ML20138P110

Proposed Tech Spec Changes to Install Automatic Shunt Trip Breaker Mod Per Generic Ltr 85-09

ML20138P110
Person / Time
Site:	Farley
Issue date:	12/16/1985
From:	ALABAMA POWER CO.
To:
Shared Package
ML20138P107	List: ML20138P105 ML20138P110
References
GL-85-09, GL-85-9, TAC-55354, TAC-55355, NUDOCS 8512240301
Download: ML20138P110 (15)

Text

{{#Wiki_filter:, y ..,= y f ^ _a g iTABLE 3.3-1 .x ] REACTOR TRIP = SYSTEM INSTD'JMENTATION- [ ,Z~ MINIMUM TGTAL N0. CHANNELS-CHANNELS ~ ^ APPLICABLE-FUNCTIONAL UNIT OF CHANNELS-TO T.< IP l OPERABLE' MODES-ACTION 1. Manual Reactor Trip 2: 1 2 1, 2 12 3*, 4*, S* 13 2. Power. Range, Neutron Flux - 2 -3 '1,:2 A'. (Hi gh - 4-2# . Low-4: 2 3 2 2# B. 3. Power Range, Heutren Flux, 4-2 3 1, 2 2# High Positive Rate 4. Power l Range, Neutron Flux, 4 2 3-1, 2 - 2# -High Negativc' Rate ,s l [ 5. Intermediate Range, Neutron 2 1 2 '1, 2, and'* 3#### _4 Fl ux - 6. Source Range, Neutron Flux A. Startup 2-1 2 2##, and

• 4 B.

Shutdown 2 -0 1### 3, 4 and 5 S-l 7. Overtemperature AT Three Loop Operation 3 '2 2 1,'2-7# 7 Two Loop Operation 3 1** 2 1, 2 9 1 8. Overpower. AT

Three Loop Operation.

3 2 2' .1, 2 7# t Two Loop Operation 3 1** 2 1, ' 2 9 3 9. Pressurizer Pressure-Low 3 2 2 1-7#

10. Pressurizer Pressure--High 3-2 2

1,.2 7# ") w l z P 8512240301 851216 [ji PDR ADOCK 05000348 3 p PDR. Lo., i

=4 -= . =. [. ,2. s (( J;;; -:J2 +, 2 TABLE 3.3-1 (Continued);. f N 4" = REACTOR TRIP-SYSTEM INSTRUMENTATION M' i g; 2 MINIMUMJ ' @' 'FUNCT10NAL UNIT-0F - CHANNELS ': .TO TRIP -OPERABLE' --TOTAL NO.i , CHANNELS. -CHANNELSj APPLICABLE-

MODES ACTION

21. ReactorfTrip' Breakers-2.1

' l' 2/ ~ 1, 2.! 1,f14' '3*, 4*','5*. 13,14

22.. ' Autom: tic' Trip Logic 2'

1: .2. 1~, 2,:and.*' .i: 4 m

9e A

~$ -g.

a 1 .. = * --m- + pg :;.c I'! [ 1 %;. ~ ' hfbN: ;&~ h ' ^; . TABLE 3.3-1"(Continued) ?w n. t h -ACTION 11,-LWith less than the Minimum Number of Channels OPERABLE, g operation may continue. provided the inoperable channel is

placed:in the tripped condition within 1 hour.

4 t - ACTION 12 - With the number of. 0PERABLE channels one less than required by the Minimum Channels. 0PERABLE requirement, restore.the. ainoperable channel to OPERABLE status within.48 hours,1-or:be in HOT' STANDBY within the next-6 hours. $a. ACTION '13 - With the. number of 0PERABLE' channels one less than required - ' inoperable" channel.to OPERABLE: status-within 48 hours, or by;the Minimum Channels ~ OPERABLE requirement, restore the' ty .open the: Reactor Trip System breakers within the next hour. - JACTION 141 IWith one. of 'the diverse. trip Lfeatures (undervoltage.or - shunt- ~ ~ ' trip attachment) inoperable, the breaker'may be considered 0PERABLE provided that the diverse trip feature is. restored ^ to OPERABLE status withins.48' hours,'or declare the breaker . inoperable and apply ACTION 1. The breaker shall not b'e 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. d' j ' b 3.- s u. w4 ~ i i 2FARLEY.- UNIT-1? 3/4 3-9 AMENDMENT NO. s us -- ., i,.. .., ;..,; -... _u.....-.

e; ~ Si" s e,. ' TABLE'4.3-l' ~ ~ ; .m z <W ~ l- , - ; REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREENTS - N~ 1.

E.

CHANNEL:

,FUNCTIONALD SURVEILLANCE-

CHANNEL MODES'IN WHICH C

CHANNEL-g- _ FUNCTIONAL' UNIT-CHECK: CALIBRATION

TEST REQUIRED-1.

Manual Reactor Trip 'N.A. -N.A.-

R(11),

^ . ' 1 ', - 2, - S/U(1)(12)

3*,;4*, S*'

J 2. Power' Range, Neutron Flux A. Hi gh' iS D(2),.M(3)~ M 1, 2' and Q(6)' B. Low-S O(2),'M(3) S/U(10)' 2 and Q(6)- ~3. Power Range, Neutron Flux, High N.A. R(6) .M' 1, ' 2 - w. 3 Positive' Rate-4. Power. Range, Neutron Flux, N.A. R(6) M 1, 2 High ;-Negativo Rate 5. Ir.termediate ' Range,-- Neutron S R(6) S/U(1) 1, 2'and-Flux / .6. Source Range,- Neutron Flux ' 'S(7) R(G) M and S/U(1). 2, 3,'4, 5, and

• 7.

OvertemperaturehT S R -M ~ 1, 2 8. OverpowerkT -S R M 1, 2 9. Pressurizer Pressure-Low S R M 1 y

10. Pressurizer Pressure--High

.S R M 1, 2 h

11. Pressurizer Water Level--High S

R M 11 'b 12. A. Loss of Flow - Single Loop - .S R M 1 B. Loss of Flow - Two Loops S-R

N.A.

1

^ s' Mb y p (. ~ [] M-c.o ( ' '^ / %~ ~ ] '~ ' f. s 1 ~ , ~ ~ e 3!. " 9.[ ? TABLE 423-IlCont1nued)- '.A ^

f; f

~ ...c j!E. 1 y.. , EACTOR. TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS,- A nR s m,' s .Cv .c $1. V 1 CHANNEL;. MODES-IN WHICH' LFUNCTIONAL' SURVEILLANCEc CHANNEL.. ..JCHANNEL'. 71 1 ' ~*: ~~' FUNCTIONAL': UNIT CHECK: -CALIBRATION: TEST REQUIRED '13. : Steam GeneratorcWater Level---

S*

.R'- .M' 1,.2~ Low-Low-1

14. : Steam /Feedwater F1ow Mismatch

- S' R: cM. 11,72. ~

and' Low. Steam Generator Water

Level . +.

15. Undervoltage - Reactor Coolant

' N. A.. R. ~'

M '

~ 1' Pumps y

16. Underfrequency. Reactor.

- N. A.' R. M 'l ~ ~ M Coolant-Pumps a T

17. Turbine Trip -

N. A. - N.A.

S/U(9)(1)

N.A.

C- .A. Low-Auto Stop 011 Pressure: B. Turbin'e Throttle-Valve ' N.A. N.A. .S/U(9)(1) .N.A. Closure

18. SafetyjInjection Input from ESF N.A..

N.A. M(4) .1', 2 -

19.. Reactor Coolant. Pump' Breaker

- N.A. N.A. R-1- Position. Trip

20. Reactor Trip $ystem Interlocks N. A. :;

.R' S/U(8) 1 ~ ~ 2

21. Reactor Trip Breaker N.A.

N.A. M(5)(14)(15), 1,:2,. j S/U(1)(14)(15) 3*,f4*, 5* 23

22. Automatic-Trip ~ Logic N.A.

? N. A.. -M(5) 1, 2, "2 - 3*,;4*, 5* r -A l '5-

23. Reactor Trip. Bypass-Breaker ~

N.A. N.A.. (13),R(11)

1, 2, 1 3*, 4*, 5*

4 11 sn vsn r-6 4 m s s

We m.. n:,y 1a $kg TABLE 4.3-1 (Continued)- d $)h TABLE NOTATION ' J-n With the reactor trip system. breakers closed and the' control' rod drive system capable of rod withdrawal. (1) -> If;not-performed:in previous 7: days'. ~ .(2)L : Heat balance only,;above 15% of RATED THERMAL! POWER. Adjust Q channel iff absolute difference is greater than 2 percent. f(3) - Compare incore to excore axial flux. difference every'31 EFPb. -Recalibrate if.the absolute difference 'is greater.than' or equal to 3 pe: cent. -(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) - :Nsutron detectors:may be excluded from CHANNEL CALIBRATION. '(7)-- Below;the-P-6 -(Block of Source Range Reactor Trip) setpoint. (8) = Logic only,iif not performed in previous 92 days. ~ (9) CHANNEL FUNCTIONAL TEST will-consist.of.. verifying that1each- ' channel indicates:a turbine trip prior to latching the-turbine and'indicatesino: turbine trip prior to P-9. - (10)'-- -If not performed in the previous 31 days. A .(11) - Independently verify OPERABILITY. of the 'undervoltage and shunt. 2 trip circuitry for;the' Manual Reactor Trip Function.. (12): ~. Verify reactor trip breaker. and reactor trip; bypass breaker?open upon ' actuation of each Main Control Board handswitch. i(13)l ELocal! manual.- shunt trip prior to placing breaker in service. Local. manual undervoitage trip prior to placing breaker in service. (14)

Under. voltage trip via Reactor Protection System.

~ l' (15) - ' Local manual. shunt trip.. ? -FARLEY:- UNIT 1 3/4 3-14 AMENDMENT N0. y o -l

+ ~. 1 g . TABLE 3.3-1: ~ x y

REACTOR-TRIP-SYSTEM INSTRUMENTATION 3'

MINIMUMi-4

P TOTAL NO.-

'CHANNELSJ CHANNELS .. APPLICABLE ro FUNCTIONAL-UNIT- '0F CHANNELS -TO TRIP' OPERABLE. MODES-1 ACTION' 1. Manual Reactor.. Trip.

2 -

1 .2 1,E 2- . 12 2-3*,-4*, 5* . 13

2..- Power Range', Neutron - Flux ~

12#. 'A. Hi gh 4' 2

3-

.1, 2 B. : Low. .4 2' ~3 2 -2# -3. Power. Range, Neutron Flux, .4 2 3 1, 2 - 2#- High Positive-Rate 4. Po'wer Range, Neutron Flux, 4 .2 3^ 1, 2 2#

High Negative Rate

'l, ,s'[ 5. Intermediate Range, Neutron 2 -1 -2 1,.2, and'*- ~ 3####- 4 Flux 6. Source Range, Nautron Flux - A. Startup 2 1 2 2##, and

• 4 B.

Shutdown 2 0 1###- 3,.4 and 5

- 5:

7.. Overtemperature. AT

.7# Three Loop Operation 3 2 2 1, 2 Two Loop Operation 3 1** 2 .1, 2 9-8. Overpower AT- ' Three Loop Operation 3L 2 2 1, 2 7#' Two Loop Operation 3 1** 2 1, 2 9 3 9. Pressurizer Pressure-Low 3 2 2 1 7#

10. Pressurizer Pressure--High 3

2 2

1, 2 7#

m-8 y t r.

= ' 'f ',? .,p_ .); : ,, -l ' -. 7 ..,7 g.g., < - = ,"f y ^ 4 _ ;Q, e,. p.. .: p .s c u + '. TABLE 5'3-1(Conti$ed)L 3. ~ ~ ,'REACTORzTRIP-SYSTEM 1 INSTRUMENTATION .^+ 2. e.- r= -- .. e .'.9,'~ K 4 .e: m. ~ -:(. ... c - 4

MINIMUM-

~ CHANNELSL ' LCHANNELS1 APPLICABLE: TOTALTNO.. ~ FUNCTIONAL UNIT 0F CHANNELS,. T -T0 TRIP.

0PERABLE.,

" MODES. -ACTIONS _ 9 y 21..; Reactor Trip Breakers'- 12-l1! 2 1,12'

1,[141 -

i 3*, 4*, 5*

13,14; -

22. ' Automatic Trip. Logic a '

.2 1; ' 2- ...1,12, and;* 1; "!O _;x ~ q,. d-s W Sh (.0 e s 4 4 es 'P h ~ G Si! .m -Z -4 2O 1 L t : tW W Y T r-m -w b

jf p

m S pigq u TABLE'3'.3-1 (Continued) - 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 1 hour. ACT10N :12 - With' the ~ number of 0PERABLE channels one less than required . by the Minimum Channels OPERABLE requirement, restore. the inoperable channel to OPERABLE status within 48 hours, or be 'in H0T STANDBY'within the next 6 hours. ACTION :13.- With the number of OPERABLE channels one less than required byJthe Minimum Channels OPERABLE requirement, restore the

inoperable ~ channel to OPERABLE status within 48 hours, or-

.open the. Reactor Trip System breakers within the next hour. - ACTION'14 - With one-of the diverse trip features (undervoltage or shunt trip attachment). inoperable, tt.'e breaker may be considered OPERABLE provided that the diverse trip feature is restored to OPERABLE. status within 48 hours, or declare the breaker inoperable ~ and apply ACTION 1. -The breaker shal; not be bypassed while-one of the diverse trip features is 11noperable except for the Ltime required for~ performing maintenance-to restore the breaker to OPERABLE status. p ,4% 4 f( TFARLEY - UNIT 2 3/4 3-9 AMENDMENT NO.

gg =. - .vy, y -a u . p. ,,g.- ~ ,)' g. TABLE--4.3-1 ' f. ~ '[ 1 RE ACTOR TRIP SYSTEM' I NSTRUME NT AT ION SURVE I LLANCE ! REQU IREMENTS.. .g a .m 2.., -i w y lE, E' 'CHdN' ELi ' MODESJIN WHICH-N e JCHANNEL! FUNCTIONAL- '-4 CHANNEL- . CALIBRATION ^ TEST:- -SURVEILLANCE.-

REQUIRED' N.

. FUNCTIONAL" UNIT ~ CHECK

1.? Manual [ Reactor.. Trip-N.A.

I N. A.m-R(11), -1,.2, S/U(1)(12)L 13*,4*,..5*- 2 2. - ' Power Range, Neutron Flux "A. Hi gh. JS. . D(2),M(3). M. -le 2__ ^. ~ h . and Q(6)- 'B.. Low 'S

D(2),M(3)l S/U(10) *

[2' L i - and.Q(6). 3. Power Range,' Neutron Flux, High N.Ac ' R(6)' M 1, 2 m) Positive Rate w r 4,

4.. Power. Range, Neutron : Flux' N. A'.-

R(6) M 1,.2 2 ; 1 High Negative Rate W' -N

4 5.

Intermediate Range, Neutron- .S. R(6) S/U(1): 1, 2 and Fl ux 6. . Source Range. Neutron Flux. S(7) - R(6). .M and S/U(1)' 2,.3, 4,1 ~ 5, and *- l ]. 7. OvertemperaturehT S R M 1; 2 - 8. Overpower h T S R M-1, 2 .g 4' g 9. Pressurizer Pressure-Low S R M 'l E S R 'M. 1, 2 - g

10. Pressurizer ~' Pressure--High i

-4

11.. Pressurizer Water: Level--High.

S R M ,.1

12. -A.

Loss of Flow - Single: Loop

S, R.

M-1- B. Loss of Flow - Two Loops S~ R N.A. 1: 4 4 m 1

m.+ -- - 5g .y' z.; 4 y c,, s .n z Y , >a c "^ .;;g '" 7.L.m.%McM 2s n - e c, i, ne ' g; #

c. ~

'.,e.. me 9 gi-s 4: /</ T ,-j-1 o ;. +l ~ 'm s, - s , ;() " '-., ,-: TABLE ^4.3-1'(Continued)' Y ' ' ~ ' g; t

g m

1 9L RE ACTOR TRIP ' SYSTEM : INSTRilENTATION -SURV81LLANCE l REQUIREENTS "f L 3o ' s ' x ~ 2 c-( ..a. s. 4 x iCHANNELn. ' TSURVEILLANCE' * ~. ' CHANNEL: CHANNEL-

• '.FUNCTIONAC

. MODES IN'WHICH-

ro !

' FUNCTIONAL UNITD CHECK iCALIBRATION TESTJ-REQUIRED-

13. " Steam Generator Water. Level- '

S;

R~

M-

' 1, : 2 ? Low-Law s-14.- Steam /Feedwater Flow Mismatch. S'

R?

iM-il, 2 and Low Steam Generator Water'- Level'

15. ;Undervoltage - Reactor Coolant.

'N.A.: .R: L. M. 'l . Pumps _16. 1Underfrequency -LReactor~ -N.A. .R-M 1-Coolant Pumps ?

17.. Turbine Trip L

. A. Low L uto Stop 011 Pressure - -N.A. N. A'. - S/U(9)(1) N.A.. A T C ' B. - Turbine. Throttle Valve - N.A. N. A. : S/U(9)(1)- (N.A. C1osure. .18. -Safety Injection Input.from ESF- 'NiA. 'N.A. M(4) 1, 2 l

19. Reactor Coolant Pump Breaker.

N.A.

N.A. R 'l ~ Position Trip

20. Reactor Trip. System. Interlodks

'.N. A. R S/U(8) 1 M(5)(14)(15),

1. 2,

21. Reactor Trip Breaker.-

N. A..

.N.A.. .S/U(1)(14)(15). 3*,L4*, 5* .3 -E -N.A. 'N.A. M(5) 1, 2, Ei

22. Automatic Trip Logic

g

3*, 4*, 5*- 5

23.. Reactor Trip Bypass' Breaker i N. A..

N.A.. ' (13),R(11)' 1, 2,1 2 ~F 3*, 4*, 5* - f e m ,_______s

l9J: nh; l@ m M TABLE 4~.311 (Continued)

w ITABLE' NOTATION

~ l $gm

*1-qWith the. reactor trip' system breakers closed and the control rod.

lj):-

drive system, capable of rod withdrawal'.

p _ l(1) .If7notfperformed in previousL7 days. W Adjust 4"~

(2) - L Heat balance only~,-above 15% of RA.ED THERMAL-POWER.

f channel ~if absolute difference lis greater than 2 percent.

(3)'- Compare-incore to'excore axial-flux difference every.31 EFPD.

'Recalibrate-if1the absolute. difference-is greater than ;or equal to 3 percent. ~ (4) - ' Manual ESF functional input check every 18 months. m 3 (5)l-u Each train.or logic channel shall be tested at least every-62 ~ days.on:a STAGGERED' TEST BASIS. I6)--.NeutrondetectorsmaybeexcludedfromCHANNELCALIBRATION. n

(7) ~ - Below the P-6 (Block.of Source' Range Reactor Trip)'setpoint.

m (8);-' ; Logic only, if not performed in previous' 92 days. -(9) -' CHANNEL 1 FUNCTIONAL TEST-will consist of. verifying that each

channel ~ indicates. a turbine trip prior to latching the turbine

-and indicates nol turbine trip prior to P-9. .(10) f If.not performed in the-previous 31. days.

(11)

', Independently verify;0PERABILITY of the undervoltage and shunt ~ , trip circuitry:;for the Manual Reactor Trip Function. 4 (12) Verify reactor trip breaker an'd reactor. trip bypass breaker open ~ upo6 actuation of each Main Control Board handswitch. (13)

Local manual shunt trip prior to placing breaker in service.

- Local manual undervoltage trip prior to placing breaker in ~ service.: (14) - iUndervoltage trip via Reactor Protection' System. (IS) - Local manual shunt trip. y ' FARLEY - UNIT 2 3/4 3-14 AMENDMENT N0. (. f z --+.vm-..,,. ,,,w~ y-,- c.--y m- -w-a,s w

y.. ;,:,

X ATTACHMENT 2 Significant-Hazards l Evaluation ' Pursuant' To 10CFR50.92 .for the Proposed Changes to the Reactor Trip and Bypass Breaker _ Techni. cal Specifications in Response to Generic Letter 85 ~ Proposed Changes: 7 Add' Applicable Modes and Action Statements _ to-Table 3.3-1, Items 1 and ~ 21;' add applicable modes and table notation to Table '4.3-1, Items 1, 21 and.22; and add Item 23 to. Table 4.3-1 for the Reactor Trip Bypass.- Breakers.

Background:

Item 4.3 of Generic Letter 83-28, " Required Actions Based on Generic 1 Implications.of' Salem ATWS Events," established the requirement for the ' automatic actuation of'the shunt trip attachment for Westinghouse plants

and requested licensees to submit any needed Technical Specification changes.

' Westinghouse developed generic design modifications'for reactor trip system automatic actuation: using' shunt coil. trip attachments. The major aspects of tha Westinghouse generic design for Type 416 breakers are

applicable to the Farley Nuclear Plant breaker modifications.and have s

been implemented. Since some licensees had responded to Generic Letter 83-28 and had indicated that.no technical specification. changes were required, NRC _ issued Generic Letter 85-09 to request licensees to submit proposed technical' specification changes and'provided_ proposed changes u to the Westinghouse Standard Technical Specifications (STS) and guidance for licensees to use in developing their Technical Specifications.. Alabama Power' Company. therefore proposes changes to the reactor trip breakerispecifications and the addition of the reactor trip bypass breaker specifications for the Farley Nuclear Plant Unit 1 and 2 Technical Specifications in response to Generic Letter 85-09. ' Analysis:. Alsbama' Power Company has reviewed the requirements of 10CFR50.92 as-they relate to the proposed ~ reactor trip.and-bypass breaker technical

specification changes and considers-the proposed changes not to involve

a significant hazards consideration. In support of this conclusion, the

~ following analysis is provided: 1)' The proposed change' will not increase the probability or s consequences of an accident previously evaluated because the 4 addition of reactor trip bypass breakers' ' surveillance requirements will provide!added assurance that diverse means of effecting a sreactor' trip exist ano will enhance the capability to shutdown the

reactor upon demand. Therefore, the probability or consequences of an! accident previously enluated have not been increased.

i"a 1.

7 iJ .l ?. ' Attachment 2- ~ - Page :2.- j ' 0) The proposed l changes will not create the possibility of a new or different kind'of: accident previously evaluated because the proposed changes ensure that a common mode failure will not exist and the -reactor will be;. shutdown when required. Since the ability to . shutdown the reactor. has been previously analyzed, these proposed

changes do not create-the possibility of a new or different kind of

_ accident from any accident previously evaluated. -3) The proposed changes will-not involv'e a significant reduction in a margin of-safety because the proposed changes enhance.the ability to " shutdown the reactor'and therefore enhance.the margin of safety ~ associated with.a reactor shutdown. The proposed changes conform to - 'NRC accepted practice and'therefore doinot significantly reduce a margin of safety.

Conclusion Based upon the analysis provided herewith. Alabama Power Company-jconsiders the~ proposed changes to the technical specifications to not Linvolve a significant hazards consideration as defined by 10CFR50.92(c).

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