Text

Amends 205 & 146 to Licenses DPR-57 & NPF-5,respectively, Revising TS Associated W/Installation of Digital Power Range Neutron Monitoring Sys
	ML20137D059
Person / Time
Site:	Hatch
Issue date:	03/21/1997
From:	Berkow H; NRC (Affiliation Not Assigned)
To:	;
Shared Package
ML20137D064	List: ML20137D059; ML20137D067;
References
	NUDOCS 9703250249
	Download: ML20137D059 (30)
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stoq't

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UNITED STATES p

il NUCLEAR REGUL.ATORY COMMISSION e

f WASHINGTON, D.C. 30006 4001

\\*****f GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON. GEORGIA DOCKET NO. 50-321 EDWIN I. HATCH NUCLEAR PLANT. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 205 License No. DPR-57 1.

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

A.

The application for ainendment to the Edwin I. Hatch Nuclear Plant, Unit 1 (the facility) Facility Operating License No. DPR-57 filed by the Georgia Power Company, acting for itself, Oglethorpe Power Corporation, Municipal Electric Authority of Georgia, and City of j

Dalton, Georgia (the licensees), dated October 29, 1996, as i

supplemented February 19, 1997, complies with the standards and j

requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission'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 Comission; C.

There is reasonable assurance (1) that the activities authorized 4

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 Comission'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 F.

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

9703250249 970321 DR ADOCK 05000321 PDR

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:

Technical Specifications q

The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 205, are hereby incorporated in the 4

i license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

l 3.

This license amendment is effective as of its date of issuance and shall be implemented prior to Unit I startup from the fall of 1997 refueling outage.

FOR TNE'WUCLEAR REGULATORY COMMISSION gY

/

j k

Her ert N. Ber

, Director Project Directorate II-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation l

Attachment:

Technical Specification Changes Date of Issuance: March 21, 1997 i

4

ATTACHMENT TO LICENSE AMENDMENT NO. 205 FACILITY OPERATING LICENSE NO. DPR-57 DOCKET NO. 50-321 Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages. The revised pages are identified by Amendment number and contain vertical lines indicating the areas of change.

\\

Power Ranae Neutron Monitor System i

Remove Paggi Insert Paaes 3.3-1 3.3-1 3.3-2 3.3-2 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 3.3-16 3.3-16 3.3-19 3.3-19 3.4-1 3.4-1 3.10-20 3.10-20 3.10-22 3.10-22

RPS Instrumentation 3.3.1.1 i

3.3 INSTRUMENTATION 3.3.1.1 Reactor Protection System (RPS) Instrumentation i

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.

4

\\

ACTIONS i

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

i Separate Condition er.try is allowed for each cha

_________________________________________________nnel.

t CONDITION REQUIRED ACTION COMPLETION TIME i

i 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.

A.2

NOTE---------

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

Place associated trip 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 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, and 2.d.

E 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 1 3.3-1 Amendment No. 205

1 RPS Instrumentation 3.3.1.1 j

ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME i

C.

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

{

with RPS trip capability.

capability not j

maintained.

i i

D.

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

Time of Condition A, Table 3.3.1.1-1 for i

l B, or C not met.

the channel.

i j

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 j

Required Action D.I to < 30% RTP.

and referenced in i;

)

Table 3.3.1.1-1.

i' i

k i

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 i

Required Action D.1 i

and referenced in i

Table 3.3.1.1-1.

I s

s 1 i

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

[

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.-

HATCH UNIT 1 3.3-2 Amendment No. 205 l

3. _. _ _. _.. _

F RPS Instrumentation 3.3.1.1 SURVEILLANCE REQUIREMENTS 4

i,

____________________________________-NOTES------------------------------------

i 1.

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

i 2.

When a channel is placed in an inoperable status solely for performance of required Surveillances, entry into associated Conditions and Required i

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 l

i 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 1

i i

j 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 m 25% RTP.

1..

j Verify the absolute difference between 7 days i

the average power range monitor channels and the calculated power (APRM) is s 2% RTP while operating at = 25% RTP.

(

i SR 3.3.1.1.3 (Notused.)

l 1

t SR 3.3.1.1.4

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

Not required to be performed when j

entering MODE 2 from MODE I until 3

12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after. entering MODE 2.

g s

Perform CHANNEL FUNCTIONAL TEST.

7 days

}

)

SR 3.3.1.1.5 Perform CHANNEL FUNCTIONAL TEST.

7 days i

(continued) i HATCH UNIT 1 3.3-3 Amendment No. 205 a

1

4 RPS Instrumentation i

3.3.1.1 SURVEILLANCE REQUIREMENTS (continued)

' SURVEILLANCE FREQUENCY 1

i SR 3.3.1.1.6 Verify the source range monitor (SRM) and Prior to i

intermediate range monitor (IRM) channels withdrawing overlap.

SRMs from the fully inserted position 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 Perfom CHANNEL FUNCTIONAL TEST.

92 days SR 3.3.1.1.10

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

For Function 2.a not required to be perfomed 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 l

(continued)

HATCH UNIT 1 3.3-4 Amendment No. 205 i

RPS Instrumentation 3.3.1.1 SURVEILLANCE REQUIREMENTS (continued) j SURVEILLANCE FREQUENCY i

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.

SR 3.3.1.1.12 Perform CHANNEL FUNCTIONAL TEST.

18 months 1

i SR 3.3.1.1.13

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

i

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.)

l SR 3.3.1.1.15 Perform LOGIC SYSTEM FUNCTIONAL TEST.

18 months 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

HATCH UNIT I 3.3-5 Amendment.No. 205

_ _. ~ _ _.. _

RPS Instrumentation 3.3.1.1 i

i

\\i Tebte 3.3.1.1 1 (pese 1 of 3) teetter Protection Syaten Instnmentation i

b

?

APPLICABLE CMDITIONS IEBtl OR GEGUIRR GEFERENCED i

OTHER til4NNELS PROM WEClflED PER TRIP RttUIRED RNtWEILLAllCE

.ALLEM4BLE PMNCTION ODMDITIONS SYSTEM ACTION D.1 REeUIRDENTS WALUE 1.

latereediate Range IIenitor

s. toutron Fleet-NIsh I

3 e

at 3.3.1.1.1 s 120/125 i

i a 3.3.1.1.4 divieione of a 3.3.1.1.4 futt acote et 3.3.1.1.7 i

AR 3.3.1.1.13 l

a 3.3.1.1.15 i

5(*)

3 SR 3.3.1.1.1 s 120/125 l

et 3.3.1.1.5 divietone of j

OR 3.3.1.1.13 futI esete m 3.3.1.1.15 i

b.

Insp I

3 8

+ m 3.3.1.1.4 NA

)

et 3.3.1.1.15 5(e) 3 s

SR 3.3.1.1.5 EA ER 3.3.1.1.15

2. Average Pouer tense sientter

a. toutron Fttet-afgh 2

3(*)

(setdemn) e at 3.3.1.1.1 s 20E RTP a 3.3.1.1.7 SR 3.3.1.1.8 m 3.3.1.1.10 m 3.3.1.1.13 b.

Sleuteted Theneet 1

3(8)

Pauer - 51sh F

SR 3.3.1.1.1 s 0.54 W +

l SR 3.3.1.1.2 62X RTP and 5 115.5%

l

)

m 3.3.1.1.8 RTP(b)

SR 3.3.1.1.10 et 3.3.1.1.13 (continued)

(::) with any centret red withdrawn free e core cett sentelnire one or more fust ensembtles.

(b) 0.58 y + ett - 0.58 at RTP ehen reest for einste toep operetten per LCo 3.4.1, seecircutetten aperating."

(c) Each AMut ehennel provides irpute to both trip systene.

l HATCH UNIT 1 3.3-6 A

4 4

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

Reactor Protection Systes Instr u entetlen 1

APPLICAsLE CONDITIONS 4

l IEEES OR REQUIRED REFERENCED i

OTNER CNAanlELS FROM M CIFIED PER TRIP REGUIRED RRVEILLANCE ALLolMBLE fUbCTION CONDITIONS SYSTEM ACTION D.1 REQUIREMENTS WALUE

3. Amoress Peuer tense j

finnitor (eentinued) 4

s. Ileutron Fi m - Nish 1

3(8)

F 3R 3.3.1.1.1 s 120E RTP l

at 3.3.1.1.2

'en 3.3.1.1.8 1

j 1

SR 3.3.1.1.10 1

at 3.3.1.1.13 d.

388P 1,2 3(C)

G sa 3.3.1.1.10 mA j

e.

Tue out.of.Four 1,2 2

e sa 3.3.1.1.1 mA Voter i

sa 3.3.1.1.10 i

SR 3.3.1.1.15 st 3.3.1.1.16

)

3. Reacter Wesset steen 1,2 2

e a 3.3.1.1.1 s 1085 pels

(

Dame Pressure-Nish i

SR 3.3.1.1.9 et 3.3.1.1.13 sa 3.3.1.1.15 4.

Roseter Wessel Water 1,2 2

G m 3.3.1.1.1 4 0 inches i

Lovet -Leu, LoveL 3

}

m 3.3.1.1.9 st 3.3.1.1.13 et 3.3.1.1.15 I

5. stein steem footetten 1

8 F

m 3.3.1.1.9 s 10E stomed Wetwe - Cleeure SR 3.3.1.1.13 sa 3.3.1.1.15

4. tryNeti Pressure-Nish 1,2 2

8 SR 3.3.1.1.1 a 1.92 pels a

SR 3.3.1.1.9 at 3.3.1.1.13

{

sa 3.3.1.1.15

,i (continued)

(c) Sech ApeN shonnet provides inpute to both trip systems.

1 I

i 1

1 HATCH UNIT 1 3.3-7 Amendment No. 205

Centrol R:d Block Instrumentation 3.3.2.1 ACTIONS (continued)

CONDITION.

REQUIRED ACTION COMPLETION TIME i

E. One or more Reactor E.1 Sussend control rod Immediately Mode Switch - Shutdown wit Wrawal.

i Position channels inoperable.

8 31 l

I E.2 Initiate action to Immediately l

fully insert all insertable control i

j rods in core cells containing one or more fuel assemblies, i

SURVEILLANCE REQUIREMENTS 1

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

1.

Refer to Table 3.3.2.1-1 to determine which SRs ' apply for each Control Rod Block Function.

2.

When an R8N channel is placed in an inoperable status solely for perfonnance of required Surve111ances, 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 control rod block capability.

SURVEILLANCE FREQUENCY SR 3.3.2.1.1 Perform CHANNEL FUNCTIONAL TEST.

184 days l

t 4

(continued)

HATCH UNIT 1 3.3-16 Amendment No. 205

t 4

3 Control Rod Block Instrumentation 4

3.3.2.1 4

Table 3.3.2.1 1 (pose 1 of 1) i Centret and stock Instrimentation 1

l 1

APPLICABLE MDES OR OTNR OPECIFIED REGUIRED SURWILLANCE ALLChan8LE i

RAICTION COWITIONS CNANNELS REGUIREE NTS VALUE l

j

1. ted Staek Honitor I

s. Lau peuer Range-Wte (e) a na 3.3.2.1.1 s 115.5/15 i

M 3.3.2.1.4 divlelens of

)

1 SR 3.3.2.1.7 futt scale l

b.

Intermediate Power (b) 2 M 3.3.2.1.1 s 109.7/125 Serge - Upeceie sa 3.3.2.1.4 divieIone of i

et 3.3.2.1.7 futi seate I

c. alsh Pouer aange-t4mcate (c),(d) 2 et 3.3.2.1.1 s 105.9/125 i

M 3.3.2.1.4 divlelene of I

SR 3.3.2.1.7 full eseie j

d.

Insp (d),(e) 2 at 3.3.2.1.1 mA

e. Deunesete (d),(e) 2 at 3.3.2.1.1 t 93/125 l

M 3.3.2.1.7 divlefone of futt scale l

2.

Red Worth Minfelser 1(f) 2(f) l 1

M 3.3.2.1.2 mA l

M 3.3.2.1.3 M 3.3.2.1.5 M 3.3.2.1.8

3. Reacter 8tede sultch-Shutdown positten (8) 2 M 3.3.2.1.6 NA 1

t' n

i to) TEnnAL POWER R 295 and

641 RTP and IICPR < 1.70.

j (b) TEWIAL pelEt t 645 and < 865 RTP and IICPR < 1.70.

s 4

(c) TEINIAL PelER k 86E and < 90E RTP and IECPR < 1.70.

(I) THEIstAL 9tnER R 901 RTP and secPR < 1.40.

(2) TIERIIAL PelER t 291 and < 90E RTP and IICPR < 1.70.

6 (f) With TNEINIAL POWER e 10E RTP.

(g) seector made euttch in the shutdeun peeltfen.

1 1

~

t 8

1 HATCH UNIT 1 3.3-19 Amendment No. 205 i

s

j Recirculation Loops Operating 3.4.1 i

3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.1 Recirculation 1. oops Operating j

LC0 3.4.1 Two recirculation loops with matched flows shall be in operation, i

i I.

One recirculation loop shall be in operation with:

The following limits applied when the associated LC0 is a.

j applicable:

1.

LC0 3.2.1, " AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR)," single loop operation limits specified in the COLR; 2.

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

single loop operation limits specified in the COLR; 3.

LCO 3.3.1.1, " Reactor Protection System (RPS)

Instrumentation," Function 2.b (Average Power Range Monitor Simulated Thermal Power-High), Allowable l

Value of Table 3.3.1.1-1 is reset for single loop operation; and b.

Core flow as a function of core thermal power in the

" Operation Allowed Region" of Figure 3.4.1-1.

APPLICABILITY:

MODES I and 2.

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.

No recirculation loops A.1 Place the reactor immediately in operation, mode switch in the shutdown position.

(continued)

HATCH UNIT 1 3.4-1 Amendment No. 205

\\

i i

SDM Test - Refueling i

3.10.8 i

f 3.10 SPECIAL OPERATIONS i

3.10.8 SHUTD0WN MARGIN (SDM) Test - Refueling i

i l

LC0 3.10.8 The reactor mode switch position specified in Table 1.1-1 i

for MODE 5 may be changed to include the startup/ hot standby position, and operation considered not to be in MODE 2, to allow SDM testing, provided the following requirements are j

met:

LC0 3.3.1.1, " Reactor Protection System a.

Instrumentation," MODE 2 requirements for Functions 2.a*

2.d. and 2.e of Table 3.3.1.1-1; j

b.

1.

i LC0 3.3.2.1, " Control Rod Block Instrumentation,"

i MODE 2 requirements for Function 2 of Table 3.3.2.1-1, with the banked position withdrawal i

sequence requirements of SR 3.3.2.1.8 changed to require the control rod sequence to conform to the i

SDM test sequence, QB 2.

Conformance to the approved control rod sequence for the SDM test is verified by a second licensed operator or other qualified member of the technical staff; Each withdrawn control rod shall be coupled to the c.

associated CRD; d.

All control rod withdrawals during out of sequence control rod moves shall be made in notch out mode; No other CORE ALTERATIONS are in progress; and e.

f.

CRD charging water header pressure m 940 psig.

l APPLICABILITY:

MODE 5 with the reactor mode switch in startup/ hot standby position.

I HATCH UNIT 1 3.10-20 Amendment No. 205

1 SDM Test -- Refueling 1

3.10.8 SURVEILLANCE REQUIREMENTS SURVEILLANCE l

FREQUENCY i

SR 3.10.8.1 Perform the NODE 2 applicable SRs for According to i

LCO 3.3.1.1, Functions 2.a 2.d and 2.e of the applicable l

Table 3.3.1.1-1.

SRs l

l SR 3.10.8.2

- NOTE------ -

i Not required to be met if SR 3.10.8.3 satisfied.

i 4

Perform the MODE 2 applicable SRs for According to LCO 3.3.2.1, Function 2 of Table 3.3.2.1-1.

the applicable SRs 4

SR 3.10.8.3

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

i Not required to be met if SR 3.10.8.2 satisfied.

i Verify movement of control rods is in During control I

compliance with the approved control rod rod movement sequence for the SDM test by a second licensed operator or other qualified member of the technical staff.

i SR 3.10.8.4 Verify no other cO'RE ALTERATIONS are in 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months j

progress.

(continued) f i'

4 l

HATCH UNIT 1 3.10-22 Amendment No. 205

pwruq g

UNITED STATES g

j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20066-0001 o

'+ *****,o i

GEORGIA POWER COMPANY OGLETHORPE POWER CORPORATION j

MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON. GEORGIA DOCKET NO. 50-366 EDWIN I. HATCH NUCLEAR PLANT. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 146 License No. NPF-5 1.

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

A.

The application for amendment to the Edwin I. Hatch Nuclear Plant, Unit 2 (the facility) Facility Operating License No. NPF-5 filed by I

the Georgia Power Company, acting for itself, Oglethorpe Power Corporation, Municipal Electric Authority of Georgia, and City of Dalton, Georgia (the licensees), dated October 29, 1996, as supplemented February 19, 1997, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act),

and the Comission'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 (1) 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 i

conducted in compliance with the Comission's regulations set forth in 10 CFR Chapter I; D.

The issuance of this amendment will not be inimical to the comon 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 Comission's regulations and all applicable requirements have been satisfied.

_.______.m____

. 2.

Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license l

amendment, and paragraph 2.C.(2) of Facility.0perating License No. NPF-5 l

1s hereby amended to. read as follows:

Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 146 are hereby incorporated in the license. The licensee 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 Unit 2 startup from the spring of 1997 refueling outage.

FOR THE NUCLEAR REGULATORY COMISSION

]

J Herbert N. B k w, Director Pfoject Directorate II-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Technical Specification Changes-Date of-Issuance:

March 21,1997 i

l I

l l

AITACHMENT TO LICENSE AMENDMENT NO. 146 FACILITY OPERATING LICENSE NO. NPF-5 DOCKET NO. 50-366 Replace the following pages, ? the Appendix "A" Technical Specifications with the enclosed pages. The res.f sed pages are identified by Amendment number and contain vertical lines indicating the areas of change.

Power Ranae Neutron Monitor System Remove Paaes Insert Paaes 3.3-1 3.3-1 3.3-2 3.3-2 3.3-3 3.3-3 3.3-4 3.3-4 3.3-5 3.3-5 3.3-7 3.3-7 3.3-8 3.3-8 3.3-17 3.3-17 3.3-20 3.3-20 3.4-1 3.4-1 1

3.10-20 3.10-20 3.10-22 3.10-22

4 L

RPS Instrumentation 3.3.1.1 i

3.3 INSTRUMENTATION 3.3.1.1 Reactor Protection System (RPS) Instrumentation LC0 3.3.1.1 The RPS instrumentation for each Function in Table 3.3.1.1-1 j

shall be OPERABLE.

i APPLICABILITY:

According to Table 3.3.1.1-1.

1 1

i ACTIONS 4

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

Separate Condition entry is allowed for each chann

___________________________________________________el.

1 i

}

i CONDITION REQUIRED ACTION COMPLETION TIME i

4 i

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.

08 A.2

NOTE---------

Not applicable for j

Functions 2.a. 2.b.

l 2.c, and 2.d.

l 4

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

4

}

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, and 2.d.

QB 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. 146 1

h RPS Instrumentation 3.3.1.1 l

ACT10NS (continued)

CONDITION REQUIRED ACT10N COMPLETION TIME C.

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

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 i

Required Action D.1 and referenced in i

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.]

fully insert all and referenced in insertable control Table 3.3.1.1-1.

rods in core cells containing one or more fuel assemblies:

HATCH UNIT 2 3.3-2 h

Amendment No.146 l

e

1 RPS Instrumentation 3.3.1.1 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 Surveillances, 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 t

l l

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 k 25% RTP.

l Verify the absolute difference between 7 days i

the average power range monitor (APRM) channels and the calculated power is j

s 2% RTP while operating at k 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 l

f (continued)

HATCH UNIT 2 3.3-3 Amendment No. 146

________m

=

RPS Instrumentation 3.3.1.1

-SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY l

1 SR 3.3.1.1.6 Verify the source range monitor (SRM) and Prior to 1

intermediate range monitor (IRM) channels withdrawing overlap.

SRMs from the fully inserted position SR 3.3.1.1.7

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

Only required to be met during entry into MODE 2 from NODE 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 hourc SR 3.3.1.1.g Perform CHANNEL FUNCTIONAL TEST.

g2 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 l

(continued)

HATCH UNIT 2 3.3-4 Amendment No.146

i RPS Instrumentation 3.3.1.1 SURVEILLANCE REQUIREMENTS (continued) f SURVEILLANCE 3

FREQUENCY SR 3.3.1.1.11 Verify Turbine Stop Valve - Closure and 18 months Turbine Control Valve Fast Closure Trip i

011 Pressure - Low Functions are no,t 4

bypassed when THERMAL POWER is 2 30% RTP.

I SR 3.3.1.1.12 Perform CHANNEL FUNCTIONAL TEST.

18 months I

i SR 3.3.1.1.13

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

i

1. Neutron detectors are excluded.

2. For Function 1, not required to be i

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 i

MODE 2.

i i

Perform CHANNEL CALIBRATION.

18 months i

4 SR 3.3.1.1.14 (Not used.)

l SR 3.3.1.1.15 Perform LOGIC SYSTEM FUNCTIONAL TEST.

18 months (continued)

HATCH UNIT 2 3.3-5 Amendment No. 146

4 RPS Instrumentation 4

3.3.1.1

}

i Table 3.3.1.1 1 (pege 1 of 3)

Reactor Protection system Instrumentation i

APPLICASLE CnWDITIONS NSES OR REGUIRED REFERENCED i

l OTHER CNANNELS FROM SPECIFIED PER TRIP REeulRED SURVEILLANCE ALLOWABLE PUNCTION CONDITIONS SYSTEM ACTION D.1 REeUIREMENTS VALUE i

1.

Intermediate Renee seenitor j

a.

Routron Fi m - Nish 2

3 a

sa 3.3.1.1.1 s 120/125

{

st 3.3.1.1.4 divisions of BR 3.3.1.1.6 futL seate q

st 3.3.1.1.7 at 3.3.1.1.13 at 3.3.1.1.15

{

S '}

3 m

sa 3.3.1.1.1 s 120/125 I

1 sa 3.3.1.1.5 divistens of j

at 3.3.1.1.13 futt scate st 3.3.1.1.1b 1

b.

Insp 2

3 s

at 3.3.1.1.4 NA 5

ER 3.3.1.1.15 5 a) 3 N

st 3.3.1.1.5 NA t

at 3.3.1.1.15 i

2.

Average Power Range stonitor a.

Neutron FLw.Nigh 2

II '3 G

M 3.3.1.1.1 5 20% RTP (Setdown)

(

et 3.3.1.1.7 i

3R 3.3.1.1.8

{

en 3.3.1.1.10 m 3.3.1.1.13 b.

Slauteted Thernet 1

3(c)

F st 3.3.1.1.1 s 0.58 W +

l j

Power - Nish i

at 3.3.1.1.2 621 RTP and s 115.5%

l st 3.3.1.1.8 RTP(b) sa 3.3.1.1.10 at 3.3.1.1.13 4

~

(continued)

With any control rod withdrawn from a core cett containing one or more fuel assembtles.

(a) i 4

(b) 0.58 W + 62% - 0.58 AW RTP when reset for single loop operation per LCO 3.4.1, "Rectreutetfon Loops cperatine."

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

l HATCH UNIT 2 3.3-7 Amendment No.146

1 RPS Instrumentation i

3.3.1.1 Table 3.3.1.1 1 (pose 2 of 3)

Reactor Protection system Instrumentation APPLICASLE CONDITIONS

$10 DES OR REGUIRED REFERENCED OTNER C#ANNELE FROM SPECIFIED PER TRIP REQUIRED

'suRVE!LLANCE ALLOWASLE FUNCTION CONDITIONS sVSTEM ACTION 0.1 REQUIREMENTS VALUE

2. Averese Peuer kerge IIent tor (continued) c.

thoutron Fluu-Nish 1

3ICI F

st 3.3.1.1.1 s 120E RTP l

m 3.3.1.1.2 SR 3.3.1.1.8 SR 3.3.1.1.10 SR 3.3.1.1.13 d.

Insp 1,2 3(CI G

sa 3.3.1.1.19 NA e.

Tue-out of Four 1,2 2

G SR 3.3.1.1.1 hA vetor SR 3.3.1.1.10 st 3.3.1.1.15 BR 3.3.1.1.16

3. aseetor Vesset steen 1.2 2

c st 3.3.1.1.1 s 1085 psis Dame Pressure - Nish SR 3.3.1.1.9 SR 3.3.1.1.13 SR 3.3.1.1.15 SR 3.3.1.1.16 6.

teactor vessel Water 1,2 2

G st 3.3.1.1.1 R 0 teches Level - Lou, Level 3 sa 3.3.1.1.9 SR 3.3.1.1.13 SR 3.3.1.1.15 SR 3.3.1.1.16 5.

8 lain Steem isolation 1

8 F

st 3.3.1.1.9 s 10% closed Vetwe - Closure SR 3.3.1.1.13 sa 3.3.1.1.15 st 3.3.1.1.16 6.

Drywel( Pressure - Nish 1,2 2

G SR 3.3.1.1.1 1 1.92 psis SR 3.3.1.1.9 BR 3.3.1.1.13 SR 3.3.1.1.15 (continued)

(c) Each APRM channet provides Irputs to both trip systees.

l HATCH UNIT 2 3.3-8 Amendment No.146

Control Rod Block Instrumentation 3.3.2.1 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E.

One or more Reactor E.1 Suspend control rod Immediately t

Mode Switch - Shutdown Position channels withdrawal.

inoperable.

AND E.2 Initiate action to Immediately l

i fully insert all insertable control l

rods in core cells containing one or more fuel assemblies.

SURVEILLANCE REQUIREMENTS

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

1.

Block Function. Refer to Table 3.3.2.1-1 to determine which SRs apply for each C 2.

When an RBM channel is placed in an inoperable status solely for performance of required Surveillances, 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 con

trol rod block capability.

SURVEILLANCE FREQUENCY SR 3.3.2.1.1 Perform CHANNEL FUNCTIONAL TEST.

184 days 1

(continued) l i

I HATCH UNIT 2 3.3-17 Amendment No.146

Centrol Rod Bicek Instrumentation 1

3.3.2.1 e

4, Tabte 3.3.2.1 1 (pese 1 of 1)

Centrol Red stock Instrsmentation 1

APPLICABLE 8moES oR OTNER i

SPECIFIED REQUIRED sukVEILLANCE ALLOWASLE i

PUNCTION COSITIONS CIWuNIELS REGUIREMENTs VALUE i

1.

Red Stock stentter a.

Lou Power targe-upscete (e) 2 at 3.3.2.1.1 s 115.5/15 SR 3.3.2.1.4 divistens of M 3.3.2.1.7 futt scale i

b.

Intermediate Power (b) 2 M 3.3.2.1.1 s 109.7/15 tange -upscale l

SR 3.3.2.1.4 divialens of SR 3.3.2.1.7 full scale I

c.

utsh Power tense-upscale (c),(d) 2 SR 3.3.2.1.1 s 105.9/125 4

I BR 3.3.2.1.4 divistens of SR 3.3.2.1.7 futt scele d.

Insp (d),(e) 2 SR 3.3.2.1.1 MA 4

e.

Deunseate j

(d),(e) 2 SR 3.3.2.1.1 2 93/125 SR 3.3.2.1.7 divisiens of j

futt scale i

2.

Sed Worth Miniefner 1(f) 2(I) 1 M 3.3.2.1.2 NA i

l et 3.3.2.1.3 SR 3.3.2.1.5 SR 3.3.2.1.8 3.

aeector leeds switch-Shutdown (s) 2 et 3.3.2.1.6 NA Positten (a) TNERNAL POWER t 295 and 4 ME RTP and NCPR < 1.70.

(b) TERMAL POWER R ME and < 84E RTP and 81CPR < 1.70.

(c) TEAMAL POER t 845 and < 90% RTP and IICPR < 1.70.

(d) THERMAL POWER t 901 RTP and 81CPR < 1.40.

(c) TIIERNAL POWER t 295 and < 901 RTP and MCPR < 1.70.

(f) With THEasIAL POWER < 10% RTP.

(s) Reacter mode auftch in the shutdown position.

HATCH UNIT 2 3.3-20 Amendment No.146

}

[

l Recirculation Leops Operating 3.4.1 l

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 l

operation, i

E j

One recirculation loop shall be in operatiors with:

2 The following limits applied when the associated LCO is a.

applicable:

(

1 1.

LC0 3.2.1, " AVERAGE PLANAR LINEAR HEAT GENERATION RATE (APLHGR)," single loop operation limits i

specified in the COLR; i,

2.

LC0 3.2.2, ' MINIMUM CRITICAL POWER RATIO (MCPR),"

single loop operation limits specified in the COLR; 3.

{

LCO 3.3.1.1, " Reactor Protection System (RPS)

Monitor Simulated Thermal Power (- High), Allowab l

Value of Table 3.3.1.1-1 is reset for single loop 3

operation; and t

b.

Core flow as a function of core thermal power in the

" Operation Allowed Region" of Figure 3.4.1-1.

i i

APPLICABILITY:

MODES I and 2.

i ACTIONS i

1 CONDITION REQUIRED ACTION COMPLETION TIME i

i t

A.

No recirculation loops A.1 Place the reactor Immediately in operation, mode switch in the shutdown position.

i i

(continued) 4

,1 i

HATCH UNIT 2 3.4-1 Amendment No.146 3

j SDM Test - Refueling 3.10.8 l

3.10 SPECIAL OPERATIONS 3.10.8 SHUTDOWN MARGIN (SDM) Test - Refueling i

i LC0 3.10.8 The reactor mode switch position specified in Table 1.1-1 for MODE 5 may be changed to include the startup/ hot standby position, and operation considered not to be in MODE 2, to l

allow SDN testing, provided the following requirements are i

met:

}!

LC0 3.3.1.1,

Reactor Protection System a.

Instrumentation," MODE 2 requirements for Functions 2.a, 2.d, and 2.e of Table 3.3.1.1-1; l

1 b.

1.

i LCO 3.3.2.1, " Control Rod Block Instrumentation,"

i MODE 2 requirements for Function 2 of Table i

3.3.2.1-1, with the banked position withdrawal i

sequence requirements of SR 3.3.2.1.8 changed to require the control rod sequence to conform to the l

SDM test sequence, QB 1

2.

Conformance to the approved control rod sequence for i

the SDM test is verified by a second licensed j

operator or other qualified member of the technical j

staff;

}

Each withdnwn control rod shall be coupled to the c.

l associated f:RD; i

d.

All control rod withdrawals during out of sequence j

control rod moves shall be made in notch out mode; 4

No t:ther CORE ALTERATIONS are in progr'ess; and e.

f.

CRD charging water header pressure a: 940 psig.

APPLICABILITY:

MODE 5 with the reactor mode switch in startup/ hot standby psition.

HATCH UNIT 2 3.10-20

.c p

Amendment No. 146

i i

I SDM Test -- Refueling 3.10.8 SURVEILLANCE REQUIREMENTS 3

SURVEILLANCE FREQUENCY SR 3.10.8.1 Perform the MODE 2 applicable SRs for j

LC0 3.3.1.1, Functions 2.a. 2.d, and 2.e of According to 1

Table 3.3.1.1-1.

the applicable l

t SRs f

1 i

SR 3.10.8.2

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

4 Not required to be met if SR 3.10.8.3 satisfied.

____________o______________________________

Perform the MODE 2 applicable SRs for LCO 3.3.2.1, Function 2 of Table 3.3.2.1-1.

According to the applicable SRs SR 3.10.8.3

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

Not required to be met if SR 3.10.8.2 satisfied.

Veriky movement of control rods is in During control compliance with the approved control rod rod movement sequence for the SOM test by a second licensed operator or other qualified member of the technical staff.

SR 3.10.8.4 Verify no other CORE ALTERATIONS are in 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months progress.

(continued)

HATCH UNIT 2 3.10-22 Amendment No.

146

.

ML20137D059

Text

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