ML20207J614

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Proposed Tech Specs Revising Setpoints for Analog Transmitter Trip Sys Instruments
ML20207J614
Person / Time
Site: Hatch Southern Nuclear icon.png
Issue date: 07/18/1986
From:
GEORGIA POWER CO.
To:
Shared Package
ML20207J601 List:
References
TAC-62029, NUDOCS 8607290188
Download: ML20207J614 (13)
v • d • e


Text

._

GeorgiaPower d ENCLOSURE 3 NRC DOCKET 50-366 OPERATING LICENSE NPF-5 EDWIN I. HATCH NUCLEAR PLANT UNIT 2 REQUEST TO REVISE SETPOINTS FOR CERTAIN ANALOG TRANSMITTER TRIP SYSTEM INSTRUMENTS PROPOSED CHANGE TO TECHNICAL SPECIFICATIONS The proposed changes to the Technical Specifications ( Appendix A to Operating License NPF-5) would be incorporated as follows:

Remove Page Insert Page 2-4 2-4 3/4 3-2 3/4 3-2 3/4 3-16 3/4 3-16 3/4 3-17 3/4 3-17 3/4 3-18 3/4 3-18 3/4 3-26 3/4 3-26 3/4 3-28 3/4 3-28 I

3/4 3-29 3/4 3-29 3/4 3 -31 3 /4 3 -31 3/4 3-35 3/4 3-35 i

B 3/4 3-6 B 3/4 3-6 0622C 07/18/86 e

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TABLE 3.3.1-1

_ REACTOR PROTECTION SYSTEM INSTRUMENTATION o

DC APPLICABLE MINIMUM NUMBER e

FUNCT10NAL UNIT OPERATIONAL OPERABLE CHANNELS COND11 IONS PER TRIP SYSTEM (a)

ACTION 3

1 Intermediate Range Monitors:

H (2C51-K601, A, 9, C, D, E,

F, C, H) a.

Neutron Flux - liigh 2,

5'*'

3 1

b.

Inope ra t ive 3, 4 2

2 2.5'"'

3 1

3, 4 2

2 2.

Average Power Range Monitor:

(2C51-x605 A, B,

C, D,

E, F) a.

Neutron Ilux - Upscale, 15%

2, 5 2

1 b.

Flow Referenced Simulated Thermal Power - Upscale 1

c.

Fixed Neutron Flux -

2 3

Upscale, 118%

1 d.

I nope ra t ive 2

3 e.

Downscale 1, 2, 5 2

4 1

F.

LPRM 2

3 1, 2, 5 (d)

NA 3.

Reactor Vessel Steam Dome Pressure -

kg High (2821-N678 A, B,

C, D) 1, 2

(J, 2B21-N045 5

b A,

B, C, D)

Y 4.

Rerctor Vessel Water Level -

P3 Low (Level 3) (2B21-N680 A, B, C, D) 1, 2 (J, 2B21-N024A, B 5

2B21-N025A, B) 5.

Main Steam Line isolation Valvo -

Closure (NA)

I

4 3

6.

Main Steam Line Radiation - High 1,

2

2 6

(2011-K603 A, B, C, D) 7.

Drywell Pressure - High 1, 2 ' "

2 5

(2C71-N650 A, B, C, D)

Proposed TS/0041q/188 J

TABtE 3.3.2-2 m

?j ISOLATION ACTUATION INSTRUMENTATION SETP0lNTS 9

ALLOWABLE TRIP FUNCTION TRIP SETP0lNT VALUE c

1.

PRIMARY CONTAINMENT ISOLATION

-4 n3 a.

Reactor Vessel Water Level 1.

Low (Level 3)

E 10 inches

  • 2 10 inches
  • 2.

Low Low (Level 2) 2 -47 inches

  • 2 -47 inches
  • 3.

Low Low Low (Level 1) 2 -113 inches

  • 2 -113 inches
  • b.

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

Main Steam Line 1.

Radiation - High 5 3 x rull power background 53 x rul l powe r backg round 2.

Pressure - Lov 2 825 psig 2 825 psig 3.

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

Main Steam Line Tunnel 4

to Temperature - High 5 194*F 5 194*r s s e.

Condenser Vacuum - Low 2 7" lig vacuum 2 7" Hg vacuum w

J.

f.

Turbine Building Area Temp. -lii gh 5 200*F S 200*F cn 2.

SECONDARY CONTAINMENT IS0tATION a.

Reactor Building Exhaust Radiation - High 5 60 mr/hr s 60 mr/hr b.

Drywnli Pres'sure - liigh 5 1.92 psig 5 1.92 psig c.

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

  • 2 -47 inches
  • d.

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

  • See Bases Figure B 3/4 3-1.

Proposed TS/00414/188 4

4

TABLE 3.3.2-2 (Continued)

=c

_ ISOLATION ACTUATION INSTRUMENTATION SETPOINTS N

i bd ALLDWABLE TRIP FUNCTION TRIP SETP0lNT VALUE 4

gj 3.

REACTOR WATER CLEANUP SYSTEM ISOLATION Il a.

A Flow - High 5 79 gpm 5 79 gpm 4

b.

Area Temperature-High 5 124*F S 124*F

.c.

Area Ventilation A Temperature - liigh 5 67'F 1 67'r d.

SLCS Initiation NA NA e.

Reactor Vessel Water Level-Low Low 2 -47 inches

  • 2 -47 inches *

(Level 2) l 4.

HICH PRESSURE COOLANT INJECTION SYSTEM ISOLATION a.

IIPCI Steam Line Flow-High 5 30;g or rated flow 5 303% or rated flow l

b.

HPCI Steam Supply Pressure - Lov 2 *00 psig 2 100 psig c.

HPCI Turbine Exhaust Diaphragm Pressure-liigh 5 20 psig 5 20 psig d.

IIPCI Pipe Penetration Room i

(a Temperature - liigh 5 169'F 5 169'F i

%s e.

Suppression Pool Area Amblent Tempe ra tu re-fligh 5 169'F

$ 169'F us c.

Suppression Pool Area. AT - liigh

< 42*F j,

g.

Suppression Pool Area Temperature

< 42*F l

%a Timer Relays NA NA h.

Emergency Area cooler Temperature -

filgh 5 169'F s 169'F I.

Drywell Pressure - liigh S 1.92 psig 5 1.92 psig l

J.

Logic Power Bus Monitors NA NA

  • See Bases Figure B 3/4 3-1.

Proposed TS/0041g/188

TABLE 3.3.2-2 (Continued)

=c ISOLATION ACTUATION INSTRUMENTATION SETPOINTS N

b$

ALLOWABLE j

TRIP FUNCTION TRIP SETPOINT VALUE f

c:

5.

REACTOR CORF ISOLATION 35 co0 LING SYSIEM ISOLATION

--4 s.

RCIC Steam Line Flow - lilgh 5 307% or rated riov s 307% or rated flow l

p, b.

RCIC Steam Supply Pressure - Lov 2 60 psig 2 60 psig c.

RCIC Turbine Exhaust Diaphragm Pressure - liigh 5 20 psig 5 20 psig d.

Emergency Area Cooler Temperature-fligh 5 169'F 5 169'i e.

Suppression Pool Area Ambient Temperature 5 169'r s 169'F liigh f.

Suppression Pool Area AT - High 5 42*F 5 42*F l

g.

Suppression Pool Area Temperature Timer Relays NA NA h.

Drywell Pressure - High 5 1.92 psig 5 1.92 psig l

b 1.

Logic Power Monitor NA NA de 6.

SHUTDOWN COOLING SYSTEM ISOLATION co a.

Reactor Vessel Water Level - Lov 2 10 inches" 2 10 inches

  • l (Level 3) b.

Reactor Steam Dome Pressure - liigh 5 145 psig s 145 psig

  • see Bases Figure B 3/4 3-1.

4 Proposed TS/00414/188

TABLE 3.3.3-1 55 EMERCENCY CORE C00LINC SYSTEM ACTUATION INSTRUMENTATION N

UC MINIMUM NUMBER APPLICABLE s

OPERABLE CHAhNELS OPERATIONAL TRIP FUNCTION c=

PER TRIP SYSTEM CONDi(IONS 2[]

1.

CORE SPRAY SYSTEM h) a.

Reactor Vessel Water Level - Low Low Low (Level 1) 2 1,2,3,4,5 (2B21-N691A,B,C,D) b.

Drywell Pressure - liigh (2E11-N69ft A,B,C,D) 2 1,2,3 c.

Reactor Steam Dome Pressure - Low (Injection Permissive)

(2B21-N690A,B.C,D) 2 1,2,3,4,5 d.

Log le Powe r Moni tor (2E21-K1 A,B) 1/ bus'*8 1,2,3,4,5 2.

LOW PRESSURE COOLANT INJECTION MODF OF RHR SYSTEM a.

Dryvell Pressure - liigh (2E11-H694A,B,C,D) 2 1,2,3 b.

Reactor Vessel Water Level - Low Low Low (Level 1) 2 1,2,3,4*,5*

(2021-N691A,B,C,0) c.

Reactor Vessel Shroud Level (Level 0) ( D rywe l l Sp ray l

Permissive) (2021-N685A, B) 1 1,2,3,4*,5*

d.

Reactor Steam Dome Pressure - Low (1,nJection Permissive)

(2B21-N690A,B,C,D) 2 La e.

Reactor !,seem Dome Pressure - Low (Recirc. Discharge Valve 1,2,3,4*,5*

]s Permissive) (2B21-N6418,C and 2B21-N690E.F) 2 1,2,3,4*,5*

r.

RHR Pump Start - Time Delay Relay 1/ pump 1,2,3,4*,5*

Cd 1)

Pump A (2E11-K70A, 2E11-K1250)

/3 2)

Pump B (2E11-K700, 2E11-K125A) cn 3)

Pump C (2E11-K758) 4)

Pump D (2E11-K75A, 2E11-K126) g.

Logic Power Monitor (2E11-K1 A,B) 1/ bus (*8 1,2,3,4*,5*

Not applicable when two core spray system subsystems are OPERABLE per Spect rication 3.5.3.1.

(a) Alarm only. When inoperable, verify power availability to the bus at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> or declare the system inoperable.

Proposed TS/0041g/188

TABLF 3.3.3-2 at EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION SETPolNTS

-4 EE ALLOWABLE TRIP FUNCTION TRIP SETPolNT val.UE c:

1.

_ CORE SPRAY SYSTEM

2:

I El a.

Reactor Vessel Water Level - Low Low Low (Level 1) 2 -113 inches

  • 2 -113 Inches
  • b.

Drywell Pressure - Illgh 5 1.92 psig 5 1.92 psig p,

c.

Reactor Steam Dome Pressure - Low 2 390 psig**

2 390 psig**

d.

Logic Power Monitor NA NA 2.

LOW PRESSURE COOLANT INJECTION MODE OF RifR SYSTEM a.

Drywell Pressure - 111gh 5 1.92 psig 5 1.92 psig b.

Reactor Vessel Water Level - Low Low Low (Level 1) 2 -113 inches" 2 -113 inches

  • c.

Reactor Vessel Shroud Level (Levet 0) - liigh 2 -202 inches

  • 2 -202 inches
  • s d.

Reactor Steam Dome Pressure-Low 2 390 psig**

2 390 psig**

e.

Reactor Steam Dome Pressure-Low 2 335 psig 2 335 psig f.

RitR Pump Start - Time Delay Relay i

1)

Pumps A, B and D 10 t I seconds 10 1 1 seconds 2)

Pump C 0.5 1 0.5 seconds 0.5 1 0.5 seconds g.

Logic Power Monitor NA NA l

tab m

  • See Cases Figure B 3/4 3-1.
    • This trip function shall be less than or equal to 500 psig.

Proposed TS/0041q/188

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i TABLE 4.3.3-1 x

fj EMERCENCY CORE C00LINC SYSTEM ACTUATION INSTRUMENTATION SURVEILIANCE REQUIREMFNTS n2c CllANNEL OPERATIONAL CllANNEL TUNCTIONAL CilANNEL CONDITIONS IN WillCH TRIP FUNCTION CllECK TEST CAllBRATION SURVEILLANCE REQUIRED 3

1.

CORE SPRAY SYSTEM

--4 po a.

Reactor Vessel Water Level -

4 Low Low Low (Level 1)

S M

R 1, 2, 3,4,5 b.

Drywell Pressure - High S

M R

1, 2, 3

c.

Reactor Steam Dome Pressure - Low S

M R

1, 2, 3,4,5

.d.

Logic Power Monitor NA R

NA 1, 2, 3,4,5 2.

LOW PRESSURE COOLANT INJECTION MODE OF RHR SYSTEM a.

D rywe l l Pressure - Illgh S

M R

1, 2, 3

b.

Reactor Vessel Water Lever-Low Low Low (Level 1)

S M

R 1, 2, 3, 4 ', 5

  • c.

Reactor Vessel Shroud Level (Level 0)

S M

R 1, 2, 3, 4 ", 5*

l d.

Reactor Steam Dome Pressure - Low S

M R

1, 2, 3, 4*, 5' e.

Reactor steam Dome Pressure - Low 6 M

R 1, 2, 3,

4*, 5" r.

RilR Pump Start-Time Delay Relay NA NA R

1, 2, 3, 4 *, 5' 4d g.

Logic Power Monitor NA R

NA 1, 2, 3, 4 *, 5'

.co

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T NOTE. SCALEsNsNCHES ABOvtVEs3EL2EEO e

WATER LEVEL NOMENCLATURE MEICHT A80VE 800.*

  • VEs5EL 2ERO NO.

IINCMEst R E A O tNC INSTRUMENT 181 573.5

  • M.5 750 BARTON (7) 559
  • 42 CE/MAC VESSE L (48 59

+32 N E pLANcE

~

(33 527 CE/MAC o

+10 BARTON/ROSEMOUNT 700 -

(23 470

-47 BARTON/ROSEMOUNT

=

tti 404

-113 BARTON/ROSEMOUNT 103 315

- 202 BARTON/ROSEMOUNT 850 - -

- 444 MAIN STEAM ggyg f

soo - -

. 577 4

g3g,>

0--

=

~-

(.>

irl.., N a uRM

.0 -.

.,4, g.e, hP5 14 '32 LO ALARu SOTTOM OF STE AM - 527 (3)

.7

-ORYER SKsRT s17 INSTRUMENT (3) to (31, 10 LOW (LEVEL 31 -

  1. 8EEC TRisNTO Acs

- 4433

"' I"

[ ag$ _ CD R E

-47 LOW LOW (LEVEL 2)*

- 470 (2) $ PRAY f

INITIATE NPe!,

45o -

RC:C 404 (1) 400

- -113 LOW LOW LOW (LEVEL 1) f d 387

- 150 -. - INITIATE RNR. C.E 252.54 START CIE3EL ANO 350 --6 l

CONTRisUTE TO A.C.E.

2/3 COR E CLOSE MSIVs

-202 MEIGHT 515(0)

Permissive 300 (LEVEL 0)

ACTIVE FUEL 250 - =

200 -:2 U R ECIRC

' RECIRCULATION PUMP TRIP M,g e,,e

- 173.5s OssCN arc E ANALYTICAL LIMITIS -58 INCHES s ucT iO N - 151.5 NOZZL E NOZZLE 150 =

=

100 - -

50 - -

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9380 2 BASES FIGURE 9 3/4 31 REACTOR VESSEL wiTER LEVELS l

HATCH - UtilT 2

~B 3/4 3-6 Proposed TS/00000/183 l

T NOT E.

SCALEiN NCHES ABOVE VESSEL 2ERO e

WATE R LEVEL NCMENCL ATURE MEICHT ABOVE VEs5EL 2Emo

~~

NO.

IINCHE51 REACING INSTRUMENT tal 573.5 4.5 BARTON 750 --'.

(7) 559

  • 42 CE/MAC VEs5EL (4)

Set

+32 NS pggwag~

C E/MAC (33 527

+10

>i BARTON/ROSEMOUNT (23 470

-47 BARTON/ROSEMOUNT 700 - -

g1) 404

-113 BARTON/ROSEMOUNT tot 315

-202 BARTON/ROSEMOUNT SSO - -

" **O ~ MAIN STEAM LINE f

soo

,. 577 e

5'=f,',=>

-a - -

183 871 ' 42 Mt ALAmu 150 =e 34 g g43 gl 3, WI SOTTOM OF STE AM 527 (3)

.yReps

'32 LD ALARM

-ORYER SEsRT 517.NST R UME NT (31 - 10 (3) 10 LOW (LEVEL 3) 8EE C NTRIB E TO ADS

_ ag33 ER

',', g _ CORE

- -47 LOW LOW (LEVEL 2)*

- 470 (2) SPRAY F

INITIATE MPCI, aso -

RC C 404 (1) sac - -

- -113 LOW LOW LOW (LEVEL Il f

- 3s7

-150 -. INITIATE RMR, C.1 gg,,w 352.54 START DIESEL AND CONTRIBLITE TO A.D.S.

2/3 CC R E CLOSE MSIV:

-202 MEIGHT

- 515 (0)

PERMasslVE 300 " "'

(LEVEL 0)

ACTIVE FUEL 250 -

200

=2 6 REclRC

' RECIRCULATION PUMP TRIP RECIRC

-178.58 Cl5 CHARGE ANALYTICAL LIMITis -58 INCHES S UCTIO N - 161.5 NCZZL E g Nozzle 1so - -

1 ioo - -

se - -

l 0.

BASES FIGURE B 3/4 31 REACTOR VESSEL WATER LEVELS l

HATCH - UNIT 2 8 3/4 3-6 Proposed TS/00000/183 1

1 r

-..,.~..__--- _-._.,- _ -. _-~,. _,.-.....-_.

. - _. _ - _ - -,,...,. -, -,, ~ - - - - - - - -. _ - - _ - - - - - -. - -,,,,, - - -, '. _,, -. -

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