Text

Proposed Tech Specs,Revising Surveillance Frequency for RTS & ESFAS Analog Instrumentation Channels & Modifying AOT & Action Times for RTS & ESFAS Analog Instrumentation Channels & Actuation Logic
	ML20206N369
Person / Time
Site:	North Anna
Issue date:	05/06/1999
From:	; VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	;
Shared Package
ML20206N365	List: ML20206N360; ML20206N369;
References
	NUDOCS 9905170207
	Download: ML20206N369 (125)
	v • d • e

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l Attachment 2 l

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Mark up of Technical Specifications Units 1 and 2 l

Virginia Electric and Fewer Comr$2ny North Anna Power Station Units 1 and 2

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332 INSTRUMENTATION 3/4.3,1 REACTOR TRIP SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION (tenrAanin) .

3.3.1.1/ As a minimum, the reactor trip system instrumentation channels and interlocks of Table 3.3-1 shall be OPERABLE. J l APPLICABILITY: As shown in Table 3.3-1.

ACTION:

As shown in Table 3.3-1. l 1

g W A .4.%IE i SURVEILLANCE REQUIREMENTS P' D - v l 4.3.1.1.1 Each reactor trip system instrumentation channe shall be demonstrated OPERABLE by the performance of the,CM.*}NEL C"CE, CH^FNEL C^r mpgrow ma giyuri ruNcrioyi16 cst b...;m-,(m.+ " - e a - -

f g nd . ~; n ble4.3-1.

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4.3.1.1.2 The !cg:: fer me i-ter!8s ~" M d*=^aF'e='Fd OPtFMIT p~rine 'n *=<-h raartar 5""'2p ""!"E 5 pad ^'"*d d""i"_g !.h* pr*"**di"; 0"> A ayc _ Th. ental 'neerlart f,,nacimn chall h.

demc=:=::d OPERABLE :: ::=: cn= p : 18 =::S: du-ing Ci-L*.""EL C ^.LSPJ. TION te:&g cf e29. 9-*! effer'ed by i "'*-la t apar='ian 2

4.3.1.1 The REACTOR TRIP SYSTEM RESPONSE TIME of each reactor trip function shall be demonstrated to be within its limit at least once per 18 monthr Neutron detectors are exempt >

from response time testing. Response of the neutron flux signal portion of the channel time shall ( l be measured from the detector output or input of the first electronic component in the channel. E Each test shall include at least one logic train such that both logic trains are tested at least once per 36 months and one channel per function such that all channels are tested at least once every N times 18 months where N is the total number of redundant channels in a specific reactor trip function as shown in the " Total No. of Channels" column of Table 3.3 1. {

NORTH ANNA - UNIT 1 3/4 3-1 Amendment No.487-

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30-97 y TABLE 3.3-1 (Continued) )

l TABLE NOTATION With the reactor trip system breakers in the closed position and the control rod drive system O '"

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"* With the Reactor Trip Breaker open for surveillance testing in accordance with Specification Table 4.3-1 (item 21 A).

The provisions of Specification 3.0.4 are not applicable.

1. High voltage to detector may be de-energized above the P-6x s e/Po N.

1. 1. Below the P-10 (Low Setpoint Power Range Neutron Flux Interlock)[etpoint. l ACTION STATEMENTS ACTION 1 - With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, be in HOT STANDBY within 6 hour6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months s: however, one channel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance I testing per Specification 4.3.1.1.1 provided the other channel isglej ACTION 2 - With the number of OPERABLE channels one less than the Total Number of Channels STARTUP and POWER OPERATION may proceed provided the following conditions are satisfied:

( w aa n . ( 17

"** W S P"W a. The inoperable channel is placed in the tripped condition within hour

& op e 4 ws 4 c+ J b. The Minimum Channels OPERABLE requirement is met however, the i

wa.at..<, 4M . inoperable channel may be bypassed for up to Yhnurt for surveillance

",') N testing of the redundant channel (s) per Specification 4.3.1.1.1. T[

aA A b't c. Either. THERMAL POWER is restricted to 5 75% of RATED THERMAL

" N t" d'd POWER and the Power RangegNeutron Flux trip setpoint is reduced to I

' " I 5 85% of RATED THERMAL POWER withinfhours: 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 .

l

d. The QUADRANT POWER TILT RATIO shall be determined to be within ,

the limit when above 75 percent of RATED THERMAL POWER with one l Power Range Channel inoperable by using the moveable incore detectors to confirm that the normalized symmetric power distribution, obtained from 2 i sets of 4 symmetric thimble locations or a full-core flux map, is consistent with the indicated QUADRANT POWER TILT RATIO at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

ACTION 3 - With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement and with the THERMAL POWER level:

NORTH ANNA - UNIT 1 3/43-5 Amendment No. 84r206-

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27 0 ^7 g TABLE 33-1 (Contmued) ;

1 4 g/ '

a. Below, - ore the inoperable channel to OPERABLE status prior to increasing AL POWER above the P-6/etpoint. !

l b. Abovef , ow the P-10 setpoint, restore the inoperable channel to - -

7 OPERABLE status prior to increasing THERMAL POWER above the P-10 5 serpoint. b

c. Above the P-10 setpoint, POWER OPERATION may continue [ >

ACTION 4 - With the number of channels OPERABLE one less than required by the l l Minimum Channels OPERABLE requirement and with the THERMAL '

POWER level: ,

a. Belo store the inoperable channel to OPERABLE status prior to increasing . Af., PbWER above the P-6[etpoint.

b. Above -

on may continue.

ACTION 5 - With the number of channels OPERABLE one less than required by the I Minimum Channels OPERABLE requirement, verify compliance with the SHUTDOWN MARGIN requirements of Specification 3.1.1.1 or 3.1.1.2, as applicable, within I hour and at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter.

ACTION 6 - Not applicable.

ACTION 7 - With the number of OPERABLE channels one less than the Total Number of i Channels STARTUP and POWER OPERATION may procee ened- !

-perforenance ef $: n:-' :-~9ed CM.ASWL PJNNON At pIEST-provided

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TABLE 3.3-1 (Continued)

ACTION 9 - ith'a'Thannel aMiated with an operating loopTnocerabl .

restore the inoperable channel to OPERABLE status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or be,in HOT STAND 8Y within he next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; clelsk however, one' channel associated an operat ng loop

- may be bypassed for up to 2 s for survei ance testing 7

,er Specifjcat_ ion 4.3.1.1.1. - - -

/ able,reitore inoperable

/ ACTION 10 - With o channel ino f che to OPE status withi es or reduc

'e pet &vEb T POW o below P-8 wi n the next 2 h s.

perati, low P-8 may c nue pursuant T!0N.11.

ACTION 11 - With less than the Minimum Number of Channels OPERA 8LE.

operation may continue provided the inoperable channel is placed in the tripped condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

ACTION 12 - With the number of channels OPERABLE one less than re-guired by the Minimum Channels OPERABLE requirenent, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in HOT STANOSY within,the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , w fe :::: m ranc+a- t4 "=k ACTION 13 - With the number of channels OPERABLE one less than required ,

. by the Minimum Channels OPERABLE requirement, restore the <

inoperable channel to OPERABLE status within (1) hou'r or >

teminate testing of the Reactor Trip Breaker and open the Reactor Trip Sypass Breaker.

ACTION 14 - With onde of the diverse trip features (undervoltage or shunt [

trip device) inoperable, restore it to OPERASLE status %

within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or declare the breaker inoperable and apply j Action 1. TNe breaker shall not be bypassed while one of \

the diverse trip features is inoperable except for the time )

required for performing maintenance to restore the breaker to (

0PERASLE status.

ACTION 15 - With the number of channels OPERA 8LE one less than required f by the Minimum Channels OPERA 8LE requirement restore the \

inoperable channel to OPERA 8LE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or )

open the reactor trip breakers within the next w -. 7

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b h bi k% s&

-0444-% g TARI F 4 L1 (Cnntinaiad)

NOTATION

- With the reactor trip system breakers closed and the control rod drive system capable of rod withdrawal.

l

- - - Belowh-10 (Low Setpoint Power Range Neutron Flux Interlock)[etpoint.

(1)- If not performed in previou (2) - Heat balance only, above 15% of RATED THERMAL POWER.

(3) - Compare incore to excore axial offset above 15% of RATED THERMAL POWER.

Adjust channelif absolute difference 2 3 percent.

(4) - Manual ESF functional input check every 18 months.

(5)- Each train or logic channel shall be tested at least every 62 days on a STAGGERED TEST BASIS.

(6)- .Neintron detectors may be excluded from CHANNFI . CAT TRR ATION.

(s,i,.n.4, ( r.Aew.d. 4. r%e u. % % r 4=t.acS a4,.6 t-The CHANNEL FUNCTIONAL TEST shall independently venfy the OPERABILITY of the undervoltage and shunt trip circuits for the s/anual gactor !

Mp%nction. The test shall also verify the grability of the Bypass Breaker [ rip

~

circuit (s).

Local manual shunt trip the reactor trip bypass breaker immediately after placing 4

the bypass breaker into service, but prior to commencing reactor trip system testing ( ,

or reactor trip breaker maintenance.

Automatic undervoltage trip.

( -

The CHANNEL FUNCTIONAL TEST shall independently verify the

/ OPERABILITY of the undervoltage and shunt trip attachments of the Reactor Trip (g - fpa cry 3urveillance in Modes 3*,4* and 5* shall also include verification that Q/& Permissives P-6 and P-10 are in their required state for existing plant conditions by observation of the permissive annunciator window.

( -

Detect 6r plateau curves shall be obtained and evaluated. The provisions of Specification 4.0.4 are not applicable for entry into Mode 2 or 1.

NORTH ANNA - UNIT 1 3/4 3-14 Amendment No. S !, 25,200

^* 2 ? 9 !

INSTRUMENTATION g ENGINFFDFn SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.2.1,(jysozw&ca)

The Engineered Safety Feature Actuation System (ESFAS) instrumentation channels and interlocks shown in Table 33-3 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 33-4.

{

APPLICABILITY: As shown in Table 33-3.

ACTION-I a. With an ESFAS instrumentation channel trip setpoint less conservative than the

! value shown in the Allowable Values column of Table 33-4, declare the channel inoperable and apply the applicable ACITON requirement of Table 33-3 until the channel is testored to OPERABLE status with the trip setpoint adjusted consistent with the Trip Setpoint value.

b. With an ESFAS instrumentation channel inoperable, take the ACTION shown in Table 33-3. -

' l

/

a /cada A~ M SURVEILLANCE REQUIREMENTS fr 2,,f'ya;f c,w ,.syta sA ,

i w 4.3.2.1.1 Each ESFAS instrumentation channe(shall be demonstrated OPERABLE by the se cu m uux s r~ s s van s, urw cu s vues f 0 ,i 7g g s J C d ^ TES- Y T6 *_k O f e ;-A-s ka- in Table 43-2.

l l

4.3.2.1.2 Tac 'egk fer i L=ck-:'-: ! bc h;;m=----A Ol'LL^.BLE f ai;; 5 =^ ,. =: i l ecmadaale;ic g. rk. .m..i L er!--y fm--am- .k.n u. f: f- _ _d 3 epgn i nLg = 37,; ;,,,,,,

)

l p r 18 e-S &s; CH A=L Cir mp A_pgy .a-. eg.g u....! .u.c..g 3 u ; 79 7 _

\ n _.an.

l 3.2.

The ENGINEERED SAFETY FEATURFkRESPONSE TIME of each function shall be demonstrated to be within the limit at least once per 18 months. Each test shall include at least one logic train such that both logic tmins are tested at least once per 36 months and one channel per function such that all channels are tested at least once per N times 18 months where N is the total number of redundant channels in a specific ESFAS function as shown in the " Total No. of Channels" Column of Table 33-3.

r NORTH ANNA - UNIT 1 3/4 3-15 Amendment No. 443.467-

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U

11-io- n y TABLE 3.3-3 (Continued)

TABLE NOTATION

. Tr ip function may be blocked in this MODE below,&P-11dM'a b

" Trip function may be blocked in this MODE belowf-12,5dPN,

'h: h:nn:! b) :::::ictM "ith the ; Otecti': fun:ti;r: d r';;d 'cr th; ;.; ;f ; rvi;; ".;;;t;r C;;'.;nt L;;; ; bell te ;,le;ed in the L ipped

-m The nrau4sione af ca cification 3.0.4 are not analic e'-

pct)*t" whers e // M /*.T*f, H /Ws,~ cs.ob siteettleT6 mas wives ar,e et.a.ea _t ad e.ges4us /ect av /$olos4=e/ 4

elatrel ****s* */ v10/ sag. .

^

ION STATEMtnis e - -

N mrirum us, cA...,ets orYMatc r- Narr e.,-f ) .g,_ ,,J ACTION 13 - With the number of OPERABLE Channels'one less than th !

v ::1 Mrd: c' Ch::::' - be in HOT STANDBY within hours '

nk and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months ; however, e.w..u t 4 orcsAsut one channel may be bypassed for up tog hours for surveillance s6 hse h 24 h testing per Specification 4.3.2.1.1. _ q guw,,.cTeLce avr .

ACTION 14 - With the number of OPERAB Channels one less than the TotalNumberofChannels,y;;retienmayproceedlierti' ae-'e : ce e' the ert ==:f rM C"^"" L FL'MCT!^F_^.L TEST, pr:vid:d the 're; r d!: th:rr:1 i -'::M '- t'- t-f;;:d

nditi;n with' ' her-

=a aa--=+4=a 1aan 4aaaarmh1.

ACTION m 15 / --With a ther el =ssec4=+=d wi+h

+w. 4......w3. ,.w....i

4. mm1 - 1 e.

+

_4. 4 nornansr".+,+b, wi+w4.

.- ,-,, _4.. ,, .

N' he5,'hMdr, one -:h=nn:1 ;;;;;j;;;d Oith ;5 ; h;5'r;

-leep ir.ey be byp;;;d fr ;; t: 2 br: fr O r;;!:rt:

testing p r *,p ;ifi;etien 4.3.2 ' '

d)

ACTION 16 - With the number of OPERAB E Channels one M an the Total Number of the inoperable Channels, channel vg..i. in is placed ionthe may proceed blocked provided g*' E condition

rd th; "' ' r CMn .;i; ^";"4",L; r;,a.iin.- .; is 4.. ..-

nr;;;d .ith'n ; he.c; one additional channel may be blocked for up to i urs for surveillance testing per Specification 4.3.2.1.1. /z) sa4,&acl Mv.J J +4.< folie.unn9 c.e cll4d., e,e 1 % s sp~ Ate e L a..a t s p ts c a,4 ,, 4 ,Tr. ped toui h*on su,s.) 12 kours. $

cl ..nIs OraAmi v<.wees.~h isOr* jM

6. r% Au. ,s.

...e,<w hir e ke n.r l m.,

be t..s pssted ko we v< <, (n e surveihas 4es b$ *4 &v ek.oris e-v' r

7,, boo g JFesb 4ew 4 ' 3 ' #' ' m NORTH ANNA-UNIT l 1

?

-:--10 ^ 2 7

TABLE 13-3 (Cannauern d,k .

ACTION 17- We n of OPERABLE channels less than the T I Number of nets' l operation proceed provided the table placed in insped ;

conditen 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and the Min hannels OPE LE require is met. One '

aedition channel may be tc=_ for un to 2 H tar -'?~~'"-

e testino net l

\ San . tion 4J.2.1.1g -

With the number of OPERABLE Channels one less than the Total Number of Channels,

[ ACTION 18-restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in at least HOT STANDBY 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 followmg 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

ACTION 19- With the number of OPERA 8LE Channels one less than the Total Number of Channels, STARTUP arW POWER OPERATION may proceed provided the follownne condhons are satisfied: a f a. The inoperable channel is placed in the tripped condition within M b.

l The Minimum Channels OPERABLE requiremord is met; however, one addhenal channel may be bypassed for up to for surveillance testing per

! Specification 4J.2.1.1. !

I w e W~ '

l km ch..is cemec met mw % y ue d.a-l b omdd M*Ca 8fj ACTION 20 - With the number of OP5RA8LE Channels one less then the Teenl44mmber e6 GhanM I A tr '

in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and at least HOT SHUTDOWN within ths following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; however, on channel may be bypassed for up to hours for '

l surveillance testing per Specif~ tion 4.3.2.1.1 provided the other hannel is OPERABE. 4,, ey

! ACTION 21 - With the number of OPERA 8LE Channels one less than the Total Number of Channels t Channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in at least the ne t 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ._

t/<< Arm GA*~** /s O M'"/JG w % /

gng - at,th less f%.7ssa, . e 9 a.nna ,<.., si e, -:-, hi ,<~swe '

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~

c v v (A),ff & ,,,a, Ar< * / Ol'fMRic cAs=#ch one A ss N** /Se A"'/ A/~ O -

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of CAname/,, tr. 6a tir saopere/4 ce a.rar/ A ofLcrAete s Ms 18 4*ers o< 6a n * * ' br/ & sM a y wrtaj tk ow f g 80A3 A e ,

NORTH AP#dA-UNIT 1 3/4322 Amendment No.44,33

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TABLE 4.3-2 (Continued)

TABLE NOTATION l

(1)' Manual actuation switches shall be tested at least once per 18 months during shutdown.

7 (2) Each train or logic channel shall be functionally tested at least every d>

other 31 days ESF slave relays. up to and including input coil continuity testing to the g y (3) The CHANNEL applying either a vacuum or pressureFUNCTIONAL TEST shall include exercis transmitter. to the appropriate side of the (4) Only slave relays be functionally that do not satisfy any of, the following criteria will tested:

7

(

1. >

A single failure in the Safeguards an inadvertent RPS or ESF actuation.

Test Cabinet circuitry would cause (

2.

The test

)

system or will two oradversely more ESFasystems.

ffect two or more components in one ESF ( l 3.

The test will create a transient (reactivity, thermal, or hydraulic condition on the RCS. ,

v n .

1 g } J,, op Ms**Zd, //MW dad 'Stoodkl SVP 'I Wl"5 " 'I*##Y I ,,,s x.

sa,Ms / ,, a.isht 4 a emed ~~' *!"-

__ s p

l \

9 (g) f ,cq hsia, or /*1 i c &*"l g,, s, g,,, ,Go.,e tty /n / 9 % o d """

4 g, g rsysacre/syx

,,,,,, p c,, i can .b n u' N / -

_~ }

t NORTH ANNA - UNIT 1 3/4 3-34 Amendment No.

i 't. 3 I :STREE::TATIori Es5ES hhmeYp$igs/&,(M //fo,7u47ou J)s7t'/7 3/4.3.1 and 3/4.3.2 ""^T:0TIVdAND ENGINEERED SAFETY IN5TRUMENTATION -

7' FEATURE $A(ESFM

, The OPERA 81LITY of.the a-

'" and ES strumentation eysta.; y !

and interlocks ensure trip *will be initiated that 1) the assidiated ESF action and/or reactor '

n the parameter monitored by each channel or combination thereof d its setpoint, 2) the specified coincidence logic a--"""" O c' fficient redundancy *il-maintained to permit a enannel te be out of service for testing or maintenance and suf-ficient system functional capability is available for protec e and ESF orcoses from diverse parameters.

f- ' The OpER*EILITY of.4hese f systems is required to provide the overall I

reliability, redundanclgind diversity assumed available in the facility oesign for the protection and mitigation of accident and transient f conditions. The integrated operation of each of these systems is con- ,

sistent with the assumptions used in the accident analyses. j i

Tne surveillance requirements specified for these systems ensure '

'l tnat tne overall system functinnal capability is maintained comparable to the criginal design standards. The. periodic surveillance tests I

cer'ormed at ..

. .. requencies are sufficient to denonstrate this I cacacility. MJ rect W -

li l- 79e measurement of response time at the speci'ied frequencies

'!: :cices assuranca that the protective and ESF acti n function associated

. : each ena-nel is co-oleted viithin the time limit assume: ir. the a i:.snt analyses, fio credit was taken in the analyses for those chan-lc::lsv.ithresponsetimesindicatedasnotapplicable.

e I

i Pesecqse time may be demonstrated by any series of sequential, overlapping or total channel test measurements provided that such tests .

ceronstrate the total channel response time as defined. Sensor response time verification may be demonstrated by either 1) in place, onsite or effsite test measurements or 2) utilizing replacement sensors with certified response times.

3 '4.3.3 t'Ot:ITORING If STRUME .'TATION 3/a.3.3.1 RAD!ATION MONITORING If:STR'JMENTATION The OPERABILITY of,the radiation monitoring channels ensures that .

1) the radiation levels are continually measured in the areas served on no "I *$ ".

wa; w,sd .:. . .+,

p /

( #b

Insert A (Basis revisions)

. Add to end of third paragraph l Specific surveillance intervals and surveillance and maintenance l outage times have been determined in accordance with WCAP-l 10271, EVALUATION OF SURVEILLANCE FREQUENCIES AND OUT OF SERVICE TIMES FOR THE REACTOR TRIP INSTRUMENTATION SYSTEM, and supplements to that report, WCAP-10271 Supplement ~2, EVALUATION OF SURVEILLANCE FREQUENCIES AND OUT OF SER.VICE TIMES FOR THE ENGINEERED SAFETY FEATURES ACTUATION SYSTEM, and supplements to that report, and WCAP-14333P, PROBABILISTIC RISK ANALYSIS OF THE RPS AND ESF TEST TIMES AND COMPLETION TIMES, as approved by the NRC and documented in SERs dated February 21,1985, February 22,1989, the SSER dated l April 30,1990 for WCAP-10271 and July 15, 1998 for WCAP-14333P. '

1

. Add a new fourth paragraph:

Surveillance testing of instrument channels is routinely performed with the channel in the tripped condition. With the exception of the Power Range Neutron Flux instrument . channels, only those instrument channels with hardware permanently installed that permits bypassing without lifting a lead or installing a jumper are i routinely tested in the bypass condition. However, an inoperable i channel may be bypassed by lifting a lead or installing a jumper to l

permit surveillance testing of another instrument channel of the same functional unit.

I 1

l l

1 03-02-99 ADMINIS'IRATIVE CONTROLS Configuration Risk Manneement Program (continued)

3) Provisions for performing an assessment after entering the LCO Action Statement for unplanned entry into the LCO Action Statement.

4) Provisions for assessing the need for additional actions after the discovery of additional equipment out of service conditions while in the LCO Action Statement.

5) Provisions for considering other applicable risk significant contributors such as 12 vel 2 issue and extemal events, qualitatively or quantitatively.

Current risk-informed action statements include: Action 3.8.1.1.b; 3.4.3.2.A.2

l l \

3 3. /. / 3. 3. 2 . /

6.9_ REPORTING REOUIREMENTS - #

ROUTINE REPORTS l 6.9.1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following repons shall be submitted to the Director of the Regional Office of Inspection and Enforcement unless otherwise noted.

i STARTUP REPORTS j 6.9.1.1 A summary repon of plant stanup and power escalation testing shall be submitted following (a) receipt of an operating license, (2) amendment to the license involving a planned increase in power level. (3) installation of fuel that has a different design or has been manufactured by a ditferent fuel supplier, and (4) modifications that may have significantly altered the nuclear, '

thermal, or hydraulic performance of the plant.

6.9.1.2 The stanun repon shall address each of the tests identified in the FSAR and shall j include a description of the measured values of the operating conditions or characteristics obtained i during the test program and a comparison of these values with design predictions and specifications. Any corrective actions that were required to obtain satisfactory operation shall also be described. Any additional specific details requested in license conditions based on other commitments shall be included in this report.

6.9.1.3 Startup reports shall be submitted within (1) 90 days following completion of the startup test program,(2) 90 days following resumption or commencement of commercial power operation or (3) 9 months following initial criticality, whichever is earliest. If the Startup Report does not cover all three events (i.e.. initial criticality, completion of startup test program, and resumption or commencement of commercial power operation), supplementary reports shall be submitted at least every three months until all three events have been completed.

NORTH ANNA - UNIT 1 6-14 Amendment No. 63-M4,218

1 l

1 1

I l

l 1

l Unit 2 l

l l

=,,m,,

vv e 7 3L4J fNSTRUMENTATION 3/4,3.1 REACTOR TRIP SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.1.1(a Asr.23*maAs a minimum), the reactor trip system instrumentation channels 3.3-1 shall be OPERABLE. g APPLICABILITY: As shown in Table 3.3-1.

ACTION:

As shown in Table 3.3-1.

SURVEILLANCE REQUIREMENTS _ _ _

"b~

4.3.1.1.1 Each reactor trip system instrumentation channe hall be demonstrated OPERABLE by the performance of the,,C" ^ "'"' '""'"' "" ^ "" " ' ' ""' * *' ^" " "" ^ """'

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rin n:^"

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n: a

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--demonstret;d O"E!L'2LE ;; ;;s; ;;n p; IS m ;i: da!..g C *J!"EL C.^.LIBRATION-tc:i .; cf : 5 chr=! :ffected by :- --!9 ep--t!--

z 4.3.1.1 he REACTOR TRIP SYSTEM RESPONSE TIME of each reactor trip function shall be demonstrated to be within its limit at least once per 18 months. Neutron detectors are exempt 7 from response time testing. Response of the neutron flux signal portion of the channel time shall 4 be measured from the detector output or input of the first electronic component in trie channel. l Each test shall include at least one logic train such that both logic trains are tested at least once per 36 months and one channel per function such that all channels are tested at least once every N times 18 months where N is the total number of redundant channels in a specific reactor trip function as shown in the " Total No. of Channels" column of Table 3.3-1. 3 NORTH ANNA - UNIT 2 3/4 3-1 Amendment No. %8-

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.y TABLE 33-1(CONTINUED)

TABLE NOTATION With the reactor trip system breakers in the closed position and the control rod dnve system a

capag a

g {n: --:gp{

g -

f*c.;;r- +: w.;;; p::x = r =rx :; x::s; S ::::f =rix , ,

is s Cx'x: Ex; '" b ;!:" E S r:;;:f :xfM: , I With the Reactor Trip Breaker open for surveillance testing in accordance with Specification Table 4.3-1 (item 21 A).

The provisions of Specification 3.0.4 are not applicable.

1. High voltage to detector may be de-energized above the p P-6 (?"x'; f Sa"~ Rx;; l

_Exis T..ypsetpoint.

Below the P 10 (Low Setpoint Power Range Neutron Flux Interlock)fetpoint, g l ACTION STATEMENTS ACTION 1 - With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement)(, be in HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; however, one channel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing per Specification 4.3.1.1.1 provided the other channel is OPERABLEj !

ACTION 2 - With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and POWER OPERATION may proceed provided the m , m ...t 4 following conditions are satisfied:

p

[ ((,, a. The inoperable channel is placed in the tripped condition within ou@.

i sme.". +' ' + " *l

'+ r mek Ve b. The Minimum Channels OPERABLE requirement is met: however, the g, g,, a . inoperable channel may be bypassed for up to pours for surveillance 4,4 we * . f** A testing of the redundant channel (s) per Specification 4.3.1.1.lM y 4 , c. Either THERMAL POWER is restricted to 575% of RATED THERMAL I

POWER and the Power Range, Neutron Flux trip setpoint is reduced to 5 85% of RATED THERMAL POWER withinfhours: 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 , d.' The QUADRANT POWER TILT RATIO shall be determined to be within the limit when above 75 percent of RATED THERMAL POWER with one Power Range Channel inoperable by using the movable incore detectors to confirm that the normalized symmetric power distribution, obtained from 2 sets of 4 symmetric thimble locations or a full-core flux map, is consistent with the indicated QUADRANT POWER TILT RATIO at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

NORTH ANNA - UNIT 2 3/43-5 Amendment No. 69,499-

Gi- 6-n TABLE 3.3-1 (CONTINUED)

ACTION 3 - With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement and with the THERM AL POWER level:

a.

Below the P-6. L vi 5vmu Roup R~u. Togetpoint. restore the inoperable channel to OPERABLE status pnor to incressms THERM AL POWER above the P-6/etpoint.

b. Above the P-6 La viSuu.ws R.ur Re.mv. Togetpoint but below the -">

P 10 setpoint. restore the inoperable channel to OPERABLE status pnor to increasing THERMAL POWER above the P-10 setpoint. 2 c.

Above the P 10 setpoint. POWER OPERATION may contmuey (

ACTION 4 -

With the number of channels OPERABLE one less than required by thp

' Minimum Channels OPERABLE requirement and with the THERMAL; POWER level:

a. Belo 6/B!; L vi L..u Roup R6.um Toy)setpoint. restore the !

inoperable channel to OPERABLE status prior to increasing THERMAL :

POWE above the P-6[etpoint.

b. Abov -6p (Elsk of ";;;n R ..g "..ner T..y'setpoint. operation may continue.

ACTION 5 -

{

With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement. verify compliance with the j

SHUTDOWN MARGIN requirements of Specification 3.1.1.1 or 3.1.1.2. as applicable. within I hour and at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter.

ACTION 6 - Not applicable.

ACTION 7 -

With the number of OPERABLE channels one less than the Total Number of Channels. STARTUP and POWER OPERATION may proceed '

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NORTH ANNA - UNIT 2 3/43-6 Amendment No.-ttt-2, 9 ,p,,,y , ,.L. .,t.5 pt <,4 m tk b,pp.: e..g, .a,.., j,;, 9, g,,,,,

b. T4 e d. cL..,., (s OPEcA8LC r<1u.eeeeest s's pe t. kwe #

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= ,

I TABLE 3.3 1 (Continued)

, ~

,,#Q ACTION 9 -

ith a channel as with'an operat loop inoperable.

restore the i rable channel to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months E status w in NOT STAND 8Y wi the next 6 home , one channel associ si with an ng loop may be ypassed for up to 2

( 5pecificatioq, Q l.1.rsf for surve ance testing per -

7 ACTION 10 - Al inoperable restore the inoperab1's channel

, OPERA 8LE status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or reduce THERMAL POWER to below the'P-8, (Slock'of Low Reactor celant Pop / low and Reactor

/ '

/ Ugge Coolant Pump,treaker Pop 4 tion) setootnt tytthin the nest'.2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months

/ OperationbelowthePg.(BlockofLowReactorCoolantPumpFlow and Reactor Coolant Pump Breaker Post 3Mn) setpoint(esy continue l- (pursuant t_o ACTION'^11.

ACTION 11 -

With less than the F11nimum Nueer of Channels OPERA 8LE. operation may continue provided the inoperable channel is placed in the j tripped condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

ACTION 12 -

With the number of channels OPERABLE one less than required by the Minimum Channels OPERA 8LE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in MOT STAllD8Y within the next 6 hour6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months sp d/;r gr. L. 7.;.;;; M; L e Le... y ACTION 13 -

With the number of channels OPERABLE one less than required byt

/

channel to OPERA 8LE status within (1) hour or terminate testing i of the Reactor Trip treaker and open the Reactor Trip Bypass N Breaker.

/

ACTION 14 - With one of the diverse trip features (undervoltage or shunt trip device) inoperable, restare it te11PERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or declare the breaker inoperable and apply Action 1.

The breaker shall not be bypassed while one of the diverse trip features is inoperable except for the time required for I performing asintenance to restore the breaker to OPERABLE status.

ACTION 15 - With the naber of channels OPERABLE one less than required by the Minteum Channels OPERABLE requirement restore the inoperable channel.to OPERA 8LE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or open the reactor /

(

trip breakers within the next hour.

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01:q TARI F 4 "4-1(CONTTNI TFD)

NOTATION

- With the reactor trip system breakers closed and the control rod drive system l capable of rod withdrawal.

Rv2 mcq...;.u.. f= &: - MP fanc'innd 'at' af 'ha cy i"jac' inn ir.p;; iv unc reactor mp oreacu a suaruusd ivi L dum:.= cf Cyd- ^P' inn 3

Below#* P- 10 (Low Setpoint Power Range Neutron Flux Interlock)fetp (1)- If not rformed in previousK (2) - Heat balance only, above 15% of RATED THERMAL POWER. Adjust channel if absolute difference >2 percent.

(3) - Compare incore to excore axial offset above 15% of RATED THERM AL POWER.

Recalibrate if absolute difference 2 3 percent. j l

(4) - Manual ESF functional input check every 18 months. l (5 ) - Each train or logic channel shall be tested at least every 62 days on a STAGGERED TEST B ASIS.

1 (6)- Neutron detectors may be excluded from CHANNEL CALIBRATION. ,

3.d m. h Aft % N 4 g T 4wI<Ir. l (71 - Below the P-6 p (Biva vi3vum Rm.e Rmsv. T etpoint.

(81 - The CH ANNEL FUNCTIONAL TEST shall independently verify the OPERABILITY of the undervoltage and shunt trip circuits for the Manual Reactor Trip Function. The test shall also verify the OPERABILITY of the Bypass Breaker trip circuit (s).

(9)- Local manual shunt trip the reactor trip bypass breaker immediately after placing ,

y the bypass breaker into service, but prior to commencing reactor trip system testing >

or reactor trip breaker maintenance. J

( 10) - Automatic undervoltage trip.

(11)- The CHANNEL FUNCTIONAL TEST shall independently verify the OPERABILITY of the undervoltage and shunt trip attachments of the Reactor Trip Br ake c afeA (12) - 3. 0 _y urveillance in Modes 3*,4* and 5* shall also include verification that frmissives P-6 and P-10 are in their required state for existing plant conditions by observation of the permissive annunciator window.

(13)- Detector plateau curves shall be obtained and evaluated. The provisions of Specification 4.0.4 are not applicable for entry into Mode 2 or 1.

l NORTH ANNA - UNIT 2 3/4 3-14 Amendment No. ! 50, ! 87,-+90-

^

S 24-N I

INSTRUMENTATION g ENGINFFnFn SAFETY FEATURE ACTUATION SYS'ITM INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.2.1 A The Engineered Safety Feature Actuation System (ESFAS) instrumentation channels and interlocks shown in Table 33-3 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 33-4. g APPLICABILTTY: As shown in Table 33-3.

ACTION:

a. With an ESFAS instnunentation channel trip setpoint less conservative than the value shown in the Allowable Values column of Table 33-4. declare the channel l inoperable and apply the applicable ACTION requirement of Table 33-3 until the channel is restored to OPERABLE status with the trip setpoint adjusted consistent with the Trip Setpoint value,

b. With an ESFAS instrumentation channel inoperable, take the ACTION shown in Table 33 3.

SURVEILLANCE REQUIREMENTS '

'l I #'#

43.2.1.1 Each ESFAS instrumentation channe shall be demonstrated OPERABLE by the

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7.__

43.2.1.

The ENGINEERED SAFETY FEATURE [ RESPONSE TIME of each E function shall be demonstrated to be within the limit at least once per 1S months. Each test shall include at least one logic train such that both logic trains are tested at least once per 36 months and one channel per function such that all channels are tested at least once per N times 18 months where N is the total number of redundant channels in a specific ESFAS function as shown in the " Total No. of Channels" Column of Table 33-3.

NORTH ANNA - UNIT 2 3/4 3-15 Amendment No. 4G7 168

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NCRTH ANNA . UNIT 2 3/4 3 21

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"21"O[

TABLE 3.3 3 (Continued)

TABLE NOTATION Trip function may be blocked in this M00E below the P-11,- (8- ruri=r

" _nu : ?'"-6 " Sf;;,- ;..;_-^':r',- setpoi nt.

N Trip function any be blocked in this MODE below the P-12.-(T !! e* a*

1 j !aj ii. d setpoint. **9 5 c" - :!(e) r rede* M " ** ^ ;--*---d"e "u--if r: d:-d :M 'rx M: :; :" n ;i:: "n- r Cr ? --- ' -- =:' 5: ;! rr ' T: t ';;r

-a eeee-The provisions of eeifientin g 1 .: ; an ---11 ema t ,

o

< or Eacr r u A~.

Isole/rd e y*it4 erm4, closedurd, me J,s,d*' AAr.a~./ aamcal/ /,p.cs s~etes are clesa./ a.,e/ e4-~

y f 16N tiAT th r.a.1 &/s GE@d/E _

mm/ hed* l ACTION 13 - ta the nunoer of OPENAsta channe i

one less than the Tot 1

^ NOT STAN08Y withi 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months I res4*n A **rr,4t- '- x fnr of and COLD 0.t5MUTDOWN r n: h.4bewithin in n theh e;h11owing f 30urs;ho however, cL. ,t jo oltunists one channel say be bypassed for up to (hours for surveillance sw t .N ze testing per Specification 4.3.2.1.1 se ':f S: : C ;r O' r n !-

k.ucs, w 4.siius y -euw ~.s *w e cao

_ f {

l ACTION 14.- With the nuncer of CPERA Channels one less than the s Total Numoer of Channels, :;;rnien may proceed @e4++-

-'

re: :" S: = t - = i r = 0"".r:'. """"!S".'. **:* , .

' ; ;;f t: tM: 'r; r r h thr ;! 1: :'*ca' d- '"e t-4;rM

= :itir ' *m'- ' "---

ACU ON 15 - -with ; cena;l n;;;in; ;;ie = nrnin; ix; 'rrrCh, ree^.;r; C; ';:;r;M :=m;? = 0."" ! :t::' : i 2'-

gl,te d

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~

12 t.;.r;; r. -:v;r, x; :==:1 r::: Stet "tM e- - r- t4 ;

1 x; ::y : i

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ACTION'16 -

ar oa % t s cree n.u

^

With the number of OPERA 8LE isannels one less W t.

Total Number of Channels,,. n re;;... say proceed provided the. inoperable channel is placed in the blocked condition and-tee "i .i c - 0.%a...% 07""_^ ^'. rn_ i : x = ' . .. i.-

nre;.; .; ;'. ' r.r; one additional channel say be ;n.:.

Blocked for us4.3.2.1.

Specification to Ed!ours . for surveillance tasting per 724.,3 F ~

Eg;$,g-

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,, g , p.7, co (, t . cLaaaei ss place =8 'a vih ~41 kes4e5 e

f LJ,

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$0rsie.tt, , ,. a%e,, a.ke**'eI3 f t S@'f 4.~5.7. ( , 7 7 /

' ~M* .

4 dew.,e L ,.,

10 0 7

TAnts s ss tr w -,e ele lt k ACTION 17- tth the numbe of OPERABLE ' one less than N' otal Number of Chaonels operation proceed provided inoperable condition is placed in the '

i hour and the Channels OP LE requirement addition channel may be t. One i for up to rs for surveilla testin0 per Specif' tion 4.3.2.1.1.

3 ACTION 18 -

With the number of OPERABLE Channels one less than the Total Number of Channl restore the moperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in at least '

HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN withm the foll hours.

ACTION 19 -

W)th thea number of OPERABLE Channels one less than the Total Num STARTUP l POWER OPERATION may proceed prowded the tonowmg condehons are satisfied:

I a.

~41 The inoperable channel is placed in the tripped condition within f 1 b.

The Minimum Channels OPERABLE requirement is met: however, one additional l channel may be bypassed for up to hours for surveillance testing per Specification 4.3.2.1.1.

v ^

&a. Cknasi?CFOM6LL ry.e.,ed res Q L o,s,Lle. cLs wl L OFerAslL sMa w.*_

ACTION 20 -

With the number of OPERABLE Channels one less than Cr 1::

in at least HOT STANDBY within hours, and at least HOT SHUTDOWN within M4 i :MI !

following 6 hour6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months s: however, one channel may be bypassed for up hours for surveillance testing per Specif tion 4.3.2.1.1 provided the othe M nnel is a.n f ACTION 21 -

With the number of OPERABLE Channels one less than the Total Number of Channels, restore the inoperable Channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in at least HOT STANDBY following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months --

and in at least HOT SHUTD

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i-t 9-7-65 TABLE 4.3-2 (Continued)

TABLE NOTATION (1)' Manual actuation switches shall be tested at least once per 18 months during shutdown.

(2) Each train or logic channel shall be functionally tested at least every other 31 days up to and including input coil continuity testing to the ESF slave relays. I (3) The CHANNEL applying eitherFUNCTIONAL TEST shall include exercising the transmitter by I a vacuum or pressure to the appropriate side of the transmitter, 1 j

(4) Only slave relays be functionally that do not satisfy any of the following criteria will tested:

i

1. '

A single failure in the Safeguards Test Cabinet circuitry would cause an inadvertent RPS or ESF actuation.

2. The test will adversely affect two or more components in one ESF I system or two or more ESF systems.

(

3.

The test will create a transient (reactivity, thermal, or hydraulic) cond] _

. % ,,.,- s , , , a a n ,, e ,n a u ~.. 4 4m '~ c" f

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NORTH ANNA - UP.IT 2 3/4 3-37 Amendment No. let-I I

l

i

\..

3/4.3 INSTRtMENTATION 8ASES pewcree.-rnp Mem @) AcnumM Syneef 3/4.3.1 and 3/4.3.2 INa1RUMNTATION : i Q4 AND ENGINEERED SAFETY FEAT 1JRES dE5Fes)

/'

R f'4 1Q TheOPERASILITYoftheprotectiveandE58tnstrumentationsystenpand interlocks ensure that 1) the associated ESF action and/or reactor trfp will be initiated when the parameter monitored by each channel or combination thereef reaches its setpoi 2) the specified coincidence logic 4e ==4aMia % &

ufficient redundancy intained to pemit a channel to be out of service f tasting or asintenance available for protective d M sufficient system functional capability is ESF rposes from diverse pareseters.

OPERA 8ILITY of these systems is required to provide the overall reliability, redundancy and diversity assumed available in the facility design j for the protection and mitigation of accident and transient conditions. The integrated operation of each of these systems is consistent with the assumptions used in the accident analyses.

The surveillance requirements specified for these systems ensure that the overall system functional capability is saintained comparable to the original design standards. The periodic surveillance tests performed a th- = W ="-

frequencies are sufficient to demonstrata this capability. pIuscer'A' The seasurement of response time at the specified frequencies provides l assurance tnat the protective and E5F action function associated with each channel is Completed within the time limit assuked in the accident analyses.

No credit was taken in the analyses for those channels with response times indicated as not applicable.

Response time may be demonstrated by any series of sequential, overlapping or total channel test osasurements provided that such tests demonstrate the {

j total channel response time as defined. Sensor response time verification may ;

be demonstrated by either 1) in place, onsite or offsite test measurements or ;

2) utilizing replacement sensors with certified response times. .

I 3/4.3.3 MONITORING INSTRUMENTATION 3/4.3.3.1 RADIATION NONITORING INSTRUMENTATION The OPERASILITY of the radiation monitoring channels ensures that 1) the radiation levels are continually measured in the areas served by the individual channels level trip and 2) theisalam setpoint ex or automatic action is initiated when the radiation w e

( (g s -..A . ., s- . ,n n h \~ t i ' a % ' ' ' \

( m a eu answa _

NORTH ANNA - UNIT 2

- w ^ u% "

8 3/4 3-1

\

I

Insert A (Basis revisions)

. Add to end of third paragraph Specific surveillance intervals and surveillance and maintenance outage times have been determined in accordance with WCAP-10271, EVALUATION OF SURVEILLANCE FREQUENCIES AND OUT OF SERVICE TIMES FOR THE REACTOR TRIP INSTRUMENTATION SYSTEM, and supplements to that report, WCAP-10271 Supplement 2, EVALUATION OF SURVEILLANCE FREQUENCIES AND OUT OF SERVICE TIMES FOR THE ENGINEERED SAFETY FEATURES ACTUATION SYSTEM, and supplements to that report, and WCAP-14333P, PROBABILISTIC RISK ANALYSIS OF THE RPS AND ESF TEST TIMES AND COMPLETION TIMES, as approved by the NRC and documented in SERs dated February 21,1985, February 22,1989, the SSER dated April 30,1990 for WCAP-10271 and July 15, 1998 for WCAP-14333P.

. Add a new fourth paragraph:

Surveillance testing of instrument channels it, routinely performed with the channel in the tripped condition. With the exception of the Power Range Neutron Flux instrument channels, only those instrument channels with hardware permanently installed that permits bypassing without lifting a lead or installing a jumper are routinely tested in the bypass condition. However, an inoperable channel may be bypassed by lifting a lead or installing a jumper to permit surveillance testing of another instrument channel of the same functional unit.

1 1

l

r i 03-02-99

. ADMINIS'_IRATIVE CONTROLS l Confieuration Risk Management Program (continued)

3) Provisions for performing an assessment after entering the LCO Action Statement for unplanned entry into the LCO Action Statement.

4) Provisions for assessing the need for additional actions after the discovery of additional equipment out of service conditions while in the LCO Action Statement.

5) Provisions for considering other applicable risk significant contributors such as level 2 issue and external events, qualitatively or quantitatively.

Current risk-informed action statements include: Action 3.8.1.1.b; 3.4.3.2.A.2

l 6.9 Y

~ REPORTING REQUIREMENTS i 3.3.l.1 j 3.3.2* l l ROUTINE REPORTS 6.9.1 in addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following repons shall be submitted to the Director of the Regional Office of Inspection and Enforcement unless otherwise noted.

STARTUP REPORTS 6.9.1.1 A summary report of plant startup and power escalation testing shall be submitted following (a) receipt of an operating license, (2) amendment to the license involving a planned increase in power level, (3) installation of fuel that has a different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the plant.

l NORTH ANNA - UNIT 2 6-14d Amendment No. 4,114, ^5, l 199

Attachment 3 l

l l

Proposed Technical Specifications Changes Units 1 and 2 1

1 Virginia Electric and Power Company North Anna Power Station Units 1 and 2 1

Unit 1 i

3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION i 3.3.1.1 (Risk-Informed) As a minimum, the reactor trip system instrumentation channels and l

interlocks of Table 3.3-1 shall be OPERABLE.

APPLICABILITY: As shown in Table 3.3-1.

ACTION:

As shown in Table 3.3-1.

SURVEILLANCE REQUIREMENTS 4.3.1.1.1 Each reactor trip system instrumentation channel, interlock, and the automatic trip logic shall be demonstrated OPERABLE by the performance of the Reactor Trip System l

l Instrumentation Surveillance Requirements specified in Table 4.3-1.

I 1

4.3.1.1.2 The REACTOR TRIP SYSTEM RESPONSE TIME of each reactor trip function shall be demonstrated to be within its limit at least once per 18 months. Neutron detectors are exempt from response time testing. Response of the neutron flux signal portion of the channel time shall be measured from the detector output or input of the first electronic component in the channel. Each )

test shall include at least one logic train such that both logic trains are tested at least once per 36 months and one channel per function such that all channels are tested at least once every N times 18 months where N is the total number of redundant channels in a specific reactor trip function as shown in the " Total No. of Channels" column of Table 3.3-1.

l l

NORTli ANNA - UNIT 1 3/43-1 Amendment No. +M,

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TABLE NOTATION With the reactor trip system breakers in the closed position and the control rod drive system capable of rod withdrawal.

Below the P-6 (Intermediate Range Neutron Flux) setpoint. l l With the Reactor Trip Breaker open for surveillance testing in accordance with l Specification Table 4.3-1 (item 21 A).

The provisions of Sprification 3.0.4 are not applicable.

1. High voltage to detector may be de-energized above the P-6 setpoint.

1. 1. Below the P-10 (Low Setpoint Power Range Neutron Flux Interlock) setpoint.

ACTION STATEMENTS ACTION 1 - With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, be in HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; however, one channel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing per Specification 4.3.1.1.1 provided the other channel is OPERABLE.

l One channel may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for concurrent surveillance testing of the reactor trip breaker and automatic trip logic, provided the other !

channel is OPERABLE. l ACTION 2 - With the number of OPERABLE channels one less than the Total Number of l l

Channels, STARTUP and POWER OPERATION may proceed provided the following conditions are satisfied:

a. The inoperable channel is placed in the tripped condition within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months . l

b. The Minimum Channels OPERABLE requirement is ' pet; however, the l inoperable channel may be bypassed for up to 12 hov. ior surveMance l testing of the redundant channel (s) per Specification 4.3.1.1.1. ;

c. Either, THERMAL POWER is restricted to 5 75% of RATED THERMAL POWER and the Power Range Neutron Flux trip setpoint is reduced to s 85% of RATED THERMAL POWER within 78 hours9.027778e-4 days 0.0217 hours 1.289683e-4 weeks 2.9679e-5 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 .

d. The QUADRANT POWER TILT RATIO shall be determined to be within the limit when above 75 percent of RATED THERMAL POWER with one Power Range Channel inoperable by using the moveable incore detectors to i confirm that the normalized symmetric power distribution, ootained from 2 sets of 4 symmetric thimble locations or a full-core flux map, is consistent with the indicated QUADRANT POWER TILT RATIO at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

ACTION 3 - With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement and with the THERMAL l POWER level:

NORTH ANNA - UNIT 1 3/43-5 Amendment No.84-206,

TABLE 3.3-1 (Continued)

! a. Below the P-6 setpoint, restore the inoperable channel to OPERABLE status

prior to increasing THERMAL POWER above the P-6 setpoint.

b. Above the P-6 setpoint, but below the P-10 setpoint, restore the inoperable l channel to OPERABLE status prior to increasing THERM AL POWER above the P-10 setpoint.

c. Above the P-10 setpoint, POWER OPERATION may continue. l ACTION 4 - With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement and with the THERMAL POWER level:

a. Below the P-6 setpoint, restore the inoperable channel to OPERABLE status prior to increasing THERMAL POWER above the P-6 setpoint.

b. Above the P-6 setpoint, operation may continue.

ACTION 5 - With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, verify compliance with the SHUTDOWN MARGIN requirements of Specification 3.1.1.1 or 3.1.1.2, as applicable, within I hour and at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter.

ACTION 6 - Not applicable.

ACTION 7 - With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and POWER OPERATION may proceed provided the following conditions are satisfied:

a. The inoperable channel is placed in the tripped condition within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

b. The Minimum Channels OPERABLE requirement is met; however, the ,

inoperable channel may be bypassed for up to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for surveillance j testing of other channels per Specification 4.3.1,1.

If the conditions are not satisfied in the time permitted, place the unit in HOT STANDBY in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , HOT SHUTDOWN within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and COLD

, SHUTDOWN in the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

ACTION 8 - With the number of OPERABLE channels one less than the Total Number of i Channels, STARTUP and POWER OPERATION may proceed provided the following conditions are satisfied:

a. The inoperable channel is placed in the tripped condition within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

b. The Minimum Channels OPERABLE requirement is met; however, the inoperable channel may be bypassed for up to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for surveillance testing of other channels per Specification 4.3.1.1.

If the conditions are not satisfied in the time permitted, reduce power to less l l than the P-7 setpoint in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

NORTH ANNA - UNIT 1 3/4 3-6 Amendment No. -206, o

I TABLE 3.3-1 (Continued)

ACTION 9 - With the number of channels OPERABLE less than the Total Number of Channels OPERABLE requirement, STARTUP and POWER OPERATION may proceed provided the inoperable channel is placed in the tripped condition within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months and the Minimum Charnels OPERABLE requirement is met, or reduce power to less than the P-8 setpoint in the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

ACTION 10 - Deleted ACTION 11 - With less than the Minimum Number of Channels OPERABLE, operation may continue provided the inoperable channel is placed in the tripped condition within I hour.

ACTION 12 - With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

l ACTION 13 - With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within (1) hour or terminate testing of the Reactor Trip Breaker and open the Reactor Trip Bypass Breaker.

ACTION 14 - With one of the diverse trip features (undervoltage or shunt trip device) inoperable, restore it to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or declare the breaker inoperable and apply Action !.The breaker shall not be bypassed while one of the diverse trip features is inoperable except for the time required for performing maintenance to restore the breaker to OPERABLE status.

ACTION 15 - With the number of channels OPERABLE one less than required by the '

Minimum Channels OPERABLE requirement restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or open the reactor trip breakers within the next hour. I ACTION 16 - With the number of channels OPERABLE one less that required by the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; however, one channel may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing per Specification 4.3.1.1, provided the other channel is OPERABLE.

ACTION 17 - With less than the Minimum Channels OPERABLE, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months determine by observation of the associated permissive annunciator window (s) that the interlock (s) is in its required state for the existing plant conditions or apply Specification 3.0.3. ]

l NORTH ANNA - UNIT 1 3/43-7 Amendment No. M,

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NOTATION

- With the reactor trip system breakers closed and the control rod drive system capable of rod withdrawal.

- - - Below the P-10 (Low Setpoint Power Range Neutron Flux Interlock) setpoint.

(1)- If not performed in previous 31 days.

(2) - licat balance only, above 15% of RATED TilERMAL POWER.

(3) - Compare incore to excore axial offset above 15% of RATED THERMAL POWER.

Adjust channel if absolute difference 2 3 percent.

(4) - Manual ESF functional input check every 18 months.

(5) - Each train or logic channel shall be tested at least every 62 days on a STAGGERED TEST B ASIS.

(6) - Neutron detectors may be excluded from CHANNEL CALIBRATION.

(7) - Below the P-6 (Intermediate Range Neutron Flux Interlock) setpoint.

(8) - The CHANNEL FUNCTIONAL TEST shall independently verify the OPERABILITY of the undervoltage and shunt trip circuits for the Manual Reactor Trip Function. The test shall also verify the OPERABILITY of the Bypass Breaker trip circuit (s).

(9) - Local manual shunt trip the reactor trip bypass breaker immediately after placing the bypass breaker into service, but prior to commencing reactor trip system testing or reactor trip breaker maintenance.

(10) - Automatic unden'oltage trip.

(11)- The CHANNEL FUNCTIONAL TEST shall independently verify the OPERABILITY of the undervoltage and shunt trip attachments of the ReactorTrip Breakers.

(12)- Quarterly Surveillance in Modes 3*,4* and 5* shall also include verification that l Permissives P-6 and P-10 are in their required state for existing plant conditions by observation of the permissive annunciator window.

(13) - Detector plateau curves shall be obtained and evaluated. The provisions of l Specification 4.0.4 are not applicable for entry into Mode 2 or 1.

NORTH ANNA - UNIT 1 3/4 3-14 Amendment No. Si,206,209,

INSTRUMENTATION 3/4.3.2 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.2.1 (Risk Informed)The Engineered Safety Feature Actuation System (ESFAS) l instrumentation channels and interlocks shown in Table 3.3-3 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3-4.

l APPLICABILITY: As shown in Table 3.3-3.

ACTION:

a. With an ESFAS instrumentation channel trip setpoint less conservative than the value shown in the Allowable Values column of Table 3.3-4, declare the channel inoperable and apply the applicable ACTION requirement of Table 3.3-3 until the channel is restored to OPERABLE status with the trip setpoint adjusted consistent with the Trip Setpoint value.

b. With an ESFAS instrumentation channel inoperable, take the ACTION shown in Table 3.3-3.

SURVEILLANCE REQUIREMENTS 4.3.2.1.1 Each ESFAS instrumentation channel, interlock, and the automatic actuation logic and relays shall be demonstrated OPERABLE by the performance of the Engineered Safety Features Actuation System instrumentation surveillance requirements specified in Table 4.3-2.

l 4.3.2.1.2 The ENGINEERED S AFETY FEATURE RESPONSE TIME of each ESFAS function l

shall be demonstrated to be within the limit at least once per 18 months. Each test shall include at least one logic train such that both logic trains are tested at least once per 36 months and one channel per function such that all channels are tested at least once per N times 18 months where N is the total number of redundant channels in a specific ESFAS function as shown in the " Total No.

of Channels" Column of Table 3.3-3.

NORTH ANNA - UNIT I 3/4 3-15 Amendment No. 123,187,

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TABLE 3.3-3 (Coruinued) l TABLE NGi ATION 1

L #

Trip function may be blocked in this MODE below the P-11 setpoint.

l Trip function may be blocked in this MODE below the P-12 setpoint.

Except when all MFIVs, MFRVs, and associated bypass valves are closed and de-activated or isolated by a closed manual valve.

l

The provisions of Specification 3.0.4 are not applicable.

ACTION STATEMENTS ACTION 13 - With the number of OPERABLE Channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in HOT STANDBY 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 following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months ; however, one channel may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing per l Specification 4.3.2.1.1.

ACTION 14 - With the number of OPERABLE Channels one less than the Total Number of Channels, STARTUP and POWER OPERATION may proceed provided the following conditions are satisfied:

a. The inoperable channel is placed in the tripped condition within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

L b. The Minimum Channels OPERABLE requirement is met; however, the inoperable channel may be bypassed for up to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for surveillance testing of other channels per Specification 4.3.2.1.

ACTION 15 - Deleted ACTION 16- With the number of OPERABLE Channels one less than the Total Number of l Channels, STARTUP and POWER OPERATION may proceed provided the !

inoperable channel is placed in the blocked condition within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ; one additional channel may be blocked for up to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for surveillance testing l per Specification 4.3.2.1.1.

l l

I 1

NORTH ANNA - UNIT 1 3/4 3-21

TABLE 3.3-3 (Continued)

ACTION 17 - With the number of OPERABLE channels one less than the Total Number of Channels, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

ACTION 18 - With the number of OPERABLE Channels one less than the Total Number of Channels, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in at least HOT STANDBY 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 following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

ACTION 19 - With the number of OPERABLE Channels one less than the Total Number of Channels, STARTUP and POWER OPERATION may proceed provided the l following conditions are satisfied:

a. The inoperable channel is placed in the tripped condition within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months . l

b. The Minimum Channels OPERABLE requirement is met; however, one additional channel may be bypassed for up to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for surveillance l l testing per Specification 4.3.2.1.1.

ACTION 20 - With the number of OPERABLE Channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to )

OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; however, one channel may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing per Specification 4.3.2.1.1 provided the other Channel is OPERABLE.

ACTION 21 - With the number of OPERABLE Channels one less than the Total Number of Channels, restore the inoperable Channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

ACTION 22 - With less than the Minimum Channels OPERABLE, within I hour deterrnine by observation of the associated permissive annunciator window (s) that the interlock (s) is in its required state for the existing plant condition or apply Specification 3.0.3.

NORTH ANNA - UNIT 1 3/4 3-22 Amendment No. 15,33,165,

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TABLE 4.3-2 (Continued)

TABLE NOTATION i

{

Except when all MFIVs, MFRVs and associated bypass valves are closed and deactivated or isolated by a closed manual valve.

]

(1) Manual actuation switches shall be tested at least once per 18 months during shutdown.

(2) Each train or logic channel shall be functionally tested at least every other 31 days up to and including input coil continuity testing to the ESF slave relays.

(3) The CH ANNEL FUNCTION AL TEST shall include exercising the transmitter by applying either a vacuum or pressure to the appropriate side of the transmitter.

(4) Only slave relays that do not satisfy any of the following criteria will be functionally tested:

1. A single failure in the Safeguards Test Cabinet circuitry would cause an inadvertent RPS or ESF actuation.

2. The test will adversely affect two or more components in one ESF system or two or more ESF systems.

3. The test will create a transient (reactivity, thermal, or hydraulic) condition on the RCS.

(5) Each train or logic channel shall be functionally tested up to and including input coil continuity testing to the ESF slave relays.

l l

NORTH ANNA - UNIT 1 3/4 3-34 Amendment No. B3,

3/4.3 INSTRUMENTATION BASES 3/4.3.1 and 3/4.3.2 REACTOR TRIP SYSTEM (RTS) AND ENGINEERED SAFETY FEATURE ACTUATION SYSTEM (ESFAS) INSTRUMENTATION 1

The OPERABILITY of the RTS and ESFAS instrumentation and interlocks ensure that

1) the associated ESF action and/or reactor trip will be initiated when the parameter monitored by l each channel or combination thereof reaches its setpoint,2) the specified coincidence logic and sufficient redundancy are maintained to permit a channel to be out of service for testing or maintenance consistent with maintaining an appropriate level of reliability of the RTS and ESFAS instrumentation and interlocks, and 3) sufficient system functional capability is available for protective and ESF purposes from diverse parameters. 1 The OPERABILITY of these systems is required to provide the overall reliability, redundancy and diversity assumed available in the facility design for the protection and mitigation l of accident and transient conditions. The integrated operation of each of these systems is consistent with the assumptions used in the accident analyses.

The surveillance requirements specified for these systems ensure that the overall system functional capability is maintained comparable to the original design standards. The periodic surveillance tests performed at the minimum frequencies are sufficient to demonstrate this capability. Specific surveillance intervals and surveillance and maintenance outage times have i been determined in accordance with WCAP-10271, " Evaluation of Surveillance Frequencies and Out of Service Times for the Reactor Trip Instrumentation System," and supplements to that report, WCAP-10271 Supplement 2 " Evaluation of Surveillance Frequencies and Out of Service Times i for the Engineered Safety Features Actuation System," and supplements to that report, and WCAP- l 14333P,"Probabilistic Risk Analysis of the RPS and ESF Test Times and Completion Times," as approved by the NRC and documented in SERs dated February 21,1985, February 22,1989, the SSER dated April 30,1990 for WCAP-10271 and July 15,1998 for the WCAP-14333P.

Surveillance testing ofinstrument channels is routinely performed with the channel in the tripped condition. With the exception of the Power Range Neutron Flux instrument channels, only thow instrument channels with hardware permanently installed that permits bypassing without lifting a lead or installing a jumper are routinely tested in the bypass condition. However, an inoperable channel may be bypassed by lifting a lead or installing ajumper to permit surveillance testing of another instrument channel of the same functional unit.

The measurement of response time at the specified frequencies provides assurance that the protective and ESF action function associated with each channel is completed within the time limit assumed in the accident analyses. No credit was taken in the analyses for those channels with response times indicated as not applicable.

NORTH ANNA - UNIT 1 B 3/4 3-1 Amendment No.

I 1

l

I t

3/4.3 INSTRUMENTATION BASES Response time may be demonstrated by any series of sequential, overlapping or total channel test measurements provided that such tests demonstrate the total channel response time as defined. Sensor response time verification may be demonstrated by either 1) in place, onsite or offsite test measurements or 2) utilizing replacement sensors with certified response times.

l 3/4.3.3 MONITORING INSTRUMENTATION 1

l 3/4.3.3.1 RADIATION MONITORING INSTRUMENTATION The OPERABILITY of the radiation monitoring channels ensures that 1) the radiation levels are continually measured in the areas served by the individual channels and 2) the alarm or automatic action is initiated when the radiation level trip setpoint is exceeded.

1 1

1 NORTH ANNA - UNIT I B 3/4 3-la Amendment No. !

i INSTRUMENTATION BASES 3/4.3.3.2 MOVABLE INCORE DETECTORS j i

The OPERABILITY of the movable incore detectors with the .specified minimum complement of equipment ensures that the measurements obtained from use of this system accurately represent the spatial neutron flux distribution of the reactor core. The OPERABILITY of this system is demonstrated by irradiating each detector used and normalizing its respective output.

For the purpose of measuring qF (Z) or Fh a full incore flux map is used. Quarter-core Hux maps, as defined in WCAP-8648, June 1976, may be used in recalibration of the excore neutron flux detection system, and full incore flux maps or symmetric incore thimbles may be used for monitoring the QUADRANT POWER TILT RATIO when one Power Range Channel is inoperable.

3/4.3.3.3 SEISMIC INSTRUMENTATION The OPERABILITY of the seismic instrumentation ensures that sufficient capability is available to promptly determine the magnitude of a seismic event and evaluate the response of those features important to safety. This capability is required to permit comparison of the measured response to that used in the design basis for the facility to determine if plant shutdown is required pursuant to Appendix "A" of 10 CFR Part 100. The instrumentation is generally consistent with the recommendations of Regulatory Guide 1.12 " Instrumentation for Earthquakes," April 1974.

3/4.3.3.4 METEOROLOGICAL INSTRUMENTATION The OPERABILITY of the meteorological instrumentation ensures that sufficient meteorological data is available for estimating potential radiation doses to the public as a result of routine or accidental release of radioactive materials to the atmosphere. This capability is required to evaluate the need for initiating protective measures to protect the health and safety of the public l and is consistent with the recommendations of Regulatory Guide 1.23,"Onsite Meteorological Programs," February 1972. A meteorological data collection program as described above is necessary to meet the requirements of subparagraph 50.36(a)(2) of 10 CFR Part 50, Appendix E to 10 CFR Part 50, and 10 CFR Part 51. l 3/4.3.3.5 AUXILIARY SHUTDOWN PANEL MONITORING INSTRUMENTATION The OPERABILITY of the remote shutdown instrumentation ensures that sufficient i capability is available to permit shutdown and maintenance of HOT STANDBY of the facility from locations outside of the control room. This capability is required in the event control room habitability is lost and is consistent with General Design Criterion 19 of 10 CFR 50.

NORTH ANNA - UNIT 1 B 3/4 3-2 Amendment No. 48, l

ADMINISTRATIVE CONTROLS Configuration Risk Management Program (continued)

3) Provisions for performing an assessment after entering the LCO Action Statement i for unplanned entry into the LCO Action Statement. l

4) Provisions for assessing the need for additional actions after the discovery of additional equipment out of service conditions while in the LCO Action Statement.

5) Provisions for considering other applicable risk significant contributors such as Level 2 issue and external events, qualitatively or quantitatively.

Current risk-informed action statements include: Action 3.8.1.1.b; 3.4.3.2.A.2; 3.3.1.1; 3.3.2.1 63 REPORTING REOUIREMENTS 1

ROUTINE REPORTS

6.9.1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted to the Director of the Regional Office of Inspection and Enforcement unless otherwise noted.

STARTUP REPORTS 6.9.1.1 A summary report of plant startup and power escalation testing shall be submitted following (a) receipt of an operating license, (2) amendment to the license involving a planned increase in power level,(3) installation of fuel that has a different design or has been manufactured by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, thermal, or hydraulic performance of the plant.

6.9.1.2 The startup report shall address each of the tests identified in the FSAR and shall include a description of the measured values of the operating conditions or characteristics obtained during the test program and a comparison of these values with design predictions and specifications. Any corrective actions that were required to obtain satisfactory operation shall also be described. Any additional specific details requested in license conditions based on other commitments shall be included in this report.

6.9.1.3 Startup reports shall be submitted within (1) 90 days following completion of the startup test program, (2) 90 days following resumption or commencement of commercial power operation, or (3) 9 months following initial criticality, whichever is earliest. If the Startup Report does not cover all three events (i.e., initial criticality, completion of startup test program, and resumption or commencement of commercial power operation), supplementary reports shall be l submitted at least every three months until all three events have been completed.

NORTH ANNA - UNIT I 6-14 Amendment No. 53,214,216, L

Unit 2 1

1 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.1.1 (Risk-Informed) As a minimum, the reactor trip system instrumentation channels and l interlocks of Table 3.3-1 shall be OPERABLE.

3 APPLICABILITY: As shown in Table 3.3-1.

ACTION:

As shown in Table 3.3-1.

SURVEILLANCE REQUIREMENTS 4.3.1.1.1 Each reactor trip system instrumentation channel, interlock, and the automatic trip logic shall be demonstrated OPERABLE by the performance of the Reactor Trip System Instrumentation Surveillance Requirements specified in Table 4.3-1.

4.3.1.1.2 The REACTOR TRIP SYSTEM RESPONSE TIME of each reactor trip function shall be demonstrated to be within its limit at least once per 18 months. Neutron detectors are exempt from response time testing. Response of the neutron flux signal portion of the channel time shall be measured from the detector output or input of the first electronic component in the channel. Each test shall include at least one logic train such that both logic trains are tested at least once per 36 months and one channel per function such that all channels are tested at least once every N times 18 months where N is the total number of redundant channels in a specific reactor trip function as shown in the " Total No. of Channels" column of Table 3.3-1. j I

NORTH ANNA - UNIT 2 3/4 3-1 Amendment No. MB,

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TABLE NOTATION

- With the reactor trip system breakers in the closed position and the control rod drive system capable of rod withdrawal.

Below the P-6 (Intermediate Range Neutron Flux) setpoint.

l With the Reactor Trip Breaker open for surveillance testing in accordance with Specification Table 4.3-1 (item 21 A).

The provisions of Specification 3.0.4 are not applicable.

1. High voltage to detector may be de-energized above the P-6 setpoint.

1. 1. Below the P-10 (Low Setpoint Power Range Neutron Flux Interlock) setpoint.

ACTION STATEMENTS l ACTION 1 - With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, be in HOT STANDBY within 6 l hours; however, one channel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing per Specification 4.3.1.1.1 provided the other channel is OPERABLE.

One channel may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for concurrent surveillance testing of the reactor trip breaker and automatic trip logic, provided the other channel is OPERABLE.

ACTION 2 - With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and POWER OPERATION may proceed provided the following conditions are satisfied:

a. The inoperable channel is placed in the tripped condition within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months . l

b. The Minimum Channels OPERABLE requirement is met; however, the .

inoperable channel may be bypassed for up to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for surveillance l I

testing of the redundant channel (s) per Specification 4.3.1.1.1.

c. Either, THERM AL POWER is restricted to 6 75% of RATED THERM AL l POWER and the Power Range Neutron Flux trip setpoint is reduced to s 85% of RATED THERM AL POWER within 78 hours9.027778e-4 days 0.0217 hours 1.289683e-4 weeks 2.9679e-5 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 . ,

d. The QUADRANT POWER TILT RATIO shall be determined to be within the limit when above 75 percent of RATED THERM AL POWER with one Power Range Channel inoperable by using the movable incore detectors to confirm that the normalized symmetric power distribution, obtained from 2 sets of 4 symmetric thimble locations or a full-core flux map, is consistent i with the indicated QU ADRANT POWER TILT RATIO at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

NORTH ANNA - UNIT 2 3/43-5 Amendment No. 50,187,

1 TABLE 3.3-1 (CONTINUED)

ACTION 3 - With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement and with the THERM AL POWER level:

a. Below the P-6 setpoint, restore the inoperable channel to OPERABLE status prior to increasing THERMAL POWER above the P-6 setpoint.

b. Above the P-6 setpoint, but below the P-10 setpoint, restore the inoperable channel to OPERABLE status prior to increasing TilERMAL POWER above the P-10 setpoint.

c. Above the P-10 setpoint, POWER OPERATION may continue. l ACTION 4 - With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement and with the THERMAL POWER level:

a. Below the P-6 setpoint, restore the inoperable channel to OPERABLE status prior to increasing THERMAL POWER above the P-6 setpoint.

b. Above the P-6 setpoint, operation may continue.

ACTION 5 - With the number of channels OPERABLE one less than required by the i Minimum Channels OPERABLE requirement, verify compliance with the SHUTDOWN MARGIN requirements of Specification 3.1.1.1 or 3.1.1.2, as applicable, within I hour and at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter.

ACTION 6 - Not applicable.

l ACTION 7 - With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and POWER OPERATION may proceed provided the i following conditions are satisfied:

, 1 1

a. The inoperable channel is placed in the tripped condition within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

b. The Minimum Channels OPERABLE requirement is met; however, the l inoperable channel may be bypassed for up to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for surveillance testing of other channels per Specification 4.3.1.1.

l If the conditions are not satisfied in the time permitted, place the unit in HOT STANDBY in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , HOT SHUTDOWN within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and COLD SHUTDOWN in the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

ACTION 8 - With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and POWER OPERATION may proceed provided the following conditions are satisfied:

l a. The inoperable channel is placed in the tripped condition within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

NORTil ANNA - UNIT 2 3/4 3-6 Amendment No. 4fr7, l

l t

TABLE 3.3-l(CONTINUED)

b. The Minimum Channels OPERABLE requirement is met; however, the inoperable channel may be bypassed for up to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for surveillance testing of other channels per Specification 4.3.1.1.

If the conditions are not satisfied in the time permitted, reduce power to less l than the P-7 setpoint in 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

ACTION 9 - With the number of channels OPERABLE less than the Total Number of Channels OPERABLE requirement, STARTUP and POWER OPERATION i may proceed provided the inoperable channel is placed in the tripped condition within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months and the Minimum Channels OPERABLE Requirement is met, or reduce power to less than the P-8 setpoint in the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

ACTION 10 - Deleted ACTION 11 - With less than the Minimum Number of Channels OPERABLE, operation may continue provided the inoperable channel is placed in the tripped condition l within I hour. '

ACTION 12 - With the number of channels OPERABLE one less than required by the l Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in HOT STANDBY within the next j 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . '

l ACTION 13 - With the number of channels OPERABLE one less than required by the l Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within (1) hour or terminate testing of the Reactor Trip Breaker and open the Reactor Trip Bypass Breaker.

ACTION 14 - With one of the diverse trip features (undervoltage or shunt trip device) ,

inoperable, restore it to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or declare the breaker inoperable and apply Action 1. The breaker shall not be bypassed while one of the diverse trip features is inoperable except for the time required for performing maintenance to restore the breaker to OPERABLE status.

ACTION 15 - With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or open the reactor trip breakers within the next hour.

ACTION 16 - With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , however one channel may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing per Specification 4.3.1.1, provided the other channel is OPERABLE.

ACTION 17 - With less than the Minimum Channels OPERABLE, within I hour determine by observation of the associated permissive annunciator window (s) that the interlock (s) is in its required state for the existing plant conditions or apply Specification 3.0.3.

NORTH ANNA - UNIT 2 3/43-7 Amendment No. 69,

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NOTATION l

- With the reactor trip system breakers closed and the control rod drive system capable of rod withdrawal.

l

- - - Below the P-10 (Low Setpoint Power Range Neutron Flux Interlock) setpoint.

! (1)- If not performed in previous 31 days.

(2) - Heat balance only, above 15% of RATED THERMAL POWER. Adjust channel if absolute difference >2 percent.

I (3) - Compare incore to excore axial offset above 15% of RATED THERMAL POWER.

Recalibrate if absolute difference 2 3 percent, i (4) - Manual ESF functional input check every 18 months.

l (5) - Each train or logic channel shall be tested at least every 62 days on a STAGGERED TEST BASIS.

(6) - Neutron detectors may be excluded from CHANNEL CALIB TION.

(7) - Below the P-6 (Intermediate Range Neutron Flux Interlock) so icint. l (8) - The CHANNEL FUNCTIONAL TEST shall independently verify the OPERABILITY of the undervoltage and shunt trip circuits for the Manual Reactor Trip Function.The test shall also verify the OPERABILITY of the Bypass Breaker trip circuit (s).

(9) - Local manual shunt trip the reactor trip bypass breaker immediately after placing the bypass breaker into service, but prior to cornmencing reactor trip system testing or reactor trip breaker mainterence.

(10) - Automatic undervoltage trip.

l (11)- The CHANNEL FUNCTIONAL TEST shall independently verify th.e OPERABILITY of the undervoltage and shunt trip attachments of the Reactor Trip Breakers.

(12) - Quarterly Surveillance in Modes 3*,4* and 5* shall also include verification that l

, Permissives P-6 and P-10 are in their required state for existing plant conditions by observation of the permissive annunciator window.

i

( - (13) - Detector plateau curves shall be obtained and evaluated. The provisions of l Specification 4.0.4 are not applicable for entry into Mode 2 or 1.

NORTH ANNA - UNIT 2 3/4 3-14 Amendment No. 150,187,190,

INSTRUMENTATION 3/4.3.2 ENGINEERED S AFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.2.1 (Risk-Informed) The Engineered Safety Feature Actuation System (ESFAS) l instmmentation channels and interlocks shown in Table 3.3-3 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3-4.

APPLICABILITY: As shown in Table 3.3-3.

ACTION:

a. With an ESFAS instrumentation channel trip setpoint less conservative than the value shown in the Allowable Values column of Table 3.3-4, declare the channel inoperable and apply the applicable ACTION requirement of Table 3.3-3 until the channel is restored to OPERABLE status with the trip setpoint adjusted consistent with the Trip Setpoint value.

b. With an ESFAS instrumentation channel inoperable, take the ACTION shown in Table 3.3-3.

SURVEILLANCE REQUIREMFNTS 4.3.2.1.1 Each ESFAS instrumentation channel, interlock, and the automatic actuation logic and relays shall be demonstrated OPERABLE by the performance of the Engineered Safety Features Actuation System instrumentation surveillance requirements specified in Table 4.3-2 4.3.2.1.2 The ENGINEERED S AFETY FEATURE RESPONSE TIME of each ESFAS function shall be demonstrated to be within the limit at least once per 18 months. Each test shall include at least one logic train such that both logic trains are tested at least once per 36 months and one channel per function such that all channels are tested at least once per N times 18 months where N is the total number of redundant channels in a specific ESFAS function as shown in the " Total No.

of Channels" Column of Table 3.3-3.

i l

I NORTH ANNA - UNIT 2 3/4 3-15 Amendment No. 107,168,

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. TABLE 3.3-3(Continued)

TABLE NOTATION Trip function may be blocked in this MODE below the P-1 I setpoint.

l Trip function may be blocked in this MODE below the P-12 setpoint.

Except when all MFIVs, MFRVs, and associated bypass valves are closed and de-activated or isolated by a closed manual valve.

The provisions of Specification 3.0.4 are not applicable.

i ACTION STATEMENTS l

ACTION 13 - With the number of OPERABLE Channels one less than the Minimum l Channels OPERABLE requirement, restore the inoperable channel to l OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , or be in at least HOT STANDBY within l the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months ; however, one channel may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing per Specification 4.3.2.1.1.

ACTION 14 - With the number of OPERABLE Channels one less than the Total Number of l

Channels, STARTUP and POWER OPERATION may proceed provided the ,

following conditions are satisfied: l

a. The inoperable channel is placed in the tripped condition within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

b. The Minimum Channels OPERABLE requirement is met; however, the inoperable channel may be bypassed for up to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for surveillance testing of other channels per Specification 4.3.2.1.

ACTION 15 - Deleted l ACTION 16- With the number of OPERABLE Channels one less than the Total Number of Channels, STARTUP and POWER OPERATION may proceed provided the inoperable channel is placed in the blocked condition within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ; one .

additional channel may be blocked for up to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for surveillance testing l per Specification 4.3.2.1.1.

l l

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NORTH ANNA - UNIT 2 3/4 3-22 Amendment No.

TABLE 3.3-3 (Continued)

ACTION 17 - With the number of OPERABLE channels one less than the Total Number of Channels, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

ACTION 18 - With the number of OPERABLE Channels one less than the Total Number of Channels, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in at least HOT STANDBY 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 following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

ACTION 19 - With the number of OPERABLE Channels one less than the Total Number of Channels, STARTUP and POWER OPERATION may proceed provided the l following conditions are satisfied:

I

a. The inoperable channel is placed in the tripped condition within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months . l

b. The Minimum Channels OPERABLE requirement is met; however, one additional channel may be bypassed for up to 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for surveillance l testing per Specification 4.3.2.1.1.

ACTION 20 - !

With the number of OPERABLE Channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; however one channel may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing per Specification 4.3.2.1.1 provided the other Channel is OPERABLE. '

ACTION 21 - With the number of OPERABLE Channels one less than the Total Number of j Channels, restore the inoperable Channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months I or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in at least HOT )

SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

ACTION 22 - With less than the Minimum Channels OPERABLE, within I hour determine by observation of the associated permissive annunciator window (s) that the interlock (s) is in its required state for the existing plant condition or apply Specification 3.0.3.

l NORTH ANNA - UNIT 2 3/4 3-23 Amendment No. M5,

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TABLE NOTATION

Except when all MFIVs. MFRVs and associated bypass valves are closed and deactivated or isolated by a closed manual valve.

(1) Manual actuation switches shall be tested at least once per 18 months during shutdown.

(2) Each train or logic channel shall be functionally tested at least every other 31 days up to and including input coil continuity testing to the ESF slave relays.

(3) The CHANNEL FUNCTIONAL TEST shall include exercising the transmitter by applying either a vacuum or pressure to the appropriate side of the transmitter.

(4) Only slave relays that do not satisfy any of the following criteria will be functionally tested:

1. A single failure in the Safeguards Test Cabinet circuitry would cause an inadvertent RPS or ESF actuation.

2. The test will adversely affect two or more components in one ESF system or two or more ESF systems.

3. The test will create a transient (reactivity, thermal, or hydraulic) condition on the RCS.

(5) Each train or logic channel shall be functionally tested up to and including input coil continuity testing to the ESF slave relays.

l l

l NORTH ANNA - UNIT 2 3/4 3-37 Amendment No. +07 I

)

3/4.3 INSTRUMENTATION BASES 3/4.3.1 and 3/4.3.2 REACTOR TRIP SYSTEM (RTS) AND ENGINEERED SAFETY FEATURE ACTUATION SYSTEM (ESFAS) INSTRUMENTATION The OPERABILITY of the RTS and ESFAS instrumentation and interlocks ensure that

1) the associated ESF action and/or reactor trip will be initiated when the parameter monitored by each channel or combination thereof exceeds its setpoint,2) the specified coincidence logic and sufficient redundancy are maintained to permit a channel to be out of service for testing or maintenance consistent with maintaining an appropriate level of reliability of the RTS and ESFAS instrumentation and interlocks, and 3) sufficient system functional capability is available for protective and ESF purposes from diverse parameters.

The OPERABILITY of these systems is required to provide the overall reliability, redundancy and diversity assumed available in the facility design for the protection and mitigation of accident and transient conditions. The integrated operation of each of these systems is consistent with the assumptions used in the accident analyses.

The surveillance requirements specified for these systems ensure that the overall system functional capability is maintained comparable to the original design standards. The periodic surveillance tests performed at the minimum frequencies are sufficient to demonstrate this capability. Specific surveillance intervals and surveillance and maintenance outage times have been determined in accordance with WCAP-10271," Evaluation of Surveillance Frequencies and Out of Service Times for the Reactor Trip Instrumentation System," and supplements to that report, WCAP-10271 Supplement 2 " Evaluation of Surveillance Frequencies and Out of Service Times for the Engineered Safety Features Actuation System," and supplements to that report, and WCAP-14333P,"Probabilistic Risk Analysis of the RPS and ESF Test Times and Completion Times," as approved by the NRC and documented in SERs dated February 21,1985, February 22,1989, the SSER dated April 30,1990 for WCAP-10271 and July 15,1998 for the WCAP-14333P.

Surveillance testing of instrument channels is routinely performed with the channel in the tripped condition. With the exception of the Power Range Neutron Flux instrument channels, only those instrument channels with hardware permanently installed that permits bypassing without lifting a lead or installing a jumper are routinely tested in the bypass condition. However, an inoperable channel may be bypassed by lifting a lead or installing ajumper to permit surveillance testing of another instrument channel of the same functional unit.

l !

The measurement of response time at the specified frequencies provides assurance that the protective and ESF action function associated with each channel is completed within the time limit assumed in the accident analyses. No credit was taken in the analyses for those channels with response times indicated as not applicable.

Response time may be demonstrated by any series of sequential, overlapping or total i I

channel test measurements provided that such tests demonstrate the total channel response time as defined. Sensor response time verification may be demonstrated by either 1) in place, onsite or offsite test measurements or 2) utilizing replacement sensors with certified response times.

NORTH ANNA - UNIT 2 B 3/4 3-1 Amendment No.

1

I ;

l 3/4.3 INSTRUMENTATION BASES 3/4.3.3 MONITORING INSTRUMENTATION 3/4.3.3.1 RADIATION MONITORING INSTRUMENTATION The OPERABILITY of the radiation monitoring channels ensures that 1) the radiation levels are continually measured in the areas served by the individual channels and 2) the alarm or automatic action is initiated when the radiation level trip setpoint is exceeded.

l l

NORTH ANNA - UNIT 2 B 3/4 3-la Amendment No.

2

l 1 1

l ADM!NISTRATIVE CONTROLS l

Configuration Risk Management Program (continued) l 3) Provisions for performing an assessment after entering the LCO Action Statement for unplanned entry into the LCO Action Statement.

4) Provisions for assessing the need for additional actions after the discovery of additional equipment out of service conditions while in the LCO Action Statement.

5) Provisions for considering other applicable risk significant contributors scch as Level 2 issue and external events, qualitatively or quantitatively.

l Current risk-informed action statements include: Action 3.8.1.1.b; 3.4.3.2.A.2; 3.3.1.1; I

3.3.2.I 6J REPORTING REOUIREMENTS ROUTINE REPORTS l

6.9.1 In addition to the applicable reporting requirements of Title 10, Code of Federal Regulations, the following reports shall be submitted to the Director of the Regional Office of Inspection and Enforcement unless otherwise noted.

STARTUP REPORTS _

6.9.1.1 A summary report of plant startup and power escalation testing shall be submitted following (a) receipt of an operating license, (2) amendment to the license involving a planned ,

increase in power level,(3) installation of fuel that has a different design or has been manufactured l by a different fuel supplier, and (4) modifications that may have significantly altered the nuclear, I thermal, or hydraulic performance of the plant.

l I

NORTH ANNA - UNIT 2 6-14d Amendment No. 47, l l4,105, 499,

l l

Attachment 4 1

1 I

l l

1 1

Significant Hazards Consideration l

l l

Virginia Electric and Power Cor.ipany North Anna Power Station Units 1 ind 2

1 NO SIGNIFl !AN ' HAZARDS CONSIDERATION DETERMINATION l

Virginia Electric and Power Company has reviewed the requirements of 10 CFR 50.92 as they relate to the proposed Reactor Trip System (RTS) and Engineered Safety Features Actuation System (ESFAS) Technical Specification changes for the North Anna Units 1 and 2 and determined that a significant hazards consideration is not

, involved in support of this conclusion, the following evaluation is provided.

Criterion 1 - Operation of North Anna Units 1 and 2 in accordance with the proposed license amendment does not involve a significant increase in the probability or consequences of an accident previously evaluated. The determination that the results of the proposed changes remain within acceptable criteria was established in the l SER(s) prepared for WCAP-10271, WCAP-10271 Supplement 1, WCAP-10271 l l Supplement 2, WCAP-10271 Supplement 2, Revision 1 and WCAP-14333 issued by letters dated February 21,1985, February 22,1989, April 30,1998, and July 15,1998.

Implementation of the proposed changes is expected to result in an increase in total RTS and ESFAS yearly unavailability. The proposed changes have been shown to result in a small increase in the core damage frequency (CDF) due to the combined ;

effects of increased RTS and ESFA.S unavailability and reduced inadvertent reactor trips.

The values determined by the WOG and presented in the WCAP for the increase in j CDF were verified by Brookhaven National Laboratory (BNL) as part of an audit and sensitivity analyses for the NRC Staff. Based on the small value of the increase compared to the range of uncertainty in the CDF, the increase is considered acceptable. The analysis performed by the WOG and presented in the WCAP included changes to the surveillance frequencies for the automatic actuation logic and actuation i relays and the reactor trip and bypass breakers. The overall increase in the CDF, including the changes to the surveillance frequencies for the automatic actuation logic and actuation relays and the reactor trip and bypass breakers, was approximately 6 percent. However, even with this increase, the overall CDF remains lower than the NRC safety goal of 10 4/ reactor year.

Changes to surveillance test frequencies for the RTS and ESFAS interlocks do not represent a significant reduction in testing. The currently specified test interval for interlock channels allows the surveillance requirement to be satisfied by verifying that

i. the permissive logic is in its required state using the annunciator status light. The I

surveillance as currently required only verifies the status of the permissive logic and does not address verification of channel setpoint or operability. The setpoint verification and channel operability is verified after a refueling shutdown. The definition of the l channel check includes comparison of the channel status with other channels for the same parameter. The requirement to routinely verify permissive status is a different consideration than the availability of trip or actuation channels which are required to change state on the occurrence of an event and for which the function availability is more dependent on the surveillance interval. Therefore, the change in the interlock Page 1 of 3

l i

surveillance requirement to at least once every 18 months does not represent a significant change in channel surveillance and does not involve a significant increase in ;

unavailability of the RTS and ESFAS. '

For the additional relaxations in WCAP-14333, the WOG evaluated the impact of the additional relaxation of allowed ' outage times and completion times, and action statements on core damage frequency. The change in core damage frequency is 3.1 percent for those plants with two out of three logic schemes that have not implemented l

the proposed surveillance test interval, allowed outage times, and completion times i evaluated in WCAP-10271 and its supplements. This analysis calculates a significantly lower increase in core damage frequency than the WCAP-10271 analysis calculated. l This can be attributed to more realistic maintenance intervals used in the current I analysis and crediting the AMSAC system as an alternative method of initiating the j auxiliary feedwater pumps. Therefore, the overall increase in CDF is estimated to be '

3.1% for the proposed changes per the generic Westinghouse analysis. l l

l The NRC performed an independent evaluation of the impact on core damage ;

frequency (CDF) and large early release fraction (LERF). The results of the staff's !

review indicate that the increase in core damage frequency is small (approximately 3.2%) and the large early release fraction would increase by only 4 percent for 2 out of 3 logic schemes that have not implemented the proposed surveillance test interval, allowed outage times, and completion times evaluated in WCAP-10271 and its supplements. Further, the absolute values for CDF still remain within NRC safety goals.

l Therefore, the proposed changes do not result in a significant increase in the severity l

or consequences of an accident previously evaluated. Implementation of the proposed l changes affects the probability of failure of the RTS and ESFAS but does not alter the l manner in which protection is afforded or the manner in which limiting criteria are l established. l Criterion 2 - The proposed license amendment does not create the possibility of a new or different kind of accident from any accident previously evaluated.

The proposed changes do not result in a change in the manner in which the RTS or ESFAS provide plant protection. No change is being made which alters the functioning of the RTS or ESFAS (other than in a test mode). Rather the likelihood or probability of the RTS or ESFAS functioning properly is affected as described above. Therefore, the proposed changes do not create the possibility of a new or different kind of accident as defined in the Safety Analysis Report.

The proposed changes do not involve hardware changes. Some existing instrumentation is designed to be tested in bypass and current Technical Specifications l allow testing in bypass. Testing in bypass is also recognized by IEEE Standards.

Therefore, testing in bypass has been previously approved and implementation of the

proposed changes for testing in bypass does not create the possibility of a new or Page 2 of 3

different kind of accident from any previously evaluated. Furthermore since the other proposed changes do not alter the physical operation or functioning of the RTS or ESFAS the possibility of a new or different kind of accident from any previously evaluated has not been created.

Criterion 3 - The proposed license amendment does not involve a significant reduction in a margin of safety.

The proposed changes do not alter the safety limits, limiting safety system setpoints or limiting conditions for operation. The RTS and ESFAS analog instrumentation remain operable to mitigate as assumed in the accident analysis. The impact of reduced testing other than as addressed above is to allow a longer time interval over which

, instrument uncertainties (e.g., drift) may act.

Implementation of the proposed changes is expected to result in an overall improvement in safety by less frequent testing of the RTS and ESFAS analog instruments will result in less inadvertent reactor trips and actuation of Engineered Safety Features components.

1 This analysis demonstrates that the proposed amendment to The North Anna Unit 1 and 2 Technical Specifications does not involve a significant increase in the probability or consequences of a previously evaluated accident, does not create the possibility of a new or different kind of accident and does not involve a significant reduction in a margin of safety.

l l

l l 1 Page 3 of 3 L

ML20206N369

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