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

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 SURVEILLANCE REQUIREMENTS 3.10 CORE ALTERATIONS (Cont) 4.10 CORE ALTERATIONS (Cont)

B. Core Monitoring (Cont) B. Core Monitoring (Cont)

2. The SRM shall have a minimum of 3 Spiral Reload cps except as specified in 3 and 4 below. During spiral reload, SRM operability will be verified by using a portable external

3. Prior to spiral unloading, the SRM's 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 shall have an initial count rate of _>3 amount of fuel is loaded to maintain 3 cps.

cps. During spiral unloading, the As an alternative to the above, up to two count rate on the SRM's may drop fuel assemblies will be loaded in different below 3 cps. cells containing control blades around each SRM to obtain the required 3 cps.

4. During spiral reload, each control cell Until these assemblies have loaded, the shall have at least one assembly with cps requirement is not necessary.

a minimum exposure of 1000 MWD/ST.

C. Spent Fuel Pool Water Level C. Spent Fuel Pool Water Level Whenever irradiated fuel is stored in the Whenever irradiated fuel is stored in the spent spent fuel pool, the pool water level shall be fuel pool, the water level shall be recorded maintained at or above 33 feet. daily.

Amendment No. 39, 41, 106,199, 228 3/4.10-2

LIMITING COND1ITONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.14 SPECIAL OPERATIONS (continued) 4.14 SPECIAL OPERATIONS (continued)

B. (Not Used) B. (Not Used)

Amendment No. 22-1-, 228 3/4.14-3

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.14 SPECIAL OPERATIONS (continued) 4.14 SPECIAL OPERATIONS (continued)

C. Single Control Rod Withdrawal - Hot C. Single Control Rod Withdrawal - Hot Shutdown 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 1. Two Source Range Monitors (SRM)

OPERABLE per Specification 3.10.B.1 are OPERABLE per Specification and 3.10.B.2, 4.10. B "Core Monitoring".

2. The Refuel Position One-Rod-Out 2. Perform functional test of the one-Interlock is OPERABLE, rod-out interlock weekly.

3. The "full-in" control rod position indication 3. Each time the control rod is for each control rod is OPERABLE or the withdrawn from the "full-in" position, associated control rod drive is disarmed, verify the control rod position indication has no "full-in" indication.

4. All other control rods are fully inserted, and 4. Verify all control rods, other than the control rod being withdrawn, are fully 5.a The withdrawn control rod is inserted every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

OPERABLE, and Table 3.1.1, uReactor Protection System (Scram) 5.a.1 Verify the Surveillance Instrumentation Requirement," channels Requirements of Tables 4.1.1 and for the following Trip Functions are 4.1.2 for channels required to be OPERABLE as required for the Refuel OPERABLE for the Refuel MODE MODE: are performed as required,

- IRM - High Flux

- IRM - Inoperative 5.a.2 Verify withdrawn control rod

- SDIV High Water Level - East accumulator pressure is greater

- SDIV High Water Level - West than minimum required every 7

- Mode Switch in Shutdown days, and

- Manual Scram 5.a.3 Insert each withdrawn control rod at OR least one notch within 7 days after control rod is withdrawn and every 7 5.b All other control rods in a five by five days thereafter.

array centered on the control rod being OR withdrawn are disarmed; at which time LCO 3.3.A.1, "Reactivity Margin - Core 5.b Verify all control rods, other than the Loading," requirements may be changed control rod being withdrawn, in a five to allow the single control rod withdrawn by five array centered on the control to be assumed to be the strongest rod being withdrawn, are disarmed control rod. 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 SURVEILLANCE REQUIREMENTS 3.14 SPECIAL OPERATIONS (continued) 4.14 SPECIAL OPERATIONS (continued)

C. Single Control Rod Withdrawal - Hot C. Single Control Rod Withdrawal - Hot Shutdown (continued) 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, 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 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 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)

1. Two source range monitors (SRM) are are OPERABLE per Specification OPERABLE per Specification 3.10.B.1 4.10.B "Core Monitoring".

and 3.1 0.B.2, 2.a The Refuel Position One-Rod-Out 2.a Perform functional test of the one-Interlock is OPERABLE, and the rod-out interlock weekly.

"full-in" control rod position indication Additionally, each time the control for each control rod is OPERABLE or rod is withdrawn from the "full-in" the associated control rod drive is position, verify the control rod disarmed, position indication has no "full-in" indication.

OR 2.b A control rod withdrawal block is OR inserted, 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. All other control rods are fully inserted, and 3. Verify all control rods, other than the control rod being withdrawn, are fully 4.a The withdrawn control rod is inserted every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

OPERABLE, and Table 3.1.1, "Reactor Protection System (Scram) 4.a.1 Verify the Surveillance Requirements Instrumentation Requirement," of Tables 4.1.1 and 4.1.2 for channels for the following Trip channels required to be OPERABLE Functions are OPERABLE as required for the Refuel MODE are performed for the Refuel MODE: as required, and

- IRM - High Flux 4.a.2 Verify withdrawn control rod

- IRM - Inoperative accumulator pressure is greater than

- SDIV High Water Level - East minimum required every 7 days, and

- SDIV High Water Level - West

- Mode Switch in Shutdown 4.a.3 Insert each withdrawn control rod at

- Manual Scram least one notch within 7 days after control rod is withdrawn and every 7 OR days thereafter.

4.b All other control rods in a five by five OR array centered on the control rod being withdrawn are disarmed; at 4.b Verify all control rods, other than the which time LCO 3.3.A.1, "Reactivity control rod being withdrawn, in a five Margin - Core Loading, "requirements by five array centered on the control may be changed to allow the single rod being withdrawn, are disarmed control rod withdrawn to be assumed every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

to be the strongest control rod.

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 SURVEILLANCE REQUIREMENTS 3.14 SPECIAL OPERATIONS (Continued) 4.14 SPECIAL OPERATIONS (Continued)

E. Multiple Control Rod Removal E. Multiole Control Rod Removal

1. Any number of control rods and/or control 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 rod drive mechanisms may be removed control rods and/or control rod drive from the reactor pressure vessel provided mechanisms from the core and/or reactor that at least the following requirements pressure vessel and at least once per 24 are satisfied until all control rods and hours thereafter until all control rods and control rod drive mechanisms are control rod drive mechanisms are reinstalled reinstalled and all control rods are fully and all control rods are fully inserted in the inserted in the core. core, verify that:

a. The reactor mode switch is a. The reactor mode switch is OPERABLE OPERABLE and locked in the Refuel and locked in the Refuel position.

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 b. Two Source Range Monitors (SRM) are OPERABLE per Specification 3.10.B.1 OPERABLE per Specification 4.10.1B and 3.10.B.2, "Core Monitoring".

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

d. No fuel is being loaded into the reactor

d. Deleted core.

e. All other control rods are fully inserted. e. All other control rods are fully inserted.

f. The four fuel assemblies are removed f. The four fuel assemblies surrounding from the core cell surrounding each each control rod and/or control rod drive control rod or control rod drive mechanism that is to be removed from the mechanism to be removed from the reactor vessel at the same time are core and/or reactor vessel. removed from the core and/or reactor vessel.

Amendment No. 228 3/4.14-8 1

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.14 SPECIAL OPERATIONS (continued) 4.14 SPECIAL OPERATIONS (continued)

F. (Not Used) F. (Not Used)

Amendment No. 228 3/4.14-9 1

LIMITING CONDITIONS FOR OPERATION SURVEILLANCE REQUIREMENTS 3.14 SPECIAL OPERATIONS (continued) 4.14 SPECIAL OPERATIONS (continued)

G. Control Rod Testing - Operating G. Control Rod Testingi - Operatinga 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 1. Prior to control rod movement, verify sequence requirements of SR 4.3.F.3 control rod sequence input to the are changed to require the control rod RWM is in conformance with the sequence to conform to the specified approved control rod sequence for test sequence, the specified test, OR OR

2. The RWM is bypassed; the 2. During control rod movement, verify requirements of LCO 3.3.F, "Rod movement of control rods is in Worth Minimizer,u are suspended; and compliance with the approved conformance to the approved control control rod sequence for the rod sequence for the specified test is specified test by a second licensed verified by a second licensed operator operator or other qualified member or other qualified member of the of the technical staff.

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.

Amendment No. 22-1-, 228 3/4.14-10 1