Text

Proposed Tech Specs Re Reactor Trip Sys Instrumentation, Removing Ref to Unit 2
	ML20098E079
Person / Time
Site:	Comanche Peak
Issue date:	05/26/1992
From:	; TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC)
To:	;
Shared Package
ML20098D949	List: ML20098E079; TXX-9225, Forwards Revised TS Pages in Support of Removal of Statements Referring to Unit 2 from 920228 Application for Amend to License NPF-87 Re Boron Dilution Mitigation Sys;
References
	NUDOCS 9206010241
	Download: ML20098E079 (7)
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RIACIOR IRIP SY5ilH IN51ROMINIAl10N

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HINIHOH i.'

10IAl NO.

CilANN[l 5 CilANNLi5 APPI ICAll! I N

j IbNCIlONAL llNil Of CilANNil5 10 l RIP OPl RAlll i HODI S,_.

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Hauual Reactor 1 rip 2

1 2

1, 2 1

c-x-

n a

d d

g 2

1 2

3, 4, 5" 9

OtPJ e -.

2.

Power Range, Neutron flux

'yorg a.

Iligh Setpoint 4

2 3

1, 7 2

04.

O' b.

Iow 5elpoint 4

2 3

1 2

2 0

3.

Power Range, Neutron flux 2

3 1, 2 e

fligh Positive Rate Y

4.

Power Range, Neutron flux, 4

2 3

1, 2 2

Y liinh Negative Rate ro 5.

Intermediate Range, Neutron Ilux 2

1 2

l', 2 3

6 Source Range, Neutron Ilux a.

Reactor Trip and Indication b

1)

Startup 2

1 2

2 2)

Shutdom 2

1 2

3, 4 5,1 i

b.

11oron Dilution I lux Doublin 2

1 2

3',4, 5

5.lg.2.

/.

Overtemperature H-16 4

2 3

1, 21 12 8.

Overpower N-16 4

2 3

t,2 12 9.

Pressurizer Pressure--low 4

2 1

L 4"

10.

Pressuriter Pressure-88igh 4

2 3

1, 2 6

m ~.

Boron Dilution Flux Doubling requirements become effective for Unit 1 six months after criticality for Cycle 3.

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Attachment to TXX;92256' Page 2 of 7 7BLE 3. 3-1 (Continuec)

TA3LE NOTATIONS 30nly if the reactor trio creakers haccen to te in tne close: : sit 4:n an: :e Control Rod Drive System is capaele of roo witncrawal.

Below tne :-5 (:nte c eciate Range Neutro : lux :ntericck) Set:oint.

CBelow the P-10 (Low 5etcoint Power Range Neutron Flux Interlock) $et:cint.

dAbove the P-7 (At Power) Setpoint

'The applicable MODES and ACTION statefrents for these channels noted in Table 3.3-2 are more restrictive and therefort. applicable.

Above the P-8 (3-loop flow permissive) Setpoint.

9Above the P-7 and below the P-B Setpoints.

The boron dilution flux doucling signals may be blocked during react 0c startu' h

Above the P-9 (Reactor trip on Turbine trip Interlock) Setpoint.

ACTION STATEMENTS ACTION 1 - Witn ne numcer of OPERABLE channels cre less than tne ui-u-

Channels CPERABLE recuirement, restore me inoperable cnaare!

to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or

- in HOT STANOBY witnin the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

ACTION 2 - Witn the number of OPERABLE channels or-less than tne Total Numbec of Channels. STARTUP and/or POWER OPERATION may pr ceec prov.ced tne following conditions are satisfied:

The inoperable channel is placed in the tripped concition e

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

The Minimum Channels OPERABLE reoutrement is met: no-ever, the inoperable channel may be bypassed for up to a nours for surveillance. testing of other channals per opecification he 4.3.1.1, and

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Either, THERMAL POWER is restricted to less than or eaual Q'yc.

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to 75% of RATED THERMAL POWER and the Power Range Neutron Flux Trip 5etpoint is reduced to less than or equal to 85% of RATED THERMAL POWER within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; or, the QUADRANT POWER TILT RATIO is monitored at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months per S'.ci fication 4. 2. 4. 2.

n m

Boron Oilution Flux Ocubling requirements becomc effective for Unit 1 six months after criticality for Cycle 3.

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COMAhCHE PEAK

UNIT 1 3/4 3-5

Attachment'to TXX-97256 P

3 of.7

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AC' ION 5'A?i"EN'S (Contiaued)

AC':"N 3 - Wit?

ne nu?cer of cnarnels CPERASLE One less t*an the Miri tum Channels CPERABLE recuirement and ith tse THERMAL cower ievel:

Belo-ine ^-6 (Intermeciate Range Neutron *' lux [nterlock) 3.

Setpoint, restore tie inoceraole channel to OPERABLE status orier to ;ncreasing THERMAL D0wER acove t~e P-5 3et oint, Above the D-E (Intermediate Range Neutron Flux Interlock) c.

Setooint but below 10?. of_ RATED THERMAL POWER, restore tne inocersele channel to OPERABLE status prior to increasing THERMAL POWER above 10% of RATED THE" MAL POWER.

ACTION 4 - With the numbe: of OPERABLE channels one less than the Minimum Channels CPERABLE recuirement, suspend all operations insolving m -~ % positive reactivity cnanges.

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ACT!CN 5,1 With the numoer of CPERABLE channels one less than the Minim.m Channels CPERABLE recuirement, restore the inoperable channel to CPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or within the text nour coen gj N cmd'~ tne reactor trip creakers

/

susoend all coerations involving

_/

positive reactivity cn ces.bnd verify either valve 1C5-3455 or s alves 1C5-6560, FCV-1118,1CS-8439,1CS-8441, and 1CS-8453 M,'

are closed and secureo in position, and verify this cositien at.

lav t enea nar la dav< t"araa'tarl Wi;b no enannels OcERABLE

( Lvwet Pt_

complete M me abo've actions within 4 nours.)snd verify tre I

positions of t.ne aoove valves at least: nce cer la cays tne ea'te3 p

"'%U M f D ER M n lerar" Numcer of Channels, STARTUP and/or POWE; OPERATION may proceec proviced the following conditions are satisfied:

The inoperable enannel is placed in the tripced conoition a.

within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and The Minimum Channels OTERABLE requirement is met, b.

l

muever, tne inoperable channel may be bypassed for up to a nours for surveillance testing of other channels per Specification 4.3.1.1.

ACTION 7 - With less than the Minimum Number of Channels OPERASLE. within i

1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months determive by ceservation of the associated permissive

" annunciator window (s) tnat the interlock is in its reovired state

. for the existing plant condition, or apply Specification 3.0.3.

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Boron Dilution Flux Ooubling requirements become effective for Unit 1 six fronths c#ter criticality for Cycle 3.

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_J COMANCHE PEAK - UNIT 1 3/4 3-6 i

I

T LAttachment' to TXX-92256

!Page'4 of?7 INSERT A ACTION 5.2* - With.the number:of OPERABLE channels one less than the-Minimum Channels Ol'ERABLE' requirement, restore the inopercble channel. to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or within the next hour verify either valve ICS 8455 or valves 1C5-8560, FCV-111B, 1C5-8439, 105-8441, and 105-8453 are closed and-secured in position, and verify this-position at least once per.14 days thereafter.

With no channels OPERABLE, compiete the above actions within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months and verify-the positions of-the above valves at least once per 14' days-thereafter.

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Attachment to TXX-92256 Page 5 Of 7 S

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Rt ACIOR.1.R__IP_ _SYSl_l M INSil.dlHI Hl Al10N SURvt 1_1_1 ANCE RI QtilRf MINIS 17 m

s.

IRIP f.

ANALOG AC IllAI I?!G MODES IUR CilANN[ t DEVICE WillCil c

CilANNil CllANNI I OPE RAl l0N','

OPERAI10NAL ACIUATION SURVI111ANCI 5

_f_ilNC s l0NAL UNI _T

_Cil( CK C AI f il9.._Al lON TEST I--_E_ S I LOGIC llSt IS R[QUIRID

~

1.

Manu?1 Reactor Trip N.A.

N A.

M. A.

R(14)

N A.

1, 2, 3, 4, S d

d

?.

Power Rasuge, Neutron I lux Iligh Setpoint S

D(2, 4),

9 N A.

NA 1

l' a.

M( 3, 4 ),

Q(4, 6),

R(4, S) h.

low Setpoint S

R(4)

S/U(l)

N. A.

P. A.

I',

7 m

s.

3.

Power Range, Neutron Ilux, N S.

R(4)

Q N. A.

N A.

1, 2

.o

. 'o liigh Positive Rate 4.

Power Range, Neutron flux, N.A.

R(4)

Q N.A.

N.A.

1, 2 liigh Negative Rate 5.

Intermediate Range, 5

R(4, 5)

S/U(1)

N.A.

I 2

C Neutron flux 6.

Sourte Range, Neutron Ilux 5 R(4, 13)

S/U(1), Q(9)

R(12 N.A.

2",

3, 4, S 7.

Overtemperature N-16 S

O(2, 4 )

Q N. A.

-M(3, 4)

H A.

1, 2 Q(4, 6)

R(4, S) 8.

Overpower N-16 S

D(2, 4)

Q N. A.

N A.

!, ?

R(4, 5) 9.

Pressurizer l'ressure--l ow S R

Q(8)

N A.

N. A.

I "I.

Pre:surizer Pressure--liigh S R

Q N A.

N.A.

.u anx

c. -v c

. ', -v

. ~,

w w"',

r w

f

Boron Dilution Flux Dcubling requirements become effective for Unit 1

's L six months,after criticality for Cycle 3.

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Attachment to TXX-92256 Page 6 of 7

' ABLE 4. 3 1 (Continuec)

TABLE NOTAT!!N5 a Oc;j 4'

tae rea: tor tri: Crea<ers naccen to De in the closec ;ositi:n aro e

Control ::d Drive 3) stem is caca0!e of roc witncrawal.

St ion ;-4 l te-S: r.e Rarge Neutr:n Flux nterlock) 5et:cint.

Below P-10 (LO. 5et:oint D0wer Range Neutron Flux Interlock) Sct;oin.

Above the P-7 ( At Co.er) Set 0cint.

Above the P-9 (Reactor trip on Turbine trip iderlot k) Setpoint.

(1)

If not performed in or.,vious 31 days.

(2) Com arison Of calorimetric to excore power and N-16 power indication acove 15% of RATED THERMAL PCWER.

Adjust excore channel and/or N-16 channel gains consistent 'ith calorimetric power if absolute difference of the rescectise channel is gr'ater tnan 2%.

The provisions of Specification 4.0.4 are not acclicaole 'ci entry into MODE 1 or 2.

(.

Single coint cetparison of inc0re to excore AXIAL FLUX OIFFERENCE acowe 15% of RATED THERMAL GOWER.

9ecalibrate if the absolute dif'erence is greater than or equal to 3%.

For the purpose of inese surveillance ecui-etents, "M"

is defined as at ' east once per 31 E:0

're :*ovisions f 3:ecification 4.0.4 are not ap' icable for entr3

-t:

MODE 1 or 2.

(4) Neutron and N-li cetectors may oe excluced from :-ANNEL CALIBRATICN.

(5)

Detecter clateau curves shall be cotained and evaluated.

For the

ntertediate 4arge Neutron Flux, Power Range Neutron Flux and N-16 :narrels the :covisicrs F 3:ecification 4.0.4 are not applicable for entry int MOCE 1 or 2.

(6)

Inc:ee - Er :o e Calioration, acove 75% of RATED Tr4ERMAL POWER.

ce e

pur :se of t ese surveillance requirements "Q" is cefined as at least once cer 92 E SC.

The provisions of Specification 4.0.4 are not a:clic-acle for entry into MODE 1 ar 2.

(7)

Eacn trate shall be tested at least every 62 days on a STAGGERED TEST BASIS.

(3)

The MODES speci'iec for tnese channels in Table 4.3-2 are more restrictive ano therefore applicable.

2 a

8 (9) Quarteriy surveillance in MOCES 3, 4, and 5 shall also incluce verifica-tion that permissises P-6 and P-10 are in their required state for exist-ing plant conditions by observation of the permissive annunciator winoow.

Quarterly surveii!ance snall include verification of the Boron Oilution Alarm Setooint of less than or e ual to an increase of twice the C0unt

,s write ithin._a 10-sim te_cet ggy m memmmm i

m f

Baron Oilution Flux Doubling requirements become effective for Unit 1 <,

s six months after criticality for Cycle 3.

A CCMANCHE7 fA D T SIi ~1

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$tachmenttnTXX-92256 A

^^

Page 7 of 7 TsBtg a 3 ' J:or 2uecl TABLE NOTATICNS (Continuec)

(.' 3 ) Setooint verification is not acolicable.

(11) The TRIP ACTUATING DEVICE ODERATICNAL TEST snaliincepencenti f verify : e OPERABILITY of the uncervoltage ano snunt trir attacnments of ine reactor trio creakers.

('2) at least once per 18 montns curing snutdown, seri'j tha*. on a siTulate:

Boron Dilttion Flux Coubling test signal tre_ normal CVCS discharge valves clos

'nc the centrifugal enarging pumos suction valves from tne RW5T open.

(13) With the hign voltage setting varied as recommended by the manufacturer, an initial discriminator bias cueve shall be measurec for eacn cetector.

Sucsecuent ciscriminator bias curves snall De octainec, evaluated anc compared to tne initial curves.

(1A) The TRIP ACTIING DEVICE 00ERATIONAL TEST snall independently verify ne OPERABILITY - the undervoltsge and shunt trio circui s for the Manual t

Reactor Trip '~ unction.

The test snall also verify the OPERABILITf of t~e Bypass Breaker trip circuit (s).

(15) Ltcal manual snurt tri. prior to placing creaker in service.

(16) Attomatic undervoltage trip. o b~

W rre

('*BoronDilutionFluxDoublingrequirementsbccomeeffectiveforUnit1 six months after criticality for Cycle 3.

y A AACv COMANCHE PEAK - UNIT 1 3/A 3-12 V

ML20098E079

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