ML17286B128

Proposed Tech Spec Table 2.2.1-1, Reactor Protection Sys Instrumentation Setpoints & Table 4.3.1.1-1, Reactor Protection Sys Instrumentation Surveillance Requirements.

ML17286B128
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Site:	Columbia
Issue date:	10/31/1991
From:	WASHINGTON PUBLIC POWER SUPPLY SYSTEM
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TABLE 2.2. 1-1 REACTOR PROTECTION SYSTEM INSTRUMENTATION SETPOINTS C/l ALI OWABLE FUNCTIONAL UNIT TRIP SETPOINT VALUES QQ4) m a~

C)

~

1. Intermediate Range Monitor, Neutron Flux - High < 120/125 divisions < 122/125 divisions I

Av~

-vn of full scale of full scale

.0 iUOQ o..~

2. Average Power Range Honitor:

OMK a. Neutron Flux-High, Setdown < 15X of RATED THERMAL POWER < 20X of RATED OOD THERMAL POWER fgv~ b. Flow Biased Simulated Thermal Power - High Ov+

OO

'vow<

'Qv

1) Flow Biased < 0.66W+ 5', with maximum of

< 0.66W+ 54X, witli".

of A-'.

v 2) High Flow Clamped <

a 113.5X of RATED <

a maximum 115.5X of RATEDQ'HERMAL THERMAL POWER POWER

c. Fixed Neutron Flux - High < 118X of RATED THERMAL POWER < 120X of RATED gg>

THERMAL POWER d.'noperative N.A. N.A.

fll-.

3. Reactor Vessel Steam Dome Pressure - High < 1037 psig < 1057 psig

4. Reactor Vessel Mater Level - Low, Level 3 > 13.0 inches above instrument > 11.0 inches abo zero* instrument zero "-,

.0:

5. Main Steam Line Isolation Valve - Closure < 10.0X closed < 12.5X closed 6.-Hake-S4ea ew~ ewep F'e N

ases gure 3/4 3-1.

(+

Ol G.

M

'h E

I J

LIMITING SAFETY SYSTEH ScHINGS BASES REACTOR PROTECTION SYSTEM INSTRUMENTATION SETPOINTS (Continued)

4. Reactor Vessel Water Level-Low The reactor vessel water level trip setpoint was chosen far enough below the normal operating level to avoid spurious trips but high enough above the fuel to assure that there is adequate protection for the fuel and pressure limits.

5. Main Steam Line Isolation Valve-Closure The main steam line isolation valve closure trip was provided to limit the amount of fission product release for certain postulated events. The HSIV's are closed automatically from measured parameters such as high steam flow, high steam line radiation, low reactor water level, high steam tunnel temperature, and low steam line pressure. The HSIV's closure c m anticipates the pressure

.and flux transients which could follow MSIV clog and thereby protects reac or vessel'pressure ard fuel thermal/hydrau'lic Sag?Zimits.

6.

failure or initiated to ladding.

reduce the con When t 'h radiation is rip i 5 ia ding. At the same time produc vp+0, the main steam line iso sp setting is hi re c o t ough above backgroun oughW~pom~p-date&'r gpo

'vels the release of fission

7. Primary Con ainment Pressure-High High pressure in the drywell could indicate a break in the primary pressure boundary systems. The reactor is tripped in order to minimize the possibility of fuel damage and reduce the amount of energy being added to the coolant.

The tr ip setting was selected as low as possible without causing spurious trips.

. WASHINGTON NUCLEAR -. UNIT 2 B 2"8

TABLE 3.3.1-1 (Continued)

REACTOR PROTECTION SYSTEM INSTRUMENTATION APPLICABLE MINIMUM OPERATIONAL OPERABLE CIIANNELS FUNCTIONAL UNIT CONDITIONS PER fRIP SYSTEH a ACTION

7. P) imary Containment Pressure - Nigh 2(g) 0cZ

8. Scram Discharge Volume Water Level - Niyh Zl

a. Level Transmitter 1, 2 Q 5(h)

I

b. Float Switch 1, 2 IVI 5(h) U

9. Turbine Throttle Valve - Closure l(i) 4(i) A

10. Turbine Governor Valve Fast Closure, Q

U Valve Trip System Oil Pressure - Low l(i) 2(J) ll. Reactor Mode Switch Shutdown Position 1, 2 3, 4 5

12. Hanual Scram 1, 2 3, 4 5

'I

+CQNTaoLLeO C0PV ~

TABLE 3.3. 1-1 (Continued)

REACTOR PROTECTION SYSTEM INSTRUMENTATION ACTION ACTION 1 Be in at leas HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

ACTION 2 Verify all insertable control rods to be inserted in the core and lock the reactor mode switch in the Shutdown position within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

ACTION 3 Suspend all operations involving CORE ALTERATIONS" and insert all insertable control rods within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

ACTION 4 Be in at least STARTUP within 6 hours.

~Acth-th

-w+tW~e ACTION 6 Initiate a reduction in THERMAL POWER within 15 minutes and reduce turbine first stage pressure to < 165 psig, equivalent to THERMAL POWER less than 30~ of RATED THERMAL POWER, within 2 hours.

ACTION 7 Verify all insertable control rods to be -inserted within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

ACTION 8 Lock the reactor mode switch in the Shutdown position within 1 hour.

ACTION 9 Suspend all operations involving CORE ALTERATIONS~, and insert all insertable control rods and lock the reactor mode switch in the SHUTDOWN position within 1 hour.

Except movement of IRM, SRM or special movable detectors, or replacement of LPRM strings provided SRM instrumentation is OPERABLE per Specification 3.9.2.

WASHINGTON NUCLEAR - UNIT 2 3/4 3-4

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%oeaoccFo co< y TABLE 3.3. 1-1 (Continued)

REACTOR PROTECTION SYSTEM INSTRUMENTATION TABLE NOTATIONS (a) A channel may be placed in an inoperable status for up to six hours for required surveillance without placing the trip system in the tripped condition provided at least one OPERABLE channel in the same trip system is monitoring that parameter.

(b) The "shorting links" shall be removed from the RPS circuitry prior to and during the time any control rod is withdrawn" and shutdown margi n demonstrations are being performed per Specification 3. 10.3.

(c) An APRM channel level or less than is inoperable if there are less than 2 LPRM inputs per 14 LPRM inputs to an APRM channel.

(d) This function shall be automatically bypassed when the reactor mode switch is not in the Run position and reactor pressure < 1037 psig.

nct4ea-i~et~eqA+ed-te-be-OPHQBhG-when-th eve~~

(f) This function is not required to be OPERABLE when PRIMARY CONTAINMENT INTEGRITY is not required.

(g) Also actuates the standby gas treatment system.

(h) With any control rod withdrawn. Not applicable to control rods removed per Specification 3.9. 10. 1 or 3.9. 10.2.

(i) This function shall be automatically bypassed when turbine first stage pressure is < 165 psig, equivalent to THERMAL POWER less than 30K of RATED THERMAL POWER.

(j) Also actuates the EOC-RPT system.

"Not required for control rods removed per Specification 3.9.10. 1 or 3.9.10.2.

WASHINGTON NUCLEAR - UNIT 2 3/4 3-5 AMENDMENT NO. 90

~

~

TABLE 3.3.1-2 M REACTOR PROTECTION SYSTEM RESPONSE TIMES CD RESPONSE TIME FUNCTIONAL UNIT Seconds rn l. Intermediate Range Monitors:

a. Neutron Flux - High N.A.

I b. Inoperative N.A.

2. Average Power Range Monitor":

a. Neutron. Flux - Upscale, Setdown N.A.

b. Flow Biased Simulated Thermal Power - Upscale 6g7 <<<<

c. Fixed Neutron Flux - Upscale < 0.09 A

d. Inoperative H.A.

Q R

3. Reactor Vessel Steam Dome Pressure - High < 0.55 Reactor Vessel Water Level - Low, Level 3 33

5. Main Steam Line Isolation Valve - Closure 1.05 0.06 0 Primary Containment Pressure " High N.A.

Scram Discharge Volume Water Level - High Ch

a. Level Transmitter U

b. Float Switch N.A.'.A.

A 9.

10.

Turbine Throttle Valve - Closure Turbine Governor Valve Fast Closure,

< 0.06 a9 Trip Oil Pressure - Low <

ll. Reactor Mode Switch Shutdown Position 0.08'.A.

.12. Manual Scram N.A.

"Neutron detectors are exempt from response time testing. Response time shall be measured from the detector output or from the input of the first electronic component in the channel.

<<<<Including simulated thermal power time constant.

SMeasured from start of turbine control valve fast closure.

II II II

TABLE 4.3.1.1-1 REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE RE UIREMENTS CHANNEL OPERATIONAL CHANNEL FUNCTIONAL CHANNEL CONDITIONS FOR WHICH FUNCTIONAL UNIT CHECK TEST CALIBRATION( ) SURVEILLANCE RE UIRED

l. Intermediate Range Monitors:

a. Neutron Flux High S/U(b), 5 S/U(c), W 2 S M 3, 4, 5

b. Inoperative N.A. W N.A. 2, 3, 4, 5

2. Average Power Range Monitor 0

a. Neutron Flux- S/U(b), S S/U(c), W SA 2 K, Upscale, Setdown S M SA 3, 5 g3

b. Flow Biased Simulated Q-Thermal Power - Upscale S,O(g) S/U(c), q W(d)(e), SA, R(h) 1 Ir

c. Fixed Neutron Flux- fT1 Upscale S/u(c), q M(d), SA U

d. Inoper ative N.A. N.A. 1, 2, 3, 5 A Q

3. Reactor Vessel Steam Dome U Pressure - High 1) 2 Reactor Vessel Mater Level-Low, Level 3 1 2

5. Hain Steam Line Isolation Valve - Closure N.A.

7. Primary Containment Pressure - High N.A. 1$ 2

ly I

t 4

%ONTaOLLeO CO< V TABLE 4.3.1.1-1 (Continued)

REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE RE UIREilENTS TABLE NOTATIONS (a) Neutron detectors may be excluded from CHANNEL CALIBRATION.

(b) The IRM and SRM channels shall be determined to overlap for at least 1/2 decade during each startup after entering OPERATIONAL CONDITION 2 and the IRM and APRM channels shall be determined to overlap for at least 1/2 decade during each controlled shutdown, if not performed within the previous 7 days.

(c) Within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> prior to startup, if not performed within the previous 7 days.

(d) This calibration shall consist of the adjustment of the APRM channel to conform to the power values calculated by a heat balance during OPERATIONAL CONDITION 1 when THERMAL POWER > 25K of RATED THERMAL POWER. Adjust the APRM channel if the absolute difference is greater than K of RATED THERMAL POWER. Any APRM channel gain adjustment made in compliance with Specification 3.2.2 shall not be included in determining the absolute difference.

(e) This calibration shall consist of the adjustment of the APRM. flow biased channel to conform to a calibrated flow signal.

(f) The LPRMs shall be calibrated at least once per 1000 effective full power hours (EFPH) using the TIP system.

(g) Measure and comoare core flow to rated core flow.

(h) This calibration shall consist of verifying the 6 + 'econd simulated thermal power, time constant.

(j) With any control rod withdrawn. Not applicable to control rods removed per Specification 3.9. 10. 1 or 3.9. 10.2.

. WASHINGTON NUCLEAR - UNIT 2 3/4 3-9

TABLE '3. 3. 2-1 ISOLATION ACTUATION INSTRUHENTATION Cl CD VALVE GROUPS HINIHUH 'PPLICABLE OPERATED BY OPERABLE CHAttNELS OPERATIONAL TRIP FUNCTION SIGNAL PER TRIP SYSTEH a CONDITION ACTION n l. PRIHARY CONTAINMENT ISOLATION a~ Reactor Vessel Mater Level I 1) Low, Level 3 5(g) 1,2,3 20

2) Low Low, Level 2 1, 2, 4 1$ 2$ 3 20

b. Drywell Pressure - High 4, 5(b)(g) 1, 2, 3 20 C. Hain Steam Line O

2) Pressure - Low 2 1 23 R

3) Flow - High= 2(d) 1 2.3 21 Hain Steam Line Tunnel XI Temperature - High 1$ 2$ 3 21 Q

e. Hain Steam Line Tunnel 4 Temperature - High 1 2 1, 2 3 21

f. Condenser Vacuum - Low 1 2 21 IT]

Hanual Initiation 3',

g. 1 2/group 2, 3 24 1/group 1, 2, 24 2

5(b)(9) 1/group 3

A

2. SECONDARY CONTAINHENT ISOLATION 1, 2, 3 24 0

a~ Reactor Building Vent Exhaust Plenum Radiation - High 3(b)( ) 1, 2, 3, and *" 25

b. Drywell Pressure - tligh 3(b)(e) 1, 2$ 3 25 C. Reactor Vessel Mater Level - Low Low, Level 2 2 1, 2, 3, and 8 25

d. Hanual Initiation 3(b) 1/group 24 3(b) 1/group $C $C 24 O

0 I

II II hi, 4 p f

COW aoLL~O COF y TABLE 3.3. 2-1 (Continued)

ISOLATION ACTUATION INSTRUMENTATION ACTION STATEMENTS ACTION 20 Be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

ACTION 21 Be in at least STARTUP with the associated isolation valves closed within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> or be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

ACTION 22 Close the affected system isolation valves within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and declare the affected system inoperable.

~

ACTION 23 Be in at least STARTUP within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

ACTION 24 Restore the manual initiation function to OPERABLE status within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> or close the affected system isolation valves within the next hour and declare the affected system inoperable or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

ACTION 25 Establish SECONDARY CONTAINMENT INTEGRITY with the standby gas treatment system operating within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

ACTION 26 Lock close or close, as applicable, the affected system isolation valves within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> and declare the affected system inoperable.

TABLE NOTATIONS "May be bypassed with reactor steam pressure < 1037 psig and all turbine stop valves closed.

""When handling irradiated fuel in the secondary containment and during CORE ALTERATIONS and operations with a potential for draining the reactor vessel.

00uring CORE ALTERATIONS and operations with a potential for draining the reactor vessel.

(a)A channel may be placed in an inoperable status 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 required surveillance without placing the trip system in the tripped con-dition provided at least one other OPERABLE channel in the same trip system is monitoring that parameter.

(b)Also actuates the standby gas treatment system.

(d)A channel is OPERABLE if 2 of 4 detectors in that channel are OPERABLE.

(e)Also actuates secondary containment ventilation isolation dampers per Table 3.6.5.2-1.

(f)Closes only RWCU system outboard isolation valve RWCU-V-4.

(g)Only valves RHR-V-123A and RHR-V-123B in Valve Group 5 are required for primary isolation.

(h)Manual initiation isolates RCIC-V-8 only and only with a coincident reactor vessel level-low, level 3.

(i)Not required for RHR-V-8 when control is transfer red to the alternate remote shutdown panel during operational conditions 1, 2 8 3 and the isolation interlocks are bypassed. When RHR-V-8 control is transferred to the remote shutdown panel under operational modes 1, 2, and 3 the associated key lock switch will be locked with the valve in the closed position. Except RHR-V-8 can be returned to, and operated from, the control room, with the interlocks and automatic isolation capability reestablished in operational conditions 2 and 3 when reactor pressure is less .than 135 psig.

WASHINGTON NUCLEAR - UNIT 2 3/4 3-15 Amendment No. 58

'f TABLE 3.3.2"2 ISOLATION ACTUATION INSTRUHENTATION SETPOINTS ALLOWABLE TRIP FUNCTION TRIP SETPOINT VALUE

1. PRIMARY CONTAINMENT ISOLATION

a. Reactor Vessel Water Level

1) Low, Level 3 > 13.0 inches* > 11.0 inches

2) Low Low, Level 2 > -50 inches* > -57 inches

b. Drywell Pressure - High < 1.68 psig < 1.88 psig C. Hain Steam Line 0R

2) Pressure - Low > 831 psig > 811 psig

3) Flow - High < 105.5 psid < 108 psid 0

d. Hain Steam Line Tunnel Temperature - High < 164'F < 170 F

e.. Hain Steam Line Tunnel h Temperature - High < 80'F < 90'F U

f. Condenser Vacuum - Low > 23 inches Hg absolute > 24.5 inches Hg absolute pressure pressure

g. Manual Initiation N.A. N.A. Q

...Q

2. SECONDARY CONTAINHENT ISOLATION

a. Reactor Building Vent Exhaust Plenum Radiation - High < 13.0 mR/h < 16 0 mR/h

b. Drywell Pressure - High < 1.68 psig < 1 88 psig C. Reactor Vessel Water Level - Low Low, Level 2 > -50 inches" > -57 inches

d. Hanual Initiation N.A. N. A.

lJ I l

~ ll lit gO

~i l

'I CONTROLLED COPY ~

TABLE 3.3.2"3 ISOLATION SYSTEM INSTRUiMENTATION RESPONSE TIiME TRIP FUNCTION RESPONSE TIME Seconds)d PRIMARY CONTAIiNMENT ISOLATION

a. Reactor Vessel Water Level

1) Low, Level 3 N.A.

2) Low Low, Level 2 < 1.0"/< 13(a)"~-

b. 'rywell Pressure - High < 13(a)

c. Main Steam Line

2) Pressure " Low < l. 0"/< 13(a)""

3) Flow - High ( Q SR/( $ 3(a).iiii

d. Main Steam Lin'e Tunnel Temperature - High N.A.

e. Main Steam Line Tunnel 6 Temperature - High N. A.

f. Condenser Vacuum - Low N. A.

g. Manual Initiation N.A.

2. SECQNOARY CONTAINMENT ISOLATION Reactor Building Vent Exhaust Plenum Radiation - Hign(bj < 13(a).

b. Orywell Pressure - High < '3(a)

C. Reactor Vessel Water Level - Low Low, Level 2 ('13(a)

d. Manual Initiation N. A.

REACTOR WATER CLEANUP SYSTEM ISOLATION

a. 0 Flow - High < 13(a'0'4

b. Heat Exchanger Area Temoerature - High N.A.

C. Heat Exchanger Area Ventilation ii Temp. - High

d. Pump Area Temperature

- High N.A.

e. Pump Area Ventilation 6 Temp.

- High N.A.

SLCS Initiation N. A.

g. Reac.or Vessel Water Level - Low Low, Level 2 < 13(a)

h. RWCU/RCIC Line Routing Area Temperature-High N. A.

RWCU Line Routing Area Temperature

- High N. A.

Manual Initiation N. A.

WASH')GTQN NUCLEAR - UNIT 2 1/P 3 )o

1 ABLE 4.3.2. 1-1 ISOLATION ACTUATIOH INSTRUMEHTATIOH SURVEILLANCE RE UIREMEHTS CllhHNEL OPERATIONAL CllhNNEL FUNCTIONAL CllhHHEL CO~DI~IO~S FOR WllICll n

I TRIP FUNCTIOH CllECK TEST CALIBRATION SURVEII.LANCE RE UIRED m

PRIMARY CONTAINMEHT ISOLATION

a. Reactor Vessel Water Level-

1) Low, Level 3 S 1 2 3

2) . Low Low, Level 2 H.A. 1 2 3 Drywell Pressure - lligh N. A. 1, 2 3 Main Steam Line

2) Pressur e - Low N.A. 1

3) Flow - lligh S 1, 2, 3

d. Main Steam Line Tunnel Temperat<<re - lligh N.h. 1, 2 3

e. Main Steam Line Tunnel h Teoqierature - lliglr N. h. Sh R 1, 2, 3

f. Condenser Vacuum - Low N.h. M R 2A 3*

g. Manual Initiation H.h. R N.A. 1 2 3.

2. SECONDARY CONTAINMENT ISOLAT1ON

a. Reactor Building Vent Exhaust P1enrim Radiation - lliglr S 1,2,3,and Drywell Pressure - lligh N.h. 1,2,3 Reactor Vessel WaLer Level - Low Low, Level 2 H.A. R 1, 2, 3, and Manual Initiation H.A. H.A. 1,2,3,and O

0