ML17285A739
| ML17285A739 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 09/14/1989 |
| From: | WASHINGTON PUBLIC POWER SUPPLY SYSTEM |
| To: | |
| Shared Package | |
| ML17285A738 | List: |
| References | |
| NUDOCS 8909280041 | |
| Download: ML17285A739 (10) | |
Text
Proposed Changes to WNP-2 Technical Specification 3/4.3.1 Reactor Protection System Instrumentation 890928004i 890914 PDR ADOCK 05000397 P
3/4. 3 INSTRUMENTATION 3/4. 3. 1 REACTOR PROTECTION SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.1 As a minimum, the reactor protection system instrumentation channels shown in Table 3.3.1-1 shall be OPERABLE with the REACTOR PROTECTION SYSTEM
RESPONSE
TIME as shown in Table 3.3.1-2.
APPLICABILITY:
As shown in Table 3.3.1-1.
ACTION:
aO b.
Mith the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip System requirement for one trip system, place the inoperabl channel(s) and/ov that trip system in the tripped condition" withi ~~ut.
The rovisions of Specification 3.0.4 are not appl icable.
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With the number of OPERABLE channels
'1ess than required by the Minimum OPERABLE Channels per Trip System requirement for both trip systems, place at least one trip system"" i~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 /> and take the ACTION requir Table 3.3.1-1.
SURVEILLANCE REQUIREMENTS 4.3.'
1 Each reactor protection s s~ instrumentat-;an channe'1 shall be demonstrated OPERABLE by the per nce of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST and CHANNEL CA/
ION operations fov the OPERATIONAL CONDITIONS and at the frequen ~ shown in Table 4.3.1.1-1.
4.3.1.2 LOGIC SYSTEM FUN L TESTS and simulated automatic operation of all channels shall be perfo
,ed at least once pev 18 months.
4.3.1.3 The REACTOR PROTECTION SYSTEM RFSPONSE TIME of each, reactor trip functional unit sho~n in Table 3.3. 1-2 shall be demonstrated to be within its limit at least once per 18 months.
Each test shall include at least one channel per trip system such that all channels are tested at least once every N-times 18 months where N is the total number of redundant channels in a speci:ic reactor trip system.
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"An inoperable channel need not be placed in the tripped condition where this would cause the Trip Function to occur.
In these
- cases, the inoperable channel shall be restored to OPERABLE status within
-hours ov he ACTION.
required by Table 3.3. 1"1 for that Trip Function shall be taken.
~If move channels are inoperable in one trip system than in the other, place the trip system with more inoperable channels in the tripped condition, except when this would cause the Trip Function,to occur.
MA HINGTON NUCLFAR - UNIT 2 3/4 3-1
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TABLE 3.3.1-1 (Continued)
REACTOR PROTECTION SYSTEM INSTRVMENTATION TABLE NOTATIONS (o
(a)
A channel may be placed fn'n inoperable status for up to 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> for required surveillance without placing the trip system fn the trspped condition provided at least one OPERABLE channel in the same trip system fs monitoring that parameter.
(b)
The "sho~ting links" shall be removed from the RPS circuftry prior to and during the time any control rod fs withdrawn" and shutdown margin demonstrations are being performed per Specification 3.10.3.
(c)
An APRM channel fs inoperable if there are less than 2 LPRM inputs per level or less than 14 RM inputs to an APRM channel.
(d)
This function shall bdwa()Comet ically bypassed when the reactor made switch is not in the Run positlpl'nd reactor pressuie s 1037 psig.
(e)
This function is not requ to be OPERABLE when the reactor pressure vessel head is removed per'fication 3.10. 1.
(f)
This function is not required gJg OPERABLE when PRIMARY CONTAINMENT INTEGRITY is not required.
(g)
Also actuates the standby gas treatment system.
(h)
With any control rod withdrawn.
Not gcable to control rods removed per Specification 3.9.10.1 or 3.9.10.2. IO+
(i)
This function shall be automatically bypassed when turbine first s age pressure is ( 163 psig, equivalent to THERMAL POWER less than 30K of RATED THERMAL POWER.
(j)
Also. ac vates the EOC-RPT system.
"Not;required for control rods removed per Specifica ion 3. Bs 10s1 or 3. Bs 10.2.
WASHINGTON NUCLEAR - UNIT 2 3/4 3-5
TABLE 4. 3. l.l-l REACTOR PROTECTIOtl SYSTEH IHSTRUIIEHTATION SURVEILLANCE RE UIREHENTS FUHCTIOtIAL UNIT Ct IAHIIEL CIIECK CINNNEL OPERATIONAL FUtICTIOIPAL CHANtIEL
)
CONDITIONS FOR WHICH TEST CALIBRATION SURVEILLANCE RE UIRED 1.
Intermediate Range Honitors:
a.
Neutron Flux - High S/U(b),
S S/U(c),
W S
W H.A.
W 2
3, 4, 5
b.
Inoperative Average Power Range llonitor(f).
a.
tteutron Flux-
- Upscale, Setdown H.A.
2, 3, 4, 5
2.
2 3,
5 b.
Flow Biased Simulated Thermal Power - Upscale S,D(g)
S/U(b+
S/U(c),
W SA Sl(tg II(d)(d), SA, II(h) 1 c.
Fixed tteutron Flux-Upscale d.
Inoperative 3.
Reactor Vessel Steam Dome Pressure
- High 4.
Reacto>
Vessel Water Level-Low, Level 3
5.
Iiain Si.earn Line Isolation Valve - Closure 6.
Hain Si,earn Line Radiation High 7.
Primary Containment Pressure
- High N.A.
tt.A.
tl.A.
S/U(,
/OI d),
- -A.
1, 2, 3, 5
1 2
1, 2
1, 2(i) 1, 2
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1 I
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k
TABLE 4. 3. 1. 1-1 (Continued)
IIEACTOR RROTECI'IOII SYSTEII INSTIIIIHENTATIONSURVEILLANCE RE UIREHEHTS FUNCTIONAL UNIT Scram Discharge Volume Water Level - Iligh a.
Level Transmitter b.
Float switch CIIANtIEL CIIECK tl.h.
N.h.
Cllht<tIEL FUWCTIOtIAL TEST CI IhtINEL CALIBRATIOW R
OPfRATIONAL CONDITIONS FOR WIIICII SURVEILLhtICE RE UIRED 1,. 2, 5(j) 1, 2, 5(j)
Turbine Thr o ttle Va 1ve-Closure 10.
Turbine Governor Valve Fast Closure Valve Trip System Oil Pressure
- Low ll.
Reactor Mode Switch.
Shutdown Position 12.
Manual Scram N.A.
W.A.
W.h.
R N A.
UI 1, 2, 3, 4, 5
1, 2, 3, 4, 5
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3/4. 3 IHSTRUMEHTATION BASES 3/4.3.1 REACTOR PROTECTION SYSTEM INSTRUMENTATION The reactor protection system automatically initiates a reactor scram to:
a.
Preserve the integrity of the fuel cladding.
b.
Preserve the integrity of the reactor coolant system.
c.
Minimize the energy which must be adsorbed following a loss-of-coolant
- accident, and d.
Prevent inadvertent criticality.
This specification provides the 1imiti+conditions for operation necessary to preserve the ability of the system to orm its intended function even during periods when instrument channels e out of service because of main-tenance.
When necessary, one channel m
e made inoperable for brief intervals to conduct required surveillance.
The reactor protection system~%ado up of two independent trip systens.
There are usually four channels
~nitor each parameter with two channels in each trip system.
The outputs e channels-in a trip system are combined in a logic so that either ch will trip that trip system.
The tripping of both trip systems will prod reactor scram.
The system meets the intent of IEEE-279 for nuclear p
lant protection systems.
The bases for the tri settings of the RPS are d
ssed in the bases for Specification 2.2. 1.
The measurement of response time't the specified frequencies provides assurance that the protective functions associated with each channel are com-pleted within the time limit assumed in the safety analyses.
Ho credit was taken for those channels with response times indicated as not applicable.
Response
time may be demonstrated by any series of sequential, overlapping or total channel test measurement, provided such tests demonstrate the total channel response time as defined.
Sensor response time verification may be demonstrated by either (1) inplace, onsite or offsite test measurements, or (2) utilizing replacement sensors with certified response times.
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