ML073100478

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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)
v • d • e


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

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