welds) in excess of the limits of Specification 3.4.6.2. *
2. A seismic occurrence greater than the Operating Basis Earthquake.
3. A loss-of-coolant accident requiring actuation of the engineered safeguards.
4. A main steam line or feedwater line break.

SA LEM - UNIT 1 3/4 4-9 Amendment No.

REACTOR COOLANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued) 4.4.5.4 Acceptance Criteria

a. As used in this Specification:
1. Imperfection means an exception to the dimensions, finish or contour of a tube from that required by fabrication drawings or specifications. Eddy-current testing indications below 20% of the nominal tube wall thickness, if detectable, may be considered as imperfections.
2. Degradation means a service-induced cracking, wastage, wear or general corrosion occurring on either inside or outside of a tube.
3. Degraded Tube means a tube containing imperfections greater than or equal to 203 of the nominal wall thickness caused by degradation.
4.  % Degradation means the percentage of the tube wall thickness affected or removed by degradation. *
5. Defect means an imperfection of such severity that it exceeds the plugging limit. A tube containing a defect is defective.
6. Plugging Limit means the imperfection depth at or beyond which the tube shall be removed from service and is equal to 40% of the nominal tube wall thickness.
7. Unserviceable describes the condition of a tube if it leaks or contains a defect large enough to affect its structural integrity in the event of an Operating Basis Earthquake, a loss-of-coolant accident, or a steam line or feedwater line break as specified in 4.4.5.3.c, above.
8. Tube Inspection means an inspection of the steam generator tube from the point of entry (hot leg side) completely around the U-bend to the top support of the cold leg.

SA LEM - UN IT 1 3/4 4-10 Amendment No.

REACTOR COO LANT SYSTEM SURVEILLANCE REQUIREMENTS (Continued)

9. Preservice Inspection means an inspection of the full length of each tube in each steam generator performed by eddy current techniques prior to sevice establish a baseline condition of the tubing. This inspection shall be performed after the field hydrostatic test and prior to initial POWER OPERATION using the equipment and techniques expected to be used during subsequent inservice inspections.
b. The steam generator shall be determined OPERABLE after completing the corresponding actions (plug all tubes exceeding the plugging limit and all tubes containing through-wall cracks) required by Table 4.4-2.

4.4.5.5 Reports

a. Following each inservice inspection of steam generator tubes, the number of tubes plugged in each steam generator shall be reported so the Commission within 15 days *

.b. The complete results of the steam generator tube inservice inspection shall be reported on an annual basis for the period in which the inspection was completed. This report shall include:

1. Number and extent of tubes inspected.
2. Location and percent of wall-thickness penetration for each indication of an imperfection.
3. Identification of tubes plugged.
c. Results of steam generator tube inspections which fall into Category C-3 and require prompt notification of the Commission shall be reported pursuant to Specificatio~ 6.9. l prior to resumption of .

plant operation. The written followup of this report shall provide*

a description of investigations conducted to determine cause of the tube degradation and corrective measures taken to prevent recurrence.

SALEM - UNIT 1 3/4 4-11 Amendment No.

EMERGENCY CORE COOLING SYSTEMS REFUELING WATER STORAGE TANK LIMITING CONDITION FOR OPERATION 3.5.5 The refueling water storage tank (RWST) shall be OPERABLE with:

a. A contained volume of between 364,500 and 400,000 gallons of borated water.
b. A boron concentration of between 2000 and ~200 ppm, and
c. A minimum water temperature of 35°F *

. APPLICABILITY: MOCES 1, 2, 3 and 4.

ACT ION:

With the refueling water storage tank inoperable, restore the tank 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 at least HOT STANI:BY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTIDWN wjthin the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> *

. SURVEILLANCE REQUIREMENTS 4.5.5 The RWST shall be demonstrated OPERABLE:

a. At least once per 7 days by:
1. Verifying the water level in the tank, and
2. Verifying the boron concentration of the water.
b. At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by verifying the RWST temperature when the outside air temperature is< 35°F.

SALEM - UNIT 1 3/4 5-9 Amendment No.

REVISED PAGES - UNIT NO. 2 TAB Lf 3. 3-1 (Continued)

Vl REACTOR TRIP SYSTEM INSTRUMENTATION

):a f;;

3:

c:

MINIMLM

z

..... TOTAL NO. CHANNELS CHANNELS APPLICAB Lf

-I FUNCT IONA L UN IT OF CHANNELS TO TR IP OPERAB Lf MOCES ACTION N

ll. Pressurizer Water Leve 1--Hi gh 3 2 2 1, 2 7#'

12. Loss of Fl ow - Single Loop 3/1 oop 2/1 oop in 2/1 oop in 1 7#

(Above P-8)

  • any in oper- each oper-ati ng 1oop at i ng loop
13. Loss of Fl ow - Two Loops 3/loop 2/loop in 2/loop 1 7#

(Above P-7 and below P-8) two oper- each oper-ating loops ating loop

-w

~

w w

I

14. Steam Generator Water Level--Low-Low 3/loop 2/loop in any oper-ating loops 2/loop in each oper-ati ng loop 1, 2 7#
15. Steam/Feedwater Flow 2/loop-level 1/1 oop-1 eve l 1/1 oop-1 eve l 1, 2 7#

Mismatch and Low Steam and coincident and Generator Water Level 2/1 oop-fl ow with 2/1 oop-f low mismatch 1/1 oop-fl ow mismatch or mismatch in same loop 2/loop-level and 1/1 oop-f low e

mismatch

):a 3

II>

16. Undervoltage-Reactor Coolant .

~

0..

Pumps 4-1/bus 1/2 twice 3 1 611 3

II>

~

c+

17. Underfrequency-Reactor Coolant Pumps 4-1/bus 1/2 twice 3 1 6#
z 0

TAB lf 3.3-3 (Continued)

Vl

)>

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION Fn 3:

c: MINIMLM

z. TOTAL NO
  • CHANNELS CHANNELS APPLICABLE

-I FUNCT IONA L UN IT OF CHANNELS TO TRIP OPERABLE MOCES ACTION N

8. AUXILIARY FEE !MATER
a. Automatic Actuation logic ** 2 1 2 1, 2, 3 20
b. Manual Initiation 1/pUIJll 1/pump l/pUllll 1, 2, 3 23
c. Steam Generator Water level--Low-Low

-w

~

w N

I i

  • Start Motor Driven Puf11>S 3/stm. gen. 2/stm. gen.

any stm. gen.

2/stm. gen. 1, 2, 3 14*

1i. Start Turbine-Driven Pu111>s 3/stm. gen. 2/stm. gen. 2/stm. gen. 1, 2, 3 14*

any 2 stm. gen.

d. Undervoltage - RCP Start Turbine-Driven Puq> 4(1/bus) 1/2 x2 3 1, 2 19

)>

ill::I

e. S.I.

Start Motor-Driven Puq>s See 1 above (All S.I. initiating functions and requirements) e Q.

it! f. Emergency Trip of Steam

I rl' Generator Feedwater Pumps Start Motor Driven Pumps 2*(1/pump) 2 2(1/pump) 1, 2 22*
z 0
    • Applies to items c and d.

-TABLE 3.3-3 (Continued) e ACTION 19 - With the number of OPERABLE Channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied: *

a. The inoperable channel is placed in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.
b. The Mini mum Channels OPERAS LE requirements is met; however, one additional channel may be bypassed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing _per Specification 4.3.2.1.

ENGINEERED SAFETY FEATURES INTER LOCKS DES !GNAT ION CONDIT ION AND SET PO INT FUNCTION P-11 With 2 of 3 pressurizer P-11 prevents or defeats manual pressure channels > 1925 block of safety injection psi g. - actuation on low pressurizer

  • pressure.

P-12 With 3 of 4 Tavg channels P-12 prevents or defeats manual

> 545°F. block of safety injection actuation high steam flow and low steam line pressure. .

With 2 of 4 Tavg channels Allows manual block of safety

< 541°F. injection actuation on high

. steam line flow and low steam

-line pressure. Causes* steam line isolation on high steam flow. Affects steam dump blocks.

ACTION 20 - *With the number of OPERABLE channels one less than the Total Number of Channels, be in at least HOT STANl:BY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in at least HOT SHUTOOWN within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; however, one channel may be bypassed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing provided the other channel is OPERABLE.

ACTION 21 - With the number of OPERABLE channels one less than the Total Number of Channels, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be* in at least HOT STANOOY within 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 />.

ACTION 22 - With the number of OPERABLE channels one less than the Minimum Number of Channels, operation may proceed provided that either:

a. The inope.rable channel is restored to OPERABLE within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, or
b. If the affected Steam Generator Feedwater Pump is ex~ected to be out of service* for more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, the inoperable channel is jumpered so as to enable the Start Circuit of the Auxiliary Feedwater Pumps upon the loss of the other Steam Generator Feedwater Pump.

ACTION 23 . - With the number of OPERABLE channels relating directly with the number of OPERABLE auxiliary feedwater pumps, the ACTIONS of L.C.O. 3.7.1.2 apply.

SALEM - UNIT 2 3/4 3-23 Amendment No *.

TAB LE 3.3-6 (Continued)

TAB LE NOTATION ACTION 23 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, perform area surveys of the monitored area with portable monitoring instrumentation at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

ACTION 24 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.4.7.1.

ACTION 25 - With the number of channels OPERABLE less.than required by the Minimum Channels OPERABLE requirement, comply with the Action requirements of Specification 3.9.9.

SALEM - UNIT 2 3/4 3-40

INSTRUMENTATION 3/4.3.4 TURBINE OVERSPEED PROTECTION LIMITING CONDITION FOR OPERATION 3.3.4 At least-one turbine overspeed protection system shall be OPERABLE.

APPLICABILITY: MO l:IS 1, 2 and 3.

ACTION:

a. With one stop valve or one control valve per high pressure turbine steam lead inoperable and/or with one reheat stop valve or one reheat intercept valve per low pressure turbine steam lead .inoperable, restore the inoperable valve(s) 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 close at least one valve in the affected steam lead; otherwise, isolate the turbine from the steam supply within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
b. With the above required turbine overspeed protection system otherwise inoperable, within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> either restore the system to OPERABLE status or isolate the turbine from the.steam supply.

SURVEILLANCE REQUIREMENTS 4.3.4.1 The provisions of Specification 4.0.4 are not applicable.

4.3.4.2 The above required turbine overspeed protection system shall be demonstrated OPERABLE:

a. At least once per 7 days by cycling each of the following valves through at least one complete cycle from the running position.
1. Four high pressure turbine stop valves.
2. Four high pressure turbine governor valves.
3. Six low pressure turbine reheat stop valves.
4. Six low pressure turbine reheat intercept valves.
b. At least once per 31 days by direct observation of the movement of each of the above valves through one complete cycle from the running position.
c. At least once per 18 months by performance of a CHANNEL CALIBRATION on the turbine overspeed protection systems.
d. At least one per 40 months by disassembling at least one of each of the above valves and performing a visual and surface inspection of valve seats, disks and stems and verifying no unacceptable flaws or corrosion.

SA LEM - UNIT 2 3/4 3-65 Amendment No.

This page intentionally blank.

  • SA I.EM - UN IT 2 3/4 3-66 Amendment No.

REACTOR* COOLANT SYSTEM OPERATIONAL LEAKAGE LIMITING CONDITION FOR OPERATION 3.4.7.2 ReactCH' Coolant System leakage shall be limited to:

a. No PRESS URE SOUN [l!\RY LEAKAGE,
b. 1 GPM UN I l.ENTIF IE D LEAKAGE,
c. 1 GPM total primary-to-secondary leakage through all steam generators and 500 gallons per day through any one steam generator,
d. 10 GPM I[fNTIFIED LfAKAGE from the Reactor Coolant System, and
e. 40 GPM CONTRO Llf D LfAKAGE at a Reactor Cool ant System pressure of 2230 +/- 20 psig.
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: MOCES 1, 2, 3 and 4.

ACT ION:

a. With any PRESSURE BOUNl)A.RY LEAKAGE, be in at least HOT STANOOY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in COLD SHUTOOWN 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 BOUN[l!\RY LEAKAGE and leakage from Reactor Coolant System Pressure Isolation Valves, reduce the leakag~

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 STANIEY 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 SHUTOOWN 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 STANIEY within the next 6*hours and in COLD SHUTOOWN within the following 30 hour3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />se SURVEILLANCE REQUIREMENTS 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 radioactivity 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 />.

SA LEM - UN IT 2 3/4 4-17 Amendment No.

REACTOR, COO LANT SYSTEM SURVEILLA~CE REQUIREMENTS (Continued)

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 />.
c. Measurement of the _CONTROLLED LEAKAGE from the reactor coolant pump seals at least once per 31 days when the Reactor Coolant System pressure is 2230 ! 20 psig and valve 2CV71 is fully closed.
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 performed with the plant at steady state conditions. The provisions of specifi"cation 4.0.4 are not applicable for entry into Mode 4, and
e. Monitoring 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 />.

4.4.7.2.2 Each Reactor Coolant System Pressure Isolation Valve specified in Table 3.4-1 shall be demonstrated OPERABLE pursuant to ~pecification 4.0.5, except that in lieu of any leakage testing required by Specification 4.0.5, each valve shall be demonstrated OPERAB 1£ by verifying 1eakage to be within its 1i mit:

a. At least once per 18 months.
b. Prior to entering MODE 2 whenever the plant has been in COLD SHUTOOWN for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or more and if leakage testing has not been performed in the previous 9 months.
c. Prior to returning the valve to service following maintenance, repair or replacement work on the valve.
d. For the Residual Heat Removal and Safety Injection Systems hot and cold leg injection valves and accumulator valves listed in Table 3.4-1 the testing 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 sytems testing will be done once per refueling.

The prov1s1ons of specification 4.0.4 are not applicable for entry into MO DE 3 or 4.

SA LEM - UNIT 2 3/4 4-18 Amendment No.

REACTOR'COOLANT SYSTEM

  • TAB LE 3.4-1 REACTOR COO LANT SYSTEM PRESSURE ISO LAT ION VALVES VALVE NO. FUNCTION 21SJ43 Safety Injection (L.P. from RHR Pumps to Cold Legs) 22SJ43 Safety Injection (L.P. from RHR Pumps to Cold Legs) 23SJ43 Safety Injection (L.P. from RHR Pumps to Cold Legs) 24SJ43 Safety Injection ( L.P. from RHR Pumps to Cold Legs) 21SJ55 Safety Injection (Accumulator Discharge to Cold Legs) 22SJ55 Safety Injection (Accumulator Discharge to Cold Legs) 23SJ55 Safety Injection (Accumulator Discharge to Cold Legs) 24SJ55 Safety Injection (Accumulator Discharge to Cold Legs) 21SJ56 Safety Injection (Accumulator Discharge to Cold Legs) 22SJ56 Safety Injection (Accumulator Discharge to Cold Legs) 23SJ56 Safety Injection (Accumulator Discharge to Cold Legs) 24SJ56 Safety Injection (Accumulator Discharge to Cold Legs) 21SJ17 Safety Injection (Boron Injection to Cold Legs) 22SJ17 Safety Injection (Boron Injection to Cold Legs) 23SJ17 *Safety Injection (Boron Injection to Cold Legs) 24SJ17 Safety Injection (Boron Injection to Cold Legs)

. 2SJ150 Safety Inject ion (Boron Injection to Cold Legs) 21SJ139 Safety Injection (H.P. from SI Pumps to Hot Legs) 22SJ139 Safety Injection (H.P. from SI Pumps to Hot Legs) 23SJ139 Safety Injection (H.P. from SI Pumps to Hot Legs) 24SJ139 Safety Injection (H.P. from SI Pumps to Hot Legs) 21SJ156 Safety Injection (H.P. from SI Pumps to Hot Legs) 22SJ156 Safety Injection (H.P. from SI Pumps to Hot Legs) 23SJ156 Safety Injection (H.P. from SI Pumps to Hot Legs}

24SJ156 Safety Injection (H.P. from SI Pumps to Hot Legs}

21SJ144 Safety Injection (H.P. from SI Pumps to Cold Legs}

22SJ144. Safety Injection '(H.P * .from SI Pumps to Cold Legs) 23SJ144 Safety Injection (H.P. from SI Pumps to Cold Legs) 24SJ144 Safety Injection {H *. P~ from SI Pumps to Cold Legs}

2RH1 RHR Suet ion from Hot Leg No. 21

.2RH2 RHR Suction from Hot .Leg No. 21 23RH27 RHR Discharge to Hot Leg No. 23 24RH27 RHR Discharge to Hot Leg No. 24 SALEM - UNIT 2 3/4 4-19 Amendment No.