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Page 1: PG Letter No. DCL-93-212 · 2017-02-28 · PG c Letter No. DCL-93-212 ENCLOSURE License Amendment Request 92-05 Replacement Marked-Up Technical Specification Pages Page 3/4 3-8 Page

PG c Letter No. DCL-93-212

ENCLOSURE

License Amendment Request 92-05Replacement Marked-Up Technical Specification Pages

Page 3/4 3-8Page 3/4 3-15Page 3/4 3-19Page 3/4 3-22Page 3/4 3-35Page B 2-7

6213S/85K

9309030212 .930827PDR ADOCK -05000275PDR

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II

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TABLE 3.3'2

REACTOR TRIP SYSTEM INSTRUMENTATION RESPONSE TIMES

FUNCTIONAL UNIT RESPONSE TIME

I. Manual Reactor Trip N.A.

2. Power Range, Neutron Flux c 0.5 secon Cl)

3. Power Range, Neutron Flux,High Positive Rate

4. Power Range, Neutron Flux,High Negative Rate

3. Intermediate Range, Neutron Flux

6. Source Range, Neutron Flux

7. Overtemperature bT

8. Overpower hT

9. Pressurizer Pressure"Low

10. Pressurizer Pressure-High

11. Pressurizer Water Level"High

12. Reactor Coolant Flow-L'ow

a. Single Loo'p(Above P-8)

b. Two Loops(Above P-7 and below P-8)„-, '.~s~

13. team Generator r evel-L'ow.-Low

14. DELETED

15. Undervoltage-Reactor Coolant Pumps

l6. Underfrequency-Reactor Coolant Pumps

N.A.

-c 0.5 ."econ& Cl)

N.A.

< 0.5 secon Cl')

< P second@ c>)

~ 4 7~coAh5

< 2 seconds

< 2 seconds

N.A.

< 1 second

< 1 second

< 2 seconds

c 1.2 seconds

< 0.6 second

I

Q~') neutron detectors are exempt from response time testing. Response time ofthe neutron flux signa) portion of the channel shall be )t)easured from.detector output or input of first electronic component in channel.

~+ APTKc. &W~ Ql XH5~~otJDIABLO CANYON " UNITS 1 8 2 3/4 3-8 Amendment Nos. 5 8, 2 8,

Au us 6, 99

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insert 5

13. Steam Generator Water level-Low-Low gNg ~

a. Steam Generator Water Level-Low-Low

b. RCS Loop bT Equivalent Power

R'2.0 seconds

N.A.

Xnsert 0

Does not include Trip Time Delays. Response times include thetransmitters, Eagle-21 Process Protection cabinets, Solid StateProtection System cabinets and actuation devices only. Thisreflects the response times necessary for THERMAL POWER in excessof 50X RTP.

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TAStX 3.3-3

ENGINEERED SAFETY FEATURES ACTUATION SYSTEH INSTRUHENTATIONCl

C7

E

Efl

Qe

tP

EAR

a. EAO

Co ContaiteentPressure-High

FUNCTIONAL UNIT

1. Safety Injection (ReactorTrip, Feebrater Isolation,Start Diesel Generators,Containment Fan Cooler Units,and Component Cooling Mater)

a. Manual Initiation

hutosetic hctuationLogic and ActuationRelays

TOTAL NO.OF CHANNELS

2.

3

CHANNELSTO rRIP

HININJHCHANNELSOPERABLE

hPPLICABLKrrooEs AcTIB!(

1, 2, 3, 4 19

1, 2, 3, 4 14

1, 2, 3, 4 20

PressurizerPressure-Let

3 1, 2, Q 20

58LB7Ebg'~e. Differential

Pressure BetweenSteea Lines-High

3/steam line 2/steam line 2/steam line 1, 2, 3any steam line

20

~+

O

Steae Flat in TmSteae Uncs-High

Coincident Mith EitherT „O-LrorLorr I T „/loop 1T „any

2 loops

1 Tang any I, 2, 3'loops

2/steam line 1/steam line I/steam line 1, 2, 3Hany 2 steamlines

20

20

3js~ l~e5 ~ Lh P -L

4etp"'=.::+~ 'A.M 8"Sl~ E.( ir J ()Ago~

C/ske~ /~aE ways/ea ]~ Z,isa~ l~W

1,2,3 20

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TASt.K 3.3-9 Cont)nued

ENGINEERED SAFETY FEATURES ACTUATION SYSTN INSTRUHEHTATIOH

FUNCTIONAL UNITTOTAL NO. CHANNELS

OF CRAMRELS TO TRIP

NINIHUNCHANNELSOPERABLE

APPLICASLKTIOOES ACTI0 II

b.

0 c.

S~selR

Automatic ActuationLogic and ActuationRelays

Ste. Gen. Mater Level-Ler-Low

1) Start NotorDriven Pumps

2) Start Turbine-Driven Pump

S. Auxilfary Feehrater

a. Nanual Initiation

3/stm. gen.

3/stm. gen.

2/stm. gen.in any opera-ting stm. gen.

2/stm. gen.in any2 operatingstm. gen.

2/stm. gen.in eachoperatingstm. gen.

2/stm. genin eachoperatingstm. gen.

1 manual 1 manual 1 manualsmitch/pump smitch/pump s~itch/pump

2 1 2

1, 2, 3

1, 2, 3

1, 2, 3

1o 2o 3 20

g+lD

o

4W d. UndervoTtage-RCP BusStart Turbine-Driven Pump

e. Safety InjectionStart Notor-DrivenPumps .

.

2/bus 1/bus on 1/busboth busses

See Item I. above for all Safety Injection initiating functions andrequirements.

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FUNCTIONAL UNIT

TABLE 3.3-3 Continued

ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION

HINIHUHTOTAL NO. CHANNELS CHANNELS APPLICABLEOF CHANNELS TO TRIP OPERABLE gODES ~CTION

1) Start Motor-Driven Pumps

a. Steam Generator Water 3/S.G.Level-Low-Low

2/S.G.in oneS.G.

2/S.G.in eachS.G.

j,2,3 20

b. RCS Loop BT

++') Start Turbine-Driven Pump

a. Steam Generator MaterLevel-Low-Low

b. RCS loop bT

4 (1/loop)

3/S.G.

4 (1/loop)

2/S.G.in oneS.G.

2/S.G.in eachS.G.

1, 2, 3

1, 2, 3

1, 2, 3

20

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TABLE 3.3-3 Continued

ACTIOH STATEHEHTS Continued

ACTION 19 - With the number of OPERABLE channels one less than the HinimumChannels OPERABLE requirement, restore the inoperable channelto OPERABLE status within 48 hours or be in at least HOT STANDBY

within the next 6 hours and in COLD SHUTDOWN within the following.30 hours.

ACTION 20 - With the number of OPERABLE channels one less than the TotalNumber of Channels, STARTUP and/or POWER OPERATION aay proceedprovided the following conditions are satisfied:

b.

The inoperable channl!1 is plac d in the tripped conditionwithin 6 hours~ and py ~ Q Q~ t gQ~~~ (

The Minimum Channels OP RABLE requirement is Net; however,the inoperable channel aay be bypassed for up to 4 hoursfor surveillance testing per Specifica-tion 4.3.2.1.

ACTION 21 - With less than the Minimum Number of Channels OPERABLE, within1 hour determine by observation of the associated permissiveannunciator window(s) that the interlock is in its requiredstate for the existing plant condition, or apply Specifica-

~ tion 3.0.3.

ACTION 22 - With the number of OPERABLE Channels one less than the HinimumChannels OPERABLE requirement, restore the inoperable channelto OPERABLE status within 6 hours or be in at least HOT STANDBY

within the next 6 hours and in at least HOT SHUTDOWN within thefollowing 6 hours; however, one channel Nay be bypassed for upto 4 hours for surveillance testing per Specification 4.3.2. 1provided the other channel is OPERABLE.

ACTION 23 - With the number of OPERABLE channels one less than the TotalHumber of Channels,.restore the inoperable channel to OPERABLE

status within 48 hours or be in at least HOT STANDBY within6 hours and in at least HOT SHUTDOWN within the following6 hours.

ICTION 24 - With the number of OPERABLE channels one less than the TotalNumber of Channels, restore the inoperable channel to OPERABLE

status within 48 hours or declare the associated pump or valve „

inoperable and take the ACTION required by Specification 3.7.1.5or 3.7.1.2 as applicable.

ACTiON 25 - Nth the number of OPERABLE channels one less than the Hiniaum':.'","=

Channels OPERABLE requirement, restore the inoperable channel toOPERABLE status within 6 hours or ba in at least HOT STANDBY

within the next.6 hours; however, one channel aay be bypassed forup to 4 hours for surveillance testing per Specification 4.3.2.1provided the other channel is OPERABLE.

DIABLO CANYON - UNITS 1 4 2 3/4 3-22 AN e t Hos, 6 an 60

) 9

E~pl~ 2.l L s4.ll~k~~

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Insert S

ACTION

gS'CTION

jP

With the number of OPERABLE channels one less than theTotal Number of Channels, STARTUP and/or POWER OPERATION

may proceed provided that within 6 hours, for the affectedprotection set, the Trip Time Delay threshold power levelfor zero seconds time is adjusted to OX RTP.

With the number of OPERABLE channels one less than theTotal Number of Channels, STARTUP and/or POWER OPERATION

'

may proceed provided the following conditions aresatisfied:

a. The inoperable channel is placed in the trip conditionwithin 6 hours, and

b. The Hinimum Channels OPERABLE requirement is met;however, the inoperable channel may be bypassed for upto 4 hours for surveillance testing of other channelsper Specification 4.3.2.1.

(~ <( ~Q((c go~

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0

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TABLE 4.3-2 Continued

TRIPACTUATIlfGOE VICEOPERA- NASTER SLAVETIONAL ACTUATION RELAY RELAYTEST LOGIC TEST TEST TEST

NOOES FORlSICffSURVE ILLAlfC~IS RE IREO

N.A., R N.h. N.A. N.A. 1

for al 1 Safety In]ection Surveillance Requineents.

7. Loss of Peter

a. 4e16 kV Emergency BusLevel 1

b. le16 kV Keergency SusLevel 2

N.h. 1) 2) 3) 4

N.h. 1, 2, 3, iN.h.

N.A. N.h.N.A. N.A.

aENGINEEREO SAFETY FEATURES ACTUATION SYSTN IIfSTRtwfENTATIONS URVElll N E Ul If 5n

WIfAt06-CHANNEl.

C CHAIflfEL OPERA-CHAIIfEL CALI- T IONAL~ FUNCTIONAL UNIT CIIECK ORATION TEST

e. 6. Aux313ery Fe)6neter (CentInued)

d. Undervoltaoe - RCP N.A. R

e. Safety In)ection See Itee 1. above

N.A. R R

B. Engineered Safety FeatureActuation Systee Interlocksa. Pressurizer Prcssure,

P-11N.h.. N.h. N.h. NA NA l)2)3

b. PI ~ Io

c. Reactor Ttip, P-I

O)Q< ~N.A. N.h. N.A. R

TABLE lfOTATIONS

N.A. N.h. N.h. 1) 2) 3

1) Each train shall be tested at least every 62 days on a STAGGEREO TEST BASIS.2) For the Plant;Vent Activity-High monitor only, a CHANNEL FUNCTIONAL TEST shall be performed at least once every

31 days.

En)(e ~l u sk.l1rgo~-~ APED>."':-

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Insert Y

(3) Trip function automatically blocked above P-ll (PressurizerPressure Interlock) setpoint and is automatically blocked belowP-ll when Safety Injection on Steam Line Pressure-Low is notblocked.

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UNIT NG SAFETY SYSTEH SETTINGS

BASES

g4 ZK5~+ ISteam Generator Mater Level

The Steam Generator bloater Level Low-Low trip protects the .reactor frloss of heat sink in the event of a sustained steam/feedwater flow mismateresulting from loss of normal feedwater. The specified Setpoint providesallowances for starting delays of the Auxiliary Feedwater System.

lid lt ddd f B-R t ~tt td B

The Undervoltage and Underfrequency Reactor Coolant Pump Bus trips providecore protection against DNB as a result of complete loss of forced coolant flow.The specified Setpoints assure a Reactor trip signal is generated before theLow Flow Trip Setpoint is reached. Time delays are incorporated in the Under-frequency and Undervoltage trips to prevent spurious Reactor trips from momen-tary electrical power transients. For undervoltage, the delay is set so thatthe time required for a signal to reach the Reactor trip breakers following thesimultaneous trip of two or more reactor coolant pump bus circuit breakers shallnot exceed 0.9 seconds. For underfrequency, the delay is set so that the timerequired for a signal to reach the Reactor trip breakers after the Underfrequen-cy Trip Setpoint is reached shall not exceed 0.3 seconds. On decreasing power,the Undervoltage and Underfrequency Reactor Coolant Pump Bus trips are automa--tically blocked by P-7 (a power level of approximately 10K of RATED THERMALPOWER with a turbine impulse chamber pressure at approximately 10K of fullpower equivalent); and on increasing power, reinstated automatically by P-7.

g ~]g Zi ~g4d.! JWQO~1

DIABLO CANYON - UNITS 1'8( 2 Amendment Nos. tt 2 7

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Insert K

The Steam Generator Water Level Low-Low trip protects the reactorfrom loss of heat sink in the event of sustained steam/feedwater flowmismatch resulting from loss of normal feedwater or a feedwater systempipe break, inside or outside of containment. This function alsoprovides input to the steam generator level control system. IEEE 279requirements are satisfied by 2/3 logic for protection functionactuation, thus allowing for a single failure of a channel and stillperforming (he protection function. Control/protection interaction isaddressed by the use of the Hedian Signal Selector which prevents a

single failure of a channel providing input to the control systemrequiring protection function action. That is, a single failure of achannel providing input to the control system does not result in thecontrol system initiating a condition requiring protection functionaction. The Hedian Signal Selector performs this by not selecting thechannels indicating the highest or lowest steam generator levels asinput to the control system.

The Trip Time Delay (TTD) creates additional operational marginwhen the plant needs it most, during early escalation to power, byallowing the operator time to recover level when the primary side loadis sufficiently small to allow such action. The TTD is based oncontinuous monitoring of primary side power through the use of RCS

loop aT. The magnitude of the delays decreases with increasing primaryside power level, up to 50% RTP. Above 50% RTP there are no time delaysfor the Low-Low Level trips.

In the event of failure of a Steam Generator Water Level channel,the channel is placed in the trip condition as input to the Solid StateProtection System and does not affect the TTD setpoint calculations forthe remaining OPERABLE channe1s'.~ Failure of the RCS loop aT channelinput to the TTD does not affect the TTD calculation for a protectionset. This results in the requirement that the operator adjust thethreshold power level for zero seconds time delay from 50% RTP to 0%

RTP, through the Han Hachine Interface.

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