Text

Amend 88 to License NPF-5,amending Tech Specs to Permit Temporary Increase in Main Steam Line High Radiation Scram & Isolation Setpoints to Facilitate Hydrogen Addition Water Chemistry Testing
	ML20148E429
Person / Time
Site:	Hatch
Issue date:	01/13/1988
From:	Crocker L; Office of Nuclear Reactor Regulation
To:	;
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	NUDOCS 8801260035
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..____

4 pasog jo UNITED STATES j

g g

g NUCLEAR REGULATORY COMMISSION 3

-l WASHINGTON, D. C. 20555

)

vi GEORGIA POWER COMPANY OCLETHORPE POWER CORPORATION MUNICIPAL ELECTRIC AUTHORITY OF GEORGIA CITY OF DALTON, GEORGIA DOCKET NO. 50-366 EDWIN I. HATCH NUCLEAR PLANT, UNIT NO. 2

~

AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.

88 License No. NPF-5 1.

The Nuclear Regulatory Comission (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 Georgia Power Company, acting for itself, Oglethorpe Power Corporation, Municipal Electric Authority of Georgia, and City of Dalton, Georgia, (the licensee) dated March 20, 1987, and supple-mented November 23, 1987, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations 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 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 Chspter 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 j

been satisfied.

B801260035 880113 DR ADOCK 050 6

l

.-.y

2.

Accordingly, the license is amended by changes to the Technical Specifi-cations 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 Appendices A and B, as revised through Amendnent No. 88. are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of its date of issuance and shall be implemented within 60 days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

\\$\\

Lawrence P. Crocker, Acting Director Project Directorate II-3 Division of Reactor Projects-I/II

Attachment:

Changes to the Technical Specifications Date of Issuance:

January 13, 1988 h

MR6'o{d/macPDf Ir3/DRP-I/II PD#II-3/DRP-I/II OGC sda PD#11-3/DRP-I/II LCrocker Acting PD 12/yb'/87 12/R1/87 1 /gb/87 12/A*J/87

e ATTACHMENT TO LICENSE AMEN 0 MENT NO. 88 FACILITY OPERATING LICENSE NO NPF-5 DOCKET NO. 50-366 Replace the following pages of the Appendix A Technical Specifications with the enclosed paaes. The revised pages are. identified by amendment number and contain vertical lines indicating the area of change.

Remove Insert Page Page 2-4 2-4 3/4 3-2 3/4 3-2 3/4 3-5 3/4 3-5 3/4 3-11 3/4 3-11 3/4 3-15 3/4 3-15 3/4 3-16 3/4 3-16 3/4 3-58a 3/4 3-58a 3/4 3-58b 3/4 3-58b 3/4 3-58c 3/4 3-58c i

4 1

j

)

D 2

~.

e

- at TABLE 2.2.1-1

>=pj REACTOR PROTECTION SYSTEM INSTRUMENTATION SETPOINTS r

FUNCTIONAL UNIT TRI? SrTPOINT ALLOWABLE VALUES cj5 1.

Intermediste Range Monitor, Neut ron f lux-High 5 120/125 divisions 5 120/125 divisions

-4 (2C51-K601 A,8,C,D,E,F,G,H) of full scale of full scale 2.

Average Power Range Monitor:

(2C51-K605 A,B,C,0 E,r) a a.

Neut ron f lux-Upsca le, 15%

5 15/125 divisions 5 20/125 divisions of fu?l scale of full scale b.

Flow Rorerenced Simulated Thermal 5 (0.58 W + 59% - 0.584W)**

5 (0.58 W + 62% - 0.584W)**

Powe r-Upsca le with a maximum with a maximum 5.113.5% or HAi[D 1 115.5% of RATED TilERNAL POWER THERMAL POWER c.

Fixed Neutron Flux-Upsca le, 118%

5 118% or RATED 5 120% of RATED THERMAL POWER THERMAL POWER 3.

Reactor vessel Steam Dome Pressure - High 5 1054 psig 5 1054 psig ro (2821-N678 A,B,C,0) 4.

Reactor Vessel We' tor Leyel - Low (Level 3) 2 10 inches above 2 10 inches above (2B21-N680 A,B,C,0) instrument zero*

instrument zero' 5.

Main Steam Line Isoiation Valve - Closure 5 10% closed 5 10% closed (NA) 6.

Main Steam Line Radiation - High 5 3 x rull-power 5 3 x rul l-power (2011-K603A,B,C,0) bac kg round ***

bac kg round***

l t

.7.

D rywe l l Pressuns - High 5 1.92 psig 5 1.92 psig (2C71-N650A,8,C,D)

%/

- g*

See Bases F igure B 3/4 3-1.

o D

- W = Total loop reci rculation flow rate in percent or rated.

Rated loop reci rculation flow is equal to 34.2 MLB/hr.

o D

4W = Maximum measured dirrerence between two-loop and single-loop drivo flow for the same core flow in percent of ra ted reci rculation riov for single-loop operation.

The va l ue i s ze ro fo r two-l oop ope ra t i on.

21 f

- - Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months prior to the planned start of the hydrogen injection test with the reactor power at greater than 20% rated power, the normal full-power radiation background level and associated trip 00 setpoints may be changed based on a calculated value of the radiation level expected during the test.

U' The backg rouno radiation level and associated trip setpoints may be adjusted during the test based on either calculations or measurements of actual radiation levels resulting from hydrogen injection. The backg round radiation level shall be determined and associated trip setpoints shall be set within 24 e

hours or re-establishing normas radiation levels after completion of hydrogen injection and prior to L

establishing reactor power levels below 20% rated power.

I I

1

=

TABLE 3.3.1-1 R.EACTOR PROTECTION SYSTEM INSTP.UMENTATION Hn APPLICABLE MINIMUM NUMBER OPERATIONAL OPERABLE CifANNELS FUNCTIONAL UNIT CONDITIONS

_P_[R_ TRIP SYSTEMfa)

ACTION c-1.

Intermediate Range Monitors:

2 (2C51-K601, A, B, C, D, E, F,

C, H) a.

Neutron Flux - High 2,

5

3

~

N 1

3, 4 2

2 b.

Inope.stive 2,5'**

3 i

3, 4 2

2 2.

Average Power Range Monitor:

(2C51-K605 A, 8, C, D, E,

F) a.

Neutron Flux - Upscale, 15%

2, 5 2

1 b.

Flow Referenced Simulated Thermal Power - Upsca le 1

c.

Fixed Neutron Flux -

2 3

Upscale, 118%

1 2

3 d.

Inope ra t ive 1, 2, 5

2 s

e.

Downscale 1

(as f.

LPRM 2

3 1, 2, 5 (d)

NA 3.

Reactor Vessel Steam Dome Pressure -

y High (2821-N678 A, 8,

C, 0) 1, 2'*8 2

5 ro is. Reactor Vessel Water Level -

Low (Level 3) (2821-N680 A, 8, C, D) 1, 2

2 5

5.

Main Steam Lina isolation Valve -

Closure (NA)

I

is 3

l 6.

Main Steam Line Radiation - High 1,

2,

2 6

l (2011-K603 A, 8, C, D) k 7.

Drywel l Pressure - High 1,

2

2 5

g (2C71-N650 A, 8, C, D) a B

(D I

c et Z

.U co CD e

1-

TABLE 3.3.1-1 (Continued)

REACTOR PROTECTION SYSTEM INSTRUMENTATXON i

ACTION 9 -

In OPERATIONAL CONDITION 1 or 2, be in at least HOT SHUTOOWN within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

In OPERATIONAL CONDITION 3 or 4, lock the reactor mode switch in the Shutdown position within one hour.

In OPERATIONAL CONDITION 5, suspend all operations involving CORE ALTERATIONS or positive reactivity changes and fully insert all insertable control rods within one hour.

TABLE NOTATIONS a.

A channel may be placed in an inoperable status for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for required surveillance without placing the trip system in the tripped condition provided at least one OPERABLE channel in the same trip system is monitoring that parameter.

b.

The "shorting links" shall be removed from the RPS circuitry during CORE ALTERATIONS and shutdown margin demonstrations performed in accordance with Specification 3.10.3.

c.

The IRM scrams are automatically bypassed when the reactor vessel mode switch is in the Run position and all APRM channels are OPERABLE and on scale.

d.

An APRM channel is inoperable if there are less than 2 LPRM inputs per level or less than eleven LPRM inputs to an APRM channel.

e.

These functions are not required to be OPERABLE when the reactor pressure vessel head is unbolted or removed, f.

This function is ausomatically bypassed when the reactor mode switch is in other than the Run position, i

g.

This function is not required to be OPERABLE when PRIMARY CONTAINMENT INTEGRITY is not required.

l h.

With any control rod withdrawn. Not applicable to control rods removed per Specification 3.9.11.1 or 3.9.11.2.

i. These functions are bypassed when turbine first stage pressure is s250*

psig, equivalent to THERMAL POWER less than 30% of RATED THERMAL POWER.

J.

Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months prior to the planned start of the hydrogen injection test with the reactor power at greater than 20% rated power, the normal full-1 power radiation background level and associated trip setpoints may be changed based on a calculated value of the radiation level expected during the test. The background radiation level and associated trip setpoints may be adjusted during the test based on either calculations or measurements of actual radiation levels resulting from hydrogen injection. The background radiation level shall be determined and associated trip setpoints shall be set within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of re-establishing normal radiation levels af ter completion of hydrogen injection and prior to establishing reactor power levels below 20% rated power.

Initial setpoint. Final setpoint to be determined durirg startup testing.

HATCH - UNIT 2 3/4 3-5 Amendment No. 88 b

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TABLE 3.3.2-1 at

_lSOLATION ACTUATION INSTRUNENTATION e

cc VALVE CROUPS MINIMUM NUMBER APPLICABLE 25 OPERATED BY OPERABLE CHANNELS OPERATIONAL

-a TRIP FUNCTION SIGNAlfal PER 1 RIP SYSTfH{bj{cl

_ CONDITION _

ACTION 1.

PRIMARY CONTAINMENT ISOLATION a.

Reactor Vessel Water Level 1.

Low (Level 3) 2, 6, 10, 2

1, 2, 3

20 (2821-N680 A, B,

C, D) 11, 12 2.

Low-Low (Level 2) 5, 2

1, 2,

3 20, (2821-N682 A, B, C, D) 3.

Low-Low-Low (Level 1) 1 2

1, 2, 3 20 (2821-N681 A, B, C, D) b.

Drywe l l Pressure - High 2, 6, 7, 10, 2

1, 2, 3 20 (2C71-N650 A, B, C, D) 12,

c.

Main Steam Line 1

Radiation - High 1,

12, (d) 2 1,

2, 3,("'

21 (2D11-K603 A, B,

C, 0) o, 2.

Pressure - Low 1

2 1

22 (2e21-N015 A, B, C, D) 3.

Flow - High 1,

2/line 1, 2, 3

21 ca (2B21-N686 A, B, C, D) 8 (2821-N687 A, B,

C, D)

~[

(2B21-N688 A, B, C, 0)

(2021-N689 A, B,

C, D) d.

Main Steam Line Tunnel Temperature - High 1

2/line

1, 2, 3

21 (2B21-N623 A, B, C, D)

(2B21-N624 A, B, C, D)

(2821-N625 A, B,

C, D)

(2821-N626 A, B,

C, D) e.

Condenser Vacuum - Low 1

2 1,

2,t'n,3t

23 (2B21-NOS6 A, B, C, D) f.

Turbine Building Area Temperature - High 1

2('8 1, 2, 3

21 (2U61-R001, 2U61-R002, 2U61-ROO3, 2061-R004) ha g.

Drywell Radiation - High (J8 1

1, 2,

3 29 D

(2D11-K621 A, 8) o.

Bw D

rt Zo CD

7ABL2 3.3.2-1 (Continued) o ISOLA?!ON ACTUATION IN$?ROMENTATION ACTION ACTION 20 Be in at least HOT SHUTDOWN within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD $HUTO M within the riext 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

ACTION 21 Be in at least STARTUP with the rain steam line isolation valves closed wMhin 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or be in at least HOT SHUTDC.N within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and it. COLD SHUTDOWN within the next 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

ACTION 22 Be in at least STARTUP within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

ACTION 23 6; in at least $TARTUP with the Group 1 isolation valves closed within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or in at least HOT SHUTDOWN within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

ACTION 24 Establish SECONDARY CONTAINWENT INTEGRITY with the stancby gas treatment system opercting within one hour.

ACTION 25 Isolate the reactor water cleanup system.

ACTION 26 Close the affected system isolation valves and declare the affected system inoperable.

ACTION 27 - Vertfy power availability to the bus 3t least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months or close the affected system isolation valve' and declare the affected system inoperable.

ACTION 28 - Close the shutdown cooling supply and reactor vessel head spray isolation valves unless reactor steam doee pressure s 145 psig.

ACTION 29 Either close the affected isolation valves within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in HOT SHUT 00WN within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the next 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

NOTES Actuates the standby gas treatment system.

When handling irradiated fuel in the secondary containment, i

See Specification 3.6.3 Table 3.6.3-1 for valves in each valve group, a.

b, A channel may be placed in an inoperable status for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ' for required surveillance without placing the trip system in the tripped condition ;rovided at least one other OPERABLE channel in the same trip system is monitoring that paraeeter.

With a design providing only one channel per trip system, an inope*able c.

channel need not be placed in the tripped condition where this would cause the Trip Function to occur. In these cases, the inoperable channel shall be restored to OPERABLE status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or the ACTION required by Table 3.3.2-1 for that Trip Function shall be taken, d.

Trips the mecharical vacuum pumps, A channel is CPERABLE if 2 of 4 instruments in that channel are OPERA 9LE.

e.

f.

May be bypassed with all turbine stop valves closed.

g.

Closes only RWCU outlet isolation valve iG31-F004, h.

Alarm only.

1.

Adjustable up to 60 minutes, j.

Isolates containrent purge and vent valves, k.

Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months prior to the planeed start of the hydrogen injection test with the reactor power at greater than 20% rated power, the norral full-power radiation background level and associated trip setpoints may be changed based on a calculated value of the radiation level expected during the test. The background radiation level and associated trip setpoints may be adjusted during the test based on either calculations or measurteents of actual radiation levels resulting from hydrogen injection. The background radiation level shall be determined and associated trip setpoints shall be set within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of re-establishing normal radiation levels after completion of hydrogen injection and prior to establishing reactor power levels below 20% rated power.

HATCH - UNIT 2 3/4 3 15 Amendment No. 88

~

TABLE 3.3.2-2 ISOLATION ACTUATION INSTRUMENTATION SETPO!NTS I

H t

c)

L ALLOWABLE I

TRIP FUNCTION TRIP SETPOINT VAluE

1.., PRIMARY CONTAINMENT ISOLATION c2

+ -e a.

Reactor Vessel Water Level H

1.

Low (Levei 3) 2 10 inches

2 10 inches

m 2.

Low Low (Level 2) 2 -4 7 inches

2 -47 inches

3.

Low Low tow (Level 1) 2 -113 inches

2 -113 inches

b.

Drywell Pressure - High 5 1.92 psig 5 1.92 psig c.

Main Steam Line 1

Radiation - High 5 3 x rul l-power backg round**

53x rull-power backg round **

2.

Pressure - Low 2 825 psig 2 825 psig 3.

Flow - High 5 138% rated flow 5 138% rated flow d.

Main Steam Line Tunnel Temperature - High 5 194*F

$ 194*F e.

Condenser Vacuum - Low 2 7" Hg vacuum 2 7" Hg vacuum f.

Turbine Building Area Temp.-High 5 200*F 5 200*F W

g.

Drywel l Radiation - High 5 138 R/hr 5 138 R/hr 4

2.

SECONDARY CONTAINMENT ISOLA 110M w1 a.

Reactor Building Exhaust m

Radiation - High 5 60 mr/hr 5 60 mr/hr b.

DryweII Pressure - High 5 1.92 psig 5 1.92 psig c.

Reactor Vessel Water Level - Low Low (Level 2) 2 -47 inches

2 -47 inches

d.

Rerueling Floor Exhaust Radiation - High 5 20 mr/hr 5 20 mr/hr

See Bases Figure B 3/4 3-1 g

- reater than 20% rated power,Within ?4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months prior to the planned start of the hydrogen injection test with the reactor power at i

g the normal full.,) owe r rad i a t i on bac kg round level and associated trip setpoints a may be changed based on a calculated value of the radiation level expected during the test.

The background radiation level and associated trip setpoints may be adjusted duris.g the test based on either calculations c.

or measurements or actual rad ia t ion levels resulting from hydrogen injection. The background radiation n

level shall be determined and associated trip setpoints shall be set within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or re-establishing

" no rme ! radiation levels arter completion or hydrogen injection and prior to establishing reactor power l eve l s be low 20" ra ted powe r.

z CD 00

TABLE 3.3.6.1-1 (SHEET 1 OF 2)

MCRECS ACTUATION _INSTRUMCNTATION I

3=

EN MINIMUM NUMBER APPLICA8lE at OPERADLE CIIANNELS OPERATIONAL TRIP FUNCTION PER TRIP SYSTEM (al[b)

_CONDITIO3_

ACTION jj 1

Reactor Vessel Water Level -

2 1, 2, 3

52 Low Low Low (Level 1) (c)

.4

-4 2B21-N691 A, B, C, D to 2.

Drywe l l Pressure - High (c) 2 1,

2, 3

52 2E11-N694 A, B,

C, D 3.

Main Steam Line Radiation - High (c) 2 1,

2, 3,'**

53 l

2Dil-k603 A, B, C, D 4.

Main Steam Line Flow - High (c) 2/line I,

2, 3

53 2821-M686 A, B, C, D 2821-N68T A, B, C, D

2821-N688 A, B, C, D 2B21-N689 A, B, C, D kY 5.

Refueling Floor Area Radiation - High (c) 1 1, 2, 3, 5, a 54 45 2021-K002 A, D c.a 6.

Control Room Air inlet Radiation - High (C) 1 1,

2, 3, 5, *

$4 g

["

1241-R615 A, B

3 cw 7.

Control Room Air Inlet Chlorine Level - High (d) 1 1, 2, 3,4,5 55 1Z41-N022 A, B

1 M

U o.

D 8n 2'

O 00 1

i

TABLE 3.3.6.7-1 (SHEET 2 0F 2)

MCRECS ACTUATION INSTRUMENTATRON ACTION ACTION 52 Take the ACTION required by Specification 3.3.3.

ACTION 53 Take the ACTION required by Specification 3.3.2.

ACTION 54 With one of the required radiation monitors inoperable, restore the a.

monitor to OPERABLE status within 7 days or, within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , initiate and maintain operation of the MCRECS in the pressurization mode of operation, b.

With no radiation monitors OPERABLE, within I hour initiate and maintain operation of the MCRECS in the pressurization mode of operation.

The provisions of Specification 3.0.4 are not applicable.

c.

ACTION 55 -

With one of the required chlorine detectors inoperable, restore the a.

inoperable detector to OPERABLE status within 7 days or, within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , initiate and maintain operation of the MCRECS in the isolation mode of operation, b.

With no chlorine detectors OPERABLE, within I hour initiate and maintain operation of the MCRECSs in the isolation mode of operation, The provisions of Specification 3.0.4 are not applicable.

c.

NOTES When handling irradiated fuel in secondary containment, A channel may be placed in an inoperable status for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for a.

required surveillance without placing the trip system in the tripped condition, provided at least one other OPERABLE channel in the same trip system is monitoring that parameter, b.

With a design providing only one channel per trip system, an inoperable channel need not be placed in the tripped condition where this would cause the Trip Function to occur. In these cases, the inoperable channel shall be restored to OPERABLE status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or the ACTION required by Table 3.3.6.7-1 for that Trip Function shall be taken.

Actuates the MCRECS in the control room pressurization mode.

c.

d.

Actuates the MCRECS in the control room isolation mode, Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months prior to the planned start of the hydrogen injection test e.

with the reactor power at greater than 20% rated power, the normal full power radiation background level and associated trip setpoints may be changed based on a calculated value of the radiation level expected during the test.

The background radiation level and associated trip setpoints may be adjusted during the test based on either calculations or measurements of actual radiation levels resulting from hydrogen injection. The background radiation level shall be determined and associated trip setpoints shall be set within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of re-establishing normal radiation levels after completion of hydrogen injection and prior to establishing reactor power levels below 20% rated power.

HATCH - UNIT 2 3/4 3-58b Amendment No. 88 5

,~ - +-

TABLE 3.3.6.7-2 MCRECS ACTUATION INSTRUMENTATION SETPOINTS 1

3>

--t

' TRIP FUNCTION r3 1

TRIP SETPOINT ALLOWABLE VA(UL e

1.

Reactor Vessel Water Level -

2 -113 inches 2 - 113 inches Low Low Low (Level 1) 55 2.

D rywe l l Pressure - High 5 1.92 psig s 1.92 psig p

--4 na 3.

Main Steam Line Radiation - High 5 3 x rull-power background *

$ 3 x rull-power background" l

4.

Main Steam Line Flow - High 5 138% rated riov s 138% rated flow 5.

Rerueling Floor Area Radiation - High 5 20 mr/ hour s 20 mr/ hour 6.

Cont rol Room Ai r Inlet s 1 mr/ hour 5 1 mr/ hour Radiation - High 7.

Control Room Air Inlet 5 5 ppm chlorine s 5 ppe chlorine Chlorine Level - High N

4 w

a un

($

li m

k 83

Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months prior to the planned start of the hydrogen injection test with the reactor power a t greater 20% ra ted Z

power. the normal full power radiation background level and associated trip setpoints may be changed based on a

?

calculated value of the radiation level expected during the test.

The background radiation level and associated trip setpoints may be adjusted dur$ng the test based on either calculations or measurements or actual 0l radiation levels resul ting f rom hydrogen injection. The background radiation level shall be determined and associated trip setpoints shall be set within 24 bcurs or re-establishing normal rad ia t ion levels af ter completion of hydrogen injection and prior to establishing reactor power levels below 20% rated power.

J

ML20148E429

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