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| number = ML073100478
| number = ML073100478
| issue date = 11/05/2007
| issue date = 11/05/2007
| title = Pilgrim Nuclear Power Station, Technical Specifications, Issuance of Amendment Control Rod Operability, Scram Insertion Time, and Control Rod Accumulator Requirements
| title = Technical Specifications, Issuance of Amendment Control Rod Operability, Scram Insertion Time, and Control Rod Accumulator Requirements
| author name =  
| author name =  
| author affiliation = NRC/NRR/ADRO/DORL/LPLI-1
| author affiliation = NRC/NRR/ADRO/DORL/LPLI-1
Line 18: Line 18:


=Text=
=Text=
{{#Wiki_filter:-3-B. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 230, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
{{#Wiki_filter:       B. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 230, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.
C. Records ENO shall keep facility operating records in accordance with the requirements of the Technical Specifications.
C. Records ENO shall keep facility operating records in accordance with the requirements of the Technical Specifications.
D. Equalizer Valve Restriction  
D. Equalizer Valve Restriction - DELETED E. Recirculation Loop Inoperable     - DELETED F. Fire Protection ENO shall implement and maintain in effect all provisions of the approved fire protection program as described in the Final Safety Analysis Report for the facility and as approved in the SER dated December 21, 1978 as supplemented subject to the following provision:
-DELETED E. Recirculation Loop Inoperable  
ENO may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.
-DELETED F. Fire Protection ENO shall implement and maintain in effect all provisions of the approved fire protection program as described in the Final Safety Analysis Report for the facility and as approved in the SER dated December 21, 1978 as supplemented subject to the following provision:
G. Physical Protection The licensee shall fully implement and maintain in effect all provisions of the Commission-approved physical security, training and qualification, and safeguards conting/ency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR2781 7 and 27822) and to the authority of 10 CFR 50.90 and 10,CFR 50.54(p). The combined set of plans, which contain Safeguards Information protected under 10 CFR 73.21, is entitled: "Pilgrim Nuclear Power Station Physical Security, Training and Qualification, and Safeguards Contingency Plan, Revision 0" submitted by letter dated October 13, 2004, as supplemented by letter dated May 15, 2006.
ENO may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.G. Physical Protection The licensee shall fully implement and maintain in effect all provisions of the Commission-approved physical security, training and qualification, and safeguards conting/ency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR2781 7 and 27822) and to the authority of 10 CFR 50.90 and 10,CFR 50.54(p).
Amendment 225, 226, 227, 228, 229, 230
The combined set of plans, which contain Safeguards Information protected under 10 CFR 73.21, is entitled: "Pilgrim Nuclear Power Station Physical Security, Training and Qualification, and Safeguards Contingency Plan, Revision 0" submitted by letter dated October 13, 2004, as supplemented by letter dated May 15, 2006.Amendment 225, 226, 227, 228, 229, 230 TABLE OF CONTENTS 1.0 DEFINITIONS 1-1 2.0 SAFETY LIMITS 2-1 2.1 Safety Limits 2-1 2.2 Safety Limit Violation 2-1 BASES B2-1 LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS


===3.0 LIMITING===
TABLE OF CONTENTS 1.0  DEFINITIONS                                                                1-1 2.0    SAFETY LIMITS                                                              2-1 2.1    Safety Limits                                                              2-1 2.2    Safety Limit Violation                                                      2-1 BASES                                                                      B2-1 LIMITING CONDITIONS FOR OPERATION                      SURVEILLANCE REQUIREMENTS 3.0   LIMITING CONDITION FOR OPERATION                             4.0           3/4.0-1 (LCO) APPLICABILITY 3.1    REACTOR PROTECTION SYSTEM                                    4.1            3/4.1-1 BASES                                                                      B3/4.1-1 3.2    PROTECTIVE INSTRUMENTATION                                  4.2            3/4.2-1 A. Primary Containment Isolation Functions                      A            3/4.2-1 B. Core and Containment Cooling Systems                          B            3/4.2-1 C. Control Rod Block Actuation                                  C            3/4.2-2 D. Radiation Monitoring Systems                                  D            3/4.2-2 E. Drywell Leak Detection                                        E            3/4.2-3 F. Surveillance Information Readouts                            F            3/4.2-3 G. Recirculation Pump Trip/ Alternate Rod Insertion              G            3/4.2-4 H. Drywell Temperature                                          H            3/4.2-5 BASES                                                                      B3/4.2-1 3.3    REACTIVITY CONTROL                                          4.3          3/4.3-1 A. Reactivity Margin - Core Loading                              A            3/4.3-1 B. Control Rod Operability                                      B            3/4.3-2 C. Control Rod Scram Times                                      C            3/4.3-7 D. Control Rod Scram Accumulators                                D            3/4.3-8 E. Reactivity Anomalies                                          E            3/4.3-10 F. Rod Worth Minimizer (RWM)                                    F            3/4.3-11' G. Scram Discharge Volume (SDV)                                  G            3/4.3-12 H. Rod Pattern Control                                          H            3/4.3-13 BASES                                                                      B3/4.3-1 3.4    STANDBY LIQUID CONTROL SYSTEM                                4.4          3/4.4-1 BASES                                                                      B3/4.4-1 3.5  CORE AND CONTAINMENT COOLING                                  4.5          3/4.5-1 SYSTEMS A. Core.Spray and LPCI Systems                                    A            3/4.5-1 B. Containment Cooling System                                    B            3/4.5-3 C. HPCI System                                                    C            3/4.5-7 D. Reactor Core Isolation Cooling (RCIC) System                  D            3/4.5-8 E. Automatic Depressurization System (ADS)                        E            3/4.5-9 F. Minimum Low Pressure Cooling and Diesel                        F Generator Availability                                                  3/4.5-10 G.    (Deleted)                                                      G            3/4.5-11 H. Maintenance of Filled Discharge Pipe                          H            3/4.5-12 BASES                                                                      B3/4.5-1 Amendment 86, 2*,,2*-4,    230
CONDITION FOR OPERATION 4.0 3/4.0-1 (LCO) APPLICABILITY


===3.1 REACTOR===
LIMITING CONDITIONS FOR OPERATION              SURVEILLANCE REQUIREMENTS 3.3  REACTIVITY CONTROL (continued)            4.3 REACTIVITY CONTROL (continued)
PROTECTION SYSTEM 4.1 3/4.1-1 BASES B3/4.1-1 3.2 PROTECTIVE INSTRUMENTATION 4.2 3/4.2-1 A. Primary Containment Isolation Functions A 3/4.2-1 B. Core and Containment Cooling Systems B 3/4.2-1 C. Control Rod Block Actuation C 3/4.2-2 D. Radiation Monitoring Systems D 3/4.2-2 E. Drywell Leak Detection E 3/4.2-3 F. Surveillance Information Readouts F 3/4.2-3 G. Recirculation Pump Trip/ Alternate Rod Insertion G 3/4.2-4 H. Drywell Temperature H 3/4.2-5 BASES B3/4.2-1 3.3 REACTIVITY CONTROL 4.3 3/4.3-1 A. Reactivity Margin -Core Loading A 3/4.3-1 B. Control Rod Operability B 3/4.3-2 C. Control Rod Scram Times C 3/4.3-7 D. Control Rod Scram Accumulators D 3/4.3-8 E. Reactivity Anomalies E 3/4.3-10 F. Rod Worth Minimizer (RWM) F 3/4.3-11'G. Scram Discharge Volume (SDV) G 3/4.3-12 H. Rod Pattern Control H 3/4.3-13 BASES B3/4.3-1 3.4 STANDBY LIQUID CONTROL SYSTEM 4.4 3/4.4-1 BASES B3/4.4-1 3.5 CORE AND CONTAINMENT COOLING 4.5 3/4.5-1 SYSTEMS A. Core.Spray and LPCI Systems A 3/4.5-1 B. Containment Cooling System B 3/4.5-3 C. HPCI System C 3/4.5-7 D. Reactor Core Isolation Cooling (RCIC) System D 3/4.5-8 E. Automatic Depressurization System (ADS) E 3/4.5-9 F. Minimum Low Pressure Cooling and Diesel F Generator Availability 3/4.5-10 G. (Deleted)
B. Control Rod Operability                    B. Control Rod Operability LCO 3.3.B.1                                     SR 4.3.B. 1.1 Each control rod shall be OPERABLE.
G 3/4.5-11 H. Maintenance of Filled Discharge Pipe H 3/4.5-12 BASES B3/4.5-1 Amendment 86, 230 LIMITING CONDITIONS FOR OPERATION 3.3 REACTIVITY CONTROL (continued)
Not required to be performed until 7 days APPLICABILITY:                                  after the control rod is withdrawn and thermal power is greater than the LPSP of RUN and STARTUP MODES; REFUEL                  the RWM.
SURVEILLANCE REQUIREMENTS
MODE W*he-thb -ea-ctor-vessel-head-i....
fully tensioned. (See also 3.10.D)              Insert each fully withdrawn OPERABLE control rod at least one notch once per 7 ACTIONS                                        days.
                            -NOTE-                   SR 4.3.B.1.2 Separate condition entry is allowed for                                    -----.-----
                                                                                ----            -NOTE each control rod.                              Not required to be performed until 31 days after the control rod is withdrawn and thermal power is greater than the LPSP of A. One withdrawn control rod .stuck.        the RWM.
Insert each partially withdrawn Rod Worth Minimizer (RWM) may be        OPERABLE control rod at least one notch bypassed as allowed by LCO 3.3.F.        once per 31 days.
: 1. Verify stuck control rod          SR 4.3.B.1.3 separation criteria are met immediately.                     Verify each withdrawn control rod does not go to the withdrawn overtravel position.
AND                                      a. Each time the control rod is withdrawn to "full out" position.
: 2. Disarm the associated control rod drive (CRD)'         AND within 2 hours.
: b. Prior to declaring control rod AND                                            OPERABLE after work on control
: 3. Perform SR 4.3.B.1.1 and                rod or CRD system that could affect SR 4.3.B.1.2 for each                  coupling.
withdrawn OPERABLE.
control rod within 24 hours        SR 4.3.B.1.4 from discovery of                Verify each control rod scram time from condition A concurrent with      fully withdrawn to notch position 04 is thermal power greater than        < 7 seconds in accordance with the Low Power Setpoint            SR 4.3.C.1, SR 4.3.C.2, SR 4.3.C.3 or (LPSP) of the RWM.                SR 4.3.C.4 AND SR 4.3.B.1.5
: 4. Verify LCO 3.3.A.1 is met within 72 hours.                  Determine the position of each control rod once per 24 hours.
AND Amendment No. 4-86, 230                                                                   3/4.3-2


===4.3 REACTIVITY===
LIMITING CONDITIONS FOR OPERATION                  SURVEILLANCE REQUIREMENTS 3.3    REACTIVITY CONTROL (continued)              _4.3  REACTIVITY CONTROL (continued)
B. Control Rod Operability (continued)            B. Control Rod Operabilitv (continued)
LCO 3.3.B.1    (continued)
: 5.        ----  NOTE ---.....-----
Not applicable when thermal power > 20% RTP.
Ensure stuck rod is in compliance with banked position withdrawal sequence.
(BPWS) within 8 hours.
OR Verify control rod drop accident limit of 280 cal/gm is not exceeded within 8 hours.
B. Two or more withdrawn control rods stuck.
: 1. Be in HOT SHUTDOWN within 12 hours.-
C. One or more control rods inoperable for reasons other than condition A or B.
: 1.                ,NOTE----------
RWM may be bypassed as allowed by LCO 3.3.F.
Fully insert inoperable control rod within 3 hours.
AND
: 2. Disarm the associated CRD within 4 hours.
Amendment No. 1-86, 230                                                                  3/4.3-3


CONTROL (continued)
LIMITING CONDITIONS FOR OPERATION                    SURVEILLANCE REQUIREMENTS 3.3    REACTIVITY CONTROL (continued).               4.3 REACTIVITY CONTROL (continued)
B. Control Rod Operability B. Control Rod Operability SR 4.3.B. 1.1 LCO 3.3.B.1 Each control rod shall be OPERABLE.APPLICABILITY:
B. Control Rod Operability (continued)             B. Control Rod Operability (continued)
RUN and STARTUP MODES; REFUEL MODE -ea-ctor-vessel-head-i....
LCO 3.3.B.1         (continued)
fully tensioned. (See also 3.10.D)ACTIONS-NOTE-Separate condition entry is allowed for each control rod.A. One withdrawn control rod .stuck.Rod Worth Minimizer (RWM) may be bypassed as allowed by LCO 3.3.F.Not required to be performed until 7 days after the control rod is withdrawn and thermal power is greater than the LPSP of the RWM.Insert each fully withdrawn OPERABLE control rod at least one notch once per 7 days.SR 4.3.B.1.2-NOTE ---- ------.-----
D.       -----------     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.1. Verify stuck control rod separation criteria are met immediately.
Not applicable when thermal power
AND 2. Disarm the associated control rod drive (CRD)'within 2 hours.AND 3. Perform SR 4.3.B.1.1 and SR 4.3.B.1.2 for each withdrawn OPERABLE.control rod within 24 hours from discovery of condition A concurrent with thermal power greater than the Low Power Setpoint (LPSP) of the RWM.AND 4. Verify LCO 3.3.A.1 is met within 72 hours.AND Insert each partially withdrawn OPERABLE control rod at least one notch once per 31 days.SR 4.3.B.1.3 Verify each withdrawn control rod does not go to the withdrawn overtravel position.a. Each time the control rod is withdrawn to "full out" position.AND b. Prior to declaring control rod OPERABLE after work on control rod or CRD system that could affect coupling.SR 4.3.B.1.4 Verify each control rod scram time from fully withdrawn to notch position 04 is< 7 seconds in accordance with SR 4.3.C.1, SR 4.3.C.2, SR 4.3.C.3 or SR 4.3.C.4 SR 4.3.B.1.5 Determine the position of each control rod once per 24 hours.Amendment No. 4-86, 230 3/4.3-2 LIMITING CONDITIONS FOR OPERATION 3.3 REACTIVITY CONTROL (continued)
            > 20% RTP.
B. Control Rod Operability (continued)
Two or more inoperable control rods not in compliance with BPWS and not separated by two or more OPERABLE control rods.
LCO 3.3.B.1 (continued)
: 1.         Restore compliance with BPWS within 8 hours.
SURVEILLANCE REQUIREMENTS
OR
_4.3 REACTIVITY CONTROL (continued)
: 2.        Verify control rod drop accident limit of 280 cal/gm is not exceeded within 8 hours.
B. Control Rod Operabilitv (continued)
OR
: 5. ----NOTE ---.....-----
: 3.        Restore control rod(s) to OPERABLE status within 8 hours.
Not applicable when thermal power > 20% RTP.Ensure stuck rod is in compliance with banked position withdrawal sequence.(BPWS) within 8 hours.OR Verify control rod drop accident limit of 280 cal/gm is not exceeded within 8 hours.B. Two or more withdrawn control rods stuck.1. Be in HOT SHUTDOWN within 12 hours.-C. One or more control rods inoperable for reasons other than condition A or B.1. ,NOTE----------
E.
RWM may be bypassed as allowed by LCO 3.3.F.AND 2.Fully insert inoperable control rod within 3 hours.Disarm the associated CRD within 4 hours.Amendment No. 1-86, 230 3/4.3-3 LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS
Not applicable when thermal power > 20% RTP.
One or more groups with four or more inoperable control rods.
          *1.         Restore control rod(s) to OPERABLE status within 8 hours.
F. Required action and associated completion time'of condition A, C, D, or E not met.
OR Nine or more control rods inoperable.
: 1.         Be in HOT SHUTDOWN within 12 hours.
Amendment No. 46, 230                                                                     3/4.3-4


===3.3 REACTIVITY===
LIMITING CONDITIONS FOR OPERATION              SURVEILLANCE REQUIREMENTS 3.3   REACTIVITY CONTROL (continued)           4.3 REACTIVITY CONTROL (continued)
 
B. Control Rod Operability (continued)       B. Control Rod Operability (continued)
CONTROL (continued).
LCO 3.3.8.3                                   SR 4.3.B.3 Control rods shall not be withdrawn for        Prior to control rod withdrawal for startup unless at least two source range       startup, verify that at least two source channels have an observed count rate           range channels have an observed equal to or greater than three counts per     count rate of at least three counts per second.                                       second.
 
===4.3 REACTIVITY===
 
CONTROL (continued)
B. Control Rod Operability (continued)
B. Control Rod Operability (continued)
LCO 3.3.B.1 (continued)
D. -----------
NOTE -....-----------
Not applicable when thermal power> 20% RTP.Two or more inoperable control rods not in compliance with BPWS and not separated by two or more OPERABLE control rods.1. Restore compliance with BPWS within 8 hours.OR 2. Verify control rod drop accident limit of 280 cal/gm is not exceeded within 8 hours.OR 3. Restore control rod(s) to OPERABLE status within 8 hours.E.Not applicable when thermal power > 20% RTP.One or more groups with four or more inoperable control rods.* 1. Restore control rod(s) to OPERABLE status within 8 hours.F. Required action and associated completion time'of condition A, C, D, or E not met.OR Nine or more control rods inoperable.
: 1. Be in HOT SHUTDOWN within 12 hours.Amendment No. 46, 230 3/4.3-4 LIMITING CONDITIONS FOR OPERATION 3.3 REACTIVITY CONTROL (continued)
B. Control Rod Operability (continued)
LCO 3.3.8.3 Control rods shall not be withdrawn for startup unless at least two source range channels have an observed count rate equal to or greater than three counts per second.APPLICABILITY:
Prior to withdrawing control rods for startup.ACTIONS: A. LCO 3.3.B.3 cannot be met.1. Place the mode switch in shutdown immediately.
SURVEILLANCE REQUIREMENTS
 
===4.3 REACTIVITY===
 
CONTROL (continued)
B. Control Rod Operability (continued)
SR 4.3.B.3 Prior to control rod withdrawal for startup, verify that at least two source range channels have an observed count rate of at least three counts per second.Amendment No. 4-6, 230 3/4.3-6 LIMITING CONDITIONS FOR OPERATION 3.3 REACTIVITY CONTROL (continued)
}C Control Rod Scram Times LCO 3.3.C SURVEILLANCE REQUIREMENTS
 
===4.3 REACTIVITY===
 
CONTROL (continued)
C. Control Rod Scram Times------.------------.
NOTE-------------
During single control rod scram time Surveillances, the-control rod drive (CRD) pumps shall be isolated from the associated scram accumulator.
: 1. No more than 10 OPERABLE control rods shall be "slow," in accordance with Table 3.3.C-1, and 2. --No more-than-2 OPERABLE control rods that are "slow" shall occupy adjacent locations.
APPLICABILITY:
APPLICABILITY:
RUN and STARTUP MODES;REFUEL MODE when the ,reactor vessel head is fully tensioned.
Prior to withdrawing control rods for startup.
ACTIONS: A. LCO 3.3.C cannot be met.1. Be in HOT SHUTDOWN within 12 hours.SR 4.3.C.1J Verify each control rod scram time is within the limits of Table 3.3.C-1 with reactor steam dome pressure _> 800 psig prior to exceeding 40% RTP after each reactor shutdown_>
ACTIONS:
120 days.SR 4.3.C.2 Verify for a representative sample, each tested control rod scram time is within the limits of Table 3.3.C-1 with reactor steam dome pressure > 800 psig within each 200 days of cumulative operation in RUN.SR 4.3.C.3 Verify each affected control rod scram time is Within the limits of Table 3.3.C-1 with any reactor steam dome pressure prior to declaring control rod OPERABLE after work on control rod or CRD System that could affect scram time.SR 4.3.C.4 Verify each affected control rod scram time is within the limits of Table 3.3.C-1 with reactor steam dome pressure >800 psig prior to exceeding 40% RTP after fuel movement within the affected core cell AND prior to exceeding 40%RTP after work on control rod or CRD System that could affect scram time.Amendment No.1-86, 230 3/4.3-7 Table 3.3.C-1 (page 1 of 1)Control Rod Scram Times S---!-------------NOTES-7------------------
A. LCO 3.3.B.3 cannot be met.
: 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-3.3.B, -"Control Rod..OPERABILITY," for control rods with scram times > 7 seconds to notch position 04. These control rods are inoperable, in accordance with SR 4.3.B.1.4, and are not considered "slow." NOTCH POSITION SCRAM TIMES (a)(b)(seconds)WHEN REACTOR STEAM DOME PRESSURE > 800 PSIG 44 0.57 34 1.23 24 1.99 04 3.51 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.Amendment No. 230 3/4.3-7a ' I LIMITING CONDITIONS FOR OPERATION 3.3 REACTIVITY CONTROL (continued)
: 1.     Place the mode switch in shutdown immediately.
'SURVEILLANCE REQUIREMENTS
Amendment No. 4-6, 230                                                                   3/4.3-6
 
===4.3 REACTIVITY===
 
CONTROL (continued)
D. Control Rod Scram Accumulators D.Control Rod Scram Accumulators LCO 3.3.D Each control rod scram accumulator shall be OPERABLE.APPLICABILITY:
RUN and STARTUP MODES;REFUEL MODE when the reactor vessel head-is fully tensioned.
ACTIONS:---- ---- ---- N O T E -.- ......- ....- -......Separate condition entry is allowed for each control rod scram accumulator.
SR 4.3.D Verify each control rod scram accumulator pressure is _>.940 psig every 7 days.A. One control rod scram accumulator inoperable with reactor steam dome pressure > 950 psig.1. N T ... ...Only applicable if the associated control rod scram time was within limits of Table 3.3.C-1 during the last scram time surveillance.
Declare the associated control rod scram time "slow" within 8 hours.OR 2. Declare the associated control rod inoperable within 8 hours.B. Two or more control rod scram accumulators inoperable, with reactor steam dome pressure_> 950 psig.1. Restore charging water header pressure to : 940 psig within 20 minutes from discovery of inoperable accumulators with charging water header < 940 psig.AND Amendment No. 230 3/4.3-8 LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS


===3.3 REACTIVITY===
LIMITING CONDITIONS FOR OPERATION            SURVEILLANCE REQUIREMENTS 3.3   REACTIVITY CONTROL (continued)        4.3  REACTIVITY CONTROL (continued)
}C    Control Rod Scram Times                C. Control Rod Scram Times LCO 3.3.C NOTE-------------
: 1. No more than 10 OPERABLE                  During single control rod scram time control rods shall be "slow," in        Surveillances, the-control rod drive accordance with Table 3.3.C-1, and      (CRD) pumps shall be isolated from the associated scram accumulator.
: 2. --No more-than-2 OPERABLE control        SR 4.3.C.1J rods that are "slow" shall occupy adjacent locations.                    Verify each control rod scram time is within the limits of Table 3.3.C-1 with reactor steam dome pressure _> 800 psig prior to exceeding 40% RTP after APPLICABILITY:                              each reactor shutdown_> 120 days.
RUN and STARTUP MODES;                      SR 4.3.C.2 REFUEL MODE when the ,reactor vessel head is fully tensioned.              Verify for a representative sample, each tested control rod scram time is within ACTIONS:                                    the limits of Table 3.3.C-1 with reactor steam dome pressure > 800 psig within A. LCO 3.3.C cannot be met.            each 200 days of cumulative operation in RUN.
: 1.      Be in HOT SHUTDOWN within 12 hours.              SR 4.3.C.3 Verify each affected control rod scram time is Within the limits of Table 3.3.C-1 with any reactor steam dome pressure prior to declaring control rod OPERABLE after work on control rod or CRD System that could affect scram time.
SR 4.3.C.4 Verify each affected control rod scram time is within the limits of Table 3.3.C-1 with reactor steam dome pressure >
800 psig prior to exceeding 40% RTP after fuel movement within the affected core cell AND prior to exceeding 40%
RTP after work on control rod or CRD System that could affect scram time.
Amendment No.1-86, 230                                                                  3/4.3-7


CONTROL (continued)  
Table 3.3.C-1 (page 1 of 1)
Control Rod Scram Times S---!-------------NOTES-          7------------------
: 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-3.3.B, -"Control Rod..
OPERABILITY," for control rods with scram times > 7 seconds to notch position
: 04. These control rods are inoperable, in accordance with SR 4.3.B.1.4, and are not considered "slow."
SCRAM TIMES (a)(b)
(seconds)
NOTCH POSITION WHEN REACTOR STEAM DOME PRESSURE > 800 PSIG 44                                              0.57 34                                              1.23 24                                              1.99 04                                            3.51 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.
Amendment No. 230                                                                  3/4.3-7a '      I


===4.3 REACTIVITY===
LIMITING CONDITIONS FOR OPERATION                      'SURVEILLANCE REQUIREMENTS 3.3    REACTIVITY CONTROL (continued)                    4.3 REACTIVITY CONTROL (continued)
D. Control Rod Scram Accumulators                    D. Control Rod Scram Accumulators LCO 3.3.D                                              SR 4.3.D Each control rod scram accumulator shall be OPERABLE.                                    Verify each control rod scram accumulator pressure is _>.940 psig APPLICABILITY:                                        every 7 days.
RUN and STARTUP MODES; REFUEL MODE when the reactor vessel head-is fully tensioned.
ACTIONS:
            ---- - - -- NO T E -.-
Separate condition entry is allowed for each control rod scram accumulator.
A. One control rod scram accumulator inoperable with reactor steam dome pressure > 950 psig.
: 1.              N T -*. ...          ...
Only applicable if the associated control rod scram time was within limits of Table 3.3.C-1 during the last scram time surveillance.
Declare the associated control rod scram time "slow" within 8 hours.
OR
: 2. Declare the associated control rod inoperable within 8 hours.
B. Two or more control rod scram accumulators inoperable, with reactor steam dome pressure
_>950 psig.
: 1. Restore charging water header pressure to : 940 psig within 20 minutes from discovery of inoperable accumulators with charging water header < 940 psig.
AND Amendment No. 230                                                                        3/4.3-8


CONTROL (continued)
LIMITING CONDITIONS FOR OPERATION              SURVEILLANCE REQUIREMENTS 3.3    REACTIVITY CONTROL (continued)          4.3  REACTIVITY CONTROL (continued)
D. Control Rod Scram Accumulators D. Control Rod Scram Accumulators (continued) (continued)
D. Control Rod Scram Accumulators             D. Control Rod Scram Accumulators (continued)                                   (continued)
LCO 3.3.D (continued) 2.1 Only applicable if the associated control rod scram time was within limits_otf_'Table_3.3.C_-1_during_the  
LCO 3.3.D (continued) 2.1 Only applicable if the associated control rod scram time was within limits
......last scram time surveillance.
_otf_'Table_3.3.C_-1_during_the     . .....
Declare the associated control rod scram time"slow" within 1 hour.OR 2.2 Declare the associated control rod inoperable within 1 hour.C. One or more control rod scram accumulators inoperable, with reactor steam dome pressure< 950 psig.1. Verify all control rods associated with inoperable accumulators are fully inserted immediately upon discovery of charging water header pressure < 940 psig.AND-2. Declare the associated control rod inoperable within 1 hour.D. Required action and associated completion time if B.1 or C.1 not met.1. --------NOTE -----Not applicable if all inoperable control rod scram accumulators are associated with fully inserted control rods.Place the reactor mode switch in the shutdown position immediately.
last scram time surveillance.
Amendment No. 186 230 3/4.3-9}}
Declare the associated control rod scram time "slow" within 1 hour.
OR 2.2   Declare the associated control rod inoperable within 1 hour.
C. One or more control rod scram accumulators inoperable, with reactor steam dome pressure
          < 950 psig.
: 1. Verify all control rods associated with inoperable accumulators are fully inserted immediately upon discovery of charging water header pressure < 940 psig.
AND
        -2. Declare the associated control rod inoperable within 1 hour.
D. Required action and associated completion time if B.1 or C.1 not met.
: 1.   --------   NOTE       -----
Not applicable if all inoperable control rod scram accumulators are associated with fully inserted control rods.
Place the reactor mode switch in the shutdown position immediately.
Amendment No. 186 230                                                       3/4.3-9}}

Latest revision as of 09:47, 13 March 2020

Technical Specifications, Issuance of Amendment Control Rod Operability, Scram Insertion Time, and Control Rod Accumulator Requirements
ML073100478
Person / Time
Site: Pilgrim
Issue date: 11/05/2007
From:
NRC/NRR/ADRO/DORL/LPLI-1
To:
kim J, NRR/ADRO/DORL, 415-4125
References
TAC MD4242
Download: ML073100478 (10)


Text

B. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 230, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

C. Records ENO shall keep facility operating records in accordance with the requirements of the Technical Specifications.

D. Equalizer Valve Restriction - DELETED E. Recirculation Loop Inoperable - DELETED F. Fire Protection ENO shall implement and maintain in effect all provisions of the approved fire protection program as described in the Final Safety Analysis Report for the facility and as approved in the SER dated December 21, 1978 as supplemented subject to the following provision:

ENO may make changes to the approved fire protection program without prior approval of the Commission only if those changes would not adversely affect the ability to achieve and maintain safe shutdown in the event of a fire.

G. Physical Protection The licensee shall fully implement and maintain in effect all provisions of the Commission-approved physical security, training and qualification, and safeguards conting/ency plans including amendments made pursuant to provisions of the Miscellaneous Amendments and Search Requirements revisions to 10 CFR 73.55 (51 FR2781 7 and 27822) and to the authority of 10 CFR 50.90 and 10,CFR 50.54(p). The combined set of plans, which contain Safeguards Information protected under 10 CFR 73.21, is entitled: "Pilgrim Nuclear Power Station Physical Security, Training and Qualification, and Safeguards Contingency Plan, Revision 0" submitted by letter dated October 13, 2004, as supplemented by letter dated May 15, 2006.

Amendment 225, 226, 227, 228, 229, 230

TABLE OF CONTENTS 1.0 DEFINITIONS 1-1 2.0 SAFETY LIMITS 2-1 2.1 Safety Limits 2-1 2.2 Safety Limit Violation 2-1 BASES B2-1 LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.0 LIMITING CONDITION FOR OPERATION 4.0 3/4.0-1 (LCO) APPLICABILITY 3.1 REACTOR PROTECTION SYSTEM 4.1 3/4.1-1 BASES B3/4.1-1 3.2 PROTECTIVE INSTRUMENTATION 4.2 3/4.2-1 A. Primary Containment Isolation Functions A 3/4.2-1 B. Core and Containment Cooling Systems B 3/4.2-1 C. Control Rod Block Actuation C 3/4.2-2 D. Radiation Monitoring Systems D 3/4.2-2 E. Drywell Leak Detection E 3/4.2-3 F. Surveillance Information Readouts F 3/4.2-3 G. Recirculation Pump Trip/ Alternate Rod Insertion G 3/4.2-4 H. Drywell Temperature H 3/4.2-5 BASES B3/4.2-1 3.3 REACTIVITY CONTROL 4.3 3/4.3-1 A. Reactivity Margin - Core Loading A 3/4.3-1 B. Control Rod Operability B 3/4.3-2 C. Control Rod Scram Times C 3/4.3-7 D. Control Rod Scram Accumulators D 3/4.3-8 E. Reactivity Anomalies E 3/4.3-10 F. Rod Worth Minimizer (RWM) F 3/4.3-11' G. Scram Discharge Volume (SDV) G 3/4.3-12 H. Rod Pattern Control H 3/4.3-13 BASES B3/4.3-1 3.4 STANDBY LIQUID CONTROL SYSTEM 4.4 3/4.4-1 BASES B3/4.4-1 3.5 CORE AND CONTAINMENT COOLING 4.5 3/4.5-1 SYSTEMS A. Core.Spray and LPCI Systems A 3/4.5-1 B. Containment Cooling System B 3/4.5-3 C. HPCI System C 3/4.5-7 D. Reactor Core Isolation Cooling (RCIC) System D 3/4.5-8 E. Automatic Depressurization System (ADS) E 3/4.5-9 F. Minimum Low Pressure Cooling and Diesel F Generator Availability 3/4.5-10 G. (Deleted) G 3/4.5-11 H. Maintenance of Filled Discharge Pipe H 3/4.5-12 BASES B3/4.5-1 Amendment 86, 2*,,2*-4, 230

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.3 REACTIVITY CONTROL (continued) 4.3 REACTIVITY CONTROL (continued)

B. Control Rod Operability B. Control Rod Operability LCO 3.3.B.1 SR 4.3.B. 1.1 Each control rod shall be OPERABLE.

Not required to be performed until 7 days APPLICABILITY: after the control rod is withdrawn and thermal power is greater than the LPSP of RUN and STARTUP MODES; REFUEL the RWM.

MODE W*he-thb -ea-ctor-vessel-head-i....

fully tensioned. (See also 3.10.D) Insert each fully withdrawn OPERABLE control rod at least one notch once per 7 ACTIONS days.

-NOTE- SR 4.3.B.1.2 Separate condition entry is allowed for -----.-----


-NOTE each control rod. Not required to be performed until 31 days after the control rod is withdrawn and thermal power is greater than the LPSP of A. One withdrawn control rod .stuck. the RWM.

Insert each partially withdrawn Rod Worth Minimizer (RWM) may be OPERABLE control rod at least one notch bypassed as allowed by LCO 3.3.F. once per 31 days.

1. Verify stuck control rod SR 4.3.B.1.3 separation criteria are met immediately. Verify each withdrawn control rod does not go to the withdrawn overtravel position.

AND a. Each time the control rod is withdrawn to "full out" position.

2. Disarm the associated control rod drive (CRD)' AND within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />.
b. Prior to declaring control rod AND OPERABLE after work on control
3. Perform SR 4.3.B.1.1 and rod or CRD system that could affect SR 4.3.B.1.2 for each coupling.

withdrawn OPERABLE.

control rod within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> SR 4.3.B.1.4 from discovery of Verify each control rod scram time from condition A concurrent with fully withdrawn to notch position 04 is thermal power greater than < 7 seconds in accordance with the Low Power Setpoint SR 4.3.C.1, SR 4.3.C.2, SR 4.3.C.3 or (LPSP) of the RWM. SR 4.3.C.4 AND SR 4.3.B.1.5

4. Verify LCO 3.3.A.1 is met within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. Determine the position of each control rod once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

AND Amendment No. 4-86, 230 3/4.3-2

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.3 REACTIVITY CONTROL (continued) _4.3 REACTIVITY CONTROL (continued)

B. Control Rod Operability (continued) B. Control Rod Operabilitv (continued)

LCO 3.3.B.1 (continued)

5. ---- NOTE ---.....-----

Not applicable when thermal power > 20% RTP.

Ensure stuck rod is in compliance with banked position withdrawal sequence.

(BPWS) within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

OR Verify control rod drop accident limit of 280 cal/gm is not exceeded within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

B. Two or more withdrawn control rods stuck.

1. Be in HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.-

C. One or more control rods inoperable for reasons other than condition A or B.

1. ,NOTE----------

RWM may be bypassed as allowed by LCO 3.3.F.

Fully insert inoperable control rod within 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />.

AND

2. Disarm the associated CRD within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

Amendment No. 1-86, 230 3/4.3-3

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.3 REACTIVITY CONTROL (continued). 4.3 REACTIVITY CONTROL (continued)

B. Control Rod Operability (continued) B. Control Rod Operability (continued)

LCO 3.3.B.1 (continued)

D. ----------- NOTE -....-----------

Not applicable when thermal power

> 20% RTP.

Two or more inoperable control rods not in compliance with BPWS and not separated by two or more OPERABLE control rods.

1. Restore compliance with BPWS within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

OR

2. Verify control rod drop accident limit of 280 cal/gm is not exceeded within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

OR

3. Restore control rod(s) to OPERABLE status within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

E.

Not applicable when thermal power > 20% RTP.

One or more groups with four or more inoperable control rods.

  • 1. Restore control rod(s) to OPERABLE status within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

F. Required action and associated completion time'of condition A, C, D, or E not met.

OR Nine or more control rods inoperable.

1. Be in HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

Amendment No. 46, 230 3/4.3-4

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.3 REACTIVITY CONTROL (continued) 4.3 REACTIVITY CONTROL (continued)

B. Control Rod Operability (continued) B. Control Rod Operability (continued)

LCO 3.3.8.3 SR 4.3.B.3 Control rods shall not be withdrawn for Prior to control rod withdrawal for startup unless at least two source range startup, verify that at least two source channels have an observed count rate range channels have an observed equal to or greater than three counts per count rate of at least three counts per second. second.

APPLICABILITY:

Prior to withdrawing control rods for startup.

ACTIONS:

A. LCO 3.3.B.3 cannot be met.

1. Place the mode switch in shutdown immediately.

Amendment No. 4-6, 230 3/4.3-6

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.3 REACTIVITY CONTROL (continued) 4.3 REACTIVITY CONTROL (continued)

}C Control Rod Scram Times C. Control Rod Scram Times LCO 3.3.C NOTE-------------

1. No more than 10 OPERABLE During single control rod scram time control rods shall be "slow," in Surveillances, the-control rod drive accordance with Table 3.3.C-1, and (CRD) pumps shall be isolated from the associated scram accumulator.
2. --No more-than-2 OPERABLE control SR 4.3.C.1J rods that are "slow" shall occupy adjacent locations. Verify each control rod scram time is within the limits of Table 3.3.C-1 with reactor steam dome pressure _> 800 psig prior to exceeding 40% RTP after APPLICABILITY: each reactor shutdown_> 120 days.

RUN and STARTUP MODES; SR 4.3.C.2 REFUEL MODE when the ,reactor vessel head is fully tensioned. Verify for a representative sample, each tested control rod scram time is within ACTIONS: the limits of Table 3.3.C-1 with reactor steam dome pressure > 800 psig within A. LCO 3.3.C cannot be met. each 200 days of cumulative operation in RUN.

1. Be in HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. SR 4.3.C.3 Verify each affected control rod scram time is Within the limits of Table 3.3.C-1 with any reactor steam dome pressure prior to declaring control rod OPERABLE after work on control rod or CRD System that could affect scram time.

SR 4.3.C.4 Verify each affected control rod scram time is within the limits of Table 3.3.C-1 with reactor steam dome pressure >

800 psig prior to exceeding 40% RTP after fuel movement within the affected core cell AND prior to exceeding 40%

RTP after work on control rod or CRD System that could affect scram time.

Amendment No.1-86, 230 3/4.3-7

Table 3.3.C-1 (page 1 of 1)

Control Rod Scram Times S---!-------------NOTES- 7------------------

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-3.3.B, -"Control Rod..

OPERABILITY," for control rods with scram times > 7 seconds to notch position

04. These control rods are inoperable, in accordance with SR 4.3.B.1.4, and are not considered "slow."

SCRAM TIMES (a)(b)

(seconds)

NOTCH POSITION WHEN REACTOR STEAM DOME PRESSURE > 800 PSIG 44 0.57 34 1.23 24 1.99 04 3.51 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.

Amendment No. 230 3/4.3-7a ' I

LIMITING CONDITIONS FOR OPERATION 'SURVEILLANCE REQUIREMENTS 3.3 REACTIVITY CONTROL (continued) 4.3 REACTIVITY CONTROL (continued)

D. Control Rod Scram Accumulators D. Control Rod Scram Accumulators LCO 3.3.D SR 4.3.D Each control rod scram accumulator shall be OPERABLE. Verify each control rod scram accumulator pressure is _>.940 psig APPLICABILITY: every 7 days.

RUN and STARTUP MODES; REFUEL MODE when the reactor vessel head-is fully tensioned.

ACTIONS:


- - -- NO T E -.-

Separate condition entry is allowed for each control rod scram accumulator.

A. One control rod scram accumulator inoperable with reactor steam dome pressure > 950 psig.

1. N T -*. ... ...

Only applicable if the associated control rod scram time was within limits of Table 3.3.C-1 during the last scram time surveillance.

Declare the associated control rod scram time "slow" within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

OR

2. Declare the associated control rod inoperable within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

B. Two or more control rod scram accumulators inoperable, with reactor steam dome pressure

_>950 psig.

1. Restore charging water header pressure to : 940 psig within 20 minutes from discovery of inoperable accumulators with charging water header < 940 psig.

AND Amendment No. 230 3/4.3-8

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.3 REACTIVITY CONTROL (continued) 4.3 REACTIVITY CONTROL (continued)

D. Control Rod Scram Accumulators D. Control Rod Scram Accumulators (continued) (continued)

LCO 3.3.D (continued) 2.1 Only applicable if the associated control rod scram time was within limits

_otf_'Table_3.3.C_-1_during_the . .....

last scram time surveillance.

Declare the associated control rod scram time "slow" within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

OR 2.2 Declare the associated control rod inoperable within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

C. One or more control rod scram accumulators inoperable, with reactor steam dome pressure

< 950 psig.

1. Verify all control rods associated with inoperable accumulators are fully inserted immediately upon discovery of charging water header pressure < 940 psig.

AND

-2. Declare the associated control rod inoperable within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

D. Required action and associated completion time if B.1 or C.1 not met.

1. -------- NOTE -----

Not applicable if all inoperable control rod scram accumulators are associated with fully inserted control rods.

Place the reactor mode switch in the shutdown position immediately.

Amendment No. 186 230 3/4.3-9