ML21305B825
| ML21305B825 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick |
| Issue date: | 11/01/2021 |
| From: | Kelly D Exelon Nuclear Generation Corp |
| To: | Brian Fuller Division of Operating Reactors |
| Fuller B | |
| Shared Package | |
| ML20275A095 | List: |
| References | |
| CY-JF-170-301 Revision 1, EPID: L-2021-OLL-0000 | |
| Download: ML21305B825 (24) | |
Text
Reactivity Anomalies 3.1.2 JAFNPP 3.1.2-1 Amendment 325 3.1 REACTIVITY CONTROL SYSTEMS 3.1.2 Reactivity Anomalies LCO 3.1.2 The reactivity difference between the measured core keff and the predicted core keff shall be within +/- 1% k/k.
APPLICABILITY: MODES 1 and 2 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
Core reactivity difference not within limit.
A.1 Reactor core reactivity difference to within limit.
72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> B.
Required Action and associated Completion Time not met.
B.1 Be in MODE 3.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />
Reactivity Anomalies 3.1.2 JAFNPP 3.1.2-2 Amendment 325 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.2.1 Verify core reactivity difference between the measured core keff and the predicated core keff is within +/- 1% k/k Once within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after reaching equilibrium conditions following startup after fuel movement within the reactor pressure vessel or control rod replacement AND 1000 MWD/T thereafter during operations in MODE 1
SLC System 3.1.7 JAFNPP 3.1.7-1 Amendment 338 3.1 REACTIVITY CONTROL SYSTEMS 3.1.7 Standby Liquid Control (SLC) System LCO 3.1.7 Two SLC subsystems shall be OPERABLE APPLICABILITY:
MODES 1, 2, and 3.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
One SLC subsystem inoperable.
A.1 Restore SLC subsystem to OPERABLE status.
7 days B.
Two SLC subsystems inoperable.
B.1 Restore one SLC subsystem to OPERABLE status.
8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> C.
Required Action and associated Completion Time not met.
C.1 Be in MODE 3.
AND C.2 Be in MODE 4.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 36 hours
SURVEILLANCE REQUIREMENTS SR 3.1.7.1 SR 3.1.7.2 SR 3.1.7.3 SR 3.1.7.4 JAFNPP SURVEILLANCE Verify available volume of sodium pentaborate solution is within the limits of Figure 3.1.7-1.
Verify temperature of sodium pentaborate solution is within the limits of Figure 3.1.7-2.
Verify temperature of pump suction piping is within the limits of Figure 3.1.7-2.
Verify continuity of explosive charge.
3.1.7-2 SLCSystem 3.1.7 FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Su rveilla nee Frequency Control Program In accordance with the Surveillance Frequency Control Program (continued)
Amendment 301 I
SURVEILLANCE REQUIREMENTS (continued)
SR 3.1.7.5 SR 3.1.7.6 SR 3.1.7.7 SR 3.1.7.8 JAFNPP SURVEILLANCE Verify the concentration of sodium pentaborate in solution is within the limits of Figure 3.1. 7-1.
Verify each SLC subsystem manual valve in the flow path that is not locked, sealed, or otherwise secured in position is in the correct position, or can be aligned to the correct position.
Verify each pump develops a flow rate~ 50 gpm at a discharge pressure ~ 1275 psig.
Verify flow through one SLC subsystem from pump into reactor pressure vessel.
3.1.7-3 SLC System 3.1.7 FREQUENCY In accordance with the Surveillance Frequency Control Program Once within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after water or sodium pentaborate is added to solution Once within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after solution temperature is restored within the limits of Figure 3.1.7-2 In accordance with the Surveillance Frequency Control Program In accordance with the lnservice Testing Program In accordance with the Surveillance Frequency Control Program (continued)
Amendment 301 I
SURVEILLANCE REQUIREMENTS (continued)
SR 3.1.7.9 SR 3.1.7.10 SR 3.1.7.11 JAFNPP SURVEILLANCE Verify all heat traced piping between storage tank and pump suction is unblocked.
Verify sodium pentaborate enrichment is~ 34. 7 atom percent B-10.
Verify sodium pentaborate enrichment in solution in the SLC tank is~ 34.7 atom percent B-10.
3.1.7-4 SLC System 3.1.7 FREQUENCY In accordance with the Surveillance Frequency Control Program Once within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after piping temperature is restored within the limits of Figure 3.1.7-2 Prior to addition to SLC tank In accordance with the Surveillance Frequency Control Program Amendment 301 I
I!
14 SLC System 3.1. 7 (4724gal. 13%)
.8 (2200gal, 13%)
J!
13 c
C>>
a.. e c *=
12 0,,
0
~ Cl)
.b,,
c C>>
G>.c 11 CJ CJ c *-
0 0 ifi 0
10 c
C>>
~
Cl a..
9
.c
~
REGION OF REQUIRED VOLUME AND CONCENTRATION (2850gal, 10%)
(4724gal, 10%)
a... ____ __..._ ____ -+ ______....., ______ t-____ _. ______
~
2000 JAFNPP 3000 4000.
Net Volume of Solution in Tank (gal)
Figure 3.1.7-1 (page 1of1)
Sodium Pentaborate Solution Volume Versus Concentration Requirements 3.1.7-5 5000 Amendment 274
90
- u.
UJ e 80 C>>
Q)
"O -
e?
70
=..
l!
CD a.
E 60 CD
~
50 6
-ACCEPT BLE-
-UNA CC PT ABLE-8 10 12 14 16 18 Concentration (Weight Percent Enriched Sodium Pentaborate)
Figure 3.1.7-2 (page 1 of 1)
Sodium Pentaborate Solution Temperature Versus Concentration Requirements SLC System 3.1. 7 20 3.1.7-6 Amendment 274
3.2 POWER DISTRIBUTION LIMITS 3.2.1 AVERAGE PLANAR LINEAR HEAT GENERATION RATE {APLHGR)
APLHGR 3.2.1 LCO 3.2.1 All APLHGRs shall be less than or equal to the limits specified in the COLR.
APPLICABILITY:
THERMAL POWER ~ 25% RTP.
ACTIONS CONDITION REQUIRED ACTION A. Any APLHGR not within A.1 Restore APLHGR(s) to limits.
within limits.
B. Required Action and 8.1 Reduce THERMAL POWER associated Completion to< 25% RTP.
Time not met.
SURVEILLANCE REQUIREMENTS SR 3.2.1.1 JAFNPP SURVEILLANCE Verify all APLHGRs are less than or equal to the limits specified in the COLR.
3.2.1-1 COMPLETION TIME 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 4 hours FREQUENCY Once within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after
~25% RTP In accordance with the Surveillance Frequency Control Program Amendment 301 I
3.2 POWER DISTRIBUTION LIMITS 3.2.2 MINIMUM CRITICAL POWER RATIO (MCPR)
MCPR 3.2.2 LCO 3.2.2 All MCPRs shall be greater than or equal to the MCPR operating limits specified in the COLR.
APPLICABILITY:
THERMAL POWER ~ 25% RTP.
ACTIONS CONDITION REQUIRED ACTION A. Any MCPR not within limits.
A.1 Restore MCPR(s) to within limits.
B. Required Action and B.1 Reduce THERMAL POWER associated Completion Time to< 25% RTP.
not met.
SURVEILLANCE REQUIREMENTS SURVEILLANCE SR 3.2.2.1 JAFNPP Verify all MCPRs are greater than or equal to the limits specified in the COLR.
3.2.2-1 COMPLETION TIME 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 4 hours FREQUENCY Once within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after
~ 25% RTP In accordance with the Surveillance Frequency Control Program (continued)
Amendment 301 I
SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE SR 3.2.2.2 Determine the MCPR limits.
JAFNPP 3.2.2-2 MCPR 3.2.2 FREQUENCY Once within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after each completion of SR 3.1.4.1 AND Once within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after each completion of SR 3.1. 4. 2 AND Once within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> after each completion of SR 3.1.4.4 Amendment 274
3.2 POWER DISTRIBUTION LIMITS 3.2.3 LINEAR HEAT GENERATION RATE (LHGR)
LHGR 3.2.3 LCO 3.2.3 All LHGRs shall be less than or equal to the limits specified in the COLR.
APPLICABILITY:
THERMAL POWER ~ 25% RTP.
ACTIONS CONDITION REQUIRED ACTION A. Any LHGR not within limits.
A.1 Restore LHGR(s) to within limits.
B. Required Action and B.1 Reduce THERMAL associated Completion POWER to < 25% RTP.
Time not met.
SURVEILLANCE REQUIREMENTS SURVEILLANCE SR 3.2.3.1 JAFNPP Verify all LHGRs are less than or equal to the limits specified in the COLR.
3.2.3-1 COMPLETION TIME 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> 4 hours FREQUENCY Once within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after
~25% RTP In accordance with the Surveillance Frequency Control Program Amendment 301 I
RPS Instrumentation 3.3.1.1 JAFNPP 3.3.1.1-1 Amendment 324 3.3 INSTRUMENTATION 3.3.1.1 Reactor Protection System (RPS) Instrumentation LCO 3.3.1.1 The RPS instrumentation for each Function in Table 3.3.1.1-1 shall be OPERABLE.
APPLICABILITY:
According to Table 3.3.1.1-1.
ACTIONS
- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - NOTE- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
- 1.
Separate Condition entry is allowed for each channel.
- 2.
When Functions 2.b and 2.c channels are inoperable due to the calculated power exceeding the APRM output by more than 2% RTP while operating at 25% RTP, entry into associated Conditions and Required Actions may be delayed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
CONDITION REQUIRED ACTION COMPLETION TIME A. One or more required channels inoperable.
A.1 Place channel in trip.
OR A.2 Place associated trip system in trip.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 12 hours B. One or more Functions with one or more required channels inoperable in both trip systems.
B.1 Place channel in one trip system in trip.
OR B.2 Place one trip system in trip.
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> 6 hours (continued)
ACTIONS (continued)
CONDITION
- c. One or more Functions C.l with RPS trip capability not maintained.
D.
Required Action and D.l associated Completion Time of Condition A.
B. or C not met.
E.
As required by E.1 Required Action D.l and referenced in Table 3.3.1.1-1.
F.
As required by F.1 Required Action D.1 and referenced in Table 3.3.1.1-1.
G.
As required by G.l Required Action D.1 and referenced in Table 3.3.1.1-1.
H.
As required by H.1 Required Action D.1 and referenced in Table 3.3.1.1-1.
JAFNPP REQUIRED ACTION Restore RPS trip capability.
Enter the Condition referenced in Table 3.3.1.1-1 for the channel.
Reduce THERMAL POWER to< 29% RTP.
Be in MODE 2.
Be in MODE 3.
Initiate action to fully insert all insertable control rods in core cells containing one or more fuel assemblies.
3.3.1.1-2 RPS Instrumentation 3.3.1.1 COMPLETION TIME 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Immediately 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 6 hours 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Immediately Amendment 274
RPS Instrumentation 3.3.1.1 JAFNPP 3.3.1.1-3 Amendment 324 SURVEILLANCE REQUIREMENTS
- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - NOTES- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
- 1.
Refer to Table 3.3.1.1-1 to determine which SRs apply for each RPS Function.
- 2.
When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> provided the associated Function maintains RPS trip capability.
SURVEILLANCE FREQUENCY SR 3.3.1.1.1 Perform CHANNEL CHECK.
In accordance with the Surveillance Frequency Control Program SR 3.3.1.1.2
- - - - - - - - - - - - - - - - NOTE- - - - - - - - - - - - - - - - - - -
Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after THERMAL POWER 25% RTP.
Verify the calculated power does not exceed the average power range monitor (APRM) channels by greater than 2% RTP while operating at 25% RTP.
In accordance with the Surveillance Frequency Control Program SR 3.3.1.1.3
- - - - - - - - - - - - - - - - NOTE- - - - - - - - - - - - - - - -
Not required to be performed when entering MODE 2 from MODE 1 until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after entering MODE 2.
Perform CHANNEL FUNCTIONAL TEST.
In accordance with the Surveillance Frequency Control Program SR 3.3.1.1.4 Perform a functional test of each RPS automatic scram contactor.
In accordance with the Surveillance Frequency Control Program (continued)
SURVEILLANCE REQUIREMENTS (continued)
SR 3.3.1.1.5 SR 3.3.1.1.6 SR 3.3.1.1. 7 SR 3.3.1.1.8 SR 3.3.1.1.9 JAFNPP SURVEILLANCE Verify the source range monitor (SRM) and intermediate range monitor (IRM) channels overlap.
- - - - - - - - - - - - - - - - - - - - - NOTE - - - - - - - - - - - - - - - - - - -
Only required to be met during entry into MODE 2 from MODE 1.
Verify the I RM and APRM channels overlap.
Calibrate the local power range monitors.
Perform CHANNEL FUNCTIONAL TEST.
NOTE-------------------
- 1. Neutron detectors are excluded.
- 2. For Functions 1.a and 2.a, not required to be performed when entering MODE 2 from MODE 1 until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after entering MODE 2.
- 3. For Function 2.b, the recirculation loop flow signal portion of the channel is excluded.
Perform CHANNEL CALIBRATION.
3.3.1.1-4 RPS Instrumentation 3.3.1.1 FREQUENCY Prior to fully withdrawing SRMs In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program (continued)
Amendment 301 I
SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE SR 3.3.1.1.10 Calibrate the trip units.
SR 3.3.1.1.11 Perform CHANNEL FUNCTIONAL TEST.
SR 3.3.1.1.12
NOTE-------------------
For Function 2.b, all portions of the channel except the recirculation loop flow signal portion are excluded.
~------------------
Perform CHANNEL CALIBRATION.
SR 3.3.1.1.13 Perform LOGIC SYSTEM FUNCTIONAL TEST.
SR 3.3.1.1.14 Verify Turbine Stop Valve-Closure and Turbine Control Valve Fast Closure, EHC Oil Pressure-Low Functions are not bypassed when THERMAL POWER is
~ 29% RTP.
SR 3.3.1.1.15
NOTE-------------------
- 1. Neutron detectors are excluded.
- 2. nn" equals 2 channels for the purpose of determining the STAGGERED TEST BASIS Frequency.
*--~----------------------
Verify the RPS RESPONSE TIME is within limits.
JAFNPP RPS Instrumentation 3.3.1.1
, -"""cr11v Y In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program Amendment 301 I
RPS Instrumentation 3.3.1.1 Table 3.3.1.1-1 (page 1 of 3)
Reactor Protection System Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER TRIP REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS SYSTEM ACTION D.1 REQUIREMENTS VALUE
- 1.
- a.
Neutron Flux - High 2
3 G
SR 3.3.1.1.1 s 120/125 SR 3.3.1.1.3 divisions of SR 3.3.1.1.4 full scale SR 3.3.1.1.5 SR 3.3.1.1.6 SR 3.3.1.1.9 SR 3.3.1.1.13 5(a) 3 H
SR 3.3.1.1.1 s 1201125 SR 3.3.1.1.3 divisions of SR 3.3.1.1.4 full scale SR 3.3.1.1.9 SR 3.3.1.1.13
- b.
Inop 2
3 G
SR 3.3.1.1.3 NA SR 3.3.1.1.4 SR 3.3.1.1.13 5(a) 3 H
SR 3.3.1.1.3 NA SR 3.3.1.1.4 SR 3.3.1.1.13
- 2.
Average Power Range Monitors
- a.
Neutron Flux - High, 2
2 G
SR 3.3.1.1.1 s 15.%' RTP (Startup)
SR 3.3.1.1.3 SR 3.3.1.1.4 SR 3.3.1.1.6 SR 3.3.1.1.7 SR 3.3.1.1.9 SR 3.3.1.1.13
- b.
Neutron Flux-High 1
2 F
SR 3.3.1.1.1 As s~ecified (Fl ow Biased)
SR 3.3.1.1.2 in t e COLR SR 3.3.1.1.4 and s 117.%' RTP SR 3.3.1.1.7 SR 3.3.1.1.8 SR 3.3.1.1.9 SR 3.3.1.1.12 SR 3.3.1.1.13 SR 3.3.1.1.15 (continued)
(a) With any control rod withdrawn fran a core cell containing one or more fuel assemblies.
JAFNPP 3.3.1.1-6 Amendment 274
3.3 INSTRUMENTATION RPS Electric Power Monitoring 3.3.8.2 3.3.8.2 Reactor Protection System (RPS) Electric Power Monitoring LCO 3.3.8.2 Two RPS electric power monitoring assemblies shall be OPERABLE for each inservice RPS motor generator set or alternate power supply.
APPLICABILITY:
MODES 1 and 2.
MODES 3. 4. and 5 with any control rod withdrawn from a core cell containing one or more fuel assemblies.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
One or both inservice A.l Remove associated 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> power supplies with inservice power one electric power supply(s) from monitoring assembly service.
- 8. One or both inservice B.l Remove associated 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> power supplies with inservice power both electric power supply(s) from monitoring assemblies service.
- c. Required Action and C.1 Be in MODE 3.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> associated Completion Time of Condition A or B not met in MODE 1 or 2.
(continued)
JAFNPP 3.3.8.2*1 Amendment 274
RPS Electric Power Monitoring 3.3.8.2 ACTIONS (continued)
CONDITION REQUIRED ACTION COMPLETION TIME D.
Required Action and D.1 associated Completion Initiate action to fully insert Immediately all insertable control rods Time of Condition A or B not in core cells containing one met in MODE 3, 4, or 5 with or more fuel assemblies.
any control rod withdrawn from a core cell containing one or more fuel assemblies.
SURVEILLANCE REQUIREMENTS SURVEILLANCE SR 3.3.8.2.1 JAFNPP
NOTE--------------------
Only required to be performed prior to entering MODE 2 from MODE 3 or 4, when in MODE 4 for
~ 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Perform CHANNEL FUNCTIONAL TEST.
3.3.8.2-2 FREQUENCY In accordance with the Surveillance Frequency Control Program (continued)
Amendment 3011
RPS Electric Power Monitoring 3.3.8.2 SURVEILLANCE REQUIREMENTS (continued)
SR 3.3.8.2.2 SR 3.3.8.2.3 SR 3.3.8.2.4 JAFNPP SURVEILLANCE Perform CHANNEL CALIBRATION of the electric power monitoring assemblies associated with the inservice RPS motor generator sets. The Allowable Values shall be:
- a.
Overvoltage ~ 132 V, with time delay set to s 4 seconds.
- b.
Undervoltage ~ 112.5 V for RPS bus A and ~
113.9 V for RPS bus B, with time delay set to ~
4 seconds.
- c.
Underfrequency ~ 57 Hz, with time delay set to s 4 seconds.
Perform CHANNEL CALIBRATION of the electric power monitoring assemblies associated with the inservice alternate power supplies. The Allowable Values shall be:
- a.
Overvoltage ~ 132 V, with time delay set to~ 4 seconds.
- b.
Undervoltage ~ 109.9 V, with time delay set to
~ 4 seconds.
- c.
Underfrequency ~ 57 Hz, with time delay set to s 4 seconds.
Perform a system functional test.
3.3.8.2-3 FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program Amendment 301 I
CY-JF-170-301 Revision 1 JAF ODCM, PART 1 Page 14 of 139
- 2.
RADIOACTIVE EFFLUENT CONTROLS 2.1.
LIQUID EFFLUENT MONITORS 2.1.1.
Control The radioactive liquid effluent monitoring instrumentation channels shown in Table 2.1-1 shall be OPERABLE with their alarm/trip setpoints set to ensure that the limits of Control 2.2.1 are not exceeded. The alarm/trip setpoints of these channels shall be determined in accordance with the OFFSITE DOSE CALCULATION MANUAL(ODCM).
2.1.2. Applicability
At all times.
Applies to the instrumentation required for monitoring radioactive liquid effluent discharges to the environment as specified in Table 2.1-1.
2.1.3.
ACTIONS
- 1.
The limiting conditions for operation of the instruments that monitor radioactive liquid effluents are given in Table 2.1-1. With a radioactive liquid effluent monitoring instrumentation channel alarm/trip set point less conservative than required by the ODCM (Part 2, Section 11.3), without delay suspend the release of radioactive liquid effluents monitored by the affected channel, or declare the channel INOPERABLE, or change the set point so it is acceptably conservative.
- 2.
With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 2.1-1. Take corrective actions to return the instruments to OPERABLE status within 30 days and, if unsuccessful, explain in the next Annual Radioactive Effluent Release Report why the INOPERABILITY was not corrected in a timely manner.
2.1.4. Surveillance Requirements
- 1.
Applicability Applies to the instrumentation for monitoring radioactive liquid effluent discharges.
- 2.
Objective To ensure that instrumentation required for radioactive liquid effluent discharges are maintained and calibrated.
- 3.
Specifications A.
The alarm/trip set points of these channels shall be determined and adjusted in accordance with the methodology and parameters in the ODCM (Part 2, Section 11.3).
B.
The surveillance requirements for the radioactive liquid effluent monitoring instrumentation is shown on Table 2.1-2.
7/20
CY-JF-170-301 Revision 1 JAF ODCM, PART 1 Page 15 of 139 2.1.5.
Bases The radioactive liquid effluent instrumentation is provided to monitor and control the releases of radioactive materials in liquid effluents during planned or unplanned releases. The alarm/trip set points for these instruments shall be calculated in accordance with methods in the ODCM (Part 2, Section 11.3) to ensure that the alarm/trip will occur prior to exceeding Part 1, Section 2.2.1 Control limits. The OPERABILITY and use of this instrumentation is consistent with the requirements of 10 CFR 50, Appendix A, General Design Criteria 60, 63, and 64.
TABLE 2.1-1 RADIOACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION Instrument Minimum Channels OPERABLE ACTION Gross radioactivity monitors providing alarm and automatic termination of release Liquid radwaste effluent line 1
(a)
Gross BETA or GAMMA radioactivity monitors providing alarm but not providing automatic termination of release Service water system effluent line 1
(b)
Flow rate measurement devices Liquid radwaste effluent line 1
(c)
NOTES FOR TABLE 2.1-1 (a)
With the number of OPERABLE channels less than the required minimum number, effluent releases may continue provided that prior to initiating a release:
- 1.
Two independent samples are analyzed;
- 2.
Two technically qualified members of the facility staff verify the discharge line valving; Otherwise, suspend release of radioactive effluents via this pathway.
(b)
With the number of OPERABLE channels less than the required minimum number, effluent releases in this pathway may continue provided that, at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, grab samples are collected and analyzed for principal GAMMA emitters at a limit of detection of at least 5x10-7 microcuries/ml. The principal GAMMA emitters for which the LLD specification applies exclusively are described in Note (c) to Table 2.2-1.
(c)
With the number of OPERABLE channels less than the required minimum number, effluent releases via this pathway may continue provided the flow rate is estimated at least once per four hours during actual releases. Pump curves or tank level decreases generated in situ may be used to estimate flow.
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CY-JF-170-301 Revision 1 JAF ODCM, PART 1 Page 16 of 139 TABLE 2.1-2 MINIMUM TEST AND CALIBRATION FREQUENCY FOR RADIATION MONITORING SYSTEMS(a)
INSTRUMENT CHANNELS CHANNEL CHECK(b)
CHANNEL FUNCTIONAL TEST(g)
CHANNEL CALIBRATION(g)
LOGIC SYSTEM FUNCTIONAL TEST(f)
Liquid Radwaste Discharge Monitor/Isolation(c)(d)(e)(f)
Daily When Discharging Quarterly Once per 18 months Once per 24 months Liquid Radwaste Discharge Radioactivity Recorder(d)
Daily Quarterly Once per 18 months Liquid Radwaste Discharge Flow Rate Measuring Devices(d)
Daily Quarterly Once per 18 months Normal Service Water Effluent Daily Quarterly Once per 18 months NOTES FOR TABLE 2.1-2 (a) Functional tests, calibrations and CHANNEL CHECKS need not be performed when these instruments are not required to be OPERABLE or are tripped.
(b) CHANNEL CHECKS shall be performed at least once per day during these periods when the instruments are required to be OPERABLE.
(c)
A SOURCE CHECK shall be performed prior to each release.
(d) Liquid radwaste effluent line instrumentation surveillance requirements need not be performed when the instruments are not required as the result of the discharge path not being utilized.
(e) An instrument CHANNEL CALIBRATION shall be performed with known radioactive sources standardized on plant equipment which has been calibrated with NIST traceable standards.
(f)
Simulated automatic actuation shall be performed once per 24 months. Simulated automatic actuation means applying a simulated signal to the sensor to actuate the circuit.
(g) A successful test of the required contact(s) of a channel relay may be performed by the verification of the change of state of a single contact of the relay. This clarifies what is an acceptable CHANNEL FUNCTIONAL TEST of a relay. This is acceptable because all of the other required contacts of the relay are verified by other Technical Specifications and non-Technical Specification tests at least once per refueling interval with the applicable extension.