Text

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
To:	;
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ML17286B127	List: GO2-91-200, Application for Amend to License NPF-21,changing Tech Specs to Eliminate Main Steam Line Radiation Monitor Scram & MSIV Closure Functions Per GE Topical Rept NEDO-31400.Changes Will Reduce Unnecessary Plant Shut Downs; ML17286B128;
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TABLE 2.2. 1-1 REACTOR PROTECTION SYSTEM INSTRUMENTATION SETPOINTS C/l QQ4) m C) a~

I Av~

-vn i o..~

.0 UOQ OMK OOD fgv~

Ov+

OO

'vow<

'Qv

v FUNCTIONAL UNIT

~

1. Intermediate Range Monitor, Neutron Flux - High

2. Average Power Range Honitor:

a.

Neutron Flux-High, Setdown b.

Flow Biased Simulated Thermal Power - High

1) Flow Biased

2) High Flow Clamped c.

Fixed Neutron Flux - High d.'noperative

3. Reactor Vessel Steam Dome Pressure - High

4. Reactor Vessel Mater Level - Low, Level 3

5. Main Steam Line Isolation Valve - Closure 6.-Hake-S4ea TRIP SETPOINT

< 120/125 divisions of full scale ALIOWABLE VALUES

< 122/125 divisions of full scale

< 0.66W+ 5', with a maximum of

< 113.5X of RATED THERMAL POWER

< 118X of RATED THERMAL POWER N.A.

< 1037 psig

> 13.0 inches above instrument zero*

< 10.0X closed ew~

< 0.66W+ 54X, witli".

a maximum of A-'.

< 115.5X of RATEDQ'HERMAL POWER

< 120X of RATED gg>

THERMAL POWER N.A.

fll-.

< 1057 psig

> 11.0 inches abo instrument zero

.0:

< 12.5X closed ewep

< 15X of RATED THERMAL POWER

< 20X of RATED THERMAL POWER F'e ases gure 3/4 3-1.

N

(+

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 ladding.

When t 'h radiation is rip i 5 initiated to reduce the con ia ding.

At the same time the main steam line iso re c o t the release of fission produc sp setting is hi ough above backgroun

'vels vp+0, oughW~pom~p-date&'r gpo 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 FUNCTIONAL UNIT APPLICABLE OPERATIONAL CONDITIONS MINIMUM OPERABLE CIIANNELS PER fRIP SYSTEH a

ACTION 7.

P) imary Containment Pressure

- Nigh 8.

Scram Discharge Volume Water Level - Niyh a.

Level Transmitter b.

Float Switch 9.

Turbine Throttle Valve - Closure 1,

2 5(h) 1, 2

5(h) l(i) 10.

Turbine Governor Valve Fast Closure, Valve Trip System Oil Pressure

- Low l(i) 2(g) 4(i) 2(J) 0 cZ Zl Q

I IVI U

A Q

U ll.

Reactor Mode Switch Shutdown Position 12.

Hanual Scram 1,

2 3,

4 5

1, 2

3, 4

5

'I

+CQNTaoLLeO C0PV~

TABLE 3.3. 1-1 (Continued)

REACTOR PROTECTION SYSTEM INSTRUMENTATION ACTION ACTION 1 ACTION 2 ACTION 3 ACTION 4 ACTION 6 ACTION 7 ACTION 8 ACTION 9 Be in at leas HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

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 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

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

Be in at least STARTUP within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

~Acth-th

-w+tW~e 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 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

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

Lock the reactor mode switch in the Shutdown position within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

Suspend all operations involving CORE ALTERATIONS~, and insert all insertable control rods and lock the reactor mode switch in the SHUTDOWN position within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

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

t

~

lp W ~

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

REACTOR PROTECTION SYSTEM INSTRUMENTATION TABLE NOTATIONS (a)

(b)

(c)

(d)

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.

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.

An APRM channel is inoperable if there are less than 2

LPRM inputs per level or less than 14 LPRM inputs to an APRM channel.

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)

(h)

Also actuates the standby gas treatment system.

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

CD rn I

Ch REACTOR PROTECTION SYSTEM RESPONSE TIMES FUNCTIONAL UNIT l.

Intermediate Range Monitors:

a.

Neutron Flux - High b.

Inoperative 2.

3.

5.

Reactor Vessel Steam Dome Pressure

- High Reactor Vessel Water Level - Low, Level 3

Main Steam Line Isolation Valve - Closure Primary Containment Pressure

" High Scram Discharge Volume Water Level - High a.

Level Transmitter b.

Float Switch 9.

Turbine Throttle Valve - Closure 10.

Turbine Governor Valve Fast Closure, Trip Oil Pressure - Low ll.

Reactor Mode Switch Shutdown Position

.12.

Manual Scram Average Power Range Monitor":

a.

Neutron. Flux - Upscale, Setdown b.

Flow Biased Simulated Thermal Power - Upscale c.

Fixed Neutron Flux - Upscale d.

Inoperative

RESPONSE

TIME Seconds N.A.

N.A.

6g7 <<<<

< 0.09 H.A.

< 0.55

.< 1.05

< 0.06 N.A.

N.A.'.A.

< 0.06 0.08'.A.

N.A.

A QR 330 U

Aa9 "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 FUNCTIONAL UNIT CHANNEL CHECK CHANNEL OPERATIONAL FUNCTIONAL CHANNEL ( )

CONDITIONS FOR WHICH TEST CALIBRATION SURVEILLANCE RE UIRED l.

Intermediate Range Monitors:

a.

Neutron Flux - High S/U(b),

5 S/U(c),

W S

M 2

3, 4, 5

2.

3.

N.A.

W b.

Inoperative Average Power Range Monitor a.

Neutron Flux-S/U(b),

S

Upscale, Setdown S

b.

Flow Biased Simulated Thermal Power - Upscale S,O(g) c.

Fixed Neutron Flux-Upscale d.

Inoper ative Reactor Vessel Steam Dome Pressure - High Reactor Vessel Mater Level-Low, Level 3

N.A.

S/U(c),

W M

S/U(c),

q S/u(c),

q N.A.

2, 3, 4, 5

SA SA 2

3, 5

M(d),

SA N.A.

1, 2, 3, 5

1) 2 1

2 W(d)(e),

SA, R(h) 1 0K, g3 IrQ-fT1U A

Q U

5.

7.

Hain Steam Line Isolation Valve - Closure Primary Containment Pressure

- High N.A.

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 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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

Cl CD n

I TRIP l.

a ~

b.

C.

Reactor Vessel Mater Level 1)

Low, Level 3

2)

Low Low, Level 2

Drywell Pressure

- High Hain Steam Line FUNCTION PRIHARY CONTAINMENT ISOLATION 5(g) 1, 2, 4

4, 5(b)(g) 1,2,3 1 $ 2 $ 3 1, 2, 3

TABLE'3. 3. 2-1 ISOLATION ACTUATION INSTRUHENTATION VALVE GROUPS HINIHUH

'PPLICABLE OPERATED BY OPERABLE CHAttNELS OPERATIONAL SIGNAL PER TRIP SYSTEH a

CONDITION ACTION 20 20 20 e.

f.

g.

2)

Pressure - Low 3)

Flow - High=

Hain Steam Line Tunnel Temperature

- High Hain Steam Line Tunnel 4 Temperature - High Condenser Vacuum - Low Hanual Initiation 2.

SECONDARY CONTAINHENT ISOLATION 1

1 1

2 5(b)(9) 2 2(d) 2 2

2/group 1/group 1/group 1

1 2.3 1$

2$

3 1,

2 3

3',

2, 3

1, 2, 3

23 21 21 21 21 24 24 24 OR XI Q

IT]

A0 a ~

b.

C.

d.

Reactor Building Vent Exhaust Plenum Radiation - High Drywell Pressure - tligh Reactor Vessel Mater Level - Low Low, Level 2

Hanual Initiation 3(b)( )

3(b)(e) 3(b) 3(b) 2 1/group 1/group 1, 2, 3, and *"

25 1,

2$

3 25 1, 2, 3, and 8

25 24

$C $C 24 O

0 I

II II hi, 4 p f

ACTION 20 ACTION 21 ACTION 22

~ ACTION 23 ACTION 24 ACTION 25 ACTION 26 COW aoLL~O COF y TABLE 3.3. 2-1 (Continued)

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

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

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

Be in at least STARTUP within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

Restore the manual initiation function to OPERABLE status within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months 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 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

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

Lock close or close, as applicable, the affected system isolation valves within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months 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 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 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 TRIP FUNCTION 1.

PRIMARY CONTAINMENT ISOLATION a.

b.

C.

Reactor Vessel Water Level 1)

Low, Level 3

2)

Low Low, Level 2

Drywell Pressure - High Hain Steam Line 2)

Pressure - Low 3)

Flow - High d.

Hain Steam Line Tunnel Temperature - High

e..

Hain Steam Line Tunnel h Temperature - High f.

Condenser Vacuum - Low g.

Manual Initiation 2.

SECONDARY CONTAINHENT ISOLATION TRIP SETPOINT

> 13.0 inches*

> -50 inches*

< 1.68 psig

> 831 psig

< 105.5 psid

< 164'F

< 80'F

> 23 inches Hg absolute pressure N.A.

ALLOWABLE VALUE

> 11.0 inches

> -57 inches

< 1.88 psig

> 811 psig

< 108 psid

< 170 F

< 90'F

> 24.5 inches pressure N.A.

0R 0

U Hg absolute Q

...Q a.

b.

C.

d.

Reactor Building Vent Exhaust Plenum Radiation - High Drywell Pressure - High Reactor Vessel Water Level - Low Low, Level 2

Hanual Initiation

< 13.0 mR/h

< 1.68 psig

> -50 inches" N.A.

< 16 0 mR/h

< 1 88 psig

> -57 inches N. A.

lJ I

l

~

ll lit gO

~i l

'I CONTROLLED COPY ~

TRIP FUNCTION TABLE 3.3.2"3 ISOLATION SYSTEM INSTRUiMENTATION RESPONSE TIiME

RESPONSE

TIME Seconds)d PRIMARY CONTAIiNMENT ISOLATION a.

Reactor Vessel Water Level 1)

Low, Level 3

2)

Low Low, Level 2

b. 'rywell Pressure - High c.

Main Steam Line 2)

Pressure

" Low 3)

Flow - High N.A.

< 1.0"/< 13(a)"~-

< 13(a)

< l. 0"/< 13(a)""

(

Q SR/(

$ 3(a).iiii d.

e.

f.

g.

Main Steam Lin'e Tunnel Temperature

- High Main Steam Line Tunnel 6 Temperature - High Condenser Vacuum - Low Manual Initiation N.A.

N. A.

N.A.

2.

SECQNOARY CONTAINMENT ISOLATION b.

C.

d.

Reactor Building Vent Exhaust Plenum Radiation - Hign(bj Orywell Pressure

- High Reactor Vessel Water Level - Low Low, Level 2

Manual Initiation

< 13(a).

< '3(a)

('13(a)

N. A.

REACTOR WATER CLEANUP SYSTEM ISOLATION a.

b.

C.

d.

e.

g.

h.

0 Flow - High Heat Exchanger Area Temoerature - High Heat Exchanger Area Ventilation ii Temp. - High Pump Area Temperature

- High Pump Area Ventilation 6 Temp. - High SLCS Initiation Reac.or Vessel Water Level - Low Low, Level 2

RWCU/RCIC Line Routing Area Temperature-High RWCU Line Routing Area Temperature

- High Manual Initiation

< 13(a'0'4 N.A.

N.A.

N. A.

< 13(a)

N. A.

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

1 ABLE 4.3.2. 1-1 ISOLATION ACTUATIOH INSTRUMEHTATIOH SURVEILLANCE RE UIREMEHTS n

Im TRIP FUNCTIOH PRIMARY CONTAINMEHT ISOLATION CllhNNEL CllECK CllhHNEL FUNCTIONAL TEST CllhHHEL CALIBRATION OPERATIONAL CO~DI~IO~S FOR WllICll SURVEII.LANCE RE UIRED a.

Reactor Vessel Water Level-1)

Low, Level 3

2)

. Low Low, Level 2

Drywell Pressure

- lligh Main Steam Line S

H.A.

N. A.

1 2

3 1

2 3

1, 2

3 2)

Pressur e - Low 3)

Flow - lligh d.

Main Steam Line Tunnel Temperat<<re

- lligh e.

Main Steam Line Tunnel h Teoqierature

- lliglr f.

Condenser Vacuum -

Low g.

Manual Initiation 2.

SECONDARY CONTAINMENT ISOLAT1ON N.A.

S N.h.

N. h.

N.h.

H.h.

Sh M

R R

R N.A.

1 1, 2, 3

1, 2

3 1, 2, 3

2A 3*

1 2 3.

a.

Reactor Building Vent Exhaust P1enrim Radiation - lliglr Drywell Pressure

- lligh Reactor Vessel WaLer Level -

Low Low, Level 2

Manual Initiation S

N.h.

H.A.

R H.A.

1,2,3,and 1,2,3 1, 2, 3, and 1,2,3,and O

0

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