ML081780254

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Technical Specifications, Limerick Unit 1, Amendment 192, License NPF-39
ML081780254
Person / Time
Site: Limerick  Constellation icon.png
Issue date: 08/05/2008
From:
NRC/NRR/ADRO/DORL/LPLI-2
To:
Bamford, Peter J., NRR/DORL 415-2833
Shared Package
ml081780155 List:
References
TAC MD7508, TAC MD7509
Download: ML081780254 (16)
v • d • e


Text

(3)

Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to receive, possess and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4)

Pursuant to the Act and 10 CFR Parts 30, 40, 70, to receive, possess, and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument calibration or associated with radioactive apparatus or components; and (5)

Pursuant to the Act and 10 CFR Parts 30, 40 and 70, to possess, but not separate, such byproduct and special. nuclear materials as may be produced by the operation of the facility, and to receive and possess, but not.

separate, such source, byproduct, and special nuclear materials as contained in the fuel assemblies and fuel channels from the Shoreham Nuclear Power Station.

  • C.

This license shall be deemed to contain and is subject to the conditions specified in the Commission's regulations set forth in 10 CFR Chapter I (except as exempted from compliance in Section 2.D. below) and is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect; and is subject to the additional conditions specified or incorporated below:

(1)

Maximum Power Level Exelon Generation Company is authorized to operate the facility at reactor core power levels not in excess of 3458 megawatts thermal (100% rated power) in accordance with the conditions specified herein and in Attachment 1 to this license. The items identified in Attachment 1 to this license shall be completed as specified. Attachment 1 is hereby incorporated into this license.

(2)

Technical Specifications' The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 192, are hereby incorporated into this license.

Exelon Generation Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

Amendment No. 62, 1-06, 1-8-1-, 447 1 92

INDEX DEFINITIONS SECTION DEFINITIONS (Continued)

PAGE 1.20a LOW (POWER)

TRIP SETPOINT (LTSP).........................

1-4 1.21 (DELETED)

I 1-4 1.22 MEMBER(S)

OF THE PUBLIC

.................................... 1-4 1.22a MAPFAC(F)

(MAPLHGR FLOW FACTOR).....

I......................1-4 1.22b MAPFAC(P)

(POWER DEPENDENT MAPLHGR MULTIPLIER)............. 1-4 1.23 MINIMUM CRITICAL POWER RATIO (MCPR)........................

-4 1.24 OFFSITE DOSE CALCULATION MANUAL............................

1-4 1.25 OPERABLE - OPERABILITY........................................

1-4 1.2.6 OPERATIONAL CONDITION CONDITION........................... 1-5 1.27 PHYSICS TESTS

............................................. 1-5 1.28 PRESSURE BOUNDARY LEAKAGE..................................

1-5 1.2.9 PRIMARY CONTAINMENT INTEGRITY..............................

1-5 1.30 PROCESS CONTROL PROGRAM

.................................... 1-5 1.31 PURGE PURGING................................................

1-6 1.32 RATED THERMAL POWER............................................

1-6 1.33 REACTOR ENCLOSURE SECONDARY CONTAINMENT INTEGRITY............ 1-6 1.34 REACTOR PROTECTION SYSTEM RESPONSE TIME.......................

1-6 1.35 RECENTLY IRRADIATED FUEL...................................

1-6 1.36 REFUELING FLOOR SECONDARY CONTAINMENT INTEGRITY.............. 1-6 1.37 REPORTABLE EVENT...

1-7 1.37a RESTRICTED AREA

........................................... 1-7 1.38 ROD DENSITY...................................................

1-7 1.39 SHUTDOWN MARGIN...............................................

1-7 1.40 SITE BOUNDARY.................................................

1-7 1.41 SOURCE CHECK..................................................

1-7 LIMERICK - UNIT 1 i i Amendment No.

-34, 48, -52, 6-6,192

INDEX ADMINISTRATIIVE CONTROLS SECTION PAGE 6.5.2-Deleted Deleted................

6-9 Deleted...................................................

.. 6-9 Deleted

................................................ 6-10 Deleted.. "..............................................

6-10 Deleted....................................................

6-10 Deleted................................................

6-10 Deleted

................................................ 6-10 Deleted....................................................

6-12 6.5.3 Deleted..................

6-12 6.6 REPORTABLE EVENT ACTION............................................

6-12a 6.7 SAFETY LIMIT VIOLATION.........................................

6-12a 6.8 PROCEDURES AND PROGRAMS 6-13 6.9 REPORTING REQUIREMENTS 6.9.1 ROUTINE REPORTS............................................

6-15 Startup Report..............................................

6-15 Annual Reports

.......................................... 6-15 Monthly Operating Reports..................................

6-16 Annual Radiological Environmental Operating Report.........

6-16 Annual Radioactive Effluent Release Report.................

6-17 CORE OPERATING LIMITS REPORTS............................

6-18a 6.9.2 SPECIAL REPORTS......................................... 6-18a 6.10 DELETED...........................................................

6-19 6.11 RADIATION PROTECTION PROGRAM.....................................

6-20 6.12 HIGH RADIATION AREA................................................

6-20 LIMERICK - UNIT 1 xxvi i Amendment No.

-;, 4-;, 44, 4-7-, 192

REACTIVITY CONTROL-SYSTEMS CONTROL ROD DRIVE COUPLING LIMITING CONDITION FOR OPERATION 3.1.3.6 All control rods shall be coupled to their drive mechanisms.

APPLICABILITY:

OPERATIONAL CONDITIONS 1, 2, and 5*.

ACTION:

a.

In OPERATIONAL CONDITIONS 1 and 2 with one control rod not coupled to its associated drive mechanism, within 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />s:

1.

If permitted by the RWM, insert the control rod drive mechanism to accomplish recoupling and verify recoupling by withdrawing the control rod, and:

a)

Observing any indicated response of the nuclear instrumenta-tion, and b)

Demonstrating that the control rod will not go to the over-travel position.

Otherwise, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

2.

If recoupling is not accomplished on the first attempt.or, if not permitted by the RWM, then until permitted by the RWM, declare the control rod inoperable, insert the control rod and disarm the associated directional control valves** either:

a)

Electrically, or b)

Hydraulically by closing the drive water and exhaust water isolation valves.

Otherwise, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

b.

In OPERATIONAL CONDITION 5*

with a withdrawn control rod not coupled to its associated drive mechanism, within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> either:

1.

Insert the control rod to accomplish recoupling and verify recoup-ling by withdrawing the control rod and demonstrating that the control rod will not go to the overtravel position, or

2.

If recoupling is not accomplished, insert the control rod and disarm the associated directionalcontrol valves** either:

a)

Electrically, or b)

Hydraulically by closing the drive water and exhaust water isolation valves.

At least each withdrawn control rod.

Not applicable to control rods removed per Specification 3.9.10.1 or 3.9.10.2.

May be rearmed intermittently, under administrative control, to permit testing associated with restoring the control rod to OPERABLE status.

LIMER T CK - UNIT 1 3/4 1.-11 Amendment No.

-, 4, 14-64, 192

REACTIVITY CONTROL SYSTEMS SURVEILLANCE REQUIREMENTS 4.1.3.6 Each affected control rod shall be demonstrated to be coupled to its drive mechanism by observing any indicated response of the nuclear instrumen-tation while withdrawing the control rod to the fully withdrawn position and then verifying that the control rod drive does not go to the overtravel position:

a.

Prior to reactor criticality, after completing CORE ALTERATIONS that could have affected the control.rod drive coupling integrity,

b.

Anytime the control rod is withdrawn to the "Full out" position in subsequent operation, and

c.

Following maintenance on or modification to the control rod or control rod drive system which could haveaffected the control rod drive coupling integrity.

LIMERICK - UNIT 1 3/4 1-12 Amendment No.

4-2-4, 192

Section 3.3.7.2 (Deleted)

THE INFORMATION FROM THIS TECHNICAL SPECIFICATIONS SECTION HAS BEEN RELOCATED TO THE TRM.

TECHNICAL SPECIFICATIONS PAGES 3/4 3-69 THROUGH 3/4 3-72 OF THIS SECTION HAVE BEEN INTENTIONALLY OMITTED.

LIMERICK - UNIT 1 3/4 3-68 Amendment No. 44, 4-,

--5192

Section 3/4.3.8 (Deleted)

THE INFORMATION FROM THIS TECHNICAL SPECIFICATIONS SECTION HAS BEEN RELOCATED TO THE TRM.

TECHNICAL SPECIFICATIONS PAGE 3/4 3-111 HAS BEEN INTENTIONALLY OMITTED.

LIMERICK - UNIT 1 3/4 3-110 Amendment No.

4-9-9, 192

REACTOR COOLANT SYSTEM 3/4.4.3 REACTOR COOLANT SYSTEM LEAKAGE LEAKAGE DETECTION SYSTEMS LIMITING CONDITION FOR OPERATION 3.4.3.1 The following reactor coolant leakage detection systems shall be OPERABLE:,

a.

The primary containment atmosphere gaseous radioactivity monitoring system,

b.

The drywell floor drain sump flow monitoring system,

c.

The drywell unit coolers condensate flow rate monitoring system, and

d.

The primary containment pressure and temperature monitoring system.

APPLICABILITY:

OPERATIONAL CONDITIONS 1, 2, and 3.*

The primary containment gaseous radioactivity monitor is not required to be operable until Operational Condition 2.

ACTIONS:

A.

With the primary containment atmosphere gaseous radioactivity monitoring system inoperable, analyze grab samples of primary containment atmosphere at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> AND restore primary containment atmosphere gaseous radioactivity monitoring system to OPERABLE status within 30 days.

B.

With the drywell floor drain sump flow monitoring system inoperable, restore the drywell floor drain sump flow monitoring system to OPERABLE status within 30 days AND increase monitoring frequency of drywell unit cooler condensate flow rate (SR 4.4.3.2.1.c) to once every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

C.

With the drywell unit coolers condensate flow rate monitoring system inoperable, AND the primary containment atmosphere gaseous radioactivity monitoring system

OPERABLE, perform a channel check of the primary containment atmosphere gaseous radioactivity monitoring system (SR 4.4.3.1.a) once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

D.

With the primary containment pressure and. temperature monitoring system inoperable, restore the primary containment pressure and temperature monitoring system to OPERABLE status within 30 days.

NOTE:

All other Tech Spec Limiting Conditions For Operation and Surveillance Requirements associated with the primary containment pressure/temperature monitoring system still apply.

Affected Tech Spec Sections include:

3/4.3.7.5. 4.4.3.2.1. 3/4.6.1.6. and 3/4.6.1.7.

E.

With the primary containment atmosphere gaseous radioactivity monitoring system inoperable AND the drywell unit coolers condensate flow rate monitoring system inoperable, restore the primary containment atmosphere gaseous radioactivity monitoring system to OPERABLE status within 30 days OR restore the drywell unit coolers condensate flow rate monitoring system to OPERABLE status within 30 days.

With the primary containment atmosphere gaseous radioactivity monitoring system inoperable, analyze grab samples of primary containment atmosphere at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

LIMERICK - UNIT 1 3/4 4-8 Amendment ;74, 444, 4-*6, 192

3/4.5 EMERGENCY CORE COOLING SYSTEMS

.3/4.5.1 ECCS -

OPERATING LIMITING CONDITION FOR OPERATION 3.5.1 The emergency core cooling systems-shall be OPERABLE with:

a.

The core spray system (CSS) consisting of two subsystems with each subsystem comprised of:

1.

Two OPERABLE CSS. pumps, and

2.

An OPERABLE flow path capable of taking suction from the suppression chamber and transferring the water through the'spray sparger to the reactor vessel.

1.

One OPERABLE LPCI pump, and

2.

An OPERABLE flow path capable of taking suction from the suppression chamber and transferring the water to the reactor vessel.

c.

The high pressure coolant injection (HPCI) system consisting of:

1.

One OPERABLE HPCI pump, and

2.

An OPERABLE flow path capable of taking suction from the suppression chamber and transferring the water to the reactor vessel.

d.

The automatic depressurization system (ADS) with at least five OPERABLE ADS valves.

APPLICABILITY:

OPERATIONAL CONDITION 1, 2* ** #,

and 3*

  • The HPCI system is not required to be OPERABLE when reactor steam dome pressure is less than or equal to 200 psig.
    • The ADS is not required to be OPERABLE when the reactor steam dome pressure is less that or equal to 100 psig.
  1. See Special Test Exception 3.10.6.
    1. Two LPCI subsystems of the RHR system may be inoperable in that they are aligned in the shutdown cooling mode when reactor vessel pressure is less than the RHR Shutdown cooling permissive setpoint.

LIMERICK - UNIT 1 3/4 5-1 Amendment No.

9-,

8-,

4-34, 192

CONTAINMENT SYSTEMS 3/4.6.3 PRIMARY CONTAINMENT ISOLATION VALVES LIMITING CONDITION FOR OPERATION 3.6.3 Each primary containment isolation valve and each instrumentation lin.e excess flow check valve shall be OPERABLE.

APPLICABILITY:

OPERATIONAL CONDITIONS 1, 2, and 3.

ACTION:

a.

With one or more of the primary containment isolation valves inoperable,**

maintain at least one isolation valve OPERABLE in each affected penetration that is open and within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> either:

1.

Restore the inoperable valve(s) to OPERABLE status, or

2.

Isolate each affected penetration by use of at least one de-activated automatic valve secured in the isolated position,* or

3.

Isolate each affected penetration by use of at least one closed manual valve or blind flange.*

Otherwise, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and, in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

b.

With one or more of the instrumentation line excess flow check valves inoperable, operation may continue and the provisions of Specification 3.0.3 are not applicable provided that within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> either:

1.

The inoperable valve is returned to OPERABLE status, or

2.

The instrument line is isolated and the associated instrument is declared inoperable.

Otherwise, be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in.COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

c.

With one or more scram discharge volume vent or drain valves inoperable, perform the applicable actions specified in Specification 3.1.3.1.

  • Isolation valves closed to satisfy these requirements may be reopened on an intermittent basis under administrative control.

Except for the scram discharge volume vent and drain valves.

LIMERICK - UNIT 1 3/4 6-17 Amendment No.

  • ,-!-4-68,4-64,192

THE INFORMATION FROM THIS TECHNICAL SPECIFICATIONS SECTION HAS BEEN RELOCATED.TO THE TRM.

LIMERICK - UNIT 1 3/4 6-49 Amendment No.

Q-4, 4-4-&,192

THE INFORMATIONFROM THIS TECHNICAL SPECIFICATIONS SECTION HAS BEEN RELOCATED TO THE TRM.

LIMERICK - UNIT I 3/4 6-51 Amendment No.

2*-,

4-g-E, 192

THE INFORMATION FROM THIS TECHNICAL SPECIFICATIONS SECTION HAS BEEN RELOCATED TO THE TRM.

LIMERICK - UNIT 1 3/4 6-51a Amendment No.

2-4, 41O-,192

PLANT SYSTEMS LIMITING CONDITION FOR OPERATION (Continued)

ACTION:

(Continued)

4.

With three ESW pump/diesel generator pairs** inoperable, restore at least.one inoperable ESW pump/diesel generator pair** to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within.the following.24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

5.

With four ESW pump/diesel generator pairs** inoperable, restore at. least one inoperable ESW pump/diesel generator pair** to OPERABLE status within 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />, or be in at least. HQT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

b.

In OPERATIONALCONDITION 4 or 5:

1.

With only one emergency service water pump and its associated flowpath OPERABLE, restore at least two pumps with at least one flow path to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or declare the associated safety related equipment inoperable and take the ACTION required by Specifications 3.5.2 and 3.8.1.2.

c.

In OPERATIONAL CONDITION *

.1.

With only one emergency service water pump and its associated flow path OPERABLE, restore at least two pumps with at. least one flow path to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or verify adequate cool i ng--rema-i ns- -avai-l ab-l e -for-the---di-esel - generators required to be OPERABLE or declare the associated diesel generator(s) inoperable and take the ACTION required by Specification 3.8.1.2.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REOUIREMENT 4.7.1.2 At least.the above required emergency service water system loop(s) shall be demonstrated. OPERABLE:

a.

In accordance with the Surveillance Frequency Control Program by verifying that each valve (manual, power-operated, or automatic) that is not locked, sealed, or otherwise secured in position, is in its correct position.

b.

In accordance with the Surveillance Frequency Control Program by verifying that:

1.

Each automatic valve actuates to its correct position on its appropriate ESW pump start signal.

2.

Each pump starts automatically when its associated diesel generator starts.

    • An ESW pump/diesel generator pair consists of an ESW pump and its associated diesel generator.

If either an ESW pump or its associated diesel generator becomes inoperable, then the ESW pump/diesel generator pair is inoperable.

LIMERICK - UNIT 1 3/4 7-4 Amendment No.

2-T,40,4,;ý,4-9,1 92

ELECTRICAL POWER SYSTEMS A.C.

SOURCES SHUTDOWN LIMITING CONDITION FOR OPERATION 3.8.1.2 As a minimum, the following A.C. electrical power sources shall be OPERABLE:

a.

One circuit between the offsite transmission network and the onsite Class 1E distribution system, and

b.

Two diesel generators each with:

1.

A day fuel tank containin.g a minimum of 200gallons of fuel.

2.

A fuel storage system containing a minimum of 33,500 gallons of fuel

3.

A fuel transfer pump.

APPLICABILITY:

OPERATIONAL CONDITIONS 4, 5, and

  • ACTION:
a.

With less than the above required A.C. electrical power sources

OPERABLE, suspend CORE ALTERATIONS, handling of irradiated fuel in the secondary containment, operations with a potential for draining the reactor vessel and crane operations over the spent fuel storage pool when fuel assemblies are.stored therein.

In addition, when in OPERATIONAL CONDITION 5 with the water level less than 22 feet above the reactor pressure vessel flange, immediately initiate corrective action to restore the required power sources to OPERABLE status as soon as practical.

b.

The provisions, of Specification 3.0.3 are not applicable.

SURVEILLANCE REOUIREMENTS 4.8.1.2 At least the above required A.C. electrical power sources shall be demonstrated OPERABLE per Surveillance Requirements 4.8.1.1.1 and 4.8.1.1.2.

LIMERICK - UNIT 1 3/4 8-9 Amendment No.

43,192

.Section 3/4.8.4.1 (Deleted)

THE INFORMATION FROM THIS TECHNICAL SPECIFICATION SECTION HAS BEEN RELOCATED TO THE TRM.

TECHNICAL SPECIFICATIONS PAGES 3/4 8-21 THROUGH 3/4 8-26 OF THE SECTION HAVE BEEN INTENTIONALLY.OMITTED.

LIMERICK - UNIT 1 3/4 8-21 Amendment No.

3-2,4Q4,-7,-94,192

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