Text

Proposed TS Section 15.3.5, Instrumentation Sys & Section 15.4.1, Operational Safety Review
	ML20125D556
Person / Time
Site:	Point Beach
Issue date:	12/10/1992
From:	; WISCONSIN ELECTRIC POWER CO.
To:	;
Shared Package
ML20125D555	List: ML20125D553; ML20125D556;
References
	NUDOCS 9212150276
	Download: ML20125D556 (27)
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.

1. Dggree-of-Brdundanev Deg ree-o f-red u nd a n cy-4 s-de f4 ned-a s-t he-di ffe rence-be t ween-themumbee-o f ope ra ble-ch a n nele-a nd-t he-mi n imum-number-o f-+h a n neb-whi c h-whe n-tel pped-w lM cause-an-automat 4c-shutdownr ml. Reactor Critical The reactor is said to be critical when the neutron chain reaction is self-sustaining and k,,, = 1.0.

nm. low Power Operation The reactor is in the low-power operating condition when the reactor is critical and the average neutron flux of the power range instrumentation indicates less than or equal to 2% of rated power.

on. Fire Suporession Water System A FIRE SUPPRESSION WATER SYSTEM she' consist of: a water source; pump (s);

and distribution piping with associated sectionalizing control or isolation valves. Such valves shall include yard post indicating valves and the first valve ahead of the water flow alarm device on each sprinkler, hose standpipe _

or spray system riser.

s l

'Init 1 - Amendment No. 32 15.1-5 Unit 2 - Amendmnnt un in January 23, 1978 9212150276 921210 6 PDR ADOCK 0500 P

_ ___ _ . i

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4 4 '._

p5, Dose Eouivalent'I-131 Dose Equivalent I-131 shall be that concentration of:1-131 (microcur'ie/ gram)L which alone would produce the same thyroid dose as the quantity and-isotopic ;

mixture of I-131, I-132, I-133, I-134, and I-135 actually present. The j thyroid dose conversion factors used for this calculation shall- be those listed in Table 111 of TID-14844, " Calculation of Distance factors for' Power and Test Reactor Sites."

qh. E - Averaae Disintearation Enerav j E shall be the average (weighted-in proportion to the concentration of each radionuclide in the reactor-coolant at the time of sampling) of the sum of-the average beta.and' gamma enargies per disintegration (in MeV) for isotopes, other than iodines, with half lives greater thur.15 minutes',. .

making up at least 95% of the total non-iodine activity _ in the coolant, t

4 l

l L - Unit 1 - Amendment No. 71 15.1-6 Unit 2 - Amendment No. 76' April 4, 1983

15.3.5 INSTRUMENTATION SYSTEM

. Qperational Safety Instrumentation Apolicability: Applies to plant instrumentation systems.

Ob.iectives: To provide-for automatic initiation of the Engineered Safety features -in the event that principal process variable limits are exceeded, and to delineate the conditions of the plant instrumentation and safety circuits necessary to ensure reactor safety.

Specification:

A. The Engineered Safety Features initiation instrumentation setting limits shail be as- stated in Table 15.3.5-1.

B. For on-line'testir.9 or in the event of a sub-system instrumentation _ channel $

failure, plant operation at rated power shall be permitted to continue in accordance with Tables 15.3.5-2 through 15.3.5-4.

C. In the event the number of channels of a particular sub-systep in service falls below the litalts given in the column entitled Minimum Operable Channels, ee-M4n4 mum-Degree-of-Redundanct-eannot-be-acWyedr operation shall be limited according to the requirement shown in Tables 15.3.5-2 through 15.3.5-4, Operator Action when minimum operable channels unavailable..

D. -The host 3 accident monitoring instrumentation channels in_ Table 15.3.5 -

shall' bel operabl e.. In the event the number of channels in a particular-sub-system falls below the minimum number _ of operable. channels given in-Column 2,. operation and subsequent _ operator action shall be in accordance with Column 3. This specification-is not applicable in ti.e cold or refueling shutdown _ conditions.

Basis: Instrumentation has been-provided to sense accident conditions and to ,

initiate operation of the Engineered Safety features (l).

i l

Unit 1 - Amendment No. 92 15.3.5 August 7, 1985-Unit 2 - Amendment No. 96

i- .;

1 TABLE 15.3.5-2 INSTRUMENT CONDITIONS FOR REACTOR TRIP i

1 2 3 4 TOTAL NO. OF MINIMUM . PERMISSIBLE NO. OF CHANNELS OPERABLE BYPASS OPERATOR ACTION IF. CONDITIONS-

, NO. FUNCTIONAL UNIT C_HANNELS _TO TRIP CHANNELS CONDITIONS OF COLUMN 3 CANNOT BE MI;T

1. Manual 2 1 1 B3 in hot shutdown in 8: hours 1

2. Nuclear Power Range ' . !

a. low setting 4 2 3 ** 2 of 4 channels Be in hot shutdownLin 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months greater than 10%

full power (low setting only) i b. high' setting 4 2 38** Be in hot shutdown in 8. hours l t

3. Nuclear Flux "

Intermediate Range 2 '1 1 2.of 4 channels Be in hot. shutdown.in 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months '.'

greater than 10%

full power j

. .i 4 '. Nuclear Flux' Source '2 1 1 1 of 2 interme- Be in-hot shutdown in 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months *. ;

Range diate range

channels greater ,

i.ian 10- amps .

5. Overtemperature Delta T 4 2 3 ** Be.in hot shutdown-in.8. hours j I

6. Overpower Delta T 4. 2 3 ** Be in hot shutdown.in 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months l

?

. li

7. Low Pressurizer Pressure 4 -2 3 ** Be'in hot shutdown'in 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months . TI

.; 8. Hi Pressurizer. Pressure > 2. 2 ** Be.in hot shutdown in'8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .'

t

9. Hi Pressurizer 3 2 2" Be'in hot shutdown in 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , 'l Water-Level F

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l TABLE 15.3.5-2(continued) 1 2 3 4 TOTAL NO. OF MINIMUM PERMISSIBLE NO. OF CHANNELS OPERABLE BYPASS OPERATOR ACTION IF CONDITIONS CHANNELS TO TRIP CHANNELS CONDITIONS OF COLUMN 3 CANNOT BE MET NO. FUNCTIONAL UNIT

10. Low Reactor Coolant System Flow Be in hot shutdown in 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months

a. Low Flow in One Loop 3/ loop 2/ loop 2/ loop"

(>50% full power) (any loop)

Low Flow in Both Loops 3/ loop 2/ loop 2/ loop" Be in hot shutdown in 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months b.

(10-50% full power) (both loops)

11. Turbine Trips Be <50%'of rated' power

a. Turbine:Autostop 3 2 2" ~

within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Oil Preesure' 21 2 2" Be <50% of rated power

b. Turbine Stop-Valve within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months

-Position

12. Steam Flow-Feedwater 2/ loop 1/ loop 1/ loop Be in hot shutdown in 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months Flow Mismatch

13. Lo Lo Steam Generator 3/ loop 2/ loop 2/ loop" Ee in hot shutdown in 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months Level (input to reactor trip)

14. 4KV Bus (A01 and A02) Be in hot shutdown in 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months

a. Undervoltage (input 2/each 1/each 1/each to reactor trip) bus bus bus

b. Underfrequency 2/each 1/each 1/each Be in hot shutdown in 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months bus bus bus Safsty Injection JSee1 Table' 11 - See Table Be in hot' shutdown

15. -in c. hours"*

15.3;5-3 15.3.5-3;

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TAB.~2E 15. 3.5-2 (continued) 1 2 3 4 TOTAL NO. OF MINIMUM PERMISSIBLE NO. OF CHANNELS OPERABLE BYPASS OPERATOR ACTION IF CONDITIONS '

NO. FUNCTIONAL UNIT CHAN?!ELS TO TRIP H C_ANNELS CONDITIONS OF COLUMN 3..CANNOT BE MET 16 L RCPLBreaker.Open- ..

' ~ ' '

Position fa. ' (>50% full" power)? J2" .11 '2 Be'inihot' shutdown?in~8Lhohrs J10..'-' 50%i fblli pow'er);

b. .

2. 7:2J I2. 3Be'in hot shutdown 1:in ; 8 : hours

' ~

17. Reactor:lTripiBreakersl T 2'- L1" ~2 i**** - Be'in hotishut.down;in 8Thours

One additional channel may be taken out of service for low power physics testing.

When block' condition exists, maintain normal operation.

- ' (If alchannelSis? detiermined; toibe.linopbrablek-f resultingiin'one ;1ess than the total?numberiof channels

~

'being-~ operable,; power!operationimayi cont.inue'ifithe-following; conditions are met:

li.?ThelminimumJnumberyofToperable. channels is stillisatistied.

2 =. rThe':af f ected." channel ' is ' placed(in 4 trip within f l' hour:

~

- - If minimum c'onditions are~not met within 24" hours after reaching hot shutdown, the unit shall be in cold shutdown within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months of'the event causing the unit shutdown.

- - - Wheh /ati powek oneT channe1Taiay?be~bypssssdifor' 6p' to ._8 ihobrs provided thatF the othdr. channel is 7

operabla.J;WhenOthe:plantf.istshut'downinndTrodjwithdrawal isipossible,Lrestore.the: inoperable. channel to1operableLstatus within/48:hourslorfopen?the7 Reactor-Trip 2 Breakers.~within:1-hour.

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a TABLE 15.3.5 -3 (continued)

EMERCENCY CCOLINC E'IGINEERED SAFETY FEATURES 1 2 3 4 NO. OF MINIMUM P*?RMISSIBLE NO. OF CHANNELS OPERABLE BYPASS OPERATOR ACTION 1F CONDITIONS ,

NO, FUNCTIONAL UNIT CHANNELS TO TRIP CHANNELS CONDITIONS OF COLUMN 3 CANNOT BE MET-T_ @ f Both ain ?ccdpufr.pc 2/ pump 1/ pump Hot-Simt-dewn"*

b. -

1/ pump Rcactor Pcucr Startc Motor Driven Pumps is Lcca Than '20'

b. Start Turbine-Driven Pump

i. Undervoltage on 4KV Buses l(A01-&;A02i 2/each 1/each 1/each Be in hot shutdown in 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months

bus bds~ bus" ii. Low Low Steam Gen.

Water Level 3/SG 2/each 2/SG" Be in hot shutdown in 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months

SG

4. SAFETY-RELATED ELECTRICAL BUSFS LOADS

a. 4.16KV Buses

1. Degraded Voltage 3/ bus 2/ bus 2/ bus" ***

s ii. Loss of Voltage 2/ bus 1/ bus' 1/ bus ***

b. 480V Buses

i. Loss of Voltage 3/ bus 2/ bus 2/ bus" Be in hot shut down in 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months ' o If minimum conditions are not met within 24 hourc after reaching hot shutdown, the unit shall be in cold shutdown within 48. hours of the event causina the unit shutdown.

M JIf1 a chsnnellisTdetermined; t o}be /incperdbls,Jresulting?::in%ne Tlessf than r theltiotal':" number of

~

channels ;being' . operable,tpower; op'erstion may(continue;: if ? thef following} conditions are mer:

1. Thelminimumi number sof1. operable;channelsfis...'stil15 satisfied. "

c 2.-l.Thecaffectedichanneliis:pls'edJinstrip-withinllEhour.

oco Normal" operdt-idn 'is? allowed ~provided" bot h~ dieselgeriersbors ~are available and the associated diesel . ,

generator 1s operstiing~ ^ arid ~providing power to -the af fected safeguards , bus. If these minimum conditions are not' met wit:hin 7 days, the af fected unit shall be placed in hot s6utidown.

006 Both cwitches must be activated simultaneously.

~

TABLE 15.3.5-4 INSTRUMENT OPERATING. CONDITIONS FOR ISOLATION FUNCTIONS 1 2 3 4 TOTAL- NO. OF MINLMUM PERMISSIBLE NO. OF CHANNELS OPERABLE BYPASS OPERATOR ACTIONS .TF CONDITIONS E FUNCTIO?AL UNIT CHANNELS TO TRIP CHANNELS CONDITIONS OF COLUMN 3 CANNOT BE MET

1. CONTAINMENT ISOLATION

a. Safety Injection See Items Ib, c, and d of Table 15.3.5-3 Be in hot shutdown in.8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months *'

b. Manual 2 1 1 Be in hot shutdown in 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months

2. STEAM LINE ISOLATION i

a. Hi Hi Steam Flow with 2/ loop 1/either 1/ loop Be in hot shutdown in 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months

loop Safety Injection See Items ib, c, and d of Table 15.3.5-3 Be in hot shutdown'in 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months *

b. Hi Steam Flow and 2/ loop 1/either 1/ loop Be in hot shutdown-in 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months

loop

4 2;. 13" .Be'in hotishutdown' in 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months

Low lTavs sith:

SafetyfInjectionT ?See1 Items Ib,- c,:and.!d'of Table 1523;5 .

Be?inThoti:ehutdown?in'8' hours

l C. Hi Containment

Pressure 3 2' 2" Be in hot shutdown in 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months *

d. Manual 1/ loop 1/ loop 1/ loop Be in hot shutdown in 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months . . ;.

3. :FEEDWATERMISOLATION

a. :H1'SteamiGenerator

Water? Level L3/SG3 2/SG( 2/SG" _

$Be?inf hot 1.shutdownfiniE h6urs* 2

. Safety]Injectiori

^ '

Jb. . #See;It'eElio'fETable 1523.5 W -Be'~inihoOsbutdown{.inL 8? hours' ;

If minimum conditions'are not met within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , steps shall be taken on the affected unit to place the unit in cold. shutdown canditions.

p6: If : Ea channel? iKde termined ;; t63 beiliicperabl'e; resulting ini onefless thsn7the." totalFnumber L o'f ichannels beingJoperablegipowsr2 operation mayicontinue(ifJtheffallowing conditions are.meti 12 <The'minimuminumber~of;operableLchannels is.etillnsatisfied.

2 a The i af fected; charinel$ is1placed.'.in L trip yithin?1< hour.

a' c g - --

- , . , _ t--

-"-w - ,

t TABLE 15.3.5-5 INSTRUMENT OPERATING CONDITIONE FOR I!OIC_5 TIC"9 POST-ACCIpJI!G MONITORING INSTRUMENTATISN 1 2 3

?OTAL MINIMUM NO. OF ^PERABLE OPERATOR ACTION IF CONDITIONS NO. FUNCTIONAL UNIT CHANNELS QJANNELS QF COLUMN 2 CA*iNOT BE MET

1. PORV Position Indicator 1/ Valve 1/ Valve If the operability of the PORV position indicator cannot be restored within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , shut the associated PORV Block Valve.

2. PORV Block Valve If the operability of the PORV Block Valve Position Indicator 1/ Valve 1/ Valve Position Indicator cannot be restored within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , shut and verify the Block Valve shut by direct observation or declare the Block Valve inoperable.

3. Safety Valve Position 2/ Valve 1/ Valve If the operability of at least One of the Safety Indicator Valve Position I?dicators cannot be restored within seven days, be in at least hi.. shutdown within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

Reactor Coolant System 4.

Subcooling 2 1 If operability of at least one subcooling monitor cannot be restored within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , be in hot i shutdown within the next twelve hours. i i

l The chEncel requirements ,in this table refer only to that portion of the . instrument channel l

~

NOTE:

required tcr post-accident' monitoring. The applicable l channels are listed-in FSAR Table _7.7-2.

~

l l

l a

l

TABLE 15.3.5-5 (continued) !

1 2 3 MINIMUM TOTAL NO. OF OPERABLE OPERATOR ACTION IF CONDITIONS 1 NO. FUNCTIONAL UNIT CHANNELS CHANNELS OF COLUMN 2 CANNOT BE MET .

l

5. AEW Fump Discharge ^

Flowrate '. 3 ' .# . ' If the' minimum. number of.AFW Pump' Discharge

~Flowrate channels required to provide. indication of.AFW flow to both' steam generators cannot.be~

restored to:anfoperable status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months ,-be' ; _

inshot;shutdownLwithinithe next twelve. hours.

6', 'A.FW to Steam Generator

'FAowrate' 4 12 1- , cIffoperability cann .)e restoredIwithin?481 hours0.00557 days 0.134 hours 7.953042e-4 weeks 1.830205e-4 months ? -

be in. hot shutdoir' hin the next twelverhours. ,

7. Containment.High Range Radiation 3 2 If the operability cannot be restored within seven days after failw e, prepare a special report to be submitted within thirty days in accordance with

15.6.9.2.D.

8. Containment Water Sump Level K;yway (Sump-A)

~ '

2 1 Operation may continue up to thirty days. If +

operability cannot be restored, be in. hot shutdowa within the next twelve hours.

9. Containment Water Sump Level (Sump B) Continucud'Indic. 2 1 If operability cannot be restored within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , be in :.ot shutdown :within the next twelve hours.

~#1 The" minimum" number ofl.[operablCUhannels:fo'ri AFW.PumpLDi'scharge FlowrateTis the:numbsrJof^LFW

~

5 Pumpf Discharge}Flowrate channels; L in? conjunction -with Lthe number of : operableJAFW to : Steam Generator..FlowrateJchannelsb required (to, provide indication ~.'of'AFW flow to both steam

~~ ~

generators '.'

NOTE: Thel ch6nneD requirement sfinithiaf table ~ refer?only; toL that portion'of 2 t.h'e ' instrumentE cliannel requirediforfpast-accident monitoring.:

1 ' The applicablel channels are 'listy'. in': FSARl Table 7.7-2.

4

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5 i

TABLE 15.3.5-5 (continued) 1 2 3 TOTAL MINIMUM NO. OF OPERABLE OPERATOR ACTION IF CONDITIONS NQ. FUNCTIONAL UNIT CHANNELS CHANNELS OF COLUMN 2 CANNOT BE MET

10. Containment Hydrogen Monitors Conc.entration 2' 1 If operability cannot be restored within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , ;

be in hot shutdown within the next six hours.

}

.11.1 > Reactor Vessel: Wide Range Level! -2 : 1 :l fIf' operability'cannot be'restorsd within'48Lhoursi be in hot 1 shutdown within:the nextl twelve; hours.

12. # Reactor' Vessel 1 Narrow '

' Range Level t 2 # ' 1' JIf operability cannot.beirestored within'48bhours,,

be.in hot shutdown within the next! twelve; hours 2' '

13. In-Core Thermocouples 39Minstalled 2/ core If cperability cannot be restored within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , per core quadrant be in hot shutdown within the next twelve hours.

t t

t 14. Main M eam Line Radiation 1/stean 1/ steam If oparability cannot be restored within seven-Men-itorc 'CA 11) line line days, prepare a special report to be submitted ..

within thirty days in accordance with 15.6.9.2.E..

15. . Refueling Water:iStorages '2L 1J If' operability cannot be: restored ~within 482 houks?

~ Tank 1 Level _

be in hot shntdown: within "the next twelve hours.

16!. -lRCS Wide ; Rangel: Pressure.: A. - 11{

' ~

LIf*operabilitplcannotTbeTrestored withinf48;h6 belin hot J shutdown withirfthe next-twelve ursi.~ '!

hours.

.1 f*1 With)onlyfone?hydrosen monito Moperabl R restore'anfinoperable.'monitop withTan independent power.LaupplyjtoTan.. OPERABLE:statusTwithin:30.l::daysfordbeJin1 hot shutdown within 6 ihours.

TNOTEiiTheschannsl?. requirements (infthis[EablefrOfer7onlyflolthatiportiod'oflitheliilstirument ch' T nnell a

Lrequired for. post-accidentLmonitoring.. LThe7 applicable" channels'are listedlin*FSAR Table 17J7.-2.~

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15.4.1 OPERATIONAL SAFETY REVIEW Applicability:

Applies to items directly related to safety limits and limiting conditions for operation.

Objective:

A. Instrumenta' ion shall be checked, tested and calibrated at sufficiently

. frequent intervals to assure safe operation.

B. Equipment and sampling tests shall be conducted at sufficiently frequent intervals to assure safe operation.

Specification:

A. Calibration, testing, and checking of analog channel and testing of logic channel shall be performed as detailed in Table 15.4.1-1.

B. Equipment and sampling tests shall be conducted as detailed in Table 15.4.1-2.

Basis:

A. Check Failures such as blown instrument fuse:, defective indicators, faultad amplifiers which result in " upscale" or "downscale" indication can be e ily recognized by simple observation of the functioning of an' instrument or system. Furthermore, such failures are, in many cases, revealed by alarm or annunciator action, and a check supplements.this type of built-in surveillance.

15.4.1-1

4 Based on experience in operation of both conventional and nuclear plant systems, I when the plant is'in operation, the minimum checking frequency of once per shift is deemed adequate for reactor and steam system instrumentation.

Calibration Calibration si..:' ka performed to ensure the presentation and acquisition of accurate information.

The nuclear flux (linear level) channels shall be calibrated at least daily' against a heat balance standard to verify drift and effects of changing rod patterns.

Other channels are subject only to " drift" errors induced within the instrumentation itself and, consequently, can tolerate longer intervals between calibration. Process system instrumentation errors induced by drift can be expected to remain witnin acceptable tolerances if recalibration is performed at intervals of each refueling shutdown. ;.

Substantial calibration shifts within a channel (essentially a channel failure) will be revealed during routine checking and testing procedures.

Thus, minimum calibration frequencies of once per-day for the nuclear flux (linear level) channels, and once each refueling shutdown for the process system channels is considered acceptable.

Testing Experience with this type of instrumentation has shown that the testir; frequency as specified in Table 15.4.1-1 will assure the _ required level of performance.

i-1

\

t 15.4.1-2 t-

B. The equipment testing and system sampling frequencies specified in Table 15.4.1-2 are considered adequate to m;intain-the status of the equipment and systems so as to assure safe operation.

4

. 15.4.1-3

t 1 y . , n.

l TABLE 15.4.1-1 MINIMUM FREQUENCIES FOR CHECKS, CALIBRATIONS, AND TESTS OF INS TRUMENT CHANNELS PLAh'T CONDITIONS CHECK CALIBRATE TEST WHEN REQUIRED NO. CH?E'EL DESCRIPTION R -

ALL

1. N2 lear Power Range -

ALL S (1) D(1,19) -

-heat Balance - M(1,2) ALL

-Signal to delta T; bistable -

actions (parmissive, rod F1 Ops, trips) FWR

-Compare results of the-incore M(4,5,20) -

detector measurements to NIS axial flux difference R -

ALL

2. Nuclear Intermediate Range -

ALL S(1)

-when not blocked P ALL

-logarithmic level; bistable action - -

(permissive, rod stop, trips)

R -

ALL

3. Nuclear Source Range -

ALL

-when not blocked S -

P ALL

-Bistable action (alarm and -

trips)

S R - PWR, HOT S/D, COLD S/P 1

4. Rear-tar Coolant Temperature ALL

- M(1,2)

-G,ertemperature delta T -

- M(1,2) ALL

-Ovarpower delta T S (1) R -

ALL

5. Reactor Coolant Flow M(1,2) ALL

-Analog and single loop loss- -

of-flow logic testing - R ALL

-Logic channel testing for reactor trip on loss of reactor coolant flow in both loops S(1) R M(1,2) ALL

6. Pressurizer Pressure S (1) R M (1,2 ) ALL

7. Pressurizer. Water Level a

e

y e

e

. ..i

.i 4

TABLE 15.4.1-1 (continued) 1 PLANT CONDITIONS

, NO. CHANNEL DESCRIPTION CHECK CALIBRATE TEST WHEN REOUIRED

8. Steam Generator Level. S (1) R M(1,17) ALL

9. Steam Generator Flow Mismatch S (.1) R M(1) ALL

10. Steam Generator Pressure S(16) R M(1) ALL 4KV Bus Undervoltage (A01 & A02) i 11.

-AFW pump actuation -

R M(1) ALL

-Reactor Protection actuation .

R M(1,2) ALL ,

F

12. 4KV Bus Underfrequency (A01 &'A02)

-to Reactor Coolant Pump trip -; R -

ALL

12. Safeguards Bus Voltage ;

-Locs of 4KV S R M(1) ALL >

-Degraded 4KV S R M(1) ALL i

-Loss of 480V S R M(1) ALL

14. L 1201VaclInstrumsnt Buses.1- l < EW(6): .- -c ' FALL 15".- Reactor? Trip _ Signal JFroin. fulLine !

4

-Turbine:Autostopu - -

H -- - :-

" . M(1)D iALL t

-Turbine fStop Walitei

~

m

~-

M(1)l 'ALL , !

t

16. T. Reac tior ETsip -lf S idnali FroniTS IE j i _ ,

' , M(1))

' TALL I

17. "FesdwaterlIsolatidni on SI iMFPL Trip ony SafetyOInj ectiion :. ~ 7RL '

' ~

-f '=

' ALE i -

-MFRV[ Shutting f onTSafetp].Inj ection ; - t , 27 ' . _

'R 4ALL

18. Accumulator-Level and Pressure S R -

ALL

19. Analog Rod' Position S (8) R M(1) ALL .

-with step counters S(1) - --

"~

ALL-

}Monitforing[ bp]OniLine ~ Comput-sr0 ](18)) --- i PWR(HOTLIS/D

A O g

l lllfIl S

N O~

ID TE IR DI NU OO CE R

T NN L L AE L L L L L L LLL L L L L L L L LH L L L L L L LLL L L L L L L L L L PW A A A A A A AAA A A A A A A A A A

)

9 3 )

T ) , ) 1 1

S 1 1 0

(

E ( (

1 T - - - - - M - - - M - Q - - ( - M R

)

d E e T u A n R i B ) ) )

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(

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1 4

5 1

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E C ) ) ) 2 L E 3 1 1 1 B ( (

A 3 C

1

( - D -

f S S D- - S M Q M M S Q - S T

n o

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I d n n o i yi a r a nm o M lc i n

R e o a w t H HtC P W au l m e

ai l o

C e C T o S a l r a r Vd i S F l t trc t t Pt t e r n b i E d d F e n nbi n n s n h u kI a t D y i i t e ein e e yn e T s c r i r c c g a m ml o m m cI 1

~ s on e s L a< A A n s n nar n n n n e e l o p o R i n i iCt i i ey o r r Bi O P

? l c c g e a a c a a ge r o p t '

N i i i r d t tse t t rv i C r Vi V V A x r r a n n nal n n er v - e Rs R R H u o o h o o oGE o o mu n n v Oo O O C A B B C C C C - - C C ES E I O PP P P O 0 1 2 3 4 5 6 7 8 9 0 1 2 3 4 5 G N 2 2 2 2 2 2 2 2 2 2 3 3 3 3 3 3 l{llI\llfll!ll ,f I1llllflll! lllll llj lt

t TABLE 15.4.1-1 (continued)

PLANT. CONDITIONS NO. CHANNEL DESCRIPTION CHECK CALIBRATE IE.ST bTEN REOUIRED

36. Radiation Monitoring System D(7) R(7) M(7) ALL !

37. Reactor Vessel Fluid Level System M R -

ALL

38. Refueling Water Storage Tank Level - R -

ALL -

39. Residtial Heat Removal Pump Flow -

R -

ALL i

40. Safety Valve Position Indicator M R -

ALL

41. Subcooling Margin Monitor M R -

ALL

42. Turbine First Stage Pressure S (1) R M(1) ALL

43. Turbine Oversps d Trips

-Independent Overspeed Frotection System -

R M(1) ALL

-Overspeed Block trip -

R M(1) ALL ,

44. Volume Control Tank Level -

R -

ALL NOTATION USED IN TABLE 15.4.1-1 S- Each shift D- Daily ,

W- Weekly Q- Qitarterly ;

M- Nonthlv P- Prior to reactor:' critical 1ty if not performed during.the previous week. 'l R- Each refueling inteival'(but not to exceed 18 months) >

PWR4. iPoweWand1LowD: Power Opsration; fa's idefined "inVSpscificatlonsl15iliC fhl_1:and 15.1(C.n.

HOT'S/DM Hot J Shutdown,yas(definedfin? Specification AS.l'.C.911l. '

COLD?S/D- Cold 7Shutidownh as definedL in ? Specification ;15T1;C.g.2 k ~

, ' REF jS/DW ResfuelingCShutdowni: as: defined in;Specificationil5il.C.g13; At& JAlliconditionsiof ' operation ~,f as defined 11n TSpecificat; ions 15.1.C.gi h'iandTn.

e I

NOTES USED IN TABLE 15.4.1-1 (1) Not required during periods of refueling shutdown, but must be performed prior to reactor cEiticalitp if it has not been performed'during the previous surveillance period.

(2) Tests of permissive and low power trip bistable setpoints which cannot be done during power operations.shall be conducted prior to kesctorncriticalitp if not done in the previous two weeks.

(3) Perform test of the isolation valve signal. .

(4) Perform by means of the moveable incore detector system. l (5) Recalibrate if the absolute difference is a3 percent. *

( 6)( Everificationioff propsrlbreakerfalignnentfandTthatf the 1201Vac.: instrument busesf arelenergized

~

(7) Radioactive' Effluent Monitoring Instrumentation Surveillance Requirements are specified in Section 15.7.4.

(8)2: VerifyLthat:the Mss 6ciated"r'6d insertionil~imit(isEnot beingTviblated"at least.'oncefper ? 4" hours i whenever! theirod iinsertidn limit r alarmi for a _ control : bank-fis= ' inoperable.

(9) Test of Narrow Range Pressure, 3.0 psig, -3.0 psig excluded.

(10) When used for the Overpressure Mitigating System, each PORV shall be demonstrated. operable by:

a. Performance of-a channel functiotal test on the PORV actuation. channel, but excluding. valve ..

operation, within 31 days prior'to entering a condition in which the PORV is required operable' and at least once per 31 days thereafter when the PORV is required operab'e. . ,

b. Testing valve operation in accordance with the inservice test requirements of the ASME Boiler-and Pressure. Vessel Code, Section;XI.

(11) Performance of a channel functional test is required, excluding valve operation.

(i2F Shif tip? checkCis7requifed Whenit he Treactfohfc'dolant? sis f emlisinot[open Ito" the LatmosphereT and fthe reactor ) coolantisystem i temperatiure :iis iless s than tthe):. minimum : temperaturej fo$ the l1n- service pressure test'assspedifiedpinjTShFigufey1513.lill

' ~ '

~

.' S~ -

( _ _-

NOTES USED IN TABLE 15.4.1-1 (continued)

~

(13)'An'AFW flow path to each steam generatorfshall-be demonstrated operable, following each cold shutdown of greater than 30 days,;prf.or to: entering power operation by verifying AFW flow to each steam generator.

(14) Calibration is to be a ve.rification of response to a source.

(15) Sample gas for calibration at 2% and 6%.

(16) A check of one pressure channel per steam generator is required whenever the steam generator could be pressurized.

(17) Includes test of logic for reactor trip on low-low level, automatic actuation logic for at.xiliary feedwater pumps, and. test of logic'for feedwater-isolation.on high-steam generator level.

(18) Rod positions must be logged at least once per hour, after a load change >10% or after >30 inches of control rod motion if the on-line computer is inoperable.

~

^

(19) The ' daily heat balance -is ~a gain adjustment performed to match Nuclear Instrumentation ~ System indicated power. level with reactorLthermal output.

~

(20) - To confirm that hot channel fsctor limits are bei ~J satisfied, the? requirements of TS 15.3.10.B must be . net'.

I O

W

_e

%_ - - ___.m- _ _ - .

.__ . . . .. m.m

.c

.-s TABLE 15.4.1-2 lilNIMUM FREQUENCIES FOR E0VIPMENT AND SAMPLING TESTS lqit Freouenc,y

- 1. Reactor Coolant Samples Gross Beta-gamma 5/ week")

activity (excluding tritium)

Tritium activity Monthly Radiochemical E Semiannually """)

Determination Isotopic Analysis.for Every two weeks")

Dose Equivalent I-131 Concentration Isotopic Analysis for a.) Once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months Iodine including I-131, whenever the specific l-133, and I-135 activity exceeds 1.0yCi/

gram Dose Equivalent I-131 or 100/E pCi/ gram.")

b.) One sample between 2 and 6 hcus following a thermal power change exceeding 15% of rated power in a one-hour period.

Chloride Concentration 5/ week")

Diss. Oxygen Conc. - 5/ week")

Fluoride Conc. Weekly

2. Reactor Coolant Boron Beron Concentration Twice/ week

3. Refueling Water Storage Boron Concentration Weekly")

Tank Water-Sample

4. Boric Acid Tanks Boron Concentration Twice/ week

5. Spray Additive Tank Na0H Concentration Monthly

6. Accumulator Baron Concentration- Monthly

7. Spent Fuel Pit -h): Boron Concentration - Monthly b)'Wat W lsvel Weekij

~~

yeqifjcatioh Unit 1 - Amendment No. 129 Page 1 of 4 October 16, 1991 Unit 2 - Amendment No. 133

,- TABLE 15.4.1-2 (Continued)

" Freauency Igit

. 8. . Secondary Coolant Gross Beta-gamma Weekly ("

Activity or gamma isotopic analysis lodine concentration Weekly when gross Beta-gamma activity equals or exceeds 1.2 pCi/cc ("

9. Control Rods p^)' Dod drop times of Each refueling or after all full length maintenance that could rods ") affect proper functioning ")

b)l R5dw6fthiinelislursinent F611oQin' g Tea W fsTdsl Q shutdow;n;priorto;commenc;ing_

R9WGEOP.eration

10. Control Rod Partial movement of Every 2 weeks "3" all rods ll, Pressurizer Safety Valves Set point Every five years ""

12. Main steam Safety Valves Set P^t Every five years ""

13. Containment Isolation Trip Functioning Each refueling shutdown

14. Refueling System Interlocks functioning Each refueling shutdown

15. Service Water System Functioning Each refueling shutdown

("

16. Primary System Leakage Evaluate Monthly

17. Diesel Fuel Supply - Fuel inventory Daily

("

18. Turbine Stop and Governor Functioning Annually Valves

19. Low Pressure Turbine Visual and magnetic Every five years Rotor Inspection (" particle or liquid penetrant

20. Boric Acid System Storage Tank Daily Temperature

21. Boric Acid System Visual observation Daily of piping

temperatures (all > 145 F)

22. Boric Acid Piping Heat Electrical circuit Monthly Tracing operability

("

-23. PORV Block Valves Complete Valve Cycle Quarterly Unit 1 - Amendment No. 129 Page 2 of 4 October 16, 1991 Unit 2 - Amendment No. 133

1 I

a TABLE 15.4-2 (Continued)

Icn1 Frequency

24. Integrity of Post Accident Evaluate Each refueling Recovery Systems Outside cycle Containment

25. Containment Purge Supply Verify valves are Monthly (9) and Exhaust Isolation Valves locked closed

26. Reactor Trip Breakers a. Verify independent Monthly (9) operability of automatic shunt and undervoltage trip-functions.

b. Verify independent Each r( fueling operability of man- shutdown ual trip to shunt and undervoltage trip functions,

27. Reactor Trip Bypass Breakers a. Verify operability Prior to of the undervoltage breaker use trip function.

b. Verify operability Each refueling of the shunt trip shutdown functions.

c. Verify operability Each refueling of the manual trip shutdown to undervoltage trip functions.

28. Atmospheric Steam' Dumps' CompleteLvalve cycle;' 1 Quarterly

29. ' Crossover Steam. Dump System. Verify operabilityLof;;; ! Quarterly each steam' dump valve.

30. :Piessurizer Heaters Verify thatXl100KW.iof? LQuarterly heaterstarelavailable.

31. CVCS; Charging: Pumps Verify operability off Obarterly pumps. (12 ).

~

' ' ~

32. Potential. Dilution'in? ~Verifyfoperabi.'ityfof Priorfto? placing Progress Alarm alarm. plantfinhcold

' shutdown.

I

a Af e

c e

HOTES USED IN TMll_LLL1-2 (1) Required only during periods of power operation.

(2) E determination will be started when the gross activity analysis or a filtered samp]e indicates =10pci/cc and will be redeterr:ined if the b primary coolant gross radioactivity of a filtered sample increases by more than 10pCi/cc.

} (3, Drop test shall be conducted at rated reactor cotilant flow. Rods shall be dropped under both colt! and hot corditions, but cold drop tests need not be timed.

(4) Drop tests will be conducted in the hot condition for rods on which maintenance wae pe.tformed.

(5) As accessible without disassembly of rotor.

(6) Not required durir3 periods of refueling shutdowa.

(7, At ler,t once per week during periods of refueling shutdown. ~

(8) At least three times per week (wita r.mxf mum time of 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months between r samp]et) durir g periods of refueling sb' tr.own.

(9) Not required during periods of colc' > e s a'ueling shutdown, but must be performed prior to exceeding 200*F if it has not been performed during the f) previous surveillance period.

(10' Samplc to be taken after a minimum of 2 EFPD and 20 days power operation

( since the reactor was last subcritical for 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or longer.

(11) An approximately equal number of vilves shall be tested each refueling outage such that all valves will be tested within a five year period. If any valve fails its tests, an additional number of valves equal to the number originally tested shall be tested. If any of the additional tested valves fail, all remaining valves shall be tested.

(12; operability of charging pumps is verified by ensuring that the pumps develop the required flowrate, as specified by the In-Service Test program.

(13;'NC. required to be performed if the reactor is subcritical.

E m

E

_ _ _ _ _ , _ _ _ _ ,,_ _ __ _

ML20125D556

Text

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