ML20236R917

Proposed Tech Specs Adding Note to Assure Maint of Automatic Isolation Capability of Containment Purge Sys W/O Inappropriately Adding Monitor EMF-39 to ESFAS Table

ML20236R917
Person / Time
Site:	McGuire, Mcguire
Issue date:	11/19/1987
From:	DUKE POWER CO.
To:
Shared Package
ML20236R914	List: ML20236R912 ML20236R917
References
NUDOCS 8711240104
Download: ML20236R917 (28)

Text

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%, q ; o L 7 r q. y Eg? 3 Q[S < ] l 7 w, 5 TABLE 3~3-3-(Continued). 39.': ~ TABLE NOTATION ,m-g. j iTrip function:mayLbe b1'ocked in:this ; MODE.below the P-11 (Pressurizer

Pressure Interlock) Setpoint.

J, J## rip; function:automati.cally. blocked above P-11: and may be blocked below [ T-. P-111when:Safetyilnjection on low steam pressure'is not blocked. "The;prov6fonsofSpecOication.3.0.4'arenotapplicable. ^ -**Theseivalues.left-blank pending NRC, approval.of.three loop operation. 1 - (in see F ' a rtachec/: n/cres hem ) ACTION STATEMENTS 4 /WitY theinumber:of>0PERABLE-channels one less than the. Minimum-o i ACTION 14 Channels OPERABLE requiramant, be in.at least. HOT STANDBY

withini6. hours and'in. COLD SHUT 00WN within.the following.

-30l: hours; however.. one; channel may be bypassed for up to 2 hours 1 ifor surveillance testing per Specification;4.3.2.1, provided '4 the other channel is OPERABLE. U With the number'of'0PERABLE channels one less than the Total LACTION115 Number of. Channels,' operation may proceed until performance of PERATIONAL TEST provided the inoperable xthe:next' required O channel.is;placed in the tripped condition within 1 nour. ? ACTION 16 ?With the nu'mber of'0PERABLE channels one less than t Number of Channels,-operation may proceed provided the inoperable c' fchannel;is placed.in the bypassed condition and the Minimum Channels OPERABLE requirement is met. One additional channel may be bypassed for up to 2 hours for surveillance testing per Specification;4.3.2.1. ACTION.17 -LWith less:than. the Minimum Channels OPERABLE requirement,- operation.may continue provided the containment purge supply and exhaust valves are maintained closed. 4 ) w } - L 3/4 3-23 (McGUIRE - UNITS 1 and 2

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N;t a _' g.. NOTE l1:%; Turbine l driven:auxiliaryfeedwaterpumpwillnot.startonablackout W- .Msignal coincident;with a. safety injection signal. t / F g, - NOTE.2 l EMF-39, which a alsof provides an'; isolation ~ signal, -is covered by a Specifications 3/4.3.3.9 and 3/4.9.4. .. e. 's i qtt i i: 't' s

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L TABLE 4.3-2 (Continued) TABLE NOTATION q s:7 (1) ;Each train shall be tested at least every 62 days on a STAGGERED TES Ml BASIS. co nnel 1 No7e /.' EMr-3sj whie A p, o vWes on tso lonen sijna), is 6/so by:ISpecik an w, 3/4.s.39.my a/4. q, y, l 4 { 4 1 i r; I , < s. t i.. l 1 4 l l a.. I l l l s I 4

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j 3/4 3-39 McGUIRE - UNITS 1 and 2 "h--

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.j .j [f H !, - ..o a' N E .,.;).- 1, 7..f.,.; ATTACHMENT 2 c ' JUSTIFICATION FOR PROPOSED TECHNICAL SPECIFICATION CHANGE j I '. r k i b 'k

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< The proposed change to Table 3.3-3 and Table 4.3-2, Item 3.c. (2) is to i m, add ' a.. note to' the applicability for the purge and exhaust isolation ' automatic actuation logic. and actuation relays. The note cross refer-ences Specifications 3.3.3.9 and 3.9.4 which also involve the operability of the containment purge system, automatic isolation, and the associated ~ . noble gas activity monitor,' EMF-39. (The proposed Note 1 of Table 3.3-3 is ' 'a. part '. of the original submittal dated February 17, 1987. Page 3/4 3-22, which references Note 1, is included for information and i consistency; no supplemental changes to this page are proposed.) m The change,'which supersedes the original proposal, is to clarify to the user. of the Technical Specifications that the system.and its associated ' instrumentation is covered by other specifications to prevent disabling a; 'the' automatic isolation capability of the system in Modes 5 and 6 if it 1 is required to be operable. An earlier event at McGuire (reference LER 369/86-10 dated July 8, 1986 precipitated this change. ) The original' form of the proposed change would have added the radiation monitor to' the ESFAS table. This has been determined to be inappro-I priate. The monitor is not an ESF and is not taken credit for in the j mitigation.of an accident. The addition of the note in the applicability 1 'of the. Specification is considered appropriate to alert the operator that while the ESFAS may not be required for the existing plant status, the - monitor.and ' actuation system are required by other applicable specifica-tions. The proposed change would ' not involve a. significant increase in the probability or ' consequences of an. accident previously evaluated. The change would help ensure the automatic isolation capability of the containment purge. system.when required thus aiding in accident miti-

gation.. While the automatic isolation of the containment purge system is not assumed in the analysis of the fuel handling accident in containment, I

cross referencing the Technical Specifications as proposed would help to ensure that containment purge would isolate and consequences would be less.than indicated by analysis. The proposed change would not create the possibility of a new or dif-ferent kind of accident. from any accident previously evaluated. The change - involves no hardware changes and ensures a safety function is enabled. The change would not actually affect any requirements in the Technical Specifications, but rather would alert users to the fact that while the ESFAS may be taken out of service, the automatic isolation i capability of the containment purge system may still be required. ] f-the proposed change would not involve a significant reduction in a margin of safety. The automatic isolation of containment purge is not assumed in the analysis of the fuel handling accident in containment, thus no margins of safety are affected. As previously stated, the proposed ~ change wculd not change any existing requirements, but merely alert users i of the Technical Specifications that multiple specifications govern the L operability of EMF-39 and the automatic isolation capability of the containment purge system. ' Based upon the preceding analysis Duke Power concludes that the proposed amendments do not involve any significant hazards considerations. v m____._

t y _ g,. ,y,. 4-I 4 .t \\ ATTACHMENT 3' .6 ADDITIONAL INFORMATION FOR CHANGES TO TABLE 3.3-3 7# 'i. [ (AUXILIARY FEEDWATER AUTOMATIC SWITCHOVER ON LOW SUCTION PRESSURE) a,, .;t J t 5 Tj t 1 I l L. r

N', E6MMk __LECTRmbYSTEM Sc6 % y j jf 6.d? SYSTEM OPERATION. 1 1 6.11 CONTROLS 6; 1.1-S'UCTION SUPPLY. SOURCES g The suction supplies for the CA pumps are'as follows' listed in the order of I - preference.; 1 \\ -SOURCE-SUPPLY VALVES 1. Upper Surge Tank. ICA4 and ICS18 2. ,CA Condensate Storage Tank. ICA6 3.- Condenser Hot Well-ICA2 and ICM265

4..

Nuclear Service Water' ICA15A, 1RN69A, ICA18B and 1RN162B i A11l S the supply' valves listed above are motor operated and can be controlled Leithe nin: the control room or at local panels. Supply valves ICA2, ICA4, ICA6, 1CS18 and.1CM265 are kept in the open position so that suction supply is available'on' demand;.while the others are kept in the closed position and 1 i Lopened~ automatically or by an. operator when the ne~ed arises. l

The first'three' sources listed abo've feed into a header which supplies all thr_ee CA pumps.

The associated. supply ~ valves for these three sources are 4 ' powered by a normal power bus.. The Nuclear Service Water supply is divided ,s ("{" Linto two lines; line A supplies CA Pumps IA and No. I while line B supplies CA Pumps 18 and'No.l1. To-insure a sufficient' supply'of feedwater during a bl'ckout, the powerLfor the motor operated valves associated with those two a supply-lines 11s from.an essential-bus. (Motor operated valves with designations ending with A are associated with. Safety irain A and powered from JETA, while .M0V's-with~ designation ending with B are associated with Safety Train B and powered from 1ETB.)- / .'On low' suction pressure,lthe RN lines will be h11gned automatically (with a 3 second~ delay) to the CA' suction header. Low suction pressure on CA Pump 1A will open the following MOVs: q%g McE E.- 14 I 2D - 2631-T 'ICA15A by means of ICAPS 5002 and 1RN69A by means of ICAPS 5350 tActr -i% - co. 26 ud. 26 @l JLow s ctionl pressure on CA Pump 1B will open the following M0V's: .1CA18B by means of 1 CAPS 5360 MCLE-lu l.gz w.zz,og and 1RN162B by means of ICAPS 5012 WEl-l% oO.45 ;,d.4g-og Low suction pressure on_CA Pump No.1 wh1 open the following MOVs: o ICA86A by means of 1 CAPS 5042 Mccr_147-2 and -29.cs .1RN69A 1 CAPS 5370 Mce.c-ns co.26wl. rr,-oi (p 1CA116B ICAPS 5390 wra_-&).n ug 29,o i k[ T 1MCSD-0147-00'-, Nm

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~ ~ W* m: s> _e (s IRN1628 by mean iof'1 CAPS 5381' McEC-ISO-CC.kG ad.lf5-c>l '9 p '1CA161C ICAPS 5044 McEE-ln n} MCUE.1 TWEsc ARE roc i 's and ICA162C-ICAPS 5380 M'en-te. 33 3 g: egg, '1CA161Cand'ICA162CareDCMotoroperatedvalvesassociatedwifhthe. Standby Shutdown System and.are powered by the SSS batteries. The suction line of each s; . pump contains a suction isolation valve (ICA7A for Pump No. 1, ICA98 for Pump IB, and ICA11A:for Pump 1A) which is normally.in the open position for supply by means-of the Upper Surge Tank, Hotwell, or CA Condensate. Storage Tank. These . isolation valves'are to be closed as an operator function whenever Nuclear LService Water isTusedlas the Auxiliary Feedwater supply. The'three suction ~ isolation' valves are all motor operated an'd can be controlled ' Leither'in the control room or? at a local panel. 'All of these valves receive 4 l power _from an essential bus, as their designations indicate. 6.1. 2 : DISCHARGE T0 STEAM GENERATORS LThe! discharge.ofeachpumpflowsthroughacontrolvalveandanisolationvalve

to its assigned. steam generator according to the following table.

FLOW TO CONTROL ISOLATION CA PUMP. STM GEN. VALVE VALVE ,\\ IAL 1A-1CA60A ICA62A L1A4 IB. ICA56A 1CA58A W -1B: IC 1CA44B ICA46B !~ '1B. 1D 1CA408 1CA42B No.: l'.

1A ICA64AB ICA66AC s

No. l' 1B -1CA52AB ICA54AC

No. 1 1C

.ICA48AB 1CA50B No. :1 - 10 1CA36AB ICA3SB x All the' valves l'isted in the table above can be~ operated in the control room or .at a panel-local to its associated pump. The control valves are air operated ~ and fail <open. All the isolation' valves listed are motor operated and normally. lkept in the open position. Each isolation valve has a computer alarm which is activated when the valve is not in the open position. _Upon automatic start of a CA pump the control valves on the discharge of the Lassociated pump will be automatically positioned to the full open position.

The. operator may regain manual control of the control valves by resetting the pilot solenoids.- There is one reset' switch per train on 1MC10, and also on the Aux Feedwater 1A & IB control. panel and Aux Feedwater pump turbine control

panel; Also, on the automatic start the minimum recirculation valves will be

' automatically' closed. 6.1.3 LOCAL' PANELS

Normally, the' Auxiliary Feedwater System is controlled and monitored from the icontrol room; however, local to each pump is a panel which contains all the

.,L ' controls and indicators necessary to operate the system. The controls and f]. indicators'on'ACAPumpPanelareassociatedwithPump1A,SafetyTrainA,and u i i MCSD-0147 l M

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p.

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w jw t."hh'. v a.,.3 I. ... P.: 3 g k-' j, I i f 4(n,. n' F. q, '>, w, r. I-g,(5:, - j. J,... n q y. 97 w$p4 a.t.W. $v;U o N, - ATTACHMENT 4" y .. ~ i m 'P 4 c r; - / ) e,g I I ( .y N': 'N:,)g r e4i p ADDITIONAL-INFORMATION'FOR CHANGES TO 4 w e. e,,- mF',.L f), v .,'/... s 'ff 3 TABLEL3.3-10 ig %yd~J s C i

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QM h &; $ ; " '~ m n y(d Wy* r D n QfC y g 67 McGUIkENUCLEARSTATION ? p gm P n ih ' REGULATORYcGUIDE 1.97,<REV. 2 REVIEW Li Mhh4 I W S K A-3(,? Variable: jRCSHot.LegWaterTemperature w, %a 8-5, +. ' N Ranged: 50*F.to 750*F m; a:. ' 7 MH ~ ' Category:- 17 ' m Y @yM l Existing Design':. Each'of1the four reactor coolant--loops employ'a QA' '~ . Condition.1. Hot Leg Water Temperature measurement t .ch nnel: and are powhr! instruments feed into one RVLIS (T ). Two oflthe T o %c ed from the' associated Class TW L 1E buss.. The other two T instruments feed into a S, h s,t' redundant.PCS channel and are. powered by that channel's < g;, , Class 1E. buss. The control board display devices f6 (recorders)shareoutputisolationdeviceswith tother non-safety equipment as described in %g m Paragraph 5.5.l.3.la. The indicated range is .0*F to.700*F. The' environmental: qualification of this f JM instrumentation.is.-described in the McGuire Nuclear . Station FSAR', Section 3.11 Land ~the NUREG 0588 g;f@Mf, ~ submittal. 1The seismic qualification:is described-f?

inithe McGuire FSAR, Section 3.10 and Paragraph 4~~'W

~ 5.5;1.3.la.of this' submittal. Redundancy / diversity. 'is' provided:by monitoring T on all four loops h along with monitoring of T on all four loops and 9, monitoring'ofincoretherm8 couples.- ' Compliance: The ' existing design does not fully comply with the d,1 ' recommendation'of RG 1.97, Rev. 2 because tne range L ldoes not conform to RG 1.97, Rev.'2 range of 50 F Lto 750*F. SAlso, the control board display devices -(recorders) are not seismically qualified and are 4', , w' interconnected to other non-seismically qualified i equipment; R u. Four channels' recorded. '~ Display: Four channels on the computer b ' Position- ~ Th'e range of the installed instrumentation is adequate Pm for the intended monitoring function. No range change is required.as the installed range is adequate for a Westinghouse NSSS" System. Also note, the present-range meets the recommendation of RG 1.97, Rev. 3. a-The recorders for this variable will be replaced ~ with seismically qualified' units'and will be "j. provided with isolated output signals which are o 1 not shared with non-seismically qualified equipment. pM,#7, ! 4'

Implementation

,T' Schedule: These modifications will be completed by the end <M lof the first refueling outage following January, 1986 for each unit, contingent upon equipment .l availability. ,y m A l 5-21 Revision 3 y je yr n (h;; k' h' ,}}