ML17279A134
| ML17279A134 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 03/10/1987 |
| From: | WASHINGTON PUBLIC POWER SUPPLY SYSTEM |
| To: | |
| Shared Package | |
| ML17279A133 | List: |
| References | |
| TAC-64942, NUDOCS 8703180343 | |
| Download: ML17279A134 (4) | |
Text
9 Dm, ew'O G3
>Cl CIO
~
DM.
A4, XM'l
'8, OO OQ,
'01 ceo
<< /"
CA 6-I CO IHSTRtNEHTATIOH TABLE 3. 3. 7. 1-1 RA01ATION HONITORIHQ INSTRtlHEHTATIOH HINIHUli CIIAHNELS APPLICAOLE OPERABLE CONDITIONS ALARH/TRIP 5 El'POINT ACTION R
IlIl
~
~
Hain Control Rnnm Ventilation Radiation Honitor 2/intake 1,2,3,5 and "
< 5000 cpm 70 2.
Area Honitors a.
Cr iticality Honitors 1)
New Fuel Storage Vault 2)
Spent Fuel St,orage Pool
~ ~z/hqa)
.u PN
+0
<< 20 mR/h TAOLE N 71 71 4JIcn IO "When Lhe main condenser air evacuation sys is in operation.
NWlth fuel in the new fuel storage vault.
NIIWith fuel in the spent fuel'torage po (a)Alarm only.
Alarm setpoint set IAW 10 CFR 70. 24. a. l.
ACTIOH STATEHENTS ACTION 70 With one of the, required monitors inoperable, place the inoperable channel in the tripped condi Lion within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />; rest.ore the inoperable channel to. OPERABLE status within 7 days, or, within the next 6 hnurs, initiate anri maintain operation of the control room emergency filtration system in the pressurization mode of nperation.
ACTIOH 7l b.
With both of the rertuired monitors inoperable, initiate and maintain operation of the control room emergency filtration system in the pressurization mode of operation within lAiour.
Wit,h the required mnnitor inoperable, assure a portable continuous monitor with the same alarm setpoint is OPERAOLE in the vicinity of the installed monitor during any fuel movement.
If no fuel movement is being made, 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 />.
(n$,
4 s
- ) ~:
i'HSTRUMEHTATIOH BASES s
'.Ra P
't j v 5
A-
. ~
ks ~
r sl "
sv v
\\
~
m "s "
I f~m
\\
a si 3/4.3.5 REACTOR CORE ISOLATIOH COOLIHG SYSTEM ACTUATIOH IHSTRUMEHTATIOH The reactor core isolation cooling system actuation instrumentation is provided to initiate actions to assure adequate core cooling in the event of reactor isolation from its primary heat sink and the loss of feedwater flow to the reactor vessel without providing actuation of any of the emergency core cooling equipment.
Operation with a trip set less conservative than its Trip Setpoint but within its specified Allowable Value is acceptable on the basis that the difference between'ach Trip Setpoint and the Allowable Value is equal to or less than the drift allowance assumed for each trip in the safety analyses.
3/4.3.6 CONTROL ROO BLOCK IMSTRUMBHTATIOM The control rod block functions are p~
ed consistent with the require" ments of Specifications 3/4.1.4,-Control RocPProgram Controls, 3/4.2, Power Distribution Limits and 3/4.3.1 Reactor~otection System Instrumentation.
The trip logic is arranged so that a ~JR n any one of the inputs will result in a control rod block.
Operation with a trip set le @onser vative than its Trip Setpoint but within its specified Allowable V is acceptable on the basis that the difference between each Trip S nt and the Allowable Value is equal to 'or less than the drift allowanc@Rmmumed for each trip in the safety analyses.
3/4.3. 7 MONITORIHG IHSTRU~ATION 3/4. 3. 7. 1 RADIATION MONITORING IHSTRUMEHTATIOH The OPERABILITY of the radiation monitoring instrumentation ensures that; (1) the radiation levels are continually measured in the areas served by the individual channels; (2) the alarm or automatic action is initiated when the radiation level trip setpoint is exceeded; and (3) sufficient information is available on selected plant parameters to monitor an'd assess these variables following an accident.
This capability is consistent with 10 CFR Part 50, Appendix A, General Design Criteria 19, 41, 60, 61, 63, and 64..
3.4. 3. 7. 2 SEISMIC MONITORING INSTRUMENTATION The OPERABILITY of the seismic monitoring instrumentation ensures that sufficient capability is available to promptly determine the magnitude of a seismic event and evaluate the response of those features important to safety.
This capability. is required to permit comparison of the measured response to that used in the design basis for 'the unit.
This instrumentation is consistent with the recommendations of Regulatory Guide 1.12, "Instrumentation for Earthquakes,"
April 1974.
43 j
~
re.r 4
MASHIHGTOH NUCLEAR - UNIT 2 8 3/4 3"4
Insert b'1 to Technical Specification Section 3/4.3.7.1 (Bases)
The criticality monitor alarm setpoints were calculated using the criteria from 10CFR 70.24.a.l that requires detecting a dose rate of 20 Rads per minute of combined neutron and galena radiation at 2 meters.
The alarm setpoint was determined by calculational methods using the gamma to gamma plus, neutron ratios from ANSI/ANS 8.3-1979, Criticality Accident Alarm
- System, Appendix B and assuming a critical mass was formed from a seismic event, with a volume of 6' 6' 6't a distance of 27.7 feet from the two detectors.
The calculated dose rate using the methodology is 5.05 R/hr.
The allowable value for the alarm setpoint was, therefore, established at 5R/hr.
1i