Text

Amends 213 & 154 to Licenses DPR-57 & NPF-05,respectively, Revising TS Associated W/Oscillation Power Range Monitor Portion of Digital Power Range Neutron Monitoring System
	ML20237D634
Person / Time
Site:	Hatch
Issue date:	08/20/1998
From:	Berkow H; NRC (Affiliation Not Assigned)
To:	;
Shared Package
ML20237D636	List: ML20237D634; ML20237D637;
References
	NUDOCS 9808270094
	Download: ML20237D634 (34)
	v • d • e

.

I p'*1u g

j UNITED STATES g

g NUCLEAR REGULATORY COMMISSION I

t WASHINGTON, D.C. *anaam anni Q

+.,.. /

SOUTHERN NUCLEAR OPERATING COMPANY. INC.

GEORGIA POWER COMPANY l

OGLETHORPE POWER CORPORATION i

MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON. GEORGIA DOCKET NO. 50-321

)

EDWIN l. HATCH NUCLEAR PLANT. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 213 License No. DPR-57 1.

The Nuclear Regulatory Commission (the Commission) has found that:

l A.

The application for amendment to the Edwin I. Hatch Nuclear Plant, Unit 1 (the facility) Facility Operating License No. DPR-57 filed by Southem Nuclear Operating Company, Inc. (Southern Nuclear), acting for itself, Georgia Power Company, Oglethorpe Power Corporation, Municipal Electric Authority of Georgia, and City of Dalton, Georgia (the licensees), dated October 29,1996, as supplemented February 19, June 20, and October 21,1997, complies with the i

standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as set forth in 10 CFR 1

Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (i) that the activities authorized by this l

amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I-1 D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

I 9808270094 900820 PDR ADOCK 05000321 P

PM

, 2.

Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-57 is hereby amended to read as follows:

-(2)

Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 213. are hereby incorporated in the license.

Southern Nuclear shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

This license amendment is effective as of its date of issuance and shall be implemented prior to the startup from the next refueling outage.

FOR THE NUCLEAR REGULATORY COMMISSION a-Her rt N. Berkow, Director Project Directorate 11-2 l

Division of Reactor Projects - 1/II Office of Nuclear Reactor Regulation

Attachment:

Technical Specification Changes Date of issuance:

August 20, 1998 l

__7_,_-_--__---_

ATTACHMENTTO LICENSE AMENDMENT NO. 213 FACILITY OPERATING LICENSE NO. DPR-57 DOCKET NO. 50-321 Replace the following pages of the operating license with the enclosed pages. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.

Remove Insert 3.3-1 3.3-1 3.3-2 3.3-2 (no change) 3.3-3 3.3-3 3.3-4 3.3-4*

3.3-5 3.3-5*

3.3-6 3.3-6 3.3-7 3.3-7*

3.3-8 3.3-8 3.3-8a*

3.3-8b*

3.4-1 3.4-1 3.4-2 3.4-2 3.4-3 3.4-3 3.4-4 3.4-4

no change - overflow page

i RPS Instrumentation

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3.3.1.1 3.3 INSTRUMENTATION 3.3.1.1 Reactor Protection System (RPS) Instrumentation 1

LCO 3.3.1.1 The RPS instrumentation for each Function in Table 3.3.1.1-1 shall be OPERABLE.

l l

APPLICABILITY:

According to Table 3.3.1.1-1.

ACTIONS i

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

l Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION-COMPLETION TIME A.

One or more required A.1 Place channel in 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months channels inoperable.

trip.

l A.2

NOTE---------

l Not applicable for

{

Functions 2.a, 2.b, i

2.c, 2.d, and 2.f.

l Place associated trip 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months system in trip.

i j

B.

NOTE----------

B.1 Place channel in one 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months l

Not applicable for trip system in trip.

Functions 2.a 2.b, 2.c 2.d, and 2.f.

QB l

l B.2 Place one trip system 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months One or more Functions in trip.

with one or more i

required channels l-inoperable in both trip systems.

(continued) i i

I HATCH UNIT 1 3.3-1 Amendment No. 213 i

l RPS Instrumentation 3.3.1.1 ACTIONS (continued) i CONDITION REQUIRED ACTION COMPLETION TIME C.

One or more Functions C.1 Restore RPS trip I heur with RPS trip capability, capability not maintained.

D.

Required Action and D.1 Enter the Condition Immediately associated Completion referenced in

(

Time of Condition A, Table 3.3.1.1-1 for B, or C not met.

the channel.

E.

As required by E.1 Reduce THERMAL POWER 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Required Action D.1 to < 30% RTP.

and referenced in Table 3.3.1.1-1.

j I

F.

As required by F.1 Be in MODE 2.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months

)

Required Action D.]

and referenced in Table 3.3.1.1-1.

G.

As required by G.1 Be in MODE 3.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Required Action D.1 and referenced in Table 3.3.1.1-1.

I i

H.

As required by H.1 Initiate action to Immediately Required Action D.1 fully insert all and referenced in insertable control i

Table 3.3.1.1-1.

rods in core cells containing one or more fuel assemblies.

(continued)

HATCH UNIT 1 3.3-2 Amendment No. 213 l

RPS Instrumentation 3.3.1.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME I.

As required by I.1 Initiate alternate 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Required Action D.1 method to detect and and referenced in suppress thermal-Table 3.3.1.1-1.

hydraulic instability oscillations.

b.N3 I.2 Restore required 120 days channels to OPERABLE.

J.

Required Action and J.1 Be in MODE 2.

4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months associated Completion i

Time of Condition I l

f not met, i

l t

SURVEILLANCE REQUIREMENTS

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

1.

Refer to Table 3.3.1.1-1 to determine which SRs apply for each RPS Function.

2.

When a channel is placed in an inoperable status solely for performance of required Surveillance, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the associated Function maintains RPS trip capability.

1 l

SURVEILLANCE FREQUENCY SR 3.3.1.1.1 Perform CHANNEL CHECK.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months (continued) 1 l

l

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l HATCH UNIT 1 3.3-3 Amendment No. 213

_____~

RPS Instrumentation 3.3.1.1 StJRVEILLANCE REQUIREMENTS (continued) l SURVEILLANCE FREQUENCY SR 3.3.1.1.2

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

Not required to be performed until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after THERMAL POWER at 25% RTP.

Verify the absolute difference between 7 days the average power range monitor (APRM) channels and the calculated power is s 2% RTP while operating at at 25% RTP.

SR 3.3.1.1.3 (Not used.)

SR 3.3.1.1.4

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

Not required to be performed when entering MODE 2 from H0DE 1 until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after entering MODE 2.

Perform CHANNEL FUNCTIONAL TEST.

7 days SR 3.3.1.1.5 Perform CHANNEL FUNCTIONAL TEST.

7 days SR 3.3.1.1.6 Verify the source range monitor (SRM) and Prior to intermediate range monitor (IRM) channels withdrawing overl ap.

SRMs from the fully inserted position (continued) l i

I HATCH UNIT 1 3.3-4 Amendment No. 213

RPS Instrumentation 3.3.1.1 i

SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY l

SR 3.3.1.1.7

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

Only required to be met during entry into l

MODE 2 from MODE 1.

Verify the IRM and APRM channels overlap.

7 days SR 3.3.1.1.8 Calibrate the local power range monitors.

1000 effective full power hours SR 3.3.1.1.9 Perform CHANNEL FUNCTIONAL TEST.

92 days i

SR 3.3.1.1.10

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

For Function 2.a. not required to be l

performed when entering MODE 2 from MODE 1 until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after entering j

MODE 2.

)

Perform CHANNEL FUNCTIONAL TEST.

184 days SR 3.3.1.1.11 Verify Turbine Stop Valve -- Closure and 184 days Turbine Control Valve Fast closure, Trip 011 Pressure -- Low Functions are not bypassed when THERMAL POWER is a: 30% RTP.

L SR 3.3.1.1.12 Perform CHANNEL FUNCTIONAL TEST.

18 months l

I 1

i (continued) l l

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HATCH UNIT 1 3.3-5 Amendment No. 213 l

l 9

RPS Instrumentation 3.3.1.1 SURVEILLANCE REQUIREMENTS (continued) f SURVEILLANCE FREQUENCY SR 3.3.1.1.13

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

1. Neutron detectors are excluded.

2. For Function 1, not required to be performed when entering MODE 2 from MODE 1 until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after entering MODE 2.

Perform CHANNEL CALIBRATION.

18 months SR 3.3.1.1.14 (Not used.)

SR 3.3.1.1.15.

Perform LOGIC SYSTEM FUNCTIONAL TEST.

18 months l

l SR 3.3.1.1.16

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

Neutron detectors are excluded.

Verify the RPS RESPONSE TIME is within 18 months on a limits.

STAGGERED TEST BASIS l

SR 3.3.1.1.17 Verify OPRM is not bypassed when APRM 18 months Simulated Thermal Power is 2: 25% and recirculation drive flow is < 60% of rated recirculation drive flow.

l 4

HATCH UNIT 1 3.3-6 Amendment No. 213

l

\\

RPS Instrumentation 3.3.1.1 l

l Table 3.3.1.1 1 (page 1 of 3)

Reactor Protection system Instementation APPLICA8tE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER TRIP REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS SYSTEM ACTION D.1 REQUIREMENTS VALUE 1.

Intenaediate Range Monitor a.

Neutron Ftum - High 2

3 C

st 3.3.1.1.1 5 120/125 SR 3.3.1.1.4 divisions of st 3.3.1.1.6 futt acate SR 3.3.1.1.7 SR 3.3.1.1.13 sa 3.3.1.1.15 5(*)

3 H

SR 3.3.1.1.1 s 120/125 st 3.3.1.1.5 divisions of SR 3.3.1.1.13 futI scale SR 3.3.1.1.15 b.

Inop 2

3 C

SR 3.3.1.1.4 NA sa 3.3.1.1.15 5(*)

3 H

st 3.3.1.1.5 NA sa 3.3.1.1.15 2.

Average Power Range Monitor a.

Woutron Flux - High 2

3IC)

G SR 3.3.1.1.1 5 20% RTP (setdown) st 3.3.1.1.7 st 3.3.1.1.8 SR 3.3.1.1.10 st 3.3.1.1.13 b.

Simulated Thermal 1

3(C)

F SR 3.3.1.1.1 s 0.58 W +

Power - High SR 3.3.1.1.2 62% RTP and SR 3.3.1.1.8 s 115.5%

SR 3.3.1.1.10 RTP(b) st 3.3.1.1.13 c.

Neutron Flux - High 1

3(*)

F st 3.3.1.1.1 s 120% RTP SR 3.3.1.1.2 BR 3.3.1.1.8 SR 3.3.1.1.10 SR 3.3.1.1.13 d.

Inop 1,2 3(8)

G SR 3.3.1.1.10 NA (continued)

(a) Vith any control rod withdrawn from a core cell containino one or more fuel assemblies.

l (b) 0.58 W + 62%

0.58 AW RTP when reset for single loop operation per LCD 3.4.1, anecirculation Loops Operating."

(c) Each APRM channel provides inputs to both trip systems.

HATCH UNIT 1 3.3-7 Amendment No. 213 l

i RPS Instrumentation 3.3.1.1 Table 3.3.1.1 1 (pege 2 of 3)

Reactor Protection system instrumentation APPLICABLE CONDIT10Ns 8G ES OR REQUIRED REFERENCED OTNER CNANNELS FROM l

,l SPECIFLED PER TRIP REQUIRED SURVEILLANCE ALLOWABLE I

FUNCTION CONDITIONS SYSTEM ACTION D.1 REQUIREMENTS VALUE 2.

Average Power Range Monitor (continued) l e.

Two out of Four 1,2 2

G sa 3.3.1.1.1 NA l

Veter sa 3.3.1.1.10 sa 3.3.1.1.15 st 3.3.1.1.16 i

f.

OPRM Upscate 1

3(8)

I sa 3.3.1.1.1 NA SR 3.3.1.1.8 SR 3.3.1.1.10 SR 3.3.1.1.13 SR 3.3.1.1.17 3.

Reactor vessel steam 1,2 2

C SR 3.3.1.1.1 5 1085 psig Dome Pressure - Nish st 3.3.1.1.9 st 3.3.1.1.13 st 3.3.1.1.15 l

4 Reactor Vessel Water 1,2 2

G SR 3.3.1.1.1 a 0 inches Level - Low, Level 3 st 3.3.1.1.9 SR 3.3.1.1.13 st 3.3.1.1.15 f

5.

Main steam Isolation 1

8 F

sa 3.3.1.1.9 s 10% closed j

Valve - Closure SR 3.3.1.1.13

{

SR 3.3.1.1.15 6.

Drywe! L Pressure - NIgh 1,2 2

C st 3.3.1.1.1 s 1.92 pele l

SR 3.3.1.1.9 l

SR 3.3.1.1.13 i

st 3.3.1.1.15 7.

Scram Discharge Volume Water Level-High a.

Resistence Temperature 1,2 2

G SR 3.3.1.1.9 s 71 settons

]

i Detector st 3.3.1.1.13 t

sa 3.3.1.1.15 I

5(*)

2 N

SR 3.3.1.1.9 s 71 gallons st 3.3.1.1.13

$R 3.3.1.1.15 b.

Float switch 1,2 2

G SR 3.3.1.1.13 5 71 gallons

)

sa 3.3.1.1.15 5(*)

2 N

st 3.3.1.1.13 s 71 gattons st 3.3.1.1.15 (continued)

(a) With any control rod withdrawn from a core cell containing one or more fuel assemblies.

l (c) Each APRM channet provides inputs to both trip systems.

i 1

I HATCH UNIT 1 3.3-8 Amendment No. 213 1

RPS Instrumentation 3.3.1.1 Table 3.3.1.1 1 (pose 3 of 3)

Raector Protection system Instrumentation APPLICABLE CONDITIONS NODES OR REQUIRED REFERENCE 0 OTNER CNANNELs FROM SPECIF!ED PER TRIP REQUIRED SURVEILLANCE ALLOWAsLE FUNCTION CONDIfl0NS SYSTEM ACTION D.1 REeulREMEWis VALUE 8.

Turbine stop t 30% RTP 4

E st 3.3.1.1.9 s 101 closed Velve - Closure at 3.3.1.1.11 st 3.3.1.1.13 st 3.3.1.1.15 9.

Turbine control Velve t 30% RTP 2

E st 3.3.1.1.9 t 600 pois feet Closure, Trip Olt st 3.3.1.1.11 Pressure - Low st 3.3.1.1.13 st 3.3.1.1.15 SR 3.3.1.1.16

10. Reactor Mode switch -

1,2 1

G st 3.3.1.1.12 NA shutsk.wn Position SR 3.3.1.1.15 5(e) 1 M

st 3.3.1.1.12 NA sa 3.3.1.1.15

11. Manuel serem 1,2 1

G SR 3.3.1.1.5 NA st 3.3.1.1.15 5(*)

1 M

st 3.3.1.1.5 NA sa 3.3.1.1.15 (e) With any control red withdrawn from a core cell containing one or more fuel asseelies.

HATCH UNIT 1 3.3-8a Amendment No. 213 l

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1 RPS Instrumentation 3.3.1.1 1

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i This page intentionally left blank.

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I HATCH UNIT 1 3.3-8b Amendment No. 213 l

u _--_ --.---- ----- --

Recirculation Loops Operating 3.4.1 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.1 Recirculation Loops Operating LCO 3.4.1 Two recirculation loops with matened flows shall be in operation, DE One recirculation loop shall be in operation with the l

following limits applied when the associated LCO is applicable:

a.

LCO 3.2.1, " AVERAGE PLANAR LINEAR HEAT GENERATION RATE l

(APLHGR)," single loop operation limits specified in the COLR; b.

LC0 3.2.2, " MINIMUM CRITICAL POWER RATIO (MCPR)," single l

loop operation limits specified in the COLR; and LCO 3.3.1.1, " Reactor Protection System (RPS) l c.

Instrumentation," Function 2.b (Average Power Range Monitor Simulated Thermal Power - High), Allowable Value of Table 3.3.1.1-1 is reset for single loop operation.

APPLICABILITY:

MODES I and 2.

l HATCH UNIT 1 3.4-1 Amendment No. 213

Recirculation Loops Operating 3.4.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

Requirements of the A.1 Satisfy the 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months LCO not met.

requirements of the LCO.

B.

Required Action and 8.1 Be in MODE 3.

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

QB No recirculation loops in operation.

1

)

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l HATCH UNIT 1 3.4-2 Amendment No. 213

(

l Recirculation loops Operating 3.4.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.1.1

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

Not required to be performed until 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after both recircuiv. ion ' loops are in operation.

Verify recirculation loop jet pump flow 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months mismatch with both recirculation loops in operation is:

a.

s 10% of rated core flow when operating at < 70% of rated core flow; and b.

s 5% of rated core flow when operating l

at 2: 70% of rated core flow, l

I l

1 SR 3.4.1.2 (Not used.)

l l

HATCH UNIT 1 3.4-3 Amendment No. 213

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4 Recirculation loops Operating 3.4.1 1

1 I

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l HATCH UNIT 1 3.4-4 Amendment No. 213 f

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p ar i

UNITED STATES

{n j

NUCLEAR REGULATORY COMMISSION 2

WASHINGTON, D.C. 20066 4001 l

SOUTHERN NUCLEAR OPERATING COMPANY. INC.

GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON. GEORGIA DOCKET NO. 50-366 EDWIN 1. HATCH NUCLEAR PLANT. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.154 License No. NPF-5 1.

The Nuclear Regulatory Commission (the Commission) has found that:

A.

The application for amendment to the Edwin 1. Hatch Nuclear Plant, Unit 2 (the facility) Facility Operating License No. NPF-5 filed by Southern Nue:sar Operating Company, Inc. (Southern Nuclear), acting for itself, Georgia Power Company, Oglethorpe Power Corporation, Municipal Electric Authority of Georgia, and City of Dalton, Georgia (the licensees), dated October 291996, as supplemented February 19, June 20, and October 21,1997, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and l

E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the

}

Commission's regulations and all applicable requirements have been satisfied.

l

. 2.

Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-5 is hereby amended to read as follows:

(2)

Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No.154 are hereby incorporated in the license.

Southern Nuclear shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

This license amendment is effective as of its date of issuance and shall be implemented prior to the startup from the next refueling outage.

FOR THE NUCLEAR REGULATORY COMMISSION 1

I-H bert N. Berkow, Director P oject Directorate 11-2 Division of Reactor Projects - l/II Office of Nuclear Reactor Regulation

Attachment:

Technical Specification I

Changes Date of issuance: August 20, 1998 l

)

t l

_J

r-i ATTACHMENTTO LICENSE AMENDMENT NO.154 FACILITY OPERATING LICENSE NO. NPF-5 DOCKET NO. 50-366 Replace the following pages of the operating license with the enclosed pages. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.

Remove Insert 3.3-1 3.3-1 3.3-2 3.3-2 (no change) 3.3-3 3.3-3 3.3-4 3.3-4*

3.3-5 3.3-5*

3.3-6 3.3-6 1

3.3-7 3.3-7

3.3-8 3.3-8 3.3-8a*

3.3-8b*

3.4-1 3.4-1 3.4-2 3.4-2 3.4-3 3.4-3 3.4-4 3.4-4

no change - overflow page

)

RPS Instrumentation 3.3.1.1 3.3 INSTRUMENTATION 3.3.1.1 Reactor Protection System (RPS) Instrumentation LCO 3.3.1.1 The RPS instrumentation for each Function in Table 3.3.1.1-1 shall be OPERABLE.

APPLICABILITY:

According to Table 3.3.1.1-1.

l ACTIONS

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

Separate Condition entry is allowed for each channel.

CONDITION REQUIRED ACTION COMPLETION TIME A.

One or more required A.1 Place channel in 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months channels inoperable.

trip.

QB A.2

NOTE---------

Not applicable for Functions 2.a. 2.b, 2.c, 2.d, and 2.f.

l t

Place associated trip 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months j

system in trip.

B.

NOTE---------

B.1 Place channel in one 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Not applicable for trip system in trip.

Functions 2.a. 2.b, 2.c, 2.d, and 2.f.

QB l

B.2 Place one trip system 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months One or more Functions in trip.

with one or more required channels inoperable in both trip systems.

(continued)

HATCH UNIT 2 3.3-1 Amendment No. 154

RPS Instrumentation 3.3.1.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME l

C.

One or more Functions C.1 Restore RPS trip I hour l

with RPS trip capability.

capability not maintained.

D.

Required Action and D.1 Enter the Condition Immediately associated Completion referenced in Time of Condition A, Table 3.3.1.1-1 for B, or C not met.

the channel.

E.

As required by E.1 Reduce THERMAL POWER 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Required Action D.)

to < 30% RTP.

and referenced in Table 3.3.1.1-1.

]

l F.

As required by F.1 Be in MODE 2.

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months Required Action D.1 and referenced in Table 3.3.1.1-1.

G.

As required by G.1 Be in MODE 3.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Required Action D.1 and referenced in Table 3.3.1.1-1.

H.

As required by H.1 Initiate action to Immediately Required Action D.1 fully insert all and referenced in insertable control Table 3.3.1.1-1.

rods in core cells containing one or more fuel assemblies.

(continued)

HATCH UNIT 2 3.3-2 Amendment No. 154 l

l

RPS Instrumentation 3.3.1.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME I.

As required by I.1 Initiate alternate 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months Required Action D.1 method to detect and and referenced in suppress thermal-Table 3.3.1.1-1.

hydraulic instability oscillations.

AND I.2 Restore required 120 days channels to OPERABLE.

J.

Required Action and J.1 Be in MODE 2.

4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months associated Completion Time of Condition I not met.

SURVEILLANCE REQUIREMENTS

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

1.

Refer to Table 3.3.1.1-1 to determine which SRs apply for each RPS Function.

2.

When a channel is placed in an inoperable status solely for performance of required Surveillance, entry into associated Conditions and Required Actions may be delayed for up to 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided the associated Function maintains RPS trip capability.

SURVEILLANCE FREQUENCY SR 3.3.1.1.1 Perform CHANNEL CHECK.

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months (continued)

HATCH UNIT 2 3.3-3 Amendment No.154

^

I RPS Instrumentation 3.3.1.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY

(

SR 3.3.1.1.2

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

Not required to be performed until I

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after THERMAL POWER a: 25% RTP.

{

j i

Verify the absolute difference between 7 days the average power range monitor (APRM) channels and the calculated power is s 2% RTP while operating at 2: 25% RTP.

SR 3.3.1.1.3 (Not used.)

l SR 3.3.1.1.4

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

Not required to be performed when entering MODE 2 from MODE 1 until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after entering MODE 2.

Perform CHANNEL FUNCTIONAL TEST.

7 days i

SR 3.3.1.1.5 Perform CHANNEL FUNCTIONAL TEST.

7 days I

SR 3.3.1.1.6 Verify the source range monitor (SRM) and Prior to intermediate range monitor (IRM) channels withdrawing overlap.

SRMs from the fully inserted position (continued) t HATCH UNIT 2 3.3-4 Amendment No. 154 l

RPS Instrumentation 3.3.1.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.3.1.1.7

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

Only required to be met during entry into MODE 2 from MODE 1.

Verify the IRM and APRM channels overlap.

7 days SR 3.3.1.1.8 Calibrate the local power range monitors.

1000 effective full power hours SR 3.3.1.1.9 Perform CHANNEL FUNCTIONAL TEST.

92 days SR 3.3.1.1.10

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

For Function 2.a, not required to be performed when entering MODE 2 from MODE 1 until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after entering MODE 2.

Perform CHANNEL FUNCTIONAL TEST.

184 days SR 3.3.1.1.11 Verify Turbine Stop Valve -- Closure and 18 months Turbine Control Valve Fast Closure, Trip Oil Pressure -- Low Functions are not bypassed when THERMAL POWER is 1 30% RTP.

SR 3.3.1.1.12 Perform CHANNEL FUNCTIONAL TEST.

18 months (continued) l I

l HATCH UNIT 2 3.3-5 Amendment No. 154 I

RPS Instrumentation 3.3.:.1 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY L

SR 3.3.1.1.13

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

l. Neutron detectors are excluded.

2. For Function 1, not required to be performed when entering MODE 2 from MODE 1 until 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after entering MODE 2.

i Perform CHANNEL CALIBRATION.

18 months SR 3.3.1.1.14 (Not used.)

SR 3.3.1.1.15 Perform LOGIC SYSTEM FUNCTIONAL TEST.

18 months l

SR 3.3.1.1.16

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

1.

Neutron detectors are excluded.

2.

For Functions 3 and 4, channel sensors are excluded.

3.

For Function 5, "n" equals 4 channels for the purpose of determining the STAGGERED TEST BASIS Frequency.

Verify the RPS RESPONSE TIME is within 18 months on a limits.

STAGGERED TEST BASIS l

SR 3.3.1.1.17 Verify OPRM is not bypassed when APRM 18 months l

Simulated Thermal Power is a: 25% and recirculation drive flow is < 60% of rated recirculation drive flow.

HATCH UNIT 2 3.3-6 Amendment No.154

RPS Instrumentation 3.3.1.1 1

I Tabte 3.3.1.1 1 (pose 1 of 3)

Reactor Protection system Instrumentation l

l APPLICASLE CONDIT10Ns MODES OR REQUIRED REFERENCED OTHER CHANNELS FRON SPECIFIED PER TRIP REQUIRED SURVEILLANCE ALLOWASLE FUNCTION CONDITIONS STsTEN ACTION D.1 REQUIREMENTS VALUE j

1.

Intermediate Renee Monitor 1

a.

Neutron Flux - High 2

3 G

SR 3.3.1.1.1 s 120/125 sa 3.3.1.1.4 divisions of sa 3.3.1.1.6 futt scale sa 3.3.1.1.7 sa 3.3.1.1.13 sa 3.3.1.1.15 5(*)

3 N

st 3.3.1.1.1 s 120/125 sR 3.3.1.1.5 divisions of SR 3.3.1.1.13 full scale st 3.3.1.1.15 b.

Inop 2

3 G

sa 3.3.1.1.4 NA

$R 3.3.1.1.15 5(*)

3 N

sa 3.3.1.1.5 NA sa 3.3.1.1.15 2.

Aversee Power Renee Monitor a.

Neutron Flux - Nigh 2

3(8)

G st 3.3.1.1.1 s 20% RTP (setdown)

$R 3.3.1.1.7 st 3.3.1.1.8 st 3.3.1.1.10 SR 3.3.1.1.13 b.

Simulated Thermal 1

3(8)

F SR 3.3.1.1.1 s 0.58 W +

Power - High st 3.3.1.1.2 62% RTP and SR 3.3.1.1.8 s 115.5%

st 3.3.1.1.10 RTP(b) sa 3.3.1.1.13 c.

Neutron Flux - High 1

3(8)

F SR 3.3.1.1.1 s 120% RTP SR 3.3.1.1.2 sa 3.3.1.1.8 st 3.3.1.1.10 st 3.3.1.1.13 d.

Inop 1,2 3I8)

G SR 3.3.1.1.10 NA (continued)

(a) With any control rod withdrawn from a core cett containing one or more fuel assemblies.

(b) 0.58 W + 62% - 0.58 &W RTP when reset for single loop operation per LC0 3.4.1, " Recirculation Loops operating."

(c) Each APRN channet provicles inputs to both trip systems.

i i

I i

l HATCH UNIT 2 3.3-7 Amendment No.

154 l

l l

[

I

RPS Instrumentation 3.3.1.1 Table 3.3.1.1 1 (page 2 of 3)

Reactor Protection system Instrumentation APPLICA8tE CON 0lT10Ns NQDEs OR ffEQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER TRIP REQUIRED SURVEILLANCE ALLOWASLE FUNCTION CONDifl0Ns SYSTEM ACTION D.1 REQUIREMENTS VALUE 2.

Average Power Range Menitor (continued) e.

Two aut of Four 1,2 2

G SR 3.3.1.1.1 NA voter SR 3.3.1.1.10 SR 3.3.1.1.15 st 3.3.1.1.16 f.

OPRM Upscale 1

3(8)

I st 3.3.1.1.1 NA SR 3.3.1.1.8 SR 3.3.1.1.10 SR 3.3.1.1.13 SR 3.3.1.1.17 3.

Reactor vessel steam 1.2 2

G SR 3.3.1.1.1 s 1085 paig Dome Pressure - Nigh SR 3.3.1.1.9 st 3.3.1.1.13 SR 3.3.1.1.15 SR 3.3.1.1.16 4 Reactor Vessel Water 1.2 2

G st 3.3.1.1.1 2 0 inches Level - Low, Level 3 st 3.3.1.1.9 st 3.3.1.1.13 SR 3.3.1.1.15 st 3.3.1.1.16 5.

Main steam Isolation 1

8 F

sa 3.3.1.1.9 s 10s closed Valve - Closure SR 3.3.1.1.13 SR 3.3.1.1.15 SR 3.3.1.1.16 6.

Drywell Pressure - High 1,2 2

G st 3.3.1.1.1 s 1.92 pois SR 3.3.1.1.9 SR 3.3.1.1.13 SR 3.3.1.1.15 7.

Scram Discharge Vol me Water Level - High e.

Resistance 1,2 2

G SR 3.3.1.1.9 s 5 7.15 j

Temperature SR 3.3.1.1.13 gallons Detector SR 3.3.1.1.15 5(*)

2 H

SR 3.3.1.1.9 s 57.15

$4 3.3.1.1.13 galIons SR 3.3.1.1.15 b.

Float switch 1,2 2

G sR 3.3.1.1.13 s 57.15 SR 3.3.1.1.15 gallons 5(*)

2 H

st 3.3.1.1.13 s 57.15 st 3.3.1.1.15 saltons (continued)

(a) With any control rod withdrawn from a core cett containing one or more fuel assemblies.

(c) Each APRM channel provides inputs to both trip systems.

i HATCH UNIT 2 3.3-8 Amendment No.154

j RPS Instrumentation 3.3.1.1 Table 3.3.1.1 1 (pose 3 of 3)

Reactor Protection System Instrumentation APPLICAsLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CNANNELS FRWI SPECIPIED PER TRIP REQUIRED SURVEILLANCE ALLOWASLE FUNCTION CONDITIONS SYSTEN ACTION D.1 REQUIREMENTS VALUE 8.

Turbine stop a 301 RTP 4

E st 3.3.1.1.9 s 101 closed Velve - Closure sa 3.3.1.1.11 st 3.3.1.1.13 sa 3.3.1.1.15 st 3.3.1.1.16 9.

Turbine Control Velve t 30% RTP 2

E st 3.3.1.1.9 2 600 psig fast Closure, Trip 011 st 3.3.1.1.11 Pressure - Low SR 3.3.1.1.13

)

SR 3.3.1.1.15 i

SR 3.3.1.1.16

10. Reactor Mode switch -

1,2 2

C st 3.3.1.1.12 NA shutdown Position sa 3.3.1.1.15 5(*)

2 N

SR 3.3.1.1.12 NA SR 3.3.1.1.15 4

11. Manuel seren 1,2 2

G st 3.3.1.1.5 NA SR 3.3.1.1.15 5(83 2

N st 3.3.1.1.5 NA 3

st 3.3.1.1.15 (a) With any control rod withdrawn from a core cell contelning one or more fuel assenbtles.

i l

HATCH UNIT 2 3.3-Ba Amendment No.154 l

l

)

RPS Instrumentation 3.3.1.1 l

4 l

I t

This page intentionally left blank.

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l l

l HATCH UNIT 2 3.3-8b Amendment No. 154 l

Recirculation loops Operating 3.4.1 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.1 Recirculation Loops Operating LCO 3.4.1 Two recirculation loops with matched flows shall be in operation, D.B One recirculation loop shall be in operation with the

[

following limits applied when the associated LC0 is l

applicable:

LCO 3.2.1, " AVERAGE PLANAR LINEAR HEAT GENERATION RATE l

a.

(APLHGR)," single loop operation limits specified in the i

COLR; b.

LCO 3.2.2 " MINIMUM CRITICAL POWER RATIO (MCPR)," single l

loop opera, tion limits specified in the COLR; and LCO 3.3.1.1, " Reactor Protection System (RPS) l c.

Instrumentation," Function 2.b (Average Power Range Monitor Simulated Thermal Power - High), Allowable Value of Table 3.3.1.1-1 is reset for single loop operation.

APPLICABILITY:

MODES 1 and 2.

l l

l i

HATCH UNIT 2 3.4-1 Amendment No.154

Recirculation Loops Operating 3.4.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

Requirements of the A.1 Satisfy the 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months LCO not met.

requirements of the LCO.

B.

Required Action and B.1 Be in H0DE 3.

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

98 No recirculation loops in operation.

I 1

l HATCH UNIT 2 3.4-2 Amendment No. 154 I

l i

Recirculation Loops Operating 3.4.1 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.1.1

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

l Not required to be performed until 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after both recirculation loops are in operation.

l Verify recirculation loop jet pump flow 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months I

mismatch with both recirculation loops in operation is:

a.

s 10% of rated core flow when i

operating at < 70% of rated core flow; and b.

s 5% of rated core flow when operating i

at a 70% of rated core flow.

SR 3.4.1.2 (Not used.)

i l

)

HATCH UNIT 2 3.4-3 Amendment No. 154

Recirculation Loops Operating 3.4.1 i

HATCH UNIT 2 3.4-4 Amendment No.

154

ML20237D634

Text

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