ML20034C742

Provides Info Forwarded to Each BWR Owner to Support plant- Specific Submittal on Changes to ECCS Actuation Instrumentation Surveillance Test Intervals & Allowed out-of-svc Times

ML20034C742
Person / Time
Site:	Limerick
Issue date:	03/22/1990
From:	Sullivan W GENERAL ELECTRIC CO.
To:	Wohl M Office of Nuclear Reactor Regulation
Shared Package
ML19302E091	List: ML20034C738 ML20034C739 ML20034C741 ML20034C742
References
NUDOCS 9005070186
Download: ML20034C742 (35)

Text

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March 22, 1990 MrN 024 90 OG90 319 32D Director of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Attention: Millard L. Wohl Technical Specification Branch subject: Clarification of Technical Specification Changes Civen in ECCS Actuation Instrumentation Analysis

Reference:

NEDC 30936p A. *BVR Owners' Group Technical Specification Improvement Methodology (With Demonstration for BVR ECCS Actuation Instrumentation), part 2 December 1986. The purpose of this letter is to provide you with information that we have forwarded to each BVR Owner to support his plant specific submittal of changes to the ECCS actuation instrumentation surveillance test intervals (STIs) and allowed out of service times (A0Ts) given'in the Reference. The information deals with clarifications to modified technical specifications given in Appendix A of the Reference. The first clarification concerned the proposed change to the repair A0Ts given on pages A 3 and A 9 for BVR 6 Solid State plants, pages A 4 and A 14 for BVR 5/6 Relay plants, and pages A 4 and A 18 for BVR 3/4 Plants. In the technical specification markup for the above product lines, Table 3.3.3 1 was not included in Appendix A of the Reference report. The proposed modification as written implies a 24 hour A0T before taking any action listed in Table 3.3.31, it was intended that the A0T of 24 hours apply to the individual actions listed in Table 3.3.3 1. Therefore, we have advised each utility to make the following changes relating to repair A0T in their plant specific submittals: l a) No change to Action b. of paragraph 3/4.3.3. The paragraph should read as follows: l "With one or more ECCS actuation instrumentation channels inoperable, take the ACTION required by Table 3.3.3 1.* /s i l b) Revise ACTIONS given in Table 3.3.3 1 according to the attached l Table 3.3.3 1 modifications (Enclosure 1) for Standard Technical l Specifications. The second clarification dealt with technical specification changes to the reactor core isolation cooling (RCIC) system. The Reference analysis 9005070186 900426 ADOCK 0500 g,,, PDR .e l*

Millcrd L. W;hl page 2 March 22, 1990 included proposed STI and A0T changes to this system (see last paragraph of page 2 1). However, markups of the proposed modifications as they should appear in the blandard Technical Specifications for the RCIC actuation vere not provided in Appendix A of the Reference report. The attached markups (Enclosure 2) of the Standard Technical Specifications for the RCIC actuation instrumentation were provided to the BWR Owners for their use in tt.eir plant specific submittals. We feel the above information has been considered in the Reference NRC approved analysia and represent clarifications to ensure plant specific changer, are properly interpreted. please give one of us a call if you should have any questions. Very eruly yours, u m,. > W. p. Sullivan J. F. Klapproth Reliability Engineering Services BWR Owners' Group programs M/C 789 (408)925 6992 M/C 382 (408)925 5434 P f Enclosures cc: BWROG Technical Specification Committee D BWROG primary Representatives of participating Utilities S. D. Floyd, BWROG Chairman G. J. Beck, BWROG Vice Chairman D. M. Grace, RRG Chairman L. S. Gifford (GE. Rockville) S. J. Stark (CE) A. E. Rogers (GE) r 1 l l l L

,Jy '1T , p.4 + e y,. i.;. y ' Enclosure 1 ?' + d ! ~ 9 j-. n Proposed Repair Allowed.Out of. Service Time; Modifications to the BCCS Actuation Instrumentation ' Standard Technical Specifications s l, t n, g N

I i l I TABLE 3'.3.31(Centinued) i (MIRGINCY CORf COOLING $Y$TE_M ACTUATION ]N$TRLMfWTATION { DCTION ACTION 30 - With the number of OPERABLE channels less non retutMd by the j Minimum OPERABLE Channels per Trip Function requirement: a. With one channel inoperable, place the inoperable channel in the tripped condition within emedevr a er seclare the j associated system inoperable. 47 Y hevo l .b...with.or. a.n...hannoi inop.rabie, deci.re we j 'tsrsociated system (neperable. ACT]DN 31 - .With the number of OPERABLE channels less than required by the i Minimum OPERABLE Channels per Trip Function requirement, declare the associated ECC$ inoperable 4)/th.'.9 M hovu ACT]DN 32 - With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip Function requirement, place j the inoperable chanM1 in he tripped condition withig -- 5 With ne number of OPERABLE channels less than requi d: k @ ACTION 33 - Minimum OPERABLE Channels per Trip Function requiremen l the inoperable channel in the tripped. condition within ::: _r I restore the inoperable channel to OPERABLE status within 7 days j er declare the associated system inoperable. ACTION 34 - With the number of OPERABLE channels less than required by the j Minimum OPERABLE Channels per Trip Function requirement, restore declare the associated ICC$ inoperable.the inoperable channel j 4 vc ACTION 35 - With the number of OPERABLE channels less han required by the Minimum OPERABLE Channels per Trip Function requirement s. For one trip systas, place that trip systen in the tripped condition within :: br" or declare the NPCI systen inoperable.

? Y /fevc b.

For both trip systems, declare the NPCI system inoperable. ACTION 36 - With the number of OPERABLE chanuls less than required by the Minimum OPERABLE Channels per Trip Function requirement, place at l 1 east one inoperable channel in the tripped condition within -- '- P or declare the NPCI system inoperable. t eNumber of OPERABLE channels less than the Totel Number ACTION 37 - t of Channels, declare the associated emergency diesel m nerator i inoperable and take the ACTION required by Specificat' on 3.4.1.1 l or 3.8.1.2, as appropriate. i ACT]QN 38 - With the number of OPERABLE channels one less than the Total Number of Channels, place the inoperable chanul in the tripped condition within 1 hour;a operation may then continue until performance of the next required CMANNEL FUNCTIONAL TEST. The provisions'of Specification 3.0.4 are not applicable. GE-575 (BWR/4) 3/4 3 30 q

I's Tgt 3.3.31 (Continusd) EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION i 1 ACTION ACTION 30 - With the number of OPERABLE channels less than required by the j Minimum OPERABLE Channels per Trip (System) (Function) requirement: (For "per Trip System") /#V heve a. For one trip system, place at least go inoperable 1 cannel in the tripped condition within p J "-* or declare the l-associated ADS trip system or ECLS inop roble. J b. For both trip systems, declare the associated ADS trip J system or ECCS inoperable. l (For "per Trip Function") i a. For the LPCS system and the LPCI mode of the RHR system, l declare the associated LPCS and/or LPCI systems inoperable, j I b. For the MPCS system and the ADS: 1. With one channel inoperable place the inoperable channel in the tripped condition wihtin enoAmyra declare the HPCS system and. associated ADS' trip \\gW or

j system inoperable.

l l 2. With more than one channel inoperable declare the HPCSsystemandtheassociatedADStrIpsystem(s) l inoperable, i ACTION 31 - With the number of OPERABLE channels less than required by i the Minimum 0PERABLE Channels per Trip Systen requirement,4d S.n# A e. l declare the associated ADS trip systen or ECCS inoperable. \\ l ACTION 32 - With the number of OPERABLE channels less than required by the 1 Minimum OPERABLE Channels per Trip System requirement, verify bus power availability at least once per 12 hours or declare the associated ECCS inoperable. ACTION 33 - With the number of OPERABLE channels less than required by the l Minteum OPERABLE Channels per Trip System requirement, restore l the inoperable channel to OPERABLE status witM,* or declare the associated ADS valve or ECCS inoperab yle. ACTION 34 - With the number of OPERABLE channels less than required by the l Minimum OPERABl.E Channels per Trip System requirement, place at least one inoperable channel in the tripped condition within i I

n 5: r* or declare the NPCS system inoperable.

l 9y hevYb "The provisions of Specification 3.0.4 are not applicable. l GE STS (BWR/5) 3/4 3-27 t <,. - ~. n--,- -,en,-m.,e ,m--w-a ,,-,-.m.---, .,,m .,.w.. -,,.,.n.,.wa-, .,. - -,,.,,,.n., cu ,,._,...,_,..,-----n---, -,,-.,-.r.-ne ,e

j TABLE 3.3.3 1 (Continued) fMERGENCY CORE COOLING $YSTEM ACTUATION INSTRLMENTATION ACTION (Continued)

• ACTION 35 -

With the number of OPERABLE channels less than the Total Nurtber l of Channels, declare the associated emergency diesel w herator l inoperable and take the ACTION required by Specificet' on 3.8.1.1 l or 3.4.1.2, as oppropriate. ACTION 36 - With the number of OPERABLE channels one less than the Total l Number of Channels, place the inoperable channel in the tripped condition within 1 hour *; operation may then continue until l performance of the next required CHANNll FUNCTIONAL TEST. I i t O r o I I 1 )

l l

l t "The provisions of Specification 3.0.4 are not applicable. GE STS (BWR/5) 3/4 3 27a i l b

I j 1. TABLE 3.3.31(Continued) l InttG[NCY C0tf COOLING SYSTEM ACTUc!0N IN$ttuNtwtATION 1 i AEll2!! ) i ACTION 30 - With the neber of OPERABLE channels less than reevived by the Mintee OPERABLE Channels per Trip Function requirement: i a. With one channel inoperable, place the inoperable channel in the tripped conditten within aan houra er Wetlace the l associated system inoperable. W hw kb b. With more than ene channel inoperable, declare the associated j i j eystas inoperable. ACTION 31 - With the neber of OPERABLE channels less than required by the i i Minime OPERABLE Channels per Trip Function requirement, place i j the inoperele channel in the tripped condition within ene-J# h e.or, e hour. Restore the inoperable channel to OPERABLE status within 7 eays or declare the associated systas inoperable. ( ACTION 32 - With the neber of OPERABLE channels less than reevired by the Minies OPERABLE Channels declare the associated AD$ per Trip Function reevirement.WM.w f 4wr3 trip systas or ECC5 inoperable. 4 ACTION 33 With the neber of OPERABLE channels less than the Minie s OPERABLE Channels per Trip Function reevirement,in place the l l inoperele channel in the tripped condition with CTION 34 - With the neber of OPERA 8LE channels less than rotu rh I i Minious OPERABLE Channels per Trip Function requirement,lare verify = bus power availability at least once per 12 hours or dec T l i the associated ECC5 inoperable.k X l ACTION 35 - With the neber of OPERABLE channels less than ree'uired by the Minime OPERABLE Channels per Trip Function reevirement, restore the inoperable channel to OPERABLE status within f ' declare the associated AD$ valve or (CC5 (noperable.h= orAg ACTION 36 - With the neber of OPERABLE channels less than required by the Minio n DPERABLE Channels per fri ion requirement: s. For one trip systas, p system in the tripped condition within er declare the NPCS systas inoperable. 6. For both trip systems, esclare the NPC5 system inoperable. ACTION 37 - With the neber of OPERABLI channels less than requirot' by the Minious OPERABLE Channels per Trip Function fotvirement, place at least one inoperele channel in the tripped condition within - - L ;".or declare the NPCS system inoperable. ACTION 34 - Number of OPERABLE channels less than the Tetal Number ~ of Channels, declare the associated seergency diesel generator inoperable and take the ACTION foquired Dy Specification 3.8.1.1 or 3.4.1.2, as appropriate. ACTION 39 - With the number of OPERABLE channels one less than the Total Number of Channels, place the inoperable channel in the tripped es,nditinn within 1 hour"; speration may then continue until performance of the next required CHANNEL FUNCTIONAL TEST. "The provisions of 5pecification 3.0.4 are not appliable. GEST 5(8WR/6) 3/4 3 31 ., i o,

IABLt 3.3.b1 (Ce44nvee) EMthCINCY C0tt C00L1W3 $YSTEM ACTUATION INSTRI#tWTATICW 8$.T.3,3l ACTION 30

• With the number of OPERABLt thannels less than required by the

., Minimum DPERABLE Channels per Trip Function requirementt a. With one thannel inoperable, place the inoperable thannel in the tripped c6ndition within 64teere* or Weclare the associated system inoperable. M hovr# b. With more than one thennel inoperable, declare the associatee system inoperable. ACTION 31

• Deleted.

ACTION 32

• With the number of OPrRABLE thannels less than reautred by the Minimum OPERABLE Channels per Trip Function requireeent,(Wth.4, hy hwe esclare the associated AD$ trip system er ECC$ inoperable.

1 ACTION 33 - With the maber of OPERABLE thannels less than the Minimum OPERABLE Channels per Trip Function requirement, place the inoperable thanne1(s) in the tripped tendition within ', ';- ACTION 34 *

Deleted, y bau6 ACT!DN 36

• With the number of OPERABLE thannels less than required by the Minism OPERABLE Channels per Trip Function requirement, restore the inoperable thannel to OPttABLE status within er detiere the associated ADS valve er ECC$ inoperable.

Jy/,,sp3 h ACTION 36

• With the number of OPERABLE thannels less than required by the S

(- Minism OPERABLE Channels per Trip Function requirements i a. For one trip system, place that trip system in the tripped tendition within --- 2:.:' or declare the HPCS system inoperable, Rhwrb b. For both trip systees, declare the NPCS systen inoperable. ACTION 37

• With the number of OPERABLE thannels less than required by the Mintom OPERA 8LE Channels per Trip Function requirement, place at least one inoperable channel in the trippas condition within
• "r"g declare the NPCS systes inoperable.

"WhtkneberofOPERABLEchannelslessthantheTotalNaber ACT30N SS of Channels, declare the associated emergency diesel generator inoperable and take the ACTION required by Specifications 3.8.1.1 er 3.8.1.2, as appropriate. ACT!DN 39

• With the number of OPERABLE thannels one less than the Total Naber of Channels, place the inoperable thannel in the tripped tendition within 1 hour *; operation may then continue until i

performance of the next required CHANNEL FUNCTIOhAL TEST. ACTION 40

• With the number of OPERABLE thannels less than required by the Minies OPERABLE Channels per Trip Function requirement, place the inoperable channel in the tripped condition within :n i:r Whevr:S Restore the inoperable channel to OPERABLE status within T says or oeclare the associated system inoperable.

'The provisions of Specification 3.0.4 are. net applicable. CLINTON

• UNIT 1 3/4 3*38 I

Proposed Modifications to the RCIC Actuation Instrumentation BWR Standard Technical Specifications

r.. 4 e WR 4 RCIC Actuation Instrweentation Technical Specification 4 e F 5 h b It-

4 I INSTRUMENTATION l $/4.3.5 REACTOR CORE ISOLATION COOLING $YSTEM ACTUATION INSTRUMENTATION i e i LIMITING CONDITION FOR OPERATION 1 i 3.3.5 The reactor core isolation cooling (RCIC) system actuation I instrumentation channels shown in Table 3.3.5 1 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip 5etpoint column of Table 3.3.5 2. 1 APPLICABILITY: OPERATIONAL CONDITIONS 1, 2 and 3 with reactor 6 team done pressure greater than (100) psig. ACTION: 4 a. With a RCIC system actuation instrumentation' channel trip setpoint i less conservative than the value shown in the Allowable Values column of Table 3.3.5-2, declare the channel inoperable until the channel is restored to OPERABLE status with its trip setpoint adjusted consistent with the Trip Setpoint value. b. With one or more RCIC system actuation instrumentation channels {j inoperable, take the ACTION required by Table 3.3.5 1. SURVE!LLANCE REQUIREMENTS f 4.3.5.1 Each RCIC system actuation instrumentation channel shall be i demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION operations at the frequencies shown j in Table 4.3. 5.1-1. l 4.3.5.2 LOGIC SYSTEM FUNCTIONAL TESTS and simulated automatic operation of all channels shall be performed at least once per 18 months, i t i + 9 GE-5TS (BWR/4) 3/4 3-46 a

1 i cs [ TABLE 3.3.5-1 l M REACTOR CORE ISOLATION COOLING SYSTEM ACT11RTION INSTWISURATISW l MINinuN l OPERaSttcmNNtt{*) FUNCTIONRL UNITS PER TRIP SYSTEM ACTION 1 I a. Reactor Vessel tieter tereel - (Low Low. Level 2) 2 50 t II b. Reactor Vessel Water Level - Nigh, tevel (8) 2 51 c. Condensate Storage Tank Water Level - Low (2)ICI $2 d. Suppression Pool Water Level - Nigh (2)IC3 52 i e. Manual Initiation (1)/(system)Id) (53) b y (a) A chaenel may be placed in en inoperable status for up to A hours for required servelliance withewt j 3 placing the trip system in the tripped condition provided at least ome other OPERaStE channel in the j same trip system is monitoring that parameter. (b) One trip system with two-out-of-two logic. (c) One trip system with one-out-of-two logic. (d) One trip system with one channel. t I I' i 1 5

I l i. TABLE 3.3.5 1 (Continued) I REACTOR CORE !$0LAT!0N COOLING SY$7EM ACTUATION IN$TRUMENTATION I ACTION 50 - With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip system requirement: i a. For one trip system, place the inoperable channel (s) and/or i that trip system in the tripped condition within ene4*er i or declare the RCIC system inoperable. SV houd b. For both trip systems, declare the RCIC system inoperable. ACTION 51 - With the number of OPERABLE channels less than required by the l minimum OPERA 8LE channels per Trip system requirement, declare the RCIC system inoperable 64,M,'n 24 hovFS, ACTION 52 - With the number of OPERA 8LE channels less than required by the Minimum OPERABLE Channels per Trip System requirement, place at least one inoperable channel in the tripped condition within mm imvi or declare the RCIC system inoperable, e1 4 h o J r.5 ACTION 53 - With the number of OPERABLE channels one less than required by l the Minimum OPERABLE Channels per Trip System requirement, restore the inoperable channel to OPERABLE statss within (0) 5:u : or declare the RCIC system inoperable. l OVheUU 6 l l GE-STS (BWR/4) 3/4 3-48 9

l i I i l i 11fj II s ^ Y $-o q I g 1 ai vi ai vi gp 4 i E 5 g g-^- ~ c E-- i al Vl Al Vi p g a i e .E g a h w I ~ 5 eE l W "t "s $ l 4 Y --1t E t t-I a, 5 I5 I8 t j z E g N ek k M g C C 8 w 7 3 g b b b t 6 E a a g g g l k 3 y v h s 2 A U D W k GE-STS (BWR/4) 3/4 3-49 ni 4

I c 3 TABLE 4.3.5.1-1 1 3 REACTOR CORE ISOLATION COOLING SYSTDI ACTUATION Ilf5TRUNEirTATielt SURVEfttANCE NUprinUEIITS a, CMMUIEL I 1 OWWWIEL FtEICTIONAL OWWWIEL I FUNCTIONAL INIITS CHECK TEST CALIS".ATICII a. Reacter Vessel Water Level - Tk (tow Low, tevel 2) S M R Yh ] b. Reactor Vessel Water S M R j Level - High, tevel (8) c. Condensate Storage Tank ^ Level - Lew (5) }h (R) 4 w d. Suppression Pool Unter Level - l A High ($) M ~ (R) f - ~ l' h (H'a)) (R) HR l e. Manuel Initiation IIR l ((a) Manual initiation seritches shell be tested at least once per 18 months during shutdeun. All other circuitry associated with eenmal initiation shall receive a OWWWIEL FUNCTIONAL TEST at least ette per M-days as part of circuitry resguired to be tested for auteestic system actestion.) 92 l I i .( ~. -

i i BWR 5 RCIC Actuation Instrumentation Technical Specification . c l 5 i t 4

{ t + INSTRUMENTATION l i 3/4.3.5 REACTOR CORE ISOLATION COOLING SY$ TEM ACTUATION IN$7RUMENTATION i LIMITING CONDITION FOR OPERATION 3.3.5 The reactor core isolation cooling (RCIC) system actuation instrumenta-I tion channels shown in Table 3.3.5-1 shall be OPERABLE with their trip set-points set consistent with-the values shown in the Trip Setpoint column of Table 3.3.5-2. APPLICABILITY: OPERATIONAL CONDITIONS 1, 2 and 3 with reactor steam done pressure greater than (100) psig. l ACTION: With a'RCIC systen actuation instrumentation channel trip setpoint a. less conservative than the value shown in the Allowable Values column of Table 3.3.5-2, declare the channel inoperable until the channel is restored to OPERABLE status with its trip setpoint adjusted consistent with the Trip Setpoint value, b. With one or more RCIC system actuation instrumentation channels inoperable, take the ACTION required by Table 3.3.5-1. C SURVEILLANCE REQUIREMENTS 4.3.5.1 Each RCIC system actuation instrumentation channel shall be demon-strated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3.5.1-1. 4.3.5.2 LOGIC SYSTEM FUNCTIONAL TESTS and simulated automatic operation of j all channels shall be performed at least once per 18 months, i' a 4 l GE-STS (BWR/5) 3/4 3-45 g e f

~ . q c) g 1ABLE 3.3.5-1 I I~ v. i REACTOR CORE ISOLATION COOLING SYSTEM ACTORf10N INSTRIRENTATION E R Mininun S GPERABLE CHANNELS') FUNCTIONAL UNITS PER TRIP SYSTEW ACTION s. Reactor Vessel Water Level - (Low Low, Level 2) 2 50 l b. Reactor Vessel Water Level - High 2(b) 51 c. Condensate Storage Tank Water Level - Low (2)ICI 52 l d. Suppression Pool Water Level - High (1)(d) 52 l e. Manual Initiation (1)/(system)(d) 53 . l = Y (a) A channel may be placed in an inoperable states for up to hours for.regsfred surveillance without_. i-placing the trip system in the tripped condition provided at least one other OPERABLE channel in the same trip system is monitoring that parameter. (b) One trip system with two-out-of-two logic. (c). One trip system with one-out-of-two logic. (d) Single channel. I 4 i i i

F

+ v r*-- -s .w +e w,-e- ,+,w w w,-.r ..w w x 4 .s ..;, w m _ m., _ _, w

p. s ] 1 l l TABLE 3.3.5 1 (Continued) i j. REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTRUMENTATION ACTION 50 - With the number of OPERABLE channels less than required by the I Minimum OPERABLE Channels per Trip System requirement: e l a. For one trip system place the inoperable channel in the tripped condition wIthin = in: or declare the RCIC system inoperable. JLy hogy) b. For both trip systems, declare the RCIC system inoperable. ACTION 51 - With the number of OPERABLE channels less than required by the minimum OPERABLE channels per Trip System requirement, declare the RCIC system inoperak1e ) N li;,,, p q hoyps a ACTION 52 - With the number of OPERABLE channels less than required by the j Minimum OPERABLE Channels per Trip System requirement place at least one inoperable channel in the tripped condition within = h eJYbh r or declare the RCIC system inoperable. M ACTION 53 - With the number of OPERABLE channels one less.tban required by the Minimum OPERABLE Channels per Trip System requirement, (() restore the inoperable channel to CPERABLE-states within f*} h = or declare the RCIC system inoperable. l $ 4 hou r.S i 5 1 l. e 4 GE-STS (BWR/5) 3/4 3-47 3 W Pt - _.,.. ~. _.

t l-i s i I i { I a 5E E 1 i t w n L E lE ^' E.g y.-- 8 E ^8 v' ^' "' I c l 11 1i i ~ L 5 g g ^ ~ c 5 h w w w Al vi Al vl k E ^ ' O g s i ~ b asaSm

d. E

~ h II ei1e 1 tt*5 a, e E RR Y-5 g t. R x)m a a 52

• C *C

,!E E mD I h O E E ~ t W W g. o e o 8 3 p 4 i d W 4 E -GE-STS (BWR/5) 3/4 3-48 I !~ rw nn,-- -- a

~ l R ] TABLE 4.3.5.1-1 m g REACTOR CORE ISOLATION COOLING SYSTEM ACTUATION INSTWWENTATION SURVEILLANCE REQUIREMENTS c R CML 5 CHMNIEL FUNCTIONAL CIWWWIEL FUNCTIONAL UNITS CHECK TEST CALIBRATIO_N a. Reactor Vessel Water Level - N R l (Low Low, level 2) S E i b. Reactor Vessel Water 5 M R Level - High i c. Condensate Storage Tank 4 (R) l Level - Low (5) M R d. Suppression Pool Water Level - l Migh (S) M >Q (R) l l b M*I > e. Manual Initiation HA M g (a) Ranual initiation switches shall be tested at least once per 18 months during shutdown. All other circuitry associated with manual initiation shall receive a CMMNIEL FUNCTICIIAL TEST at least once per'M-Jays as part of circuitry required to be tested for automatic system actuation. l 4 Nb l 4 l I 4 t y

e o

b i .f L i BWR 6 RCIC-Actuation' Instrumentation a Technical Specification - (4 l l* l-t f p 4 y , =..,

i i f i. IN$7 RUM (NTATION i 3/4.3.5, REACTOR CORf !$0LAUON COOLING SY$ TEM ACTUATION INSTRLMENTATION LIMITING CONDITION FOR OPERATION -3.3.5 The reactor core isolation cooline (RCIC) systen actuation instr oenta-tion channels shown in Tele 3.3.51 shall be OPERA 8LE with their trip set-points set consistent with the values shown in the Trip 5etpoint colon of Table 3.3.5-2. APPLICABILITY: OPERATIONAL CONDIT!0NS'1, 2 and 3 with reactor steam done pressure greater than (100) psig. 0.511E: With a'RCIC system actuation instrumentation channel trip setpoint. a. less conservative than the value shown in the Allowable Values colan of. Table 3.3.5-2 declare the channel inoperable until the channel is restored to OPERABLE status with its trip setpoint adjusted consistent with the Trip 5etpoint value. b. With one or more RCIC systes actuation instrumentation channels i i inoperable, take the ACTION required by Table 3.3.5-1. J l T gURVEILLANCEREQUIREMENTS l 4.3.5.1 fach RCIC systes actuation instroentation channel shall be demon-strated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL' FUNCTIONAL-Ti!$T and CHANNEL CAL 1tRATION operations at the-frequencies shown in Table 4.3.5.1-1. 4.3.5.2 LOGIC 5YSTEM FUNCTIONAL TESTS and simulated avtamatic operation of all channels shall be performed at least once per 18 months. I + GE-STS (BWR/6) 3/4 3-49 26 l

' O i t L! TABLE 3.3.5-1 o m-REACTOR CIN ISOLATIM C00Lter. SYSTfn ACTWTIM IIISTMATIM 4 nInnan i [ SPERABLE DIAIWIEth) 4 s ~ FINICil0IIAL INIlis [ PER TRIP SYSTEn Atilm O s. Reacter vessel tieter tevel - towtow,tevel21 2 se y II b. Ileacter Wesset tieter tevel - Nigh, Level 9 2 53 K c. Condensate Storage Tank 1Anter tevel - Low (2)I*I SF i d. Suppressten Peel tieter Level - Mid (2)I*I ,52 e. Meneel Initletten (1)/(system)I#I l53 6 R (a) A channet may be pieced la en fasperable states for w to R hours for reqIeired servelstance without placing the'tely system la the trlpped cond4tlen provided at least one other OPERABLE channet in the l T same trly system is monitoring thet parameter. E (b) One trly systearwith two-est-of-two logic. j (c) One trip system with one-out-of-two logic. i (d) One trip system with one channel. j i 1 1 f 1 1+ j j .f ) i i i f i i e- ..e.ea. r,, m x .s ,..-...,._~O ..,..,_.J.,, n--

~ IN$74WM[WTATION 1 i TAB.E 3 3.5-1 (continued) REACTOR c)RE E50LAT;DN C00.D10 SYSTEM ACTJATIUN IN5"RUnENTC ON ACTION 50 - With'the number ef OPE:lABLE channels less than required by'the Minimum OPERABLE' Channels per Trip system requirement: 004 w & J' .Y a. '- - : ^ ';.,.12, pTece he inoperable channe15fenehe 7 t ^n ; ;.;,.,.:_ in the tripped condition within one hour er declare the RCIC system inoperable. PVhevy w,',aL ow.84 - e o -J:- _ -11 ' ; - -!'^s b. ' r n'., ;. :e :;;"-, declare the RCIC systes inoperable. X ACTION 81 - With the number of OPERABLE channels less than required by the Minimum OPERABLE chonnels per Trip Systes requi t, esclare l the RCIC system inoperableu/d4/y. yhs, g i ACTION 52 - With the number of OPERA 8LE channels less than required by the i Minious OPERABLE Channels per Trip systes requirement place at least one inoperable channel in the tripped conditlen 4 within :$::yhouts hre the RCIC system inoperable. in er t i. ACTION 53 - With the number of OPERABLE channels les's than required by the l Minism OPERABLE Channels per Trip systen requirement, restore' O ~ <=P ra aaa i a oPraa's as== 4= === ar 5 4 l declare the RCIC systes inoperable.- fp./ /;our:5 - e I a O 4 e 1 GE-STS (BWR/6) 3/4 3-51 l u

i gM ..V a a El*"-{:1-{ Jf g 5 e=g =n ee 4 , g g s

i. l ear,.

Al VI Al V1 l g D ) a ~ g ~ s 5. I 5 E hE ,' i

==.w II y, g g 3 B m e.B& E g l 33g{ I I_ 5 W 8 33# e

• d w,!,!jjj i

z g a = ,e oe o ~ GE-STS (BWR/6) -3/4 3-52 26

g TAgtE4.3.5.1-i ~ REACTOR COE 150tATION COOLIIEi SY5ftM ACTWRilSN Ill51NWENTATION $WWEfttNICE EqWIBt9ENis g -eeIi GWWWEL ~ OWWWIEL FUNtil0IIRL OWWWEL 3 FINICTIONRL IHills CHECK TEST CALI9114lleN a. Reacter Vessel Water towel - owtow,tevel2k 5 M+k R(a) s b. Reacter Vessel water /9-5 OG . R ~ tevel - Nteh, tevel (ST c. Condensate Storage Tank M level - low M -- / R ~ i d. segyresslen Peel Water tevel - Nigh M R I e. Manuel Initiatten M OdN M L a, X I (a) Calfbrate trip unit at leest once per% days. g 9:2 ](b) Manuel Infilatten switches shell be tested at least once per 18 months dering shutdeun. circultry assectated with manuel faltletten shell receive a OWWOIEL FINICTISIIRL TEST at leest once-All other y l per M days as a part of circuitry.reetstred to be tested for automatic systee actuation. i 7b X 4 i 1 i 4 1 + 5 i l 1 i } e. M l ~-

m..

~ l -4: E r '( i BWR 6 (Clinton) Solid State RCIC Actuation Instrumentation Technical Specification e l [. -I l 1 i 1 l. i l l ~ ! I t l~ l l- ,D [.1_

I. ( ~ e l, INSTRUMENTATION REACTOR CORE 15'0LAT10N COOLING SY$ TEM ACTUATION INSTRU 3/4.3.5 I L LIMITING CONDITION FOR OPERATION The reactor core isolation cooling (RCIC). system actuation instrumenta-tien channels shown in Table 3.3.5 2 shall be OPERABLE with their trip set-3.3.5 points set consistent with the values shown in the Trip 5etpoint column of i Table 3.3.5-2. - l OPERATIONAL CONDITIONS 1, 2, and 3 with reactor steam dome APPLICABILITY: 4 pressure Greater than 150 psig. l ETigN: i With an RCIC system actuation instrumentation channel trip s a a. 3.3.5-2, declare the channel inoperable until the channel is restored to OPERABLE status with its trip setpoint adjusted consistent with the Trip l setpoint value. With one or more RCIC system actuation instrumentation channels inoperable, take the ACTION required by Table 3.3.5-1. ~ b. .'b

i SURVE1LLANCE REQUIREMENTS Each RCIC system actuation instrumentation channel shall be demon-TEST and CHANNEL CALIBRATION operations at the frequen 4.3.5.1 4.3.5.1-1.

LOGIC SYSTEM FUNCTIONAL TESTS shall be performed at least once per-4.3.5.2 All RCIC actuation system logic =shall be manually tested independent of the SELF TEST SYSTEM such that all trip functions are tested 18 months. i' at least once every four fuel cycles.* ~ t L l l 1 " Manual testing for the purpose of satisfying Specification 4.3 i eutage. 1 3/4-3-58 1 CLINTON - UNIT 1 ) i p

D: a. t TA8tf 3.3.5-1 i n r, 5 REACTOR CORE 150tAff98 COOLIM SYSTEM ACTURTICII NATION e NEWIlWI c

==0tt C== cts I s PER TRIP SYSTEM ACTION d FINICTIOmL Witi$ -2(b)(a) 50 Reactor Vessel ifater level - tow tow,I.evel 2 a. 2 *I 51 I b. Reactor Wessel lister level - Nigh, tevel 8 I#N*I 52 2 NCIC Storage T,enet teater Level - tow c. 7 INI*I 52 2 i d. Suppression Peel tester level - Nf p I 'I 53 I e. IIoneel Initiatten 1 \\ w w f e ) i l \\ i l 1 I i g. 1 I .I i r I,.. ,I I 1 l f.

• )

p. f-(~yp.,. p

t + TABLE 3.3.51 (Continued ' REACTOR CORE !$0LAT10N COOLING SY$ TEM ACTUATION INSTRUMENTATION l TABLE NOTATION $ (a) A channel may be placed in an inoperable status for up to t hours for l required surveillance without placing the trip system in the tripped j condition provided at least one other OPERABLE channel in the same trip _ system is monitoring that parameter. (b) Two trip systems with two channels per trip system. (c) One trip system with two-out-of-two logic. (d) One' trip system with one-out of-two logic. j (e) One trip system with one channel, i i 1, ACTION ACTION 50 - With the number of.TGABLE channels less than required by the i Minimum OPERABLE Channels per Trip Systen requirement: a. For 1 trip system place the inoperable channel (s) and/or. that trip system In the tripped condition within ;;.; i.e.,7 or declare the RCIC system inoperable. 381 hwr'b b. For both trip systems, declare the RCIC system inoperable. ACT!bH51-With the number of OPERABLE channels less than required by the i Minimum CPERABLE channels per Trip System requirement, declare 1 the RCIC systea-inoperable A/,Wl%.?( hows. 1 8 i l ACTION 52 - With the number of OPERABLE channels less than required by the t Minimum OPERABLE Channels per Trip System requirement, p16ce at least one inoperable channel in the tripped condition i within 44 eve or declare the RCIC system inoperable. 9 9 how.b ACTION 53 - With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip System requirement, restore l the inoperable channel to OPERABLE status within 0 t.;... or j declare the RCIC system inoperable. pc/ hogg

3 r

CLINTON - UNIT 1 3/4 3-60 + i e . _, - - ~ _ -..

TM_ .5-2 C MKim CSK ISOLATl8N COOtllE SYSTEM K1MTim IW5TEWENTATION SETF91WT5 es i-5 E Att9MAOLE l' h FW CiteNAL WITS Trip SETPSINT VALUE Reacter Vessel Water level - tow tow, tevel 2 1 -45.5 fa.* 1 -47.7 in. 4 a. .I a b. Reacter vessel Water tevel - Nigh. Level 8 < 52.9 in.* i 52.5 in. l c. KIC Storage Tank tevel - tow 1 3% In.** 1 e in.** < 6% In.t _ 12 in.t l d. Suppression Peel Water level - Nfgh I e. Moneel intilatten m m l 1 t'.

• See Bases Figere 3 3/4 3-1.
  • Instrument rere is 739'. 19-3/4" est.

t Instrument revs is 731' 5" est. l 1 i i i. l ) I i t 4 i kV .. ~.. - -

~ 4 T MLE 4.3.5.1-1 b MACTOR CORE 1$0LATim COOLINE SYSTEM ACienT1911 INSTERNGITATTSN SWRWILLMitt SE4WTSUIENTS i 'i o OWWWIEL OWWWIEL FUIICTIGIIRL OWWWIEL 5 FUIICTISIIAL WIIITS CIECK TEST CALI911AT195 e -e a. Reacter Vessel tinter Level - M4 h R(, Low Low, Level 2 5 b. Reacter Vessel ifeter )k R(,I Level - High Level 8 5 M c. RCIC Storage Tank s R,) g Level - tow 5 n d. Seppression Pool Water Level - R) g S n e k High e. Manuel Initiation IIA R NR 5 i i (a) Calibrate the analog trip module at leest' ence perKdays. 9L e y e t I (a u .. ~ -

i d f 5 Enclosuro 6 Limerick Generating Station, Unit 1 Instrument Drift Data for RPS and ECCS Including Common Instrumentation There are 42 channels of trip instrumentation in the Reactor Prototion System (RPS), and 96 channels in Emergency Core Cooling Systems (ECCS) which are currently tested monthly as required by Technical Specifications, Tables 4.3.1.1 and 4.3.3.1. Of those 138 channels,112 channels utilize Rosemount trip units. A review of surveillance data shoots was performed for 14 of the trip units to determino how much the trip setting changed over a period of three consecutivo surveillance intervals from 11/89 to 2/90. The results are: CHANNEL NET CHANGE (3 MOS) M1111ampores(MA) ECCS 1) PIS-51-IN656A ADS /RHR LPCI PUMP DISCH 0.01 MA 2) PIS-52-1N655A ADS / CORE SPRAY PMP DISCH 0.00 3) LIS-55-1N661B HPCI/ CST LEVEL LOW 0.01 4) LIS-55-1N662B HPCI/SUPP POOL LVL HIGH 0.00 5) LIS-42-1N695A ADS / REACTOR LOW LVL 3 0.00 6) LS-42-1N693B HPCI&RCIC/ REACTOR HI LVL 8 0.01 7) PIS-51-1N655A ADS /RHR LPCI PMP DISCH HI 0.01 8) PIS-42-1N694A DRYWELL PRESSURE HI 0.01 9) PIS-42-1N690A REACTOR PRESSURE LOW 0.01 RPS 10) PIS-42-1N650A DRYWELL PRESSURE HI 0.01 11) PIS-42-1N678A REACTOR PRESSURE HI 0.01 12) PS-42-1N679A REACTOR PRESSURE HI 0.01 13) LIS-42-1N680A REACTOR. LOW LEVEL 3 0.01 14) LISH-42-1N601B SCRAM DISCH VOL LEVEL HI 0.01 .The trip units in the affected channels are primarily Rosemount Model 510DUs. The allowabic drift for this trip unit for a three month period, calculated using the methodology described in NEDC-31336, GENERAL ELECTRIC INSTRUMENT SETPOINT METHODOLOGY, is approximately 10.02 MA. Wri

.s t If.all of-the change in trip unit setting reported above-is- -cttributed to-drift, the worst case actual drift is 50% of the 'cllowable~ drift as determined from the GE setpoint_ methodology end used in the setpoint' calculations. Based on the:above, drift' experienced in the plantiis less than-the' drift used in setpoint calculation, and the surveillance test-interval can be increased.to quarterly. I s f s h r r-+-, A.. . -}}