ML071560542

Tech Spec Pages for Amendment 228 Single Control Rod Withdrawal Allowances

ML071560542
Person / Time
Site:	Pilgrim
Issue date:	04/25/2007
From:	NRC/NRR/ADRO/DORL/LPLI-1
To:
References
TAC MC9018
Download: ML071560542 (12)

Text

-3-B. Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 22q 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 contingency 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.Amendment 228 I TABLE OF CONTENTS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS

3.6 PRIMARY

SYSTEM BOUNDARY 4.6 3/4.6-1 A. Thermal and Pressurization Limitations A 3/4.6-1 B. Coolant Chemistry B 3/4.6-3 C. Coolant Leakage C 3/4.6-4 D. Safety and Relief Valves D 3/4.6-6 E. Jet Pumps E 3/4.6-7 F. Jet Pump Flow Mismatch F 3/4.6-8 G. Structural Integrity G 3/4.6-8 H. Deleted H 3/4.6-8 I. Shock Suppressors (Snubbers)

I 3/4.6-9 BASES B3/4.6-1 3.7 CONTAINMENT SYSTEMS 4.7 3/4.7-1 A. Primary Containment A 3/4.7-1 B. Standby Gas Treatment System and Control B Room High Efficiency Air Filtration System 3/4.7-11 C. Secondary Containment C 3/4.7-16 BASES B3/4.7-1 3.8 PLANT SYSTEMS 4.8 3/4.8-1 3.8.1 Main Condenser Offgas 4.8.1 3/4.8-1 3.8.2 Mechanical Vacuum Pump 4.8.2 3/4.8-2 BASES 133/4.8-1 3.9 AUXILIARY ELECTRICAL SYSTEM 4.9 3/4.9-1 A. Auxiliary Electrical Equipment A 3/4.9-1 B. Operation with Inoperable Equipment B 3/4.9-4 BASES B3/4.9-1 3.10 CORE ALTERATIONS 4.10 3/4.10-1 A. Refueling Interlocks A 3/4.10-1 B. Core Monitoring B 3/4.10-1 C. Spent Fuel Pool Water Level C 3/4.10-2 BASES B3/4.10-1 3.11 REACTOR FUEL ASSEMBLY 4.11 3/4.11-1 A. Average Planar Linear Heat Generation Rate A (APLHGR) 3/4.11-1 B. Linear Heat Generation Rate (LHGR) B 3/4.11-2 C. Minimum Critical Power Ratio (MCPR) C 3/4.11-2 D. Power/Flow Relationship During Power D Operation 3/4.11-4 BASES B3/4.1 1-1 Amendment No. 1-79, 228 ii TABLE OF CONTENTS LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.12 FIRE PROTECTION 4.12 3/4.12-1 Alternate Shutdown Panels 3/4.12-1 BASES B3/4.12-1 3.13 INSERVICE CODE TESTING 4.13 3/4.13-1 A. Inservice Code Testing of Pumps and 3/4.13-1 Valves BASES B3/4.13-1 3.14 SPECIAL OPERATIONS 4.14 3/4.14-1 A. Inservice Hydrostatic and A. 3/4.14-1 Leak Testing Operation B. (Not Used) B. 3/4.14-3 C. Single Control Rod Withdrawal

-Hot C. 3/4.14-4 Shutdown D. Single Control Rod Withdrawal

-Cold D. 3/4.14-6 Shutdown E. Multiple Control Rod Removal E. 3/4.14-8 F. (Not Used) F. 3/4.14-9 G. Control Rod Testing -Operating G. 3/4.14-10 BASES B3/4.14-1 4.0 DESIGN FEATURES 4.0-1 4.1 Site Location 4.0-1 4.2 Reactor Core 4.0-1 4.3 Fuel Storage 4.0-1 4.3.1 Criticality 4.0-1 4.3.2 Drainage 4.0-2 4.3.3 Capacity 4.0-2 4.3.4 Heavy Loads 4.0-2 5.0 ADMINISTRATIVE CONTROLS 5.0-1 5.1 Responsibility 5.0-1 5.2 Organization 5.0-2 5.3 Unit Staff Qualifications 5.0-4 5.4 Procedures 5.0-5 5.5 Programs and Manuals 5.0-6 5.6 Reporting Requirements 5.0-11 5.7 High Radiation Area 5.0-14 Amendment No. 179, 187, 21.1, 221, 228 iii LIMITING CONDITION FOR OPERATION 3.10 CORE ALTERATIONS (Cont)B. Core Monitoring (Cont)2. The SRM shall have a minimum of 3 cps except as specified in 3 and 4 below.3. Prior to spiral unloading, the SRM's shall have an initial count rate of _> 3 cps. During spiral unloading, the count rate on the SRM's may drop below 3 cps.4. During spiral reload, each control cell shall have at least one assembly with a minimum exposure of 1000 MWD/ST.C. Spent Fuel Pool Water Level Whenever irradiated fuel is stored in the spent fuel pool, the pool water level shall be maintained at or above 33 feet.SURVEILLANCE REQUIREMENTS 4.10 CORE ALTERATIONS (Cont)B. Core Monitoring (Cont)Spiral Reload During spiral reload, SRM operability will be verified by using a portable external source every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> until the required amount of fuel is loaded to maintain 3 cps.As an alternative to the above, up to two fuel assemblies will be loaded in different cells containing control blades around each SRM to obtain the required 3 cps.Until these assemblies have loaded, the cps requirement is not necessary.

C. Spent Fuel Pool Water Level Whenever irradiated fuel is stored in the spent fuel pool, the water level shall be recorded daily.Amendment No. 39, 41, 106,199, 228 3/4.10-2 LIMITING COND1ITONS FOR OPERATION 3.14 SPECIAL OPERATIONS (continued)

B. (Not Used)SURVEILLANCE REQUIREMENTS 4.14 SPECIAL OPERATIONS (continued)

B. (Not Used)Amendment No. 22-1-, 228 3/4.14-3 LIMITING CONDITIONS FOR OPERATION 3.14 SPECIAL OPERATIONS (continued)

C. Single Control Rod Withdrawal

-Hot Shutdown Specification The MODE definition specified in Specification 1.0 for Hot Shutdown may be changed to include the reactor mode switch in the Refuel position, and operation considered not to be in Refuel MODE, to, allow withdrawal of a single control rod, provided the following requirements are met: 1. Two Source Range Monitors (SRM) are OPERABLE per Specification 3.10.B.1 and 3.10.B.2, 2. The Refuel Position One-Rod-Out Interlock is OPERABLE, 3. The "full-in" control rod position indication for each control rod is OPERABLE or the associated control rod drive is disarmed, 4. All other control rods are fully inserted, and 5.a The withdrawn control rod is OPERABLE, and Table 3.1.1, uReactor Protection System (Scram)Instrumentation Requirement," channels for the following Trip Functions are OPERABLE as required for the Refuel MODE:-IRM -High Flux-IRM -Inoperative

-SDIV High Water Level -East-SDIV High Water Level -West-Mode Switch in Shutdown-Manual Scram OR 5.b All other control rods in a five by five array centered on the control rod being withdrawn are disarmed; at which time LCO 3.3.A.1, "Reactivity Margin -Core Loading," requirements may be changed to allow the single control rod withdrawn to be assumed to be the strongest control rod.SURVEILLANCE REQUIREMENTS 4.14 SPECIAL OPERATIONS (continued)

C. Single Control Rod Withdrawal

-Hot Shutdown 1. Two Source Range Monitors (SRM)are OPERABLE per Specification 4.10. B "Core Monitoring".

2. Perform functional test of the one-rod-out interlock weekly.3. Each time the control rod is withdrawn from the "full-in" position, verify the control rod position indication has no "full-in" indication.

4. Verify all control rods, other than the control rod being withdrawn, are fully inserted every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.5.a.1 Verify the Surveillance Requirements of Tables 4.1.1 and 4.1.2 for channels required to be OPERABLE for the Refuel MODE are performed as required, 5.a.2 Verify withdrawn control rod accumulator pressure is greater than minimum required every 7 days, and 5.a.3 Insert each withdrawn control rod at least one notch within 7 days after control rod is withdrawn and every 7 days thereafter.

OR 5.b Verify all control rods, other than the control rod being withdrawn, in a five by five array centered on the control rod being withdrawn, are disarmed every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.Amendment No. 228 3/4.14-4 LIMITING CONDITIONS FOR OPERATION 3.14 SPECIAL OPERATIONS (continued)

C. Single Control Rod Withdrawal

-Hot Shutdown (continued)

Applicability Hot Shutdown MODE with the reactor mode switch in Refuel position.Actions A. One or more of the above requirements not met, 1. Immediately initiate action to fully insert all insertable control rods, SURVEILLANCE REQUIREMENTS 4.14 SPECIAL OPERATIONS (continued)

C. Single Control Rod Withdrawal

-Hot Shutdown (continued)

AND 2. Place the reactor mode switch in the Shutdown position within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.Amendment No. 228 3/4.14-5 1 LIMITING CONDITIONS FOR OPERATION 3.14 SPECIAL OPERATIONS (continued)

D. Single Control Rod Withdrawal

-Cold Shutdown Specification The MODE definition specified in Specification 1.0 for Cold Shutdown may be changed to include the reactor mode switch in the Refuel position, and operation considered not to be in Refuel MODE, to allow withdrawal of a single control rod, provided the following requirements are met: 1. Two source range monitors (SRM) are OPERABLE per Specification 3.10.B.1 and 3.1 0.B.2, 2.a The Refuel Position One-Rod-Out Interlock is OPERABLE, and the"full-in" control rod position indication for each control rod is OPERABLE or the associated control rod drive is disarmed, OR 2.b A control rod withdrawal block is inserted, 3. All other control rods are fully inserted, and 4.a The withdrawn control rod is OPERABLE, and Table 3.1.1,"Reactor Protection System (Scram)Instrumentation Requirement," channels for the following Trip Functions are OPERABLE as required for the Refuel MODE:-IRM -High Flux-IRM -Inoperative

-SDIV High Water Level -East-SDIV High Water Level -West-Mode Switch in Shutdown-Manual Scram OR 4.b All other control rods in a five by five array centered on the control rod being withdrawn are disarmed; at which time LCO 3.3.A.1, "Reactivity Margin -Core Loading, "requirements may be changed to allow the single control rod withdrawn to be assumed to be the strongest control rod.SURVEILLANCE REQUIREMENTS 4.14 SPECIAL OPERATIONS (continued)

D. Single Control Rod Withdrawal

-Cold Shutdown 1. Two Source Range Monitors (SRM)are OPERABLE per Specification 4.10.B "Core Monitoring".

2.a Perform functional test of the one-rod-out interlock weekly.Additionally, each time the control rod is withdrawn from the "full-in" position, verify the control rod position indication has no "full-in" indication.

OR 2.b Verify a control rod block is inserted every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.3. Verify all control rods, other than the control rod being withdrawn, are fully inserted every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.4.a.1 Verify the Surveillance Requirements of Tables 4.1.1 and 4.1.2 for channels required to be OPERABLE for the Refuel MODE are performed as required, and 4.a.2 Verify withdrawn control rod accumulator pressure is greater than minimum required every 7 days, and 4.a.3 Insert each withdrawn control rod at least one notch within 7 days after control rod is withdrawn and every 7 days thereafter.

OR 4.b Verify all control rods, other than the control rod being withdrawn, in a five by five array centered on the control rod being withdrawn, are disarmed every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.Amendment No. 228 3/4.14-6 1 LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.14 SPECIAL OPERATIONS (continued) 4.14 SPECIAL OPERATIONS (continued)

D. Single Control Rod Withdrawal

-Cold D. Single Control Rod Withdrawal

-Cold Shutdown (continued)

Shutdown (continued)

Aoplicability Cold Shutdown MODE with the reactor mode switch in Refuel position.Actions A. With one or more of the above requirements not met with the affected control rod insertable, 1. Immediately initiate action to fully insert all insertable control. rods, AND 2. Place the reactor mode switch in the Shutdown position within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.B. With one or more of the above requirements not met with the affected control rod not insertable, 1. Immediately suspend withdrawal of the control rod and removal of associated CRD, AND 2.1 Immediately initiate action to fully insert all control rods.OR 2.2 Immediately initiate action to satisfy the requirements of this LCO.Amendment No. 228 3/4.14-7 1 LIMITING CONDITIONS FOR OPERATION 3.14 SPECIAL OPERATIONS (Continued)

SURVEILLANCE REQUIREMENTS 4.14 SPECIAL OPERATIONS (Continued)

E. Multiple Control Rod Removal E. Multiole Control Rod Removal 1. Any number of control rods and/or control rod drive mechanisms may be removed from the reactor pressure vessel provided that at least the following requirements are satisfied until all control rods and control rod drive mechanisms are reinstalled and all control rods are fully inserted in the core.a. The reactor mode switch is OPERABLE and locked in the Refuel position except that the position indication may be bypassed, as.required, for those control rods and/or control rod drive mechanisms to be removed, after the fuel assemblies have been removed as specified below.b. *Two source range monitors (SRM) are OPERABLE per Specification 3.10.B.1 and 3.10.B.2, c. The Reactivity Margin requirements of Specifications 3.3.A.1 are satisfied.

d. No fuel is being loaded into the reactor core.e. All other control rods are fully inserted.f. The four fuel assemblies are removed from the core cell surrounding each control rod or control rod drive mechanism to be removed from the core and/or reactor vessel.1. Within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> prior to the start of removal of control rods and/or control rod drive mechanisms from the core and/or reactor pressure vessel and at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> thereafter until all control rods and control rod drive mechanisms are reinstalled and all control rods are fully inserted in the core, verify that: a. The reactor mode switch is OPERABLE and locked in the Refuel position.b. Two Source Range Monitors (SRM) are OPERABLE per Specification 4.10.1B"Core Monitoring".

c. The Reactivity Margin requirements of Specification 3.3.A.1 are satisfied.

d. Deleted e. All other control rods are fully inserted.f. The four fuel assemblies surrounding each control rod and/or control rod drive mechanism that is to be removed from the reactor vessel at the same time are removed from the core and/or reactor vessel.Amendment No. 228 3/4.14-8 1 LIMITING CONDITIONS FOR OPERATION 3.14 SPECIAL OPERATIONS (continued)

F. (Not Used)SURVEILLANCE REQUIREMENTS 4.14 SPECIAL OPERATIONS (continued)

F. (Not Used)Amendment No. 228 3/4.14-9 1 LIMITING CONDITIONS FOR OPERATION 3.14 SPECIAL OPERATIONS (continued)

G. Control Rod Testing -Operating Specification The requirements of LCO 3.3.H, "Rod Pattern Control," may be suspended to allow performance of reactivity margin demonstrations, control rod scram time testing, control rod friction testing, and the Startup Test Program,'provided:

1. The banked position withdrawal sequence requirements of SR 4.3.F.3 are changed to require the control rod sequence to conform to the specified test sequence, SURVEILLANCE REQUIREMENTS 4.14 SPECIAL OPERATIONS (continued)

G. Control Rod Testingi -Operatinga

1. Prior to control rod movement, verify control rod sequence input to the RWM is in conformance with the approved control rod sequence for the specified test, OR OR 2. The RWM is bypassed; the requirements of LCO 3.3.F, "Rod Worth Minimizer,u are suspended; and conformance to the approved control rod sequence for the specified test is verified by a second licensed operator or other qualified member of the technical staff.Applicability Run MODE and startup MODE with the requirements of LCO 3.3.H not met.Actions Above requirements not met immediately suspend performance of the test and exception to LCO 3.3.H.2. During control rod movement, verify movement of control rods is in compliance with the approved control rod sequence for the specified test by a second licensed operator or other qualified member of the technical staff.Amendment No. 22-1-, 228 3/4.14-10 1