Text

Technical Specifications, Issuance of Amendments Regarding Refueling Interlocks (TAC Nos. MD4444 & MD4445)
	ML072820058
Person / Time
Site:	Hatch
Issue date:	10/04/2007
From:	; NRC/NRR/ADRO/DORL/LPLII-1
To:	;
	Martin R, NRR/DORL, 415-1493
Shared Package
ML072410048	List: ML072410052; ML072820058;
References
	TAC MD4444, TAC MD4445
	Download: ML072820058 (33)
	v • d • e

for sample analysis or Instrument calibration, or associated with radioactive apparatus or components; (6)

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

C.

This renewed license shall be deemed to contain and Is subject to the conditions

. pe-tined in the following Commission regulations inlO CFR Chapter I: Part20, Section 30.34 of Part 30, Section 40.41 of Part 40, Section 50.54 of Part 50, and Section 70.32 of Part 70; all applicable provisions of the Act and the rules, regulations, and orders of the Commission now or hereafter In effect; and the additional conditions specified or Incorporated below;.

(1)

Maximum Power Level Southern Nuclear is authorized to operate the facility at steady state reactor core power levels not In excess of 2804 megawatts thermal.

(2)

Technical Specifications The Technical Specifications (Appendix A) and the Environmental Protection Plan (Appendix B). as revised through Amendment No. 2 5 3 are hereby. Incorporated In the renewed license. Southern Nuclear shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

The Surveillance Requirement (SR) contained In the Technical Specifications and listed below, Is not required to be performed Immediately upon Implementation of Amendment No. 195. The SR listed below shall be successfully demonstrated prior to the time and condition specified:

SR 3.8.1.18 shall be successfully demonstrated at its next regularly scheduled performance

(3)

Fi. Projection Southern Nuclear shall Implement and maintain in effect all provisions of the fire protection program, which Is referenced In the Updated Final 0 -.

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1 as Containe IIn Intho upu=1Vu r-he Hazards Analysis and Fire Protection Program for Edwin I. Hatch Nuclear Plant Units I and 2, which was originally submitted by letter dated July 22, 1986. Southern Nuclear may make changes to the fire protection program without-prior Commission approval only If the changes Renewed License No. DPR-57 Amendment. No. 2 5 3

TABLE OF CONTENTS (continued) 3.6 CONTAINMENT SYSTEMS (continued) 3.6.1.6 Low-Low Set (LLS) Valves..........................................................................

3.6-15 3.6.1.7 Reactor Building-to-Suppression Chamber Vacuum Breakers...................

3.6-17 3.6.1.8 Suppression Chamber-to-Drywell Vacuum Breakers..................................

3.6-19 3.6.2.1 Suppression Pool Average Temperature....................................................

3.6-21

-3.6.2.2---- - Suppression -Pool -Water-Level-...

3.6-24-.

3.6.2.3 Residual Heat Removal (RHR) Suppression Pool Cooling..........................

3.6-25 3.6.2.4 Residual Heat Removal (RHR) Suppression Pool Spray...........................

3.6-27 3.6.3.1 Containment Atmosphere Dilution (CAD) System.......................................

3.6-29 3.6.3.2 Primary Containment Oxygen Concentration..............................................

3.6-31 3.6.4.1 Secondary Containment.............................................................................

3.6-32 3.6.4.2 Secondary Containment Isolation Valves (SCIVs)..................

3.6-35 3.6.4.3 Standby Gas Treatment (SGT) System......................................................

3.6-38 3.7 PLANT SYSTEMS......................................................................................

3.7-1 3.7.1 Residual Heat Removal Service Water (RHRSVV) System..........................

3.7-1 3.7.2 Plant Service Water (PSW) System and Ultimate Heat Sink (UHS)............

3.7-3 3.7.3 Diesel Generator (DG) 1 B Standby Service Water (SSW) System.............

3.7-6 3.7.4 Main Control Room Environmental Control (MCREC) System....................

3.7-8 3.7.5 Control Room Air Conditioning (AC) System...............................................

3.7-12 3.7.6 Main Condenser Offgas..............................................................................

3.7-16 3.7.7 Main Turbine Bypass System.....................................................................

3.7-18 3.7.8 Spent Fuel Storage Pool Water Level.........................................................

3.7-19 3.8 ELECTRICAL POWER SYSTEMS.............................................................

3.8-1 3.8.1 A C Sources - O perating...............................................................................

3.8-1 3.8.2 AC Sources - Shutdown.............................................................................

3.8-20 3.8.3 Diesel Fuel Oil and Transfer, Lube Oil, and Starting Air..............................

3.8-23 3.8.4 DC Sources - Operating..............................................................................

3.8-26 3.8.5 DC Sources - Shutdown.............................................................................

3.8-31 3.8.6 Battery Cell Parameters............................................................................

3.8-33 3.8.7 Distribution Systems - Operating................................................................

3.8-36 q R nic rihe if ien Qw*!cfm Mr hi it+nAo n

02.

1 "e%

istibu ti w

,j 3.9 REFUELING OPERATIONS......................................................................

3.9-1 3.9.1 Refueling Equipment Interlocks.................................................................

3.9-1 3.9.2 Refuel Position One-Rod-Out Interlock.......................................................

3.9-3 3.9.3 Control Rod Position..................

I.................

3.9-4 3.9.4 Control Rod Position Indication...........................................

....................... 3.9-5 3.9.5 Control Rod OPERABILITY - Refueling......................................................

3.9-7 (continued)

HATCH UNIT 1 iii Amendment No. 253

TABLE OF CONTENTS (continued) 3.9 REFUELING OPERATIONS (continued) 3.9.6 Reactor Pressure Vessel (RPV) Water Level..............................................

3.9-8 3.9.7 Residual Heat Removal (RHR) - High Water Level.....................................

3.9-9 3.9.8 Residual Heat Removal (RHR) - Low Water Level......................................

3.9-11 3.10 SPECIAL OPERATIONS 3.10-1 3.10.1 Inservice Leak and Hydrostatic Testing Operation......................................

3.10-1 3.10.2 Reactor Mode Switch Interlock Testing.......................................................

3.10-3 3.10.3 Single Control Rod Withdrawal - Hot Shutdown..........................................

3.10-5 3.10.4 Single Control Rod Withdrawal - Cold Shutdown 3.1,0-8 3.10.5 Single Control Rod Drive (CRD) Removal - Refueling................................

3.10-11 3.10.6 Multiple Control Rod Withdrawal - Refueling...............................................

3.10-13 3.10.7 Control Rod Testing - Operating 3.10-15 3.10.8 SHUTDOWN MARGIN (SDM) Test - Refueling....................

3.10-17 4.0 DESIG N FEATURES..................................................................................

4.0-1 4.1 S ite...........................................................................................

................. 4.0-1 4.2 R eactor C ore..............................................................................................

4.0-1 4.3 Fuel S torage...............................................................................................

4.0-2 5.0 ADMINISTRATIVE CONTROLS................................................................

5.0-1 5.1 Responsibility...........................................

5.0-1 5.2 O rganization..............................................................................................

5.0-2 5.3 U nit Staff Q ualifications..............................................................................

5.0-5 5.4 P rocedures.................................................................................................

5.0-6 5.5 Program s and M anuals...............................................................................

5.0-7 5.6 Reporting Requirem ents.............................................................................

5.0-18 5.7 H igh Radiation A rea....................................................................................

5.0-21 (continued)

HATCH UNIT 1 iv Amendment No. 253

Refueling Equipment Interlocks 3.9.1 3.9 REFUELING OPERATIONS 3.9.1 ' Refueling Equipment Interlocks LCO 3.9.1 APPLICABILITY:

The refueling equipment interlocks shall be OPERABLE.

During in-vessel fuel movement with equipment associated with the interlocks.

ACTIONS CONDITION j

REQUIRED ACTION COMPLETION TIME A.

One or more required A.I Suspend in-vessel fuel Immediately refueling equipment movement with interlocks inoperable, equipment associated with the inoperable interlock(s).

OR A.2.1 Insert a control rod Immediately withdrawal block.

AND A.2.2 Verify all control rods are Immediately fully inserted.

HATCH UNIT 1 3.9-1 Amendment No. 253

Refueling Equipment Interlocks 3.9.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.1.1 Perform CHANNEL FUNCTIONAL TEST on each 7 days of the following required refueling equipment interlock inputs:

a.-

All-rods-in,

b.

Refuel platform position,

c.

Refuel platform fuel grapple, fuel loaded,

d.

Refuel platform fuel grapple full-up position,

e.

Refuel platform frame-mounted hoist, fuel

loaded,

f.

Refuel platform trolley-mounted hoist, fuel loaded, and

g.

Service platform hoist, fuel loaded.

HATCH UNIT 1 3.9-2 Amendment No. 2 5 1

Refuel Position One-Rod-Out Interlock 3.9.2 3.9 REFUELING OPERATIONS 3.9.2 Refuel Position One-Rod-Out Interlock LCO 3.9.2

,APPLICABILITY:

The refuel position one-rod-out interlock shall be OPERABLE.

-MODE.5 with the reactor-mode switch-in the-refuel-position-and-any--

control rod withdrawn.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

Refuel position one-rod-out A.1 Suspend control rod Immediately interlock inoperable, withdrawal.

AND A.2 Initiate action to fully Immediately insert all insertable control rods in core cells containing one or more fuel assemblies.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.2.1 Verify reactor mode switch locked in refuel 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months position.

SR 3.9.2.2 NOTE Not required to be performed until 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months after any control rod-is withdrawn.

Perform CHANNEL FUNCTIONAL TEST.

7 days HATCH UNIT 1 3.9-3 Amendment No.2 5

Control Rod Position 3.9.3 3.9 REFUELING OPERATIONS 3.9.3 Control Rod Position LCO 3.9.3

-APPLICABILITY:-

All control rods shall be fully inserted.

-When loading-fuel -assemblies into the-core.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One or more control rods A. 1 Suspend loading fuel Immediately not fully inserted, assemblies into the core.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.3.1 Verify all control rods are fully inserted.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months HATCH UNIT 1 3.9-4 Amendment No.2 5 3 I

Control Rod Position Indication 3.9.4 3.9 REFUELING OPERATIONS 3.9.4 Control Rod Position Indication LCO 3.9.4 APPLICABILITY:

The control rod full-in position indication channel for each control rod shall be OPERABLE.

MODE 5.

ACTIONS

)TE---.

Separate Condition entry is allowed for each required channel.

CONDITION REQUIRED ACTION COMPLETION TIME A.

One or more required A.1.1 Suspend in-vessel fuel Immediately control rod position movement.

indication channels inoperable.

AND A.1.2 Suspend control rod Immediately withdrawal.

AND A.1.3 Initiate action to fully Immediately insert all insertable control rods in core cells containing one or more fuel assemblies.

OR A.2.1 Initiate action to fully Immediately insert the control rod associated with the inoperable position indicator.

AND (continued)

HATCH UNIT 1 3.9-5 Amendment No.2 5 31

Control Rod Position Indication 3.9.4 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

(continued)

A.2.2 Initiate action to disarm Immediately the control rod drive associated with the fully inserted control rod.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.4.1 Verify the required channel has no full-in indication Each time the on each control rod that is not full-in.

control rod is withdrawn from the full-in position HATCH UNIT 1 3.9-6 Amendment No. 2531

Control Rod OPERABILITY - Refueling 3.9.5 3.9 REFUELING OPERATIONS 3.9.5 Control Rod OPERABILITY - Refueling LCO 3.9.5 APPLICABILITY':

Each withdrawn control rod shall be OPERABLE.

MODE-5..

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One or more withdrawn A. 1 Initiate action to fully Immediately control rods inoperable.

I insert inoperable j

withdrawn control rods.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.5.1 NOTE-----

Not required to be performed until 7 days after the control rod is withdrawn.

Insert each withdrawn control rod at least one 7 days notch.

SR 3.9.5.2 Verify each withdrawn control rod scram 7 days I I UIQ~l3L.I 1J/l*O*,.

Is

-Il.

HATCH UNIT 1 3.9-7 Amendment No. 251

RPV Water Level 3.9.6 3.9 REFUELING OPERATIONS 3.9.6 Reactor Pressure Vessel (RPV) Water Level LCO 3.9.6 APPLICABILITY:

RPV water level shall be a 23 ft above the top of the irradiated fuel assemblies seated within the RPV.

During movement of irradiated fuel assemblies within the RPV, During movement of new fuel assemblies or handling of control rods within the RPV, when irradiated fuel assemblies are seated within the RPV.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A..

RPV water level not within A.1 Suspend movement of Immediately limit.

fuel assemblies and handling of control rods within the RPV.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.6.1 Verify RPV water level is > 23 ft above the top of 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months the irradiated fuel assemblies seated within the RPV.

HATCH UNIT 1 3.9-8 Amendment No.2 -53

RHR - High Water Level 3.9.7 3.9 REFUELING OPERATIONS 3.9.7 Residual Heat Removal (RHR) - High Water Level LCO 3.9.7 One RHR shutdown cooling subsystem shall be OPERABLE and in operation.

-NOTE ---.-.-----------------------------...----

The required RHR shutdown cooling subsystem may be removed from operation for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period.

APPLICABILITY:

MODE 5 with irradiated fuel in the reactor pressure vessel (RPV) and the water level > 22 ft 1/8 inches above the top of the RPV flange.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

Required RHR shutdown A.1 Verify an alternate 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months cooling subsystem method of decay heat inoperable, removal is available.

AND Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter B.

Required Action and B. 1 Suspend loading Immediately associated Completion irradiated fuel Time of Condition A not assemblies into the met.

RPV.

AND B.2 Initiate action to restore Immediately secondary containment to OPERABLE status.

AND (continued)

HATCH UNIT 1 3.9-9 Amendment No. 2531

RHR - High Water Level 3.9.7 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B.

(continued)

B.3 Initiate action to restore Immediately required standby gas treatment subsystem(s) to OPERABLE status.

AND B.4 Initiate action to restore Immediately isolation capability in each required secondary containment penetration flow path not isolated.

C.

No RHR shutdown cooling C.1 Verify reactor coolant 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from discovery subsystem in operation.

circulation by an of no reactor coolant alternate method, circulation AND Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter AND C.2 Monitor reactor coolant Once per hour temperature.

SURVEILLANCE REQUIREMENTS SURVEILLANCE I FREQUENCY

-SR, -3.9.7.1-

..... Verify -one-RHR shutdown-cooling-subsystem-is operating.

-12 hours-HATCH UNIT 1 3.9-10 Amendment No. 2 _5 3

RHR - Low Water Level 3.9.8 3.9 REFUELING OPERATIONS-3.9.8 Residual Heat Removal (RHR) - Low Water Level LCO 3.9.8 Two RHR shutdown cooling subsystems shall be OPERABLE, and one RHR shutdown cooling subsystem shall be in operation.

The required operating shutdown cooling subsystem may be removed from operation for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period.

MODE 5 with irradiated fuel in the reactor pressure vessel (RPV) and the water level < 22 ft 1/8 inches above the top of the RPV flange.

APPLICABILITY:

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One or two required RHR A.1 Verify an alternate 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months shutdown cooling method of decay heat subsystems inoperable, removal is available for AND each inoperable required RHR shutdown Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months cooling subsystem.

thereafter B.

Required Action and B.1 Initiate action to restore Immediately associated Completion secondary containment Time of Condition A not to OPERABLE status.

met.

AND B.2 Initiate action to restore Immediately required standby gas treatment subsystem(s) to OPERABLE status.

AND (continued)

HATCH UNIT 1 3.9-11 Amendment No.251

RHR - Low Water Level 3.9.8 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B.

(continued)

B.3 Initiate action to restore Immediately isolation capability in each required secondary containment

.........-penetration-flo w-path...

not isolated.

C.

No RHR shutdown cooling C. 1 Verify reactor coolant 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from discovery subsystem in operation.

circulation by an of no reactor coolant alternate method.

circulation AND Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter AND C.2 Monitor reactor coolant Once per hour temperature.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.8.1 Verify one RHR shutdown cooling subsystem is 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months operating.

HATCH UNIT 1 3.9-12 Amendment No.2 _53

Refueling Equipment Interlocks B 3.9.1 BASES (continued)

APPLICABILITY In MODE 5, a prompt reactivity excursion could cause fuel damage and subsequent release of radioactive material to the environment.

The refueling equipment interlocks protect against prompt reactivity excursions during MODE 5. The interlocks are required to be OPERABLE during in-vessel fuel movement with refueling equipment associated with the interlocks.

In MODES 1, 2, 3, and 4, the reactor pressure vessel head is on, and CORE ALTERATIONS are not possible. Therefore, the refueling interlocks are not required to be OPERABLE in these MODES.

ACTIONS A.1, A.2.1, and A.2.2 With one or more of the required refueling equipment interlocks inoperable, the unit must be placed in a condition in which the LCO does not apply. Therefore, Required Action A.1 requires that in-vessel fuel movement with the affected refueling equipment must be immediately suspended. This action ensures that operations are not performed with equipment that would potentially not be blocked from unacceptable operations (e.g., loading fuel into a cell with a control rod withdrawn). Suspension of in-vessel fuel movement shall not preclude completion of movement of a component to a safe position.

Alternatively, Required Actions A.2.1 and A.2.2 require a control rod withdrawal block to be inserted, and all control rods to be subsequently verified to be fully inserted. Required Action A.2.1 ensures no control rods can be withdrawn, because a block to control rod withdrawal is in place. The withdrawal block utilized must ensure that if rod withdrawal is requested, the rod will not respond (i.e., it will remain inserted). Required Action A.2.2 is performed after placing the rod withdrawal block in effect, and provides a verification that all control rods are fully inserted. This verification that all control rods are fully inserted is in addition to the periodic verification required by SR 3.9.3.1.

Like Required Action A.1, Required Actions A.2.1 and A.2.2 ensure unacceptable operations are blocked (e.g., loading fuel into a cell with the control rod withdrawn).

(continued)

HATCH UNIT 1 B 3.9-3 Amendment No. 253

Refueling Equipment Interlocks B 3.9.1 BASES (continued)

SURVEILLANCE REQUIREMENTS SR 3.9.1.1 Performance of a CHANNEL FUNCTIONAL TEST demonstrates each required refueling equipment interlock will function properly when a simulated or actual signal indicative of a required condition is injected into the logic. The CHANNEL FUNCTIONAL TEST may be performed by any series of sequential,-overlapping,--or total-channel --

steps so that the entire channel is tested.

The 7 day Frequency is based on engineering judgment and is considered adequate in view of other indications of refueling interlocks and their associated input status that are available to unit operations personnel.

REFERENCES

1.

10 CFR 50, Appendix A, GDC 26.

2.

FSAR, Section 7.6.3.

3.

FSAR, Section 14.3.3.3.

4.

FSAR, Section 14.3.3.4.

5.

NRC No.93-102, "Final Policy Statement on Technical Specification Improvements," July 23, 1993.

HATCH UNIT 1 B 3.9-4 REVISION Amendment No. 253 I

.4-(6)

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

C.

This renewed license shall be deemed to contain, and is subject to, the conditions specified In the following Commission regulations in 10 CFR Chapter 1: Part 20, Section 30.34 of Part 30, Section 40.41 of Part 40, Section 50.54 of Part 50, and Section 70.32 of Part 70; all applicable provisions of the Act and the rules, regulations, and orders of the Commission now or hereafter in

-effect; and the additional conditions2 specified or incorporated-below:

(1)

Maximum Power Level Southern Nuclear is authorized to operate the facility at steady state reactor core power levels not In excess of 2,804 megawatts thermal, In accordance with the conditions specified herein.

(2)

Technical Specifications The Technical Specifications (Appendix A) and the Environmental Protection Plan (Appendix B), as revised through Amendment No. 19 7 are hereby Incorporated in the renewed license. Southern Nuclear snau operate the facility In accordance with the Technical Specifications and the Environmental Protection Plan.

(3)

Additional Conditiors The matters specified In the following conditions shall be completed to the satisfac-ton of the Commission within the stated time periods following the Issuance of the renewed license or within the operational restrictions Indicated. The removal of these conditions shall be made by an amendment to the license supported by a favorable evaluation by the Commission.

(a)

Fire Protertion Southern Nuclear shall Implement and maintain In effect all provisions of the fire protection program, which Is referenced In the the Updated Final Safety Analysis Report for the facility, as contained 2The original licensee authorized to possess, use, and operate the facility was Georgia Power Company (GPC). Consequently, certain historical references to GPC remain In certain license c o n d itio n s....................

Renewed Ucense No. NPF-5 Arnendment No. 19 7

TABLE OF CONTENTS 3.8 ELECTRICAL POWER SYSTEMS (continued) 3.8.6 Battery Cell Parameters 3.8-33 3.8.7 Distribution Systems - Operating................................................................

3.8-36 3.8.8 Distribution Systems - Shutdown...............................................................

3.8-39 3.9 REFUELING OPERATIONS......................................................................

3.9-1 3.9.1 Refueling Equipment Interlocks..................................................................

3.9-1 3.9.2 Refuel Position One-Rod-Out Interlock.......................................................

3.9-3 3.9.3 Control Rod Position...................................................................................

3.9-4 3.9.4 Control Rod Position Indication...................................................................

3.9-5 3.9.5 Control Rod OPERABILITY - Refueling......................................................

3.9-7 3.9.6 Reactor Pressure Vessel (RPV) Water Level..............................................

3.9-8 3.9.7 Residual Heat Removal (RHR) - High Water Level.....................................

3.9-9 3.9.8 Residual Heat Removal (RHR) - Low Water Level......................................

3.9-11 3.10 SPECIAL OPERATIONS............................................................................

3.10-1 3.10.1 Inservice Leak and Hydrostatic Testing Operation......................................

3.10-1 3.10.2 Reactor Mode Switch Interlock Testing.......................................................

3.10-3 3.10.3 Single Control Rod Withdrawal - Hot Shutdown..........................................

3.10-5 3.10.4 Single Control Rod Withdrawal - Cold Shutdown........................................

3.10-8 3.10.5 Single Control Rod Drive (CRD)

Removal - Refueling.............................................................................

3.10-11 3.10.6 Multiple Control Rod Withdrawal - Refueling...............................................

3.10-13 3.10.7 Control Rod Testing - Operating.................................................................

3.10-15 3.10.8 SHUTDOWN MARGIN (SDM) Test - Refueling 3.10-17 4.0 DESIGN FEATURES..................................................................................

4.0-1 4.1 S ite.............................................................................................................

4.0 -1 4.2 R eactor C ore.............................................................................................

4.0- 1 4.3 F uel S to rage................................................

............................................ 4.0-2 (continued)

HATCH UNIT 2 iv Amendment No. 197

Refueling Equipment Interlocks B 3.9.1 3.9 REFUELING OPERATIONS 3.9.1 Refueling Equipment Interlocks LCO 3.9.1 APPLICABILITY:-

The refueling equipment interlocks shall be OPERABLE.

During-in-vessel-fuel-movement with equipment associated with-the interlocks.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One or more required A. I Suspend in-vessel fuel Immediately refueling equipment movement with interlocks inoperable, equipment associated with the inoperable interlock(s).

OR A.2.1 Insert a control rod Immediately withdrawal block.

AND A.2.2 Verify all control rods are Immediately fully inserted.

HATCH UNIT 2 3.9-1 Amendment No. 197

Refueling Equipment Interlocks B 3.9.1 SURVEILLANCE-REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.1.1 Perform CHANNEL FUNCTIONAL TEST on each 7 days of the following required refueling equipment interlock inputs:

a. -

A ll-ro d s -in,-.

b.

Refuel platform position,

c.

Refuel platform fuel grapple, fuel loaded,

d.

Refuel platform fuel grapple full-up position,

e.

Refuel platform frame-mounted hoist, fuel

loaded,

f.

Refuel platform trolley-mounted hoist, fuel loaded, and

g.

Service platform hoist, fuel loaded.

HATCH UNIT 2 3.9-2 Amendment No. 1971

Refuel Position One-Rod-Out Interlock 3.9.2 3.9 REFUELING OPERATIONS 3.9.2 Refuel Position One-Rod-Out Interlock LCO 3.9.2 APPLICABILIT'Y:

The refuel position one-rod-out interlock shall be OPERABLE.

MODE 5 with the-reactor mode-switch-in the refuel-position and-any-control rod withdrawn.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

Refuel position one-rod-out A.1 Suspend control rod immediately interlock inoperable, withdrawal.

AND A.2 Initiate action to fully Immediately insert all insertable control rods in core cells containing one or more fuel assemblies.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.2.1 Verify reactor mode switch locked in refuel 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months position.

SR 3.9.2.2 Not required to be performed until 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months after any control rod is withdrawn. -....

Perform CHANNEL FUNCTIONAL TEST.

7 days HATCH UNIT 2 3.9-3 Amendment No. 19 71

Control Rod Position 3.9.3 3.9 REFUELING OPERATIONS 3.9.3 Control Rod Position LCO 3.9.3 All control rods shall be fully inserted.

APPLICABILITY:

When loading fuel assemblies into the core.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One or more control rods A.1 Suspend loading fuel Immediately not fully inserted, assemblies into the core.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.3.1 Verify all control rods are fully inserted.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months HATCH UNIT 2 3.9-4 Amendment No. 1 9 7 1

Control Rod Position Indication 3.9.4 3.9-REFUELING OPERATIONS 3.9.4 Control Rod Position Indication LCO 3.9.4 APPLICABILITY:

The control rod full-in position indication channel for each control rod shall be OPERABLE.

MODE 5.

ACTIONS

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

Separate Condition entry is allowed for each required channel.

CONDITION REQUIRED ACTION COMPLETION TIME A.

One or more required A.1.1 Suspend in-vessel fuel Immediately control rod position movement.

indication channels inoperable.

AND A.1.2 Suspend control rod Immediately withdrawal.

AND A.1.3 Initiate action to fully Immediately insert all insertable control rods in core cells containing one or more fuel assemblies.

OR A.2.1 initiate action to fuily immediately insert the control rod associated with the inoperable position ndicator.r..-

AND (continued)

HATCH UNIT 2 3.9-5 Amendment No. 1 9 7 1

Control Rod Position Indication 3.9.4 ACTIONS.......

CONDITION REQUIRED ACTION COMPLETION TIME A.

(continued)

A.2.2 Initiate action to disarm Immediately the control rod drive associated with the fully inserted control rod.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.4.1 Verify the required channel has no full-in indication Each time the on each control rod that is not full-in, control rod is withdrawn from the full-in position HATCH UNIT 2 3.9-6 Amendment No.19 71

Control Rod OPERABILITY - Refueling 3.9.5 3.9 REFUELING OPERATIONS -....

3.9.5 Control Rod OPERABILITY - Refueling LCO 3.9.5 APPLICABILITY:

Each withdrawn control rod shall be OPERABLE.

MODE 5.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One or more withdrawn A.1 Initiate action to fully Immediately control rods inoperable.

insert inoperable withdrawn control rods.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.5.1 Not required to be performed until 7 days after the control rod is withdrawn.

Insert each withdrawn control rod at least one 7 days notch.

SR 3.9.5.2 Verify each withdrawn control rod scram 7 days acc~um ulatora presr is a

U-t pz1V HATCH UNIT 2

'3.9-7 Amendment No. 1 9 7 I

RPV Water Level 3.9.6 3.9 REFUELING OPERATIONS.

3.9.6 Reactor Pressure Vessel (RPV) Water Level LCO 3.9.6 APPLICABILITY:

RPV water level shall be a 23 ft above the top of the irradiated fuel assemblies seated within the RPV.

During movement of irradiated fuel assemblies within the RPV, During movement of new fuel assemblies or handling of control rods within the RPV, when irradiated fuel assemblies are seated within the RPV.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

RPV water level not within A.1 Suspend movement of Immediately

limit, fuel assemblies and handling of control rods within the RPV.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.6.1 Verify RPV water level is ? 23 ft above the top of 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months the irradiated fuel assemblies seated within the RPV.

HATCH UNIT 2 3.9-8 Amendment No.19 7 I

RHR - High Water Level 3.9.7 3.9 REFUELING OPERATIONS 3.9.7 Residual Heat Removal (RHR) - High Water Level LCO 3.9.7 One RHR shutdown cooling subsystem shall be OPERABLE and in operation.

NOT The required RHR shutdown cooling subsystem may be removed from operation for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period.

APPLICABILITY:

MODE 5 with irradiated fuel in the reactor pressure vessel (RPV) and the water level > 22 ft 1/8 inches above the top of the RPV flange.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

Required RHR shutdown A. 1 Verify an alternate 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months cooling subsystem method of decay heat inoperable, removal is available.

AND Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter B.

Required Action and B.1 Suspend loading Immediately associated Completion irradiated fuel Time of Condition A not assemblies into the met.

RPV.

AND B.2 Initiate action to restore Immediately secondary containment AD to OPERABLE status.

AND

~bitiiiedy HATCH UNIT 2 3.9-9 Amendment No. 1971

RHR - High Water Level 3.9.7 A CT IO NS CONDITION REQUIRED ACTION COMPLETION TIME B.

(continued)

B.3 Initiate action to restore Immediately required standby gas treatment subsystem(s) to OPERABLE status.

AND B.4 Initiate action to restore Immediately isolation capability in each required secondary containment penetration flow path not isolated.

C.

No RHR shutdown cooling C.1 Verify reactor coolant 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from discovery subsystem in operation.

circulation by an of no reactor coolant alternate method, circulation AND Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter AND C.2 Mon,,t.. reactor coolant Once per hour temperature.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.7..

Verify one RHR shutdown cooling subsystem. is 12-hours operating.

HATCH UNIT 2 3.9-10 Amendment No. 1 9 7 1

RHR - Low Water Level 3.9.8 3.9 REFUELING OPERATIONS 3.9.8 Residual Heat Removal (RHR) - Low Water Level LCO 3.9.8 Two RHR shutdown cooling subsystems shall be OPERABLE, and one RHR shutdown cooling subsystem shall be in operation.

II.

If%'-w-1 I.

The required operating shutdown cooling subsystem may be removed from operation for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months per 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period.

MODE 5 with irradiated fuel in the reactor pressure vessel (RPV) and the water level < 22 ft 1/8 inches above the top of the RPV flange.

APPLICABILITY:

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

One or two required RHR A.1 Verify an alternate 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months shutdown cooling method of decay heat subsystems inoperable, removal is available for AND each inoperable required RHR shutdown Once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months cooling subsystem.

thereafter B.

Required Action and B.1 Initiate action to restore Immediately associated Completion secondary containment Time of Condition A not to OPERABLE status.

met.

AND B.2 Initiate action to restore Immediately required standby gas treatment subsystem(s) to OPERABLE status.

AND (continued)

HATCH UNIT 2 3.9-11 Amendment No. 1 9 77

RHR - Low Water Level 3.9.8 ACTIO NS.

CONDITION REQUIRED ACTION COMPLETION TIME B.

(continued)

B.3 Initiate action to restore Immediately isolation capability in each required secondary containment

--- -- penetration-flow-path...

not isolated.

C.

No RHR shutdown cooling C.1 Verify reactor coolant 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months from discovery subsystem in operation.

circulation by an of no reactor coolant alternate method.

circulation AND Once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter AND C.2 Monitor reactor coolant Once per hour temperature.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.9.8.1 Verify one RHR shutdown cooling subsystem is 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months operating.

HATCH UNIT 2 3.9-12 Amendment No. 19 7 1

Refueling Equipment Interlocks B 3.9.1 BASES (continued)

APPLICABILITY In MODE 5, a prompt reactivity excursion could cause fuel damage and subsequent release of radioactive material to the environment.

The refueling equipment interlocks protect against prompt reactivity excursions during MODE 5. The interlocks are required to be OPERABLE during in-vessel fuel movement with refueling equipment associated with the interlocks.

In MODES 1,2, 3, and 4, the reactor pressure vessel head is on, and CORE ALTERATIONS are not possible. Therefore, the refueling interlocks are not required to be OPERABLE in these MODES.

ACTIONS A.1. A.2.1. and A.2.2 With one or more of the required refueling equipment interlocks inoperable, the unit must be placed in a condition in which the LCO does not apply. Therefore, Required Action A.1 requires that in-vessel fuel movement with the affected refueling equipment must be immediately suspended. This action ensures that operations are not performed with equipment that would potentially not be blocked from unacceptable operations (e.g., loading fuel into a cell with a control rod withdrawn). Suspension of in-vessel fuel movement shall not preclude completion of movement of a component to a safe position.

Alternatively, Required Actions A.2.1 and A.2.2 require a control rod withdrawal block to be inserted, and all control rods to be subsequently verified to be fully inserted. Required Action A.2.1 ensures no control rods can be withdrawn, because a block to control rod withdrawal is in place. The withdrawal block utilized must ensure that if rod withdrawal is requested, the rod will not respond (i.e., it will remain inserted). Required Action A.2.2 is performed after placing the rod withdrawal block in effect, and provides a verification that all control rods are fully inserted. This verification that all control rods are fully inserted is in addition to the periodic verification required by SR 3.9.3.1.

Like Required Action A.1, Required Actions A.2.1 and A.2.2 ensure unacceptable operations are blocked (e.g., loading fuel into a cell with the control rod withdrawn).

(continued)

HATCH UNIT 2 B 3.9-3 Amendment No.

197

Refueling Equipment Interlocks B 3.9.1

-BASES (continued)

SURVEILLANCE REQUIREMENTS SR 3.9.1.1 Performance of a CHANNEL FUNCTIONAL TEST demonstrates each required refueling equipment interlock will function properly when a simulated or actual signal indicative of a required condition is injected into the logic. The CHANNEL FUNCTIONAL TEST may be performed by any series-of sequential, overlapping, or total channel steps so that the entire channel is tested.

The 7 day Frequency is based on engineering judgment and is considered adequate in view of other indications of refueling interlocks and their associated input status that are available to unit operations personnel.

REFERENCES

1.

10 CFR 50, Appendix A, GDC 26.

2.

FSAR, Section 7.6.1.

3.

FSAR, Section 15.1.13.

4.

FSAR, Section 15.1.14.

5.

NRC No.93-102, "Final Policy Statement on Technical Specification Improvements," July 23, 1993.

HATCH UNIT 2 B 3.9-4 REVISION Amendment No.

197

v t e Letter Sequence Approval
TAC:MD4444, (Approved, Closed) TAC:MD4445, (Approved, Closed)
Initiation Request Acceptance... Administration Questions Answers Results Approval, Approval Other:
MONTHYEAR2007-10-04 [Table View]

ML072820058

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