ML19052A094
| ML19052A094 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 02/21/2019 |
| From: | Brian Fuller Operations Branch I |
| To: | Kelly D Exelon Generation Co |
| Shared Package | |
| ML18163A275 | List: |
| References | |
| CAC 0500 | |
| Download: ML19052A094 (41) | |
Text
Control Rod OPERABILITY 3.1.3 3.1 REACTIVITY CONTROL SYSTEMS 3.1.3 Control Rod OPERABILITY LCO 3.1.3 Each control rod shall be OPERABLE.
APPLICABILITY:
MODES 1 and 2.
ACTIONS
- * * * * * -* * * * * * * * * * -* * * -* * * * * * -* * * ----* NOTE -------------------------------. -... -
Separate Condition entry is allowed for each control rod.
CONDITION REQUIRED ACTION A.
One withdrawn control
NOTE---******-***
rod stuck.
Rod worth minimizer CRWM) may be bypassed as allowed by LCO 3.3.2.1. "Control Rod Block Instrumentation," if required, to allow continued operation.
A.l AND Verify stuck control rod separation criteria met.
COMPLETION TIME Immediately A.2 Disarm the associated 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> control rod drive CCRD).
AND (continued)
JAFNPP 3.1.3-1 Amendment 274
ACTIONS CONDITION A.
(continued)
A.3 AND A.4 B.
Two or more withdrawn B.1 control rods stuck.
- c.
One or more control rods C.1 inoperable for reasons other than Condition A or B.
AND C.2 JAFNPP REQUIRED ACTION Perform SR 3.1.3.2 for each withdrawn OPERABLE control rod.
Perform SR 3.1.1.1.
Be in MODE3.
- - - - - NOTE- - - - -
RWM may be bypassed as allowed by LCO 3.3.2.1, if required, to allow insertion of inoperable control rod and continued operation.
Fully insert inoperable control rod.
Disarm the associated CRD.
3.1.3-2 Control Rod Operability 3.1.3 COMPLETION TIME 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> from discovery of Condition A concurrent with THERMAL POWER greater than the low power setpoint (LPSP) of the RWM 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> 12 hours 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> 4 hours (continued)
Amendment 291
ACTIONS (continued)
CONDITION D.
NOTE ---------
Not applicable when THERMAL POWER
> 10% RTP.
Two or more inoperable control rods not in compliance with banked position withdrawal sequence CBPWS) and not separated by two or more OPERABLE control rods.
E. Required Action and associated Completion Time of Condition A, C, or D not met.
OR Nine or more control rods inoperable.
JAFNPP D.1 OR D.2 E.1 Control Rod OPERABILITY 3.1.3 REQUIRED ACTION COMPLETION TIME Restore compliance 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> with BPWS.
Restore control rod 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> to OPERABLE status.
Be in MODE 3.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 3.1.3-3 Amendment 274
Control Rod OPERABILITY 3.1.3 SURVEILLANCE REQUIREMENTS SR 3.1.3.1 SR 3.1.3.2 SR 3.1.3.3 SR 3.1.3.4 JAFNPP SURVEILLANCE Determine the position of each control rod.
- - - - - - - - - - - NOTE- - - - - - - - - - - - - - -
Not required to be performed until 31 days after the control rod is withdrawn and THERMAL POWER is greater than the LPSP of the RWM.
Insert each withdrawn control rod at least one notch.
Verify each control rod scram time from fully withdrawn to notch position 04 is ~ 7 seconds.
Verify each control rod does not go to the withdrawn overtravel position.
3.1.3-4 FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with SR 3.1.4.1, SR 3.1.4.2, SR 3.1.4.3, and SR 3.1.4.4 Each time the control rod is withdrawn to *full out* position Prior to declaring control rod OPERABLE after work on control rod or CRD System that could affect coupling Amendment 301 I
Control Rod Scram Times 3.1.4 3.1 REACTIVITY CONTROL SYSTEMS 3.1.4 Control Rod Scram Times LCO 3.1.4
- a.
No more than 10 OPERABLE control rods shall be "slow,"
in accordance with Table 3.1.4-1: and
- b.
No more than 2 OPERABLE control rods that are "slow" shall occupy adjacent locations.
APPLICABILITY:
MODES 1 and 2.
ACTIONS CONDITION A.
Requirements of the LCO not met.
SURVEILLANCE REQUIREMENTS A.l REQUIRED ACT! ON COMPLETION TIME Be in MODE 3.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />
NOTE -----------------* -------------------
During single control rod scram time Surveillances, the control rod drive CCRD) pumps shall be isolated from the associated scram accumulator.
SR 3.1.4.1 JAFNPP SURVEILLANCE Verify each control rod scram time is within the limits of Table 3.1.4-1 with reactor steam dome pressure ~ 800 psig.
3.1.4-1 FREQUENCY Prior to exceeding 40% RTP after each reactor shutdown
~ 120 days (continued)
Amendment 274
Control Rod Scram Times 3.1.4 SURVEILLANCE REQUIREMENTS (continued)
SR 3.1.4.2 SR 3.1.4.3 SR 3.1.4.4 JAFNPP SURVEILLANCE Verify, for a representative sample, each tested control rod scram time is within the limits of Table 3.1.4-1 with reactor steam dome pressure
~ 800 psig.
Verify each affected control rod scram time is within the limits of Table 3.1.4-1 with any reactor steam dome pressure.
Verify each affected control rod scram time is within the limits of Table 3.1.4-1 with reactor steam dome pressure ~ 800 psig.
3.1.4-2 FREQUENCY In accordance with the Surveillance Frequency Control Program Prior to declaring control rod OPERABLE after work on control rod or CRD System that could affect scram time Prior to exceeding 40% RTP after fuel movement within the affected core cell Prior to exceeding 40% RTP after work on control rod or CRD System that could affect scram time Amendment 301 I
Table 3.1.4-1 (page 1of1)
Control Rod Scram Times Control Rod Scram Times 3.1.4
- - - - - - - - - - - - - - - - - - - - - - - - - NOTES- -- - - - - - - - - - - - -- - - - - - - - - -
- 1.
OPERABLE control rods with scram times not within the limits of this Table are considered "slow."
- 2.
Enter applicable Conditions and Required Actions of LCO 3.1.3, "Control Rod OPERABILITY," for control rods with scram times> 7 seconds to notch position 04.
These control rods are inoperable, in accordance with SR 3.1.3.3, and are not considered "slow."
NOTCH POSITION 46 36 26 06 SCRAM TIMES (a) (b) when REACTOR STEAM DOME PRESSURE ~ 800 psig (seconds) 0.44 1.08 1.83 3.35 (a)
Maximum scram time from fully withdrawn position, based on de-energization of scram pilot valve solenoids at time zero.
(b)
Scram times as a function of reactor steam dome pressure, when < 800 psig, are within established limits.
JAFNPP 3.1.4-3 Amendment 291
3.1 REACTIVITY CONTROL SYSTEMS Control Rod Scram Accumulators 3.1.5 3.1.5 Control Rod Scram Accumulators LCO 3.1.5 Each control rod scram accumulator shall be OPERABLE.
APPLICABILITY:
MODES 1 and 2.
ACTIONS
* ------------------------NOTE -------------------------------------
Separate Condition entry is allowed for each control rod scram accumulator.
CONDITION REQUIRED ACTION COMPLETION TIME A.
One control rod scram A.1
NOTE ---------
accumulator inoperable Only applicable if with reactor steam the associated dome pressure control rod scram
- 1: 900 psig.
time was within the limits of Table 3.1.4-1 during the last scram time Surveillance.
Declare the 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> associated control rod scram time "slow."
OR A.2 Declare the 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> associated control rod inoperable.
(continued)
JAFNPP 3.1.5-1 Amendment 274
ACTIONS (continued)
CONDITION B.
Two or more control 8.1 rod scram accumulators inoperable with reactor steam dome pressure ~ 900 psig.
AND 8.2.1 OR 8.2.2
- c.
One or more control C.l rod scram accumulators inoperable with reactor steam dome pressure < 900 psig.
AND JAFNPP Control Rod Scram Accumulators 3.1.5 REQUIRED ACTION COMPLETION TIME Restore charging 20 minutes from water header pressure discovery of to ~ 940 psig.
Condition B concurrent with charging water header pressure
< 940 psig
NOTE ---------
Only applicable if the associated control rod scram time was within the limits of Table 3.1.4-1 during the last scram time Surveillance.
Declare the 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> associated control rod scram time "slow."
Declare the 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> associated control rod inoperable.
Verify all control Immediately upon rods associated with discovery of inoperable charging water accumulators are header pressure fully inserted.
< 940 psig (continued) 3.1.5-2 Amendment 274
Control Rod Scram Accumulators 3.1.5 ACTIONS (continued)
CONDITION REQUIRED ACTION C. (continued)
C.2 Declare the associated control rod inoperable.
D. Required Action B.1 or C.1 D.1
- - - - - - - NOTE- - - - - - - -
and associated Completion Not applicable if all Time not met.
inoperable control rod scram accumulators are associated with fully inserted control rods.
Place the reactor mode switch in the shutdown position.
SURVEILLANCE REQUIREMENTS SURVEILLANCE SR 3.1.5.1 JAFNPP Verify each control rod scram accumulator pressure is~ 940 psig.
3.1.5-3 COMPLETION TIME 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Immediately FREQUENCY In accordance with the Surveillance Frequency Control Program Amendment 301 I
3.3 INSTRUMENTATION 3.3.1.2 Source Range Monitor CSRM) Instrumentation SRM Instrumentation 3.3.1.2 LCO 3.3.1.2 The SRM instrumentation in Table 3.3.1.2-1 shall be OPERABLE.
APPLICABILITY:
According to Table 3.3.1.2-1.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
One or more required A.1 Restore required SRMs 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> SRMs inoperable in to OPERABLE status.
MODE 2 with intermediate range monitors CIRMs) on Range 2 or below.
B. Three required SRMs B.l Suspend control rod Immediately inoperable in MODE 2 withdrawal.
with IRMs on Range 2 or below.
- 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.
(continued)
JAFNPP 3.3.1.2-1 Amendment 274
ACTIONS (continued)
CONDITION D. One or more required SRMs D.1 inoperable in MODE 3 or 4.
AND D.2 E. One or more required SRMs E.1 inoperable in MODE 5.
AND E.2 SURVEILLANCE REQUIREMENTS REQUIRED ACTION Fully insert all insertable control rods.
Place reactor mode switch in the shutdown position.
Suspend CORE ALTERATIONS except for control rod insertion.
Initiate action to fully insert all insertable control rods in core cells containing one or more fuel assemblies.
SRM Instrumentation 3.3.1.2 COMPLETION TIME 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 1 hour Immediately Immediately
- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - NOTE - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
Refer to Table 3.3.1.2-1 to determine which SRs apply for each applicable MODE or other specified condition.
SURVEILLANCE SR 3.3.1.2.1 Perform CHANNEL CHECK.
JAFNPP 3.3.1.2-2 FREQUENCY In accordance with the Surveillance Frequency Control Program (continued)
Amendment 301 I
SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE SR 3.3.1.2.2
NOTE-------------------
SRM Instrumentation 3.3.1.2 FREQUENCY
- 1. Only required to be met during CORE ALTERATIONS.
SR 3.3.1.2.3 SR 3.3.1.2.4 JAFNPP
- 2. One SRM may be used to satisfy more than one of the following.
Verify an OPERABLE SRM detector is located in:
- a. The fueled region;
- b. The core quadrant where CORE ALTERATIONS are being performed, when the associated SRM is included in the fueled region; and
- c. A core quadrant adjacent to where CORE ALTERATIONS are being performed, when the associated SRM is included in the fueled region.
Perform CHANNEL CHECK.
NOTE-------------------
Not required to be met with less than or equal to four fuel assemblies adjacent to the SRM and no other fuel assemblies in the associated core quadrant.
Verify count rate is~ 3.0 cps with a signal to noise ratio~ 2:1.
3.3.1.2-3 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 REQUIRMENTS (continued)
SR 3.3.1.2.5 SR 3.3.1.2.6 SR 3.3.1.2.7 JAFNPP SURVEILLANCE
NOTE-------------------
The determination of signal to noise ratio is not required to be met with less than or equal to four fuel assemblies adjacent to the SRM and no other fuel assemblies in the associated core quadrant.
Perform CHANNEL FUNCTIONAL TEST and determination of signal to noise ratio.
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 IRMs on Range 2 or below.
Perform CHANNEL FUNCTIONAL TEST and determination of signal to noise ratio.
- - - - - - - - - - - - - - - - - - - - - NOTE - - - - - - - - - - - - - - - - - - -
- 1. Neutron detectors are excluded.
- 2. 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 IRMs on Range 2 or below.
Perform CHANNEL CALIBRATION.
3.3.1.2-4 SRM Instrumentation 3.3.1.2 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
FUNCTION
- 1.
Source Range Monitor (a)
With IRMs on Range 2 or below.
Table 3.3.1.2-1 (page 1 of 1)
Source Range Monitor Instrumentation APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS 3,4 5
REQUIRED CHANNELS 3
2 SRM Instrumentation 3.3.1.2 SURVEILLANCE REQUIREMENTS SR 3.3.1.2.1 SR 3.3.1.2.4 SR 3.3.1.2.6 SR 3.3.1.2.7 SR 3.3.1.2.3 SR 3.3.1.2.4 SR 3.3.1.2.6 SR 3.3.1.2.7 SR 3.3.1.2.1 SR 3.3.1.2.2 SR 3.3.1.2.4 SR 3.3.1.2.5 SR 3.3.1.2.7 (b)
Only one SRM channel is required to be OPERABLE during spiral offload or reload when the fueled region includes only that SRM detector.
(c)
Special movable detectors may be used in place of SRMs if connected to normal SRM circuits.
JAFNPP 3.3.1.2-5 Amendment 274
3.3 INSTRUMENTATION Control Rod Block Instrumentation 3.3.2.1 3.3.2.l Control Rod Block Instrumentation LCO 3.3.2.l The control rod block instrumentation for each Function in Table 3.3.2.1-1 shall be OPERABLE.
APPLICABILITY:
According to Table 3.3.2.1-1.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
One rod block monitor A.l Restore RBM channel 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> (RSM) channel to OPERABLE status.
B.
Required Action and B.1 Place one RBM channel 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> associated Completion in trip.
Time of Condition A not met.
OR Two RBM channels inoperable.
- c.
Rod worth minimizer C.l Suspend control rod Immediately CRWM) inoperable movement except by during reactor scram.
startup.
OR (continued)
JAFNPP 3.3.2.1-1 Amendment 274
ACTIONS CONDITION
- c.
(continued)
D.
RWM inoperable during reactor shutdown.
JAFNPP Control Rod Block Instrumentation 3.3.2.1 REQUIRED ACTION COMPLETION TIME C.2.1.1 Verify ~ 12 rods Immediately withdrawn.
OR C.2.1.2 Verify by Immediately administrative methods that startup with RWM inoperable has not been performed in the current calendar year.
AND C.2.2 Verify movement of During control control rods is in rod movement compliance with banked position withdrawal sequence (BPWS) by a second licensed operator or other qualified member of the technical staff.
D.1 Verify movement of During control control rods is in rod movement compliance with BPWS by a second licensed operator or other qualified member of the technical staff.
(continued) 3.3.2.1-2 Amendment 274
Control Rod Block Instrumentation 3.3.2.1 ACTIONS (continued)
CONDITION E. One or more Reactor Mode Switch-Shutdown Position channels inoperable.
SURVEILLANCE REQUIREMENTS E.1 E.2 REQUIRED ACTION Suspend control rod withdrawal.
Initiate action to fully insert all insertable control rods in core cells containing one or more fuel assemblies.
COMPLETION TIME Immediately Immediately
- - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - NOTE - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -
- 1.
Refer to Table 3.3.2.1-1 to determine which SRs apply for each Control Rod Block Function.
- 2.
When an RBM 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 control rod block capability.
SR 3.3.2.1.1 SR 3.3.2.1.2 JAFNPP SURVEILLANCE Perform CHANNEL FUNCTIONAL TEST.
NOTE-------------------
Not required to be performed until 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after any control rod is withdrawn at ::5: 10% RTP in MODE 2.
Perform CHANNEL FUNCTIONAL TEST.
3.3.2.1-3 FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program Amendment 301 I
Control Rod Block Instrumentation 3.3.2.1 SURVEILLANCE REQUIREMENTS (continued)
SR 3.3.2.1.3 SR 3.3.2.1.4 SR 3.3.2.1.5 SR 3.3.2.1.6 JAFNPP SU RVEI LLAl\\ICE
NOTE-------------------
Not required to be performed until 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after THERMAL POWER is~ 10% RTP in MODE 1.
Perform CHANNEL FUNCTIONAL TEST.
NOTE-------------------
Neutron detectors are excluded.
Verify the RBM is not bypassed:
- a. When THERMAL POWER is~ 30% RTP; and
- b. When a peripheral control rod is not selected.
NOTE-------------------
- 1. Neutron detectors are excluded.
- 2. For Function 1.a, the recirculation loop flow signal portion of the channel is excluded.
Perform CHANNEL CALIBRATION.
Verify the RWM is not bypassed when THERMAL POWER is~ 10% RTP.
3.3.2.1-4 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 In accordance with the Surveillance Frequency Control Program (continued)
Amendment 301 I
Control Rod Block Instrumentation 3.3.2.1 SURVEILLANCE REQUIREMENTS {continued)
SR 3.3.2.1. 7 SR 3.3.2.1.8 SR 3.3.2.1.9 JAFNPP SURVEILLANCE
NOTE-------------------
Not required to be performed until 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after reactor mode switch is in the shutdown position.
Perform CHANNEL FUNCTIONAL TEST.
NOTE-------------------
For Function 1.a, all portions of the channel except the recirculation loop flow signal portion are excluded.
Perform CHANNEL CALIBRATION.
FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program Verify control rod sequences input to the RWM are in Prior to declaring conformance with BPWS.
RWM OPERABLE following loading of sequence into RWM 3.3.2.1-5 Amendment 301 I
Control Rod Block Instrumentation 3.3.2.1 FUNCTION
- 1. Rod Block Monitor
- a. Upscale
- b. Inop
- c. Downscale
- 2. Rod Worth Mini*izer
- 3. Reactor Mode Switch - Shutd~n Position Table 3.3.2.l*l (page 1 of 1)
Control Rod Block Instrumentation APPLICABLE MODES OR OT1£R SPECIFIED CONDITIONS (a)
(a)
Ca>
1 Cb),2Cb)
(C)
REQUIRED CHANNELS 2
2 2
1 2
(a)
THERMAL PCMER ~ 30t RTP and no peripheral control rod selected.
Cb)
With THERMAL ~ER ~ lOt RTP.
(c)
Reactor mode switch in the shutdown position.
JAFNPP 3.3.2.1-6 SlRVEILLANCE REQUIREMENTS SR 3.3.Z.l.4 SR 3.3.2.1.5 SR 3.3.2.1.8 SR 3.3.2.1.1 SR 3.3.2.1.4 SR 3.3.2.1.4 SR 3.3.2.1.5 SR 3.3.2.1.2 SR 3.3.2.1.3 SR 3.3.2.1.6 SR 3.3.2.1.9 SR 3.3.2.1.7 ALLCMABLE VALUE As sroli fi ed in the OLR NA
~ 2.5/125 divisions of full scale NA NA Amendment 274
Primary Containment Isolation Instrumentation 3.3.6.1 3.3 INSTRUMENTATION 3.3.6.1 Primary Containment Isolation Instrumentation LCO 3.3.6.1 The primary containment isolation instrumentation for each Function in Table 3.3.6.1-1 shall be OPERABLE.
APPLICABILITY:
According to Table 3.3.6.1-1.
ACTIONS
NOTES ------------------------------------
- 1. Penetration flow paths may be unisolated intermittently under administrative controls.
- 2. Separate Condition entry is allowed for each channel.
CONDITION REQUIRED ACT! ON COMPLETION TIME A.
One or more required A.1 Place channel in 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for channels inoperable.
trip.
Functions 2.a, 2.b, 2.d. 2.g, 5.e, 5. f, 6.b, 7.a, and 7.b AND 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for Functions other than Functions 2.a, 2.b, 2.d, 2.g, 5.e, 5. f, 6.b. 7.a. and 7.b B.
One or more Functions B.1 Restore isolation 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> with isolation capability.
capability not maintained.
(continued)
JAFNPP 3.3.6.1-1 Amendment 274
ACTIONS (continued)
CONDITION
- c. Required Action and associated Completion Time of Condition A or B not met.
D.
As required by Required Action C.1 and referenced in Table 3.3.6.1-1.
E.
As required by Required Action C.1 and referenced in Table 3.3.6.1-1.
F.
As required by Required Action C.l and referenced in Table 3.3.6.1-1.
G.
As required by Required Action C.l and referenced in Table 3.3.6.1-1.
JAFNPP Primary Containment Isolation Instrumentation 3.3.6.1 REQUIRED ACTION COMPLETION TIME C.l Enter the Condition Immediately referenced in Table 3.3.6.1-1 for the channel.
D.1 Isolate associated 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> main steam line CMSL).
OR D.2.1 Be in MODE 3.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> AND D.2.2 Be in MODE 4.
36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> E.1 Be in MODE 2.
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> F.l Isolate the affected 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> penetration flow path(s).
G.1 Isolate the affected 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> penetration flow path(s).
(continued) 3.3.6.1-2 Amendment 274
ACTIONS (continued)
CONDITION H.
Required Action and H.1 associated Completion Time of Condition F or AND G not met.
H.2 OR As required by Required Action C.l and referenced in Table 3.3.6.1-1.
I. As required by I.1 Required Action C.1 and referenced in Table 3.3.6.1-1.
OR I.2 J. As required by J.1 Required Action C.1 and referenced in Table 3.3.6.1-1.
OR J.2 JAFNPP Primary Containment Isolation Instrumentation 3.3.6.1 REQUIRED ACTION COMPLETION TIME Be in MODE 3.
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Be in MODE 4.
36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> Declare associated 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> standby liquid control subsystem CSLC) inoperable.
Isolate the Reactor 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> Water Cleanup System.
Initiate action to Immediately restore channel to OPERABLE status.
Initiate action to Immediately isolate the Residual Heat Removal CRHR)
Shutdown Cooling System.
3.3.6.1-3 Amendment 274
Primary Containment Isolation Instrumentation 3.3.6.1 SURVEILLANCE REQUIREMENTS
NOTES----------------------------------
- 1. Refer to Table 3.3.6.1-1 to determine which SRs apply for each Primary Containment Isolation 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 as follows: (a) for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for Functions 2.d, 2.g, 7.a, and 7.b; and (b) for up to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for Functions other than 2.d, 2.g, 7.a, and 7.b provided the associated Function maintains isolation capability.
SURVEILLANCE SR 3.3.6.1.1 Perform CHANNEL CHECK.
SR 3.3.6.1.2 Perform CHANNEL FUNCTIONAL TEST.
- - - - - - - - - - - - - - - - - - NOTE - - - - - - - - - - - - - - - - -
For Functions 1.f and 2.f, radiation detectors are excluded.
Perform CHANNEL CALIBRATION.
JAFNPP 3.3.6.1-4 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 (continued)
Amendment 301 I
Primary Containment Isolation Instrumentation 3.3.6.1 SURVEILLANCE REQUIREMENTS (continued)
SURVEILLANCE SR 3.3.6.1.4 Calibrate the trip units.
SR 3.3.6.1.5 Perform CHANNEL CALIBRATION.
SR 3.3.6.1.6 Calibrate the radiation detectors.
SR 3.3.6.1. 7 Perform LOGIC SYSTEM FUNCTIONAL TEST.
- - - - - - - - - - - - - - - - - - NOTE - - - - - - - - - - - - - - - - -
"n" equals 2 channels for the purpose of determining the STAGGERED TEST BASIS Frequency.
JAFNPP Verify the ISOLATION INSTRUMENTATION RESPONSE TIME is within limits.
3.3.6.1-5 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 In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program Amendment 301 I
Primary Containment Isolation Instrumentation 3.3.6.1 Table 3.3.6.1-1 (page 1 of 6)
Primary Containment Isolation Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER TRIP REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS SYSTEM ACTION C.1 REQUIREMENTS VALUE
- 1. Main Steam Line Isolation
- a.
Reactor Vessel Water 1.2,3 2
~ 18 inches Leve 1 - Low Low Low SR 3.3.6.1.2 (level 1)
SR 3.3.6.1.4 SR 3.3.6.1.5 SR 3.3.6.1.7 SR 3.3.6.1.8
- b.
2 E
~ 825 psig Pressure - Low SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.5 SR 3.3.6.1.7 SR 3.3.6.1.8
- c.
Main Steam Line 1.2,3 2 ~er D
SR 3.3.6.1.1 s 125.9 psid Flow-High M L SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.5 SR 3.3.6.1.7 SR 3.3.6.1.8
- d.
Condenser Vacuum - Low 1,
2 D
~ 8 inches 2<a>. 3(a)
SR 3.3.6.1.2 Hg vacuum SR 3.3.6.1.4 SR 3.3.6.1.5 SR 3.3.6.1.7
- e.
Main Steam Tunnel Area 1.2.3 8
D SR 3.3.6.1.1 s 195°F Temperature - High SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.5 SR 3.3.6.1.7
- f. Main Steam Line 1.2.3 2
F SR 3.3.6.1.1 s 3 times Radiation - High SR 3.3.6.1.3 Norma 1 Ful 1 SR 3.3.6.1.6 Power SR 3.3.6.1.7
Background
con 1nue (a) With any turbine stop valve not closed.
(b) Not used.
JAFNPP 3.3.6.1-6 Amendment 274
Primary Containment Isolation Instrumentation 3.3.6.1 Table 3.3.6.1-1 (page 2 of 6)
Primary Containment Isolation Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER TRIP REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS SYSTEM ACTION C.l REQUIREMENTS VALUE
- 2. Primary Containment Isolation
- a. Reactor Vessel Water 1.2,3 2
~ 177 inches Level - Low (Level 3)
SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.5 SR 3.3.6.1.7
- b.
Drywe 11 Pressure - High 1,2,3 2
H SR 3.3.6.1.1 s 2.7 psig SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.5 SR 3.3.6.1.7
- c. Containment 1,2,3 1
F SR 3.3.6.1.1 s 450 R/hr Radiation - High SR 3.3.6.1.2 SR 3.3.6.1.5 SR 3.3.6.1.7
- d.
Drywel l Pressure - High 1,2,3 2Cc)
F SR 3.3.6.1.1 s: 2. 7 psig SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.5 SR 3.3.6.1.7
- e. Reactor Vessel Water 1.2.3 2
~ 18 inches Level - Low Low Low SR 3.3.6.1.2 (level 1)
SR 3.3.6.1.4 SR 3.3.6.1.5 SR 3.3.6.1.7
- f. Main Steam Line 1,2,3 2
F SR 3.3.6.1.1 s 3 times Radiation - High SR 3.3.6.1.3 Normal Full SR 3.3.6.1.6 Power SR 3.3.6.1.7
Background
- g. Reactor Vessel Water 1,2,3 2Cc)
~ 177 inches Level - Low (Level 3)
SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.5 SR 3.3.6.1.7 cont1nu (b)
Not used.
(c) Only one trip system provided for each associated penetration.
JAFNPP 3.3.6.1-7 Amendment 274
Primary Containment Isolation Instrumentation 3.3.6.1 Table 3.3.6.1-1 (page 3 of 6)
Primary Containment Isolation Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER TRIP REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS SYSTEM ACTION C.l REQUIREMENTS VALUE
- 3.
High Pressure Coolant Injection (HPCI) System Isolation 1,2,3 1
F SR 3.3.6.1.1 s 168.24
- a.
HPCI Steam Line SR 3.3.6.1.2 inches of Flow-High SR 3.3.6.1.4 water dP SR 3.3.6.1.5 SR 3.3.6.1.7
- b.
HPCI Steam Supply Line 1.2.3 2
~ 61 psig and Pressure - Low SR 3.3.6.1.2 s 90 psig SR 3.3.6.1.4 SR 3.3.6.1.5 SR 3.3.6.1.7
- c.
HPCI Turbine 1.2.3 2
F SR 3.3.6.1.3 s 9.9 psig Exhaust Di~hragm SR 3.3.6.1.7 Pressure -
i gh
- d.
HPCI Steam Line 1,2,3 1
F SR 3.3.6.1.1 s 160°F Penetration (Drywell SR 3.3.6.1.2 Entrance) Area SR 3.3.6.1.4 Temperature - High SR 3.3.6.1.5 SR 3.3.6.1.7
- e.
HPCI Steam Line Torus 1,2,3 1
F SR 3.3.6.1.l s 160°F Roan Area SR 3.3.6.1.2 Temperature - High SR 3.3.6.1.4 SR 3.3.6.1.5 SR 3.3.6.1.7
- f.
RHR Heat Exchanger A 1.2.3 1
F SR 3.3.6.1.1 s 170°F Area Temperature - High SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.5 SR 3.3.6.1.7
- g.
RHR Heat Exchanger B 1.2.3 1
F SR 3.3.6.1.1 s 170°F Area Temperature - High SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.5 SR 3.3.6.1.7
- h.
RB Southwest Area of 1.2.3 1
F SR 3.3.6.1.1 s 144°F Elevation 272' SR 3.3.6.1.2 Temperature - High SR 3.3.6.1.4 SR 3.3.6.1.5 SR 3.3.6.1.7
- i. RB Southeast Area of 1,2,3 1
F SR 3.3.6.1.1 s 144°F Elevation 272' SR 3.3.6.1.2 Temperature - High SR 3.3.6.1.4 SR 3.3.6.1.5 SR 3.3.6.1.7 (continued)
JAFNPP 3.3.6.1-8 Amendment 274
Primary Containment Isolation Instrumentation 3.3.6.1 Table 3.3.6.1-1 (page 4 of 6)
Primary Containment Isolation Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER TRIP REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS SYSTEM ACTION C.1 REQUIREMENTS VALUE
- 3.
HPCI System Isolation (continued)
- j. HPCI Equipment Area 1.2.3 2
F SR 3.3.6.1.1 s 144°F Temperature - High SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.5 SR 3.3.6.1.7
- 4. Reactor Core Isolation Cooling (RCIC) System Isolation
- a.
RCIC Steam Line 1.2.3 1
F SR 3.3.6.1.1 s 272.26 inches Fl ow - High SR 3.3.6.1.2 of water dP SR 3.3.6.1.4 SR 3.3.6.1.5 SR 3.3.6.1.7
- b.
RCIC Steam Supply 1,2,3 2
)! 58 psig and Line Pressure - Low SR 3.3.6.1.2 s 93 psig SR 3.3.6.1.4 SR 3.3.6.1.5 SR 3.3.6.1.7
- c.
RCIC Turbine 1.2.3 2
F SR 3.3.6.1.3 s 5 psig Exhaust Diaphragm SR 3.3.6.1.7 Pressure - High
- d.
RCIC Steam Line 1.2.3 1
F SR 3.3.6.1.1 s 160°F Penetration (Drywell SR 3.3.6.1.2 Entrance) Area SR 3.3.6.1.4 Temperature - High SR 3.3.6.1.5 SR 3.3.6.1.7
- e.
RCIC Steam Line Torus 1.2.3 1
F SR 3.3.6.1.1 s 160°F Room Area SR 3.3.6.1.2 Temperature - High SR 3.3.6.1.4 SR 3.3.6.1.5 SR 3.3.6.1.7
- f. RCIC Equipment Area 1,2,3 2
F SR 3.3.6.1.1 s 144°F Temperature - High SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.5 SR 3.3.6.1.7 continue JAFNPP 3.3.6.1-9 Amendment 274
- 5.
- 6.
(d)
(e)
FUNCTION Reactor Water Cleanup (RWCU)
System Isolation
- a.
RWCU Suction Line Penetration Area Temperature - High
- b.
RWCU Pump Area Temperature - High
- c.
RWCU Heat Exchanger Room Area Temperature - High
- d.
SLC System Initiation
- e.
Low (Level 3)
- f.
Drywell Pressure - High Shutdown Cooling System Isolation
- a.
Reactor Pressure - High
- b.
Low (Level 3)
Primary Containment Isolation Instrumentation 3.3.6.1 Table 3.3.6.1-1 (page 5 of 6)
Primary Containment Isolation Instrumentation APPLICABLE REQUIRED CONDITIONS SURVEILLANCE ALLOWABLE MODES OR CHANNELS REFERENCED REQUIREMENTS VALUE OTHER PER TRIP FROM SPECIFIED SYSTEM REQUIRED CONDITIONS ACTION C.1 1,2,3 1
$ 144°F SR 3.3.6.1.7 1,2,3 1 per F
$ 165°F for Pump room SR 3.3.6.1.7 Room Aand $
175°Ffor Pump Room B 1,2,3 1
$ 155°f SR 3.3.6.1.7 1,2 2(d)
SR 3.3.6.1.7 NA 1,2,3 2
- 177 inches SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.5 SR 3.3.6.1.7 1,2,3 2
$ 2.7 psig SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.5 SR 3.3.6.1.7 1,2,3 1
$ 74 psig SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.5 SR 3.3.6.1.7 3,4,5 2(e)
- 177 inches SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.5 SR 3.3.6.1.7 (continued)
SLC System Initiation only inputs into one of the two trip systems and only isolates one valve in the RWCU suction and return line.
Only one trip system required in MODES 4 and 5 when RHR Shutdown Cooling System integrity maintained.
JAFNPP 3.3.6.1-10 Amendment 298
FUNCTION
- 7. Traversing Incore Probe System Isolation
- a. Reactor Vessel Water Level - Low (Level 3)
- b.
Drywel l Pressure - High JAFNPP Primary Containment Isolation Instrumentation 3.3.6.1 Table 3.3.6.1*1 (page 6 of 6)
Primary Containment Isolation Instrumentation APPLICABLE MODES OR OTHER SPECIFIED CONDITIONS 1.2,3 1.2.3 REQUIRED CHANNELS PER TRIP SYSTEM 2
2 CONDITIONS REFERENCED FROM REQUIRED ACTION C.l G
G 3.3.6.1-11 SURVEILLANCE REQUIREMENTS SR 3.3.6.1.l SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.5 SR 3.3.6.1.7 SR 3.3.6.1.1 SR 3.3.6.1.2 SR 3.3.6.1.4 SR 3.3.6.1.5 SR 3.3.6.1.7 ALLOWABLE VALUE
- I!: 177 inches s 2.7 psig Amendment 274
ECCS - Operating 3.5.1 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) AND REACTOR CORE ISOLATION COOLING (RCIC) SYSTEM 3.5.1 ECCS-Operating LCO 3.5.1 Each ECCS injection/spray subsystem and the Automatic Depressurization System (ADS) function of six safety/relief valves shall be OPERABLE.
APPLICABILITY:
MODE 1, MODES 2 and 3, except high pressure coolant injection (HPCI) and ADS valves are not required to be OPERABLE with reactor steam dome pressure ~ 150 psig.
ACTIONS
NOTE--------------------------------
LCO 3.0.4.b is not applicable to HPCI.
CONDITION REQUIRED ACTION COMPLETION TIME A.
One low pressure ECCS A.1 Restore low pressure 7 days injection/spray ECCS injection/spray subsystem inoperable.
subsystem(s) to OR OPERABLE status.
One low pressure coolant injection (LPCI) pump in both LPCI subsystems inoperable.
B.
Required Action and B.1 Bein MODE3.
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 not AND met.
B.2 Be in MODE4.
36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> (continued)
JAFNPP 3.5.1-1 Amendment 284
ACTIONS (continued)
CONDITION
- c.
HPCI System C.1 inoperable.
AND C.2 D.
HPCI System D.l inoperable.
AND OR Condition A entered.
D.2 E.
One required ADS valve E.1 inoperable.
F.
One required ADS valve F.1 inoperable.
AND OR Condition A entered.
F.2 JAFNPP REQUIRED ACTION Verify by administrative means RCIC System is OPERABLE.
Restore HPCI System to OPERABLE status.
Restore HPCI System to OPERABLE status.
Restore low pressure ECCS injection/spray subsystem(s) to OPERABLE status.
Restore required ADS valve to OPERABLE status.
Restore required ADS valve to OPERABLE status.
Restore low pressure ECCS injection/spray subsystem(s) to OPERABLE status.
3.5.1-2 ECCS-Operating 3.5.1 COMPLETION TIME Immediately 14 days 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> 72 hours 14 days 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> 72 hours (continued)
Amendment 274
ACTIONS (continued)
CONDITION REQUIRED ACTION G. Required Action and associated G.1 Be in MODE 3.
Completion Time of Condition C, D, E, or F not met.
AND QR G.2 Reduce reactor steam dome pressure to Two or more required ADS
- 150 psig.
valves inoperable.
H. Two or more low pressure ECCS H.1 Enter LCO 3.0.3.
injection/spray subsystems inoperable for reasons other than Condition A.
QR HPCI System and one or more required ADS valves inoperable.
SURVEILLANCE REQUIREMENTS SURVEILLANCE SR 3.5.1.1 JAFNPP Verify, for each ECCS injection/spray subsystem, the piping is filled with water from the pump discharge valve to the injection valve.
3.5.1-3 ECCS - Operating 3.5.1 COMPLETION TIME 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 36 hours Immediately FREQUENCY In accordance with the Surveillance Frequency Control Program (continued)
Amendment 301 I
SURVEILLANCE REQUIREMENTS (continued)
SR 3.5.1.2 SR 3.5.1.3 SR 3.5.1.4 SR 3.5.1.5 JAFNPP SURVEILLANCE
~~~~~~--NOTE~~~~~~~-
Low pressure coolant injection (LPCI) subsystems may be considered OPERABLE during alignment and operation for decay heat removal with reactor steam dome pressure less than the Residual Heat Removal (RHR) cut in permissive pressure in MODE 3, if capable of being manually realigned and not otherwise inoperable.
Verify each ECCS injection/spray subsystem manual, power operated, and automatic valve in the flow path, that is not locked, sealed, or otherwise secured in position, is in the correct position.
Verify ADS pneumatic supply header pressure is
~95 psig.
Verify the RHR System cross tie valves are closed and power is removed from the electrical valve operator.
Cycle open and closed each LPCI motor operated valve independent power supply battery charger AC input breaker and verify each LPCI inverter output voltage is
~ 576 V and ~ 624 V while supplying the respective bus.
3.5.1-4 ECCS - Operating 3.5.1 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 In accordance with the Surveillance Frequency Control Program (continued)
Amendment 301
SURVEILLANCE REQUIREMENTS (continued)
SR 3.5.1.6 SR 3.5.1. 7 SR 3.5.1.8 JAFNPP SURVEILLANCE
NOTE --------------------
Not required to be performed if performed within the previous 31 days.
Verify each recirculation pump discharge valve cycles through one complete cycle of full travel or is de-energized in the closed position.
Verify the following ECCS pumps develop the specified flow rate against a system head corresponding to the specified reactor pressure above primary containment pressure.
SYSTEM HEAD CORRESPONDING TO A REACTOR PRESSURE NO.
ABOVE PRIMARY OF CONTAINMENT SYSTEM FLOW RATE PUMPS PRESSURE OF Core Spray
~ 4265 gpm 1
~ 113 psi LPCI
~ 7700 gpm 1
~ 20 psi
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 reactor steam pressure and flow are adequate to perform the test.
Verify, with reactor pressure ~ 1040 psig and ~ 970 psig, the HPCI pump can develop a flow rate ~ 3400 gpm against a system head corresponding to reactor pressure.
3.5.1-5 ECCS-Operating 3.5.1 FREQUENCY Once each startup prior to exceeding 25% RTP In accordance with the Inservice Testing Program In accordance with the Inservice Testing Program (continued)
Amendment 274
SURVEILLANCE REQUIREMENTS (continued)
SR 3.5.1.9 SR 3.5.1.10 SR 3.5.1.11 SR 3.5.1.12 JAFNPP SURVEILLANCE
~~~~~~~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 reactor steam pressure and flow are adequate to perform the test.
Verify, with reactor pressure :5 165 psig, the HPCI pump can develop a flow rate ~ 3400 gpm against a system head corresponding to reactor pressure.
~~~~~~-NOTE~~~~~~~
- 1. For the HPCI System, 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 reactor steam pressure and flow are adequate to perform the test.
- 2. Vessel injection/spray may be excluded.
Verify each ECCS injection/spray subsystem actuates on an actual or simulated automatic initiation signal.
~~~~~~~NOTE~~~~~~~
Va Ive actuation may be excluded.
Verify the ADS actuates on an actual or simulated automatic initiation signal.
Verify each LPCI motor operated valve independent power supply inverter capacity is adequate to supply and maintain in OPERABLE status the required emergency loads for the design duty cycle.
3.5.1-6 ECCS-Operating 3.5.1 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 In accordance with the Surveillance Frequency Control Program (continued)
Amendment 301
SURVEILLANCE REQUIREMENTS (continued)
SR 3.5.1.13 JAFNPP SURVEILLANCE Verify each required ADS valve is capable of being opened.
3.5.1-7 ECCS-Operating 3.5.1 FREQUENCY In accordance with the lnservice Testing Program Amendment 297
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