ML062570483

From kanterella
Jump to navigation Jump to search

Technical Specifications, Issuance of Amendments Adoption of Alternative Source Term Methodology, MB6530, MB6531, MB6532, MB6533, MC8275, MC8276, MC8277 & MC8278
ML062570483
Person / Time
Site: Dresden, Quad Cities  
Issue date: 09/11/2006
From:
Plant Licensing Branch III-2
To:
banerjee M, NRR/ADRO/DORL, 415-2277
Shared Package
ML062070292 List:
References
TAC MB6530, TAC MB6531, TAC MB6532, TAC MB6533, TAC MC8275, TAC MC8276, TAC MC8277, TAC MC8278
Download: ML062570483 (52)
v • d • e


Text

Definitions 1.1 1.1 Definitirns (continued)

CHANNEL FUNCTIONAL TEST CORE ALTERATION A CHANNEL FUNCTIONAL TEST shall be the injection of a simulated or actual signal into the channel as close to the sensor as practicable to verify OPERABILITY of all devices in the channel required for channel OPERABILITY.

The CHANNEL FUNCTIONAL TEST may be performed by means of any series of sequential, overlapping, or total channel steps.

CORE ALTERATION shall be the movement of any fuel,

sources, or reactivity control components, within the reactor vessel with the vessel head removed and fuel in the vessel.

The following exceptions are not considered to be CORE ALTERATIONS:

a.

Movement of source range monitors, local power range monitors, intermediate range monitors, traversing incore probes, or special movable detectors (including undervessel replacement);

and

b.

Control rod movement, provided there are no fuel assemblies in the associated core cell.

Suspension of CORE ALTERATIONS shall not preclude completion of movement of a component to a safe position.

The COLR is the unit specific document that provides cycle specific parameter limits for the current reload cycle.

These cycle specific limits shall be determined for each reload cycle in accordance with Specification 5.6;5.

Plant operation within these limits is addressed in individual Specifications.

DOSE EQUIVALENT 1-131 shall be that concentration of 1-131 (microcuries/gram) that alone would produce the same dose as the quantity and isotopic mixture of 1-131, 1-132, 1-133, 1-134, and 1-135 actually present.

The dose conversion factors used for this calculation shall be the inhalation committed dose conversion factors in Federal CORE OPERATING LIMITS REPORT (COLR)

DOSE EQUIVALENT 1-131 (continued)

(continued)

Dresden 2 and 3 I1.I-1-2 Amendment No.

221/212

Definitions 1.1 1.1 Definitions DOSE EQUIVALENT 1-131 Guidance Report 11, "Limiting Values of (continued)

Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submersion, and Ingestion," 1939.

LEAKAGE LEAKAGE shall be:

a.

Identified LEAKAGE

1.

LEAKAGE into the drywell, such as that from pump seals or valve packing, that is captured and conducted to a suMp or collecting tank; or

2.

LEAKAGE into the drywell atmosphere from sources that are both specifically located and known either not to interfere with the operation of leakage detection systems or not to be pressure boundary LEAKAGE;

b.

Unidentified LEAKAGE All LEAKAGE into the drywell that is not identified LEAKAGE; C.

Total LEAKAGE Sun of the identified and unidentified LEAKAGE; and

d.

Pressure Boundary LEAKAGE LEAKAGE through a nonisolable fault in a Reactor Coolant System (RCS) component body, pipe wall, or vessel wall.

(continued)

Dresden 2 and 3 1.1-3 Amendment No.

221/212

SLC System 3.1.7 3.1 REACTIVITY COMTROL SYSTEMS 3.1.7 Standby Liquid Control (SLC)

System LCO 3.1.7 Two SLC subsystems shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, and 3.

I ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One SLC subsystem A.1 Restore SLC subsystem 7 days inoperable, to OPERABLE status.

B.

Two SLC subsystems B.1 Restore one SLC 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> inoperable, subsystem to OPERABLE status.

C.

Required Action and C.1 Be in MODE 3.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> associated Completion Time not met.

AND C.2 Be in MODE 4.

36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> Dresden 2 and 3 3.1.7-1 Amendment No.

221/212

Primary Containment Isolation instrumentation 3.3.6.1 T tble 2.1.6 1-1 (page 3 of 3:

Primary Containmer,: Iso!ation Inszumenr:irGn APPLICABLE COND ifOti

'IUDES lIR REQUIRED REFERENCED OTHER CHANNELS iROM SPECIFIED PER TRIP REQUIRED SURVEILLANCE ALLOWABLE ijilcTiOH CONI[,ITIONS SYSTEM ACF1iON C. I REJREI4ENTS VALUE

5.

Reactor Water Cleanup System Isolatiun

a.

SLC System Initiation 1.2,3 1

H SP 3.3.6.1.1 NA

b.

Reac-or Vessel Water 1.2,3 2

F SR 3.3.b.I.l 1 2.65 inches.

Loel -LUw SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.6 SR 3.3.6.1.7

6.

Shutdown Cooling System Isolation

a.

Recirculation Line 1,2,3 2

F SR 3.3.6.1.2 s 346°F Water SR 3.3.6.1.6 Temperature-High SR 3.3.6.1.7

b.

Reactor Ve-sel Wat.r 3,4,5 21A 1

SR 3.3.6.1.1 Z 2.65 inches Level-Low SR 3.3.6.1.2 SR 3.3.6.1.3 SR 3.3.6.1.6 SR 3.3.6.1.7 (b) In MODES 4 and 5, provided Shutdown Cooling System integrity is maintained, only one channel per trip system with an Isolation signal available to one shutdown cooling pump suc:ion isolation valve is required.

Dresden 2 and 3 3. 3. 6.I-7 Amendment No.

221/212

Secondary Containment Isolation Instrumentation 3.3.6.2 Ib :

-..2.6.2-1 (Pige I Cf Ii Secondary Containment [501a0o 011 Instrumen-a0ion APPLICABLE MODES OR REOULRED OTHER CHANNELS SPECIFIED PER SURVEILLANCE ALLOWABLE FIJNCI [ON CONDITIONS TRIP SYSTE1 REOUIREMENTS VALUE

1. Reactor Vessel Water 1,2,3, 2

SR 3.3.6.2.1 2 2.65 inches Level-Low (a)

SR 3.3.6.2.2 SR 3.3.6.2.3 SR 3.3.6.2.5 SR 3.3.6.2.6

2.

Orywell-Pressure-High 1,2.3 2

SR 3.3.6.2.2 s 1.94 psig SR 3.3.6.2.4 SR 3.3.6.2.6

3.

Reactor Building Exhaust 1.2.3, 2

SR 3.3.6.2.1 s 14.9 mR/hr Radiation-High (a).(bl SR 3.3.6.2.2 SR 3.3.6.2.4 SR 3.3.6.2.6

4.

Refueling Floor 1,2,3.

2 SR 3.3.6,2.1 s 100 mR/hr Radiation-High (a),(b)

SR 3.3.6.2.2 SR 3,3.6.2.4 SR 3.3.6.2.6 (a)

During operations with d potential for draining the reactor vessel.

(b)

During movemennt of recently irradiated fuel assemblies In secondary containment.

I Dresden 2 and 3 3.3.6.2-4 Amendment No.

221/212

CREV System instrumentation 3.3.7.1 3.3 INSTRUMENTATION 3*3.7,1 Control Room Emergency Ventilation (CREV)

System Instrumentation LCO 3.3.7.1.

APPLICABILITY:

Two channels of the Reactor Building Ventilation System-High High Radiatioii Alarm Function shall be OPERABLE.

MODES 1, 2, and 3, During movement of recently irradiated fuel assemblies in the secondary containment, During operations with a potential for draining the reactor vessel (OPDRVs).

IJ ACTIONS

NOTE -------------------------------------

Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A.

One or more channels A. I Declare CREV System 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> from inoperable.

inoperable, discovery of loss of CREV System Instrumentation alarm capability in both trip systems AND A.2 Restore channel to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> OPERABLE status.

(continued)

Dresden 2 and 3 3.3.7.1-1 Amendment No.

221/212

PCIVs 3.4.1. 3 SURVEILLANCE REQUiREMENTS SURVEILLANCE FREQUENCY SR 3.6.1.3.10 Verify the leakage rate through each MSIV In accordance leakage path is : 34 scfh 1when tested at with the 2 25 psig, and the combined leakage rate Primary for all MSIV leakage paths is

  • 86 scfh Containment when tested at Ž 25 psig.

Leakage Rate Testing Program Dresden 2 and 3 3.6.1.3-9 Amendment No.

221/212

Secondary Containment 3,6.4.1 3.6 CONTAINMENT SYSTEMS 3.6.4.1 Secondary Containment LCO 3.6.4.1 The secondary containment shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, and 3, During movement of recently irradiated the secondary containment, During operations with a potential for vessel (OPDRVs).

fuel assemblies in draining the reactor II ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

Secondary containment A.1 Restore secondary 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> inoperable in MODE 1, containment to 2, or 3.

OPERABLE status.

B.

Required Action and B.1 Be in MODE 3.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> associated Completion Time of Condition A AND not met.

B.2 Be in MODE 4.

36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> C.

Secondary containment C.1

NOTE ---------

inoperable during LCO 3.0.3 is not movement of recently applicable.

irradiated fuel assemblies in the secondary containment Suspend movement of Immediately or during OPDRVs.

recently irradiated fuel assemblies in the secondary containment.

AND C.2 Initiate action to Immediately suspend OPDRVs.

Dresden 2 and ')

3.6.4.1-1 Amendment No.

221/212

Secondary Containment 3.6.4.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.4.1.1 Verify secondary containment vacuum is 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />

> 0.25 inch of vacuum water gauge.

SR 3.6.4.1.2 Verify one secondary containment access 31 days door in each access opening is closed.

SR 3.6.4.1.3 Verify the secondary containment can be 24 months on a maintained Ž 0.25 inch of vacuum water STAGGERED TEST gauge for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> using one SGT subsystem BASIS for each at a flow rate

  • 4000 cfm.

SGT subsystem SR 3.6.4.1.4 Verify all secondary containment 24 months equipment hatches are closed and sealed.

Dresden 9.

and 3 3.6.4.1-2 Amendment No.

221/212

C CI VIS

61.
4. 2 3.6 CONTAINMENT SYSTEMS 3.6.4.2 Secondary Containment Isolation Valves (SCIVs)

LCO 3.6.4.2 APPLICABILITY:

Each SCIV shall be OPERABLE.

MODES 1, 2, and 3, During movement of recently irradiated fuel assemblies in the secondary containment, During operations with a potential for draining the reactor vessel (OPDRVs).

ACTIONS

NOTES ------------------------------------

1. Penetration flow paths may be unisolated intermittently under administrative controls.
2.

Separate Condition entry is allowed for each penetration flow path.

3.

Enter applicable Conditions and Required Actions for systems made inoperable by SCIVs.

CONDITION REQUIRED ACTION COMPLETION TIME A.

One or more A.1 Isolate the affected 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> penetration flow paths penetration flow path with one SCIV by use of at least inoperable, one closed and de-activated automatic valve, closed manual valve, or blind flange.

AUn u

I (continued)

Dresden 2 and 3 3.6.4.2-1 Amendment No.

221/212

SCIVs 1.6.4.2 ACTION'S CONDITION REQUIRED ACTION COMPLETION TIME C.

Required Action and C.1 Be in MODE 3.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> associated Completion Time of Condition A AND or B not met in MODE 1, 2, or 3.

C.2 Be in MODE 4.

36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> D.

Required Action and D.1

NOTE ---------

associated Completion LCO 3.0.3 is not Time of Condition A applicable.

or B not met during movement of recently irradiated fuel Suspend movement of Immediately assemblies in the recently irradiated secondary containment fuel assemblies in or during OPDRVs.

the secondary containment.

AND D.2 Initiate action to Immediately suspend OPDRVs.

Dresden 2 and 3 3.6.4.2-3 Amendment No.

221/212

SGT System

3.
6. 4.3 3.6 CONITAINMENT SYSTEMS 3.6.4.3 Standby Gas Treatment (SGT)

System LCO 3.6.4.3 Two SGT subsystems shall be OPERABLE.

APPLICABILITY:

MODES 1, 2, and 3, During movement of recently irradiated the secondary containment, During operations with a potential for vessel (OPDRVs).

fuel assemblies in draining the reactor ii ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One SGT subsystem A.1 Restore SGT 7 days inoperable, subsystem to OPERABLE status.

B.

Required Action and B.1 Be in MODE 3.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> associated Completion Time of Condition A AND not met in MODE 1, 2, or 3.

B.2 Be in MODE 4.

36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> C.

Required Action and

NOTE ------------

associated Completion LCP 3,0.3 is not applicable.

Time of Condition A not met during movement of recently C.1 Place OPERABLE SGT Immediately irradiated fuel subsystem in assemblies in the operation.

secondary containment or during OPDRVs.

OR (continued)

Dresden 2 and 3 3.6.4.3-1 Amendment No.

221/212

SGT System 3.6.4.3 ACT ION S CONDITION PEQUIRED ACTION COMPLETION TIME C.

(continued)

C.2.1 Suspend movement of Immediately recently irradiated fuel assemblies in secondary containment.

AND C.2.2 Initiate action to Immediately suspend OPDRVs.

D.

Two SGT subsystems D.1 Restore one SGT I hour inoperable in MODE 1, subsystem to 2, or 3.

OPERABLE status.

E.

Required Action and E.1 Be in MODE 3.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> associated Completion Time of Condition 0 AND not met.

E.2 Be in MODE 4.

36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> F.

Two SGT subsystems F.1

NOTE --------

inoperable during LCO 3.0.3 Is not movement of recently applicable.

irradiated fuel assemblies in the secondary containment Suspend movement of Immediately or during OPDRVs.

recently irradiated fuel assemblies in secondary containment.

AND F.2 Initiate action to Immediately suspend OPDRVs.

Dresden 2 and 3 3.6.4.3-2 Amendment No.

221/212

SGT System 3.6.4.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.6.4.3.1 Operate each SGT subsystem for 31 days

> 10 continuous hours with heaters operating.

SR 3.6.4.3.2 Perform required SGT filter testing in In accordance accordance with the Ventilation Filter with the VFTP Testing Program (VFTP).

SR 3.6.4.3.3 Verify each SGT subsystem actuates on an 24 months actual or simulated initiation signal.

Dresden 2 and 3 3.6,4.3-3 Amendment No. 221/212

CREV Sys tern 3.7.4 3.7 PLAIIT SYSTEMS 3.7.4 Control Room Emergency Ventilation (CREV)

System LCO

3.7.4 APPLICABILITY

The CREV System shall be OPERABLE.

MODES 1, 2, and 3, During movement of recently irradiated fuel assemblies in the secondary containment, During operations with a potential for draining the reactor vessel (OPDRVs).

II ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

CREV System inoperable A.1 Restore CREV System 7 days in MODE 1, 2, or 3.

to OPERABLE status.

B.

Required Action and 8.1 Be in MODE 3.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> associated Completion Time of Condition A AND not met in MODE 1, 2, or 3.

B.2 Be in MODE 4.

36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> C.

CREV System inoperable

NOTE -------------

during movement of LCO 3.0.3 is not applicable.

recently irradiated fuel assemblies in the secondary containment C.1 Suspend movement of Immediately or during OPDRVs.

recently irradiated fuel assemblies in the secondary containment.

AUD C.2 Initiate action to Immediately suspend OPDRVs.

Dresden 2 and 3 3.7.4-1 Amendment No.

221/212

CREV System 3.7.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.4.1 Operate the CREV System for Ž 10 continuous 31 days hours with the heaters operating.

SR 3.7.4.2 Perform required CREV filter testing in In accordance accordance with the Ventilation Filter with the VFTP Testing Program (VFTP).

SR 3.7.4.3 Verify the CREV System actuates on a manual 24 months initiation signal.

SR 3.7.4.4 Verify the CREV System can maintain a 24 months positive pressure ofŽe 0.125 inches water gauge relative to the adjacent areas during the isolation/pressurization mode of operation at a flow rate of

Dresden 2 and 3 3.7.4-2 Amendment No.

221/212

Control Room Emergency Ventilation AC System 3.7.

1.7 PLANT SYSTEMS 3.7.5 Control Room Emergency Ventilation Air Conditioning (AC)

System LCO

3.7.5 APPLICABILITY

The Control Room Emergency Ventilation AC System shall be OPERABLE.

MODES 1, 2, and 3, During movement of recently irradiated fuel assemblies in the secondary containment, During operations with a potential for draining the reactor vessel (OPDRVs).

Jt ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

Control Room Emergency A.1 Restore Control Room 30 days Ventilation AC System Emergen.cy Ventilation inoperable in MODE 1, AC System to OPERABLE 2, or 3.

status.

B.

Required Action and B.1 Be in MODE 3.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> associated Completion Time of Condition A AND not met in MODE 1, 2, or 3.

B.2 Be in MODE 4.

36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> C.* Control Room Emergency ------------ NOTE -------------

Ventilation AC System LCO 3.0.3 is not applicable.

inoperable during movement of recently irradiated fuel C.1 Suspend movement of Immediately assemblies in the recently irradiated secondary containment fuel assemblies in or during OPDRVs.

the secondary containment.

AND C.2 Initiate action to Immediately suspend OPORVs.

Dresden 2 and 3 3.7.5-1 Amendment No.

221/212

Control Room Emergency Ventilation AC System 3.7.5 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.5.l Verify the Control Room Emergency 24 months Ventilation AC System has the capability to remove the assumed heat load.

Dresden 2 and 3 3.7.5-2 Amendment No.

221/212

AC Sources-Operating 3.8.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.1.20 -------------------

NOTE --------------------

All DG starts may be preceded by an

.ngine prelube period.

Verify, when started simultaneously from 10 years standby condition, each OG achieves, in

13 seconds, voltage Ž 3952 V and frequency Ž 58.8 Hz.

SR 3.8.1.21

NOTE-----------------

When the opposite unit is in MODE 4 or 5, or moving recently irradiated fuel assemblies in secondary containment, the following opposite unit SRs are not required to be performed: SR 3.8.1.3, SR 3.8.1.10 through SR 3.8.1.12, and SR 3.8.1.14 through SR 3.8.1.17.

For required opposite unit AC electrical In accordance power sources, the SRs of the opposite with applicable unit's Specification 3.8.1, except SRs SR 3.8.1.9, SR 3.8.1.13, SR 3.8.1.18, SR 3.8.1.19, and SR 3.8.1.20, are applicable.

I Dresden 2 and 3 3.8.1-15 Amendment No.

221/212

AC Sources-Shutdown 3,8.2 3.8 ELECTRICAL POWER SYSTEMS 3.8.2 AC Sources-Shutdown LCO 3.8.2 The following AC electrical power sources shall be OPERABLE:

a.

One qualified circuit between the offsite transmission network and the onsite Class IE AC electrical power distribution subsystem(s) required by LCO 3.8.8, "Distribution Systems-Shutdown"; and

b.

One diesel generator (DG) capable of supplying one division of the onsite Class 1E AC electrical power distribution subsystem(s) required by LCO 3.8.8.

MODES 4 and 5, During movement of recently 'irradiated fuel assemblies in the secondary containment.

APPLICABILITY:

I Dresden 2 and 3 3.8.2-1 Amendment No.

221/212

AC Sources-Shutdown 3.8.2 ACT IONS CONDITION REQUIRED ACTION COMPLETION TIME A.

(continued)

A.2.2 Suspend movement of Immediately recently irradiated fuel assemblies in the secondary containment.

A.2.3 Initiate action to Immediately suspend operations with a potential for draining the reactor vessel (OPDRVs).

AND A.2.4 Initiate action to Immediately restore required offsite power circuit to OPERABLE status.

(continued)

Dresden 2 and 3 3.8.2-3 Amendment No.

221/212

AC SOL~rceS-ShUtdown ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B.

One required DG B.1 Suspend CORE Immediately inoperable, ALTERATIONS.

AND B.2 Suspend movement of Immediately recently irradiated fuel assemblies in secondary containment.

AND B.3 Initiate action to Immediately suspend OPDRVs.

AND B.4 Initiate action to Immediately restore required DG to OPERABLE status.

I Dresden 2 and 3I 3.8.2-4 Amendment No.

221/212

DC Sources-Shutdown 3.3.5 3.8 ELECTRICAL POWER SYSTEMS 3.8.5 DC Sources-Shutdown LCO

3.8.5 APPLICABILITY

One 250 VDC and one 125 VDC electrical power subsystem shall be OPERABLE to support the 250 VDC and one 125 VDC Class 1E electrical power distribution subsystems required by LCO 3.8.8, "Distribution Systems-Shutdown."

MODES 4 and 5, During movement of recently irradiated fuel assemblies in the secondary containment.

I ACTIONS

NOTE -------------------------------------

LCO 3.0.3 is not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A.

One or more required A.1 Declare affected Immediately DC electrical power required feature(s) subsystems inoperable.

inoperable.

OR A.2.1 Suspend CORE Immediately ALTERATIONS.

A.2.2 Suspend movement of Immediately recently irradiated fuel assemblies in the secondary containment.

AND I_

(continued)

I Dresden 2 and 3 3.8.5-1 Amendment No.

221/212

Distribution Systems-Shutdown 3.8,8 3.8 ELECTRICAL POWER SYSTEMS 3.8.8 Distribution Systems-Shutdown LCO 3.8.8 The necessary portions of the AC, DC, and the opposite unit's Division 2 electrical power distribution subsystems shall be OPERABLE to support equipment required to be OPERABLE.

APPLICABILITY:

MODES 4 and 5, During movement of recently irradiated fuel assemblies in the secondary containment.

ACTIONS

NOTE-LCO 3.0.3 is not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A.

One or more required A.1 Declare associated Immediately AC or DC electrical supported required power distribution feature(s) subsystems inoperable.

Inoperable.

OR A.2.1

  • Suspend CORE Immediately ALTERATIONS.

AND (continued)

I Dresden 2 and 3 3.8.8-1 Amendment No. 221/212

Distribution Systems-Shutdown 3.8,8 ACT ION S CONDITION REQUIRED ACTION COMPLETION TIME A.

(continued)

A.2.2 Suspend movement of recently irradiated fuel assemblies in the secondary containment.

AND A.2.3 Initiate action to suspend operations with a potential for draining the reactor vessel.

AND A.2.4 Initiate actions to restore required AC and DC electrical power distribution subsystems to OPERABLE status.

AND A.2.5 Declare associated required shutdown cooling subsystem(s) inoperable and not in operation.

Immediately Immediately Immediately Immediately SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.8.1 Verify correct breaker alignments and 7 days voltage to required AC and DC electrical power distribution subsystems.

Dresden 2 and 3 3.8.8-2 Amendment No.

221/212

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.1L Primary Containment Leakage Rate Testing Program (continued)

2.

NE! 94 1995, Section 9.2.3:

The first Unit 3 Type A test performed after the July 14,

1994, Type A test shall be performed no later than July 13, 2009.
b.

The peak calculated primary containment internal pressure for the design basis loss of coolant accident, P,,

is 43.9 psig.

c.

The maximum allowable primary containment leakage rate, L,,

at P,, is 3% of primary containment air weight per day.

d.

Leakage rate acceptance criteria are:

1. Primary containment overall leakage rate acceptance criterion is ! 1.0 L,.

During the first unit startup following testing in accordance with this program, the leakage rate acceptance criteria are : 0.60 L, for the combined Type B and Type C tests, and ! 0.75 L, for Type A tests.

2.

Air lock testing acceptance criteria is the overall air lock leakage rate is

  • 0.05 L, when tested at Ž P,.
e.

The provisions of SR 3.0.3 are applicable to the Primary Containment Leakage Rate Testing Program.

5.5.13 Battery Monitoring and Maintenance Program This Program provides for restoration and maintenance, based on the recommendations of IEEE Standard 450-1995, "IEEE Recommended Practice for Maintenance, Testing, and Replacement of Vented Lead-Acid Batteries for Stationary Applications," including the following:

a.

Actions to restore battery cells with float voltage

< 2.13 V, and

b.

Actions to equalize and test battery cells that had been discovered with electrolyte level below the minimum established design limit.

Dresden 2 and 3 5.5-12 Amendment No.

221/212

DE f I ; I i t inS 1.1 0 filn riClS CHANNEL CHECK icontinuedi CHANNEL FUNCTIONAL TEST CORE ALTERATION status derived from independent instrument channels measuring the same parameter, A CHANNEL FUNCTIONAL TEST shall be the injection of a simulated or actual signal into the channel

.as close to the sensor as practicable to verify OPERABILITY of all devices in the channel required for channel OPERABILITY.

The CHANNEL FUNCTIONAL TEST may be performed by means of any series of sequential, overlapping, or total channel steps.

CORE ALTERATION shall be the movement of any fuel, sources, or reactivity control components, within the reactor vessel with the vessel head removed and fuel in the vessel.

The following exceptions are not considered to be CORE ALTERATIONS:

a.

Movement of source range monitors, local power range monitors, intermediate range monitors, traversing incore probes, or special movable

.detectors (including undervessel replacement);

and

b.

Control rod movement, provided there are no fuel assemblies in the associated core cell.

Suspension of CORE ALTERATIONS shall not preclude completion of movement of a component to a safe position.

CORE OPERATING LIMITS REPORT (COLR)

DOSE EQUIVALENT 1-131 The COLR is the unit specific document that provides cycle specific parameter limits, for the current reload cycle.

These cycle specific limits shall be determined for each reload cycle in accordance with Specification 5.6.5.

Plant operation within these limits is addressed in Individual Specifications.

DOSE EQUIVALENT 1-131 shall be that concentration of 1-131 (microcuries/gram) that alone would produce the same dose as the quantity and isotopic mixture of 1-131, 1-132, 1-133, 1-134, and 1-135 actually present.

The dose conversion factors used for this calculation shall be the inhalation committed dose conversion factors in Federal Il (conti nued)

Quad Cities I and 2 1.1-2 Amendment No.

233/229

Cei Lions~

1.1 1.1 GefW'*ti]cs DOSE EQUIVALENT [-131 Guidance Report ii, "Limiting Values of Cconri Vi ed:

Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submei'sion, and Ingestion," 1989.

LEAKAGE LEAKAGE shall be:

a.

Identified LEAKAGE

1.

LEAKAGE into the drywell, such as that from pump seals or valve packing, that is captured and conducted to a sump or collecting tank; or

2.

LEAKAGE into the drywel) atmosphere from sources that are both specifically located and known either not to interfere with the operation of leakage detection systems or not to be pressure boundary LEAKAGE;

b.

Unidentified LEAKAGE All LEAKAGE into the drywell that is not identified LEAKAGE;

c.

Total LEAKAGE Sum of the identified and unidentified LEAKAGE; and

d.

Pressure Boundary LEAKAGE LEAKAGE through a nonisolable fault in a Reactor Coolant System (RCS) component body, pipe wall, or vessel wall.

(continued)

Quad Cities I and 2 1.1-3 Amendment No.

233/229

SLC System j.1.,

I.1 REACTI1[ITI CONTROL SY'STEMS 3.1.7 Standby Liquid Control (SISC)

System LCO

3.1.7 APPLICABILITY

Two SLC subsystems shall be OPERABLE.

MODES 1, 2, and 3.

I ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One SLC subsystem A.1 Restore SLC subsystem 7 days inoperable, to OPERABLE status.

B.

Two SLC subsystems B.1 Restore one SLC 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> inoperable, subsystem to OPERABLE status.

C.

Required Action and C.1 Be in MODE 3.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> associated Completion Time not met.

AND C.2 Be in MODE 4.

36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> Quad Cities 1 and 2 3.1.7-1 Amendment No.

233/229

Primaryi Cont a ni Ert 1rc a ti on I n Strument ati on

.ie 3.6.i-1

p. APPLICABLE CON1" EIOtiS MOOES OR REIJI RED REFEREINCEO OTHER CHAHIIEL5 FROM SPECIF1ED PER TRIP REGUIR.ED SUME I LLANMA ALL6WARLE FIJNCT ION COMOMTIONS SYSTEH ACTION C.1 REMUIfREMENTS VALUE 5

ReJc r.w r Water 171 eanip CSys zemf lsuiricOn a

SLC Systrm initiation L1.23 t

H SR 3.31.1..

NA

0.

Reactcr V2&-e, Water 1.2,3 2

1 SR 3.3.6.i.1 a 2.6 inches Level-Law SR 3.3.6.1.2 SR 3.3.6. 1.3 SR 3.3.6.1.6 SR 3.3.6.1.1

6.

RHR Shutdown Cooling Sy*tem I0sola3tion

a.

Reactor Vessel 1.2,3 2

F SR 3.3.6.1.2 130 psi4 Pressure-High SR 3.3.6.1.4 SR 3.3.6.1.7

b.

Reactur Vessel Water 3,4.5 21(b)

I SR 3.3.6.1.1

In MODES 4 and 5, provided RIIR Shutdown Cooling System integrity is maintained, only one channel per trip systein with an isolation signal available to Coe shutdown cColing pump Suctlon isolation valve is required.

I Quad Cities I and 2 3.3.6.1-7 Amendment No.

233/229

2ecc~~~nd~~~y Lotimn rs~t~

UntLmen t-a t on, Td~

2.2.6 P

1 ~g e

APPLICAILLE

  • 0DEL OR REQUIRED OIIER CHAIMELS SPECIFIED PER SURVE!LLANCE ALLOWABLE FUHUMCTI CONDi'IOtS rR[P S"SfEM RE.UtLREMEV4IS 4ALUE
i. Reuctor Vesiel,ater 1.2,3, 2

SR 3.3.6.2.1 1

3.8 inches

-a; SR 3.3.6.2.2 SR 3.3.6.2.3 SR 3.3.6.2.5 SR 3.3.6.2.6

2.

Orywe.I Pressure-High 1,2.3 2

SR 3.3.6.2.2

-< 2.43 psig SR 3.3.6.2.4 SR 3.3.6.2.6

3.

Raictor Building Exhaust 1.2.3, 2

SR 3.3.6.2.1

_< 9 mR/hr Radiatton-liiqgh (a),(bJ SR 3.3.6.2.2 SR 3.3.6.2.4 SR 3.3.6.2.6

4.

Refueiing floor 1,2.3, 2

SR 3.3.6.2.1

100 nR/hr Radiation-Hi*'h (3),(bl SR 3.3.6.2.2 SR 3.3.6.2.4 SR.3.3.6.2.6 (a)

During operations wi1th a poteni~tal for draining~ the reactor vessel (b)

During movement of recenzly irradiated fuel assemblies In secondary containment.

I Quad Cities 1 and 2 3.3.6.2-4 Amendment No.

233/229

":REV -ystEm Ici - tion 1nsturtenuati.i,

!i*bi-. 3.2.7.1 1 (pagE I 6f Iý Co,, R. ý

  • cn Erierg;.nr.y lj.%n*. iatlo)r, (CRLI)

Sys*em lcoý l.=i'

!!*n.-Er umant a:1,)n A-IFLICAlIE MIOES OR OTiiER SPECIFIED CONlO

{T {OTS REQUIRED CHAUNLLS PER iPIP SY STE,4 COlOI~iiOriS REFERENCED FR~OM REQUIRED

CTION A.1 SURVEILLANCE REQUEREMENTS A, I OniAlLE 4ALIIE FIIUNCH ION i

Reactor Vetisei ý)ater Le l

4-L u

-Ow

2.

DrywalIl Prfessure--fligh (al I.2,3 SR SR SR SR CSR 3.3.7.1.1 3.3.7.1.2 3.3.1.1.3 3 3.7. 1.5 3.3. 7.1.6

> 3.3 iricnhe 2

C SR 3.3.7.1.2 SR 3.3.1.1.4 SR 3.3.7.1.6

< 2.43 psly

3.

Main Steam Line Flow-lHigh 1,2,3 2 per HSL

4.

Refueling Floor Radlation-High

5.

Reactor Building Ventilation Ehdaust RadiatIon-HIgh 1.2,3.

(a),(b) 2 a

SR SR SR SR SR B

SR SR SR SR a

SR SR SR SR 3.3.7.1.1 3.3.7.1.2 3.3.7.1.3 3.3.7.1.5 3.3.7.1.6 3.3.7.1.1 3.3.7.1.2 3.3.7.1.4 3.3.7.1.6 3.3. 7.1A 3.3.7.1.2 3.3.7.1.4 3.3.7.1.6 5 248.1 psidc-

5 100 mR/hr 1,2,3, (a),(b) 2

-5 9 mR/hr (a)

During operations with a potential for draining zhe reactor vessel, (b)

During movement of recently irradiated fuel assembfles In the secondary containment.

(c) Function 3 is OPERABLE wi-h an actual Trip Setpoint value found outside its calibration tolerance band provided the Trip Setpoint value Is conservative with respect to Its associated Allowable Vaiue and the channel is re-adjusted to within the established setting tolerance band of the flominal Trip Setpoint.

I Quad Cities I and 2 3.3.7.1-4 Amendment No.

233/229

P I-VI' 3 613 IURV ILLANCL REQU I REMENTS SUPV E I LLAHC E F P EQU EICY P. 3 6.1....

II Verify the leakage rate through each MSIV in accordarc;_e leakage path is < 34 scfh when tested at with the

> 25 psig, and the combined leakage rate Primary for all MSIV leakage paths is < 86 scfh Containment when tested at Ž> 25 psig.

Leakage Rate Testing Program Quad Cities I and 2 3.6.1.3-8 Amendment No.

233/229

Ie~d yCzt mn 3.6 CCOiTArIi'IENT S (STEMS 6ý.. 4 1 I condJa-n t a inmr: i LCO 3 6,4.1 The secondary containment shall be OPERABLE.

APPLICABILITY:

MODES 1 2, and 3, During movement of recently irradiated the secondary containment, During operations with a potential for vessel (OPDRVs).

fuel assemblies in draining the reactor II ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

Secondary containment A.1 Restore secondary 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> inoperable in MODE 1, containment to 2, or 3.

OPERABLE status.

B.

Required Action and B.1 Be in MODE 3.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> associated Completion Time of Condition A AND not met.

B.2 Be in MODE 4.

36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> C.

Secondary containment C.

NOTE ---------

inoperable during LCO 3.0.3 is not movement of recently applicable.

irradiated fuel assemblies in the secondary containment Suspend movement of Immediately.

or during OPDRVs.

recently irradiated fuel assemblies in the secondary containment.

AN C.2 Initiate action to Immediately suspend OPDRVs.

Quad Cities 1 and 2 3.6.4.1-1 Amendment No. 233/229

3

a.

.4.

-URVEILLANCE REQUIREMENTS SURVEI LLAI.NCE I

EQUENC' SR 3.6.4.i.I Verify secondary containment vacuum is 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 0.10 inch of vacuum water gauge.

SR 3.6.4.1.2 Verify one secondary containment access 31 days door in each access opening is closed.

SR 3.6.4.1.3 Verify the secondary containment can be 24 months on a maintained Ž 0.25 inch of vacuum water STAGGERED TEST gauge for I hour using one SGT subsystem BASIS for each at a flow rate : 4000 cfm.

SGT subsystem SR 3.6.4.1.4 Verify all secondary containment 24 months equipment hatches are closed and sealed.

Quad Cities 1 and 2 3.6.4.1-2 Amendment No.

233/229

C I~I ~

'3.6.4.2

.6 CONTAHIMiENT SYSTEMS 3.6.4.2

%ecundary Containment Isolation Valves (SC[Vs)

LCO 3.6.4.2 APPLICABILIT'I:

Each SCIV shall be OPERABLE.

MODES 1, 2, and 3, Ouring movement of recently irradiated fuel assemblies in the secondary containment, During operations with a potential for draining the reactor vessel (OPDRVs).

II ACTIONS

NOTES ------------------------------------

1. Penetration flow paths may be unisolated intermittently under administrative controls.
2.

Separate Condition entry is allowed for each penetration flow path.

3.

Enter applicable Conditions and Required Actions for systems made inoperable by SCIVs.

CONDITION REQUIRED ACTION COMPLETION TIME A.

One or more A.1 Isolate the affected 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> penetration flow paths penetration flow path with one SCIV by use of at least inoperable, one closed and de-activated automatic valve, closed manual valve, or blind flange.

AND (continued)

Quad Cities 1 and 2 3'.6.4.2-1 Amendment No.

233/229

SC L/s

.4.2 ACT I ON'S COND ITION REQUIRED ACTION COMIPLETION TINE C.

Required Action and C.1 Be in MODE 3.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> associated Completion Time of Condition A AND or B not met in MODE 1, 2, or 3.

C.2 Be in MODE 4.

36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> D.

Required Action and D.-I

NOTE-------

associated Completion LCO 3.0.3 is not Time of Condition A applicable.

or B not met during movement of recently irradiated fuel Suspend movement of Immediately assemblies in the recently irradiated secondary containment fuel assemblies in or during OPDRVs.

the secondary containment.

AND D.2 Initiate action to Immediately suspend OPDRVs.

Quad Cities 1 and 2 3.6.4.2-3 Amendment No.

233/229

SC...

j-3.

I

y.

4 3 3.6 CONTA HIIMENIT SI'TEMS 1.6.4.3 StanIoy Gas Treatment (SGT)

System LCO 3.6.4.3 APPLICABILITi':

Two SGT subsystems shall be OPERABLE.

MODES 1, 2, and 3, During movement of recently irradiated fuel assemblies in the secondary containment, During operations with a potential for draining the reactor vessel (OPDRVs).

II ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One SGT subsystem A.1 Restore SGT 7 days inoperable, subsystem to OPERABLE status.

B.

Required Action and B.1 Be in MODE 3.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> associated Completion Time of Condition A AND not met in MODE 1, 2, or 3.

B.2 Be in MODE 4.

36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> C.

Required. Action and

NOTE ------------

associated Completion LCO 3.0.3 is not applicable.

Time of Condition A not met during movement of recently C.1 Place OPERABLE SGT Immediately irradiated fuel subsystem in assemblies in the operation.

secondary containment or during OPDRVs.

OR I_

(continued)

Quad Cities I and 2 3.6.4.3-1 Amendment No. 233/229

SGT Si/scem CONDITIO N REQUIRED ACTION COMPLETION TIME C,

icnt.i nued C.2.L Suspend movement of Immediately recently irradiated fuel assemblies in secondary cuntainment.

AMD, C.2.2 Initiate action to Immediately suspend OPDRVs.

D.

Two SGT subsystems D.1 Restore one SGT 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> inoperable in MODE 1, subsystem to 2, or 3.

OPERABLE status.

E.

Required Action and E.1 Be in MODE 3.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> associated Completion Time of Condition D AU not met.

E.2 Be in MODE 4.

36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> F.

Two SGT subsystems F.1

NOTE --------

inoperable during LCO 3.0.3 is not movement of recently applicable.

irradiate.d fuel assemblies in the secondary containment Suspend movement of Immediately or during OPDRVs.

recently irradiated fuel assemblies in secondary containment.

AND F.2 Initiate action to Immediately suspend OPDRVs.

I Quad Cities 1 and 2 3.6.4.3-2 Amendment No.

233/229

t ez M:

SURV E i LLArlCE R.E I0I 1 PE MIE INT S SURVEILLANCE FREQUIElC Y SR 3.6.4.3.I Operate each SGT subsystem for 31 days 10 contin-Luous hours with heaters operating.

SR 3 6 4 3.2 Perform required SGT filter testing in In accordance accordance with the Ventilation Filter with the VFTP Testing Program (VFTP).

SR 3.6.4.3.3 Verify each SGT subsystem actuates on an 24 months actual or simulated initiation signal.

Quad Cities 1 and 2 3.6.4.3-3 Amendment No.

233/229

CF.EI 4 c Z-M 371.4 3.,

PL.-fIT 2K TEMS 3.7.4 Control Room Emergency Ventilation (CREV)

System LCO

3.7.4 APPLICABILITY

The CREV System shall be OPERABLE.

MODES 1, 2, and 3, During movement of recently irradiated fuel assemblies in the secondary containment, During operations with a potential for draining the reactor vessel (OPDRVs).

II ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

CREV System inoperable

'A.1 Restore CREV System 7 days in MODE 1, 2, or 3.

to OPERABLE status.

B.

Required Action and B.1 Be in MODE 3.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> associated Completion Time of Condition A AND not met in MODE 1, 2, or 3.

B.2 Be in MODE 4.

36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> C.

CREV System inoperable ------------ NOTE-----------

during movement of LCO 3.0.3 is not applicable.

recently irradiated fuel assemblies in the secondary containment C.1 Suspend movement of Immediately or during OPDRVs.

recently irradiated fuel assemblies in the secondary containment.

AND C.2 Initiate action to Immediately suspend OPDRVs.

Quad Cities 1 and 2

3. 7.4-1 Amendment No.

233/229

C REV Eis7efn

.7.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCe SR 37.4.1 Operate the CREV System for e 10 continuous 31 days hours with the heaters operating.

SR

3. 1.4.2 Perform required CREV filter testing in In accordance accordance with the Ventilation Filter with the VFTP Testing Program (VFTP),

SR 3.7.4.3 Verify the CREV System isolation dampers 24 months close on an actual or simulated initiation signal.

SR 3.7.4.4 Verify the CREV System can maintain a 24 months positive pressure of z 0.125 inches water gauge relative to the adjacent areas during the pressurization mode of operation at a flow rate of

Quad Cities 1 and 2 3.7.4-2 Amendment No. 233/229

Conrtrol Room Emergency Ventilation AC

!)jstem

-77.

7 PLAhT SYVTEMH 37.5 Control Pc,,,m Emergency Ventilation Air Conditioning (AC)

System LCO

3.7.5 APPLICABILITY

The Control Room Emergency Ventilation AC System shall be OPERABLE.

MODES 1, 2, and 3, During movement of recently irradiated fuel assemblies in the secondary containment, During operations with a potential for draining the reactor vessel (OPDRVs).

II ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

Control Room Emergency A.1 Restore Control Room 30 days Ventilation AC System Emergency Ventilation inoperable in MODE 1, AC System to OPERABLE 2, or 3.

status.

B.

Required Action and B.A Be in MODE 3.

12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> associated Completion Time of Condition A AND not met in MODE 1, 2, or 3.

B.2 Be in MODE 4.

36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> C.

Control Room Emergency ------------ NOTE -------------

Ventilation AC System LCO 3.0.3 is not applicable.

inoperable during movement of recently irradiated fuel C.1 Suspend movement of Immediately assemblies in the recently irradiated secondary containment fuel assemblies in or during OPDRVs.

the secondary containment.

AND C.2 Initiate action to Immediately suspend OPDRVs.

Quad Cities 1 and 2 3.7.5-1 Amendment No.

233/229

Control Poom Emergency Ventilation AC Syztem 3,7,5C SURVEILLANCE REQUIREMENTS SUJVE[I LLANICE FREQUEl!CY SR 3 7 5.1 Verify the Control Room Emergency 24 months Ventilation AC System has the capability to remove the assumed heat load.

Quad Cities I and 2 3.7.5-2 Amendment No. 233/229

-L Sources-Operating 3.3.1 SURVEILLANCE REQUiR.EMEiMITS SURVE i LLANCE FREGOJEiC I SR 3 -.

.1.

,20

.-.NOTE...

All DG starts may be preceded by an engine prelube period,

Verify, when started simultaneously from I0 years standby condition, each OG achieves, in

_< 13 seconds, voltage _ 3952 V and frequency _Ž 58.8 Hz.

SR 3.8.1.21 NOTE --------------------

When the opposite unit is in MODE 4 or 5, or moving recently irradiated fuel assemblies in secondary containment, the following opposite unit SRs are not required to be performed: SR 3.8.1.3, SR 3.8.1.10 through SR 3.8.1.12, and SR 3.8.1.14 through SR 3.8.1.17.

For required opposite unit AC electrical In accordance power sources, the SRs of the opposite with applicable unit's Specification 3.8.1, except SRs SR 3.8.1.9, SR 3.8.1.13, SR 3.8.1.18, SR 3.8.1.19, and SR 3.8.1.20, are applicable.

I Quad Cities I and 2 3.8.1-15 Amendment No.

233/229

ACS0LI-C orE Liht io* in 3.8 ELECTRICAL POWER SYSTEMS 3.8.

2 AC 41 ur*es-ShuLdown LCO 3.8.2 The following AC electrical power sources shall be OPERABLE:

a.

One qualified circuit between the offsite transmission network and the onsite Class 1E AC electrical power distribution subsystem(s) required by LCO 3.8.8, "Distribution Systems-Shutdown"; and

b.

One diesel generator (DG) capable of supplying one division of the onsite Class IE AC electrical power distribution subsystem(s) required by LCO 3.8.8.

MODES 4 and 5, During movement of recently irradiated fuel assemblies in the secondary containment.

APPLI*CABILITY:

I Quad Cities 1 and 2 3.8.2-1 Amendment No.

233/229

Ai-S6 U CC z-S-j ULtOrn11 3.3.

2 ACTIONS CONDI TION REQUIRED ACTION COMFLETION TIME A.

fconTinupd)

A.2,2 Suspend movement of Immediately recently irradiated fuel assemblies in the secondary containment.

AND A.2.3 Initiate action to Immediately suspend operations with a potential for draining the reactor vessel (OPDRVs).

A.2.4 Initiate action to Immediately restore required offsite power circuit to OPERABLE status.

(continued)

I Quad Cities I and 2 3.8.2-3 Amendment No.

233/229

AC Sources-Shutj-iwn CONDITION REQUIRED ACTION COMPLETION TIME S.

One required DG B.I Suspend CORE Immediately inoperable.

ALTERATIONS.

AND B.2 Suspend movement of Immediately recently irradiated fuel assemblies in secondary containment.

AND B.3 Initiate action to Immediately suspend OPDRVs.

B.4 Initiate action to Immediately restore required DG to OPERABLE status.

I Quad Cities 1 and 2 3.8.2-4 Amendment No. 233/229

DC SjurCES-S~hLitdo,-'wn

.a ELECTRICAL POWER S.(STEMS

.23.5 DC Sources-Shutdown LCO 3.8.5 One 250 VDC and one 125 VDC electrical power subsystem shall be OPERABLE to support the 250 VDC and one 125 VOC Class 1E electrical power distribution subsystems required by LCO 3.8.8, "Distribution Systems-Shutdown."

APPLICABILITY:

MODES 4 and 5, During movement of recently irradiated fuel assemblies in the secondary containment.

ACTIONS

NOTE---------------------------------

LCO 3.0.3 is not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A.

One or more required A.1 Declare affec.ted Immediately DC electrical power required feature(s) subsystems inoperable, inoperable.

A.2.1 Suspend CORE Immediately ALTERATIONS.

AND A.2.2 Suspend movement of Immediately recently irradiated fuel assemblies in the secondary containment.

AND I (continued)

I I

Quad Cities 1 and 2 3.8.5-1 Amendment No. 233/229

Distribution Systems-Shutdown

.8 ELECTRIC AL POWER SYSTEIIS 8,

I8 Oistribution Systems-Shutdown LCO

3.8.8 APPLICABILITY

The necessary portions of the AC, DC, and the opposite unit's electrical power distribution subsystems shall be OPERABLE to support equipment required to be OPERABLE.

MODES 4 and 5, During movement of recently irradiated fuel assemblies in the secondary containment.

ACTIONS NOTE -------------------------------------

LCO 3.0.3 is not applicable.

CONDITION REQUIRED ACTION COMPLETION TIME A.

One or more required A.1 Declare associated Immediately AC or DC electrical supported required power distribution feature(s) subsystems inoperable, inoperable.

OR A.2.1 Suspend CORE Immediately ALTERATIONS.

I_

(continued)

Quad Cities 1 and 2 3.8.8-1 Amendment No. 233/229

Distribution Systems-Shutdown I.

A C Ii.J W)

CCiDITION REQUIRED ACTION COMPLETIJrA T[ME A.

( rorr iniied I A.2.2 Suspend movement of recently irradiated fuel assemblies in the secondary containment.

A.2.3 Initiate action to suspend operations with a potential for draining the reactor vessel.

A.2.4 Initiate actions to restore required AC and OC electrical power distribution subsystems to OPERABLE status.

AtND A.2.5 Declare associated required shutdown cooling subsystem(s) inoperable and not in operation.

Immediately Immediately Immediately Immediately I

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.8.8.1 Verify correct breaker alignments and 7 days voltage to required AC and DC electrical power distribution subsystems.

Quad Cities I and 2 3.8.8-2 Amendment No.

233/229

Programs ard Manuals

r.

PgrograTs aid Manuals 5.5.12 Primar, Containment Leakage Rate Testing Program (corLtinued)

2.

NEI 94-01

1995, Section 9.2.3:

The first Unit 2 Type A test performed after the May 17,

1993, Type A test shall be performed no later than May 16, 2008.
b.

The peak calculated primary containment internal pressure for the design basis loss of coolant accident, P,, is 43.9 psig.

c.

The maximum allowable primary containment leakage rate, L,,

at P,, is 3% of primary containment air weight per day.

d.

Leakage rate acceptance criteria are.

1.

Primary containment overall leakage rate acceptance criterion is

1.0 La.

During the first unit startup following testing in accordance with this program, the leakage rate acceptance criteria are ! 0.60 La for the combined Type B and Type C tests, and ! 0.75 La for Type A tests.

2.

Air lock testing acceptance criteria is the overall air lock leakage rate is 5 0.05 La when tested at 2 Pa.

e.

The provisions of SR 3.0.3 are applicable to the Primary Containment Leakage Rate Testing Program.

Quad Cities I and 2 5.5-12 Amendment No. 233/229

Retrieved from "https://kanterella.com/w/index.php?title=ML062570483&oldid=5358078"