ML20100R383

Applicant Exhibit A-59,consisting of Intracompany Correspondence Justifying Continued Operation of Unit W/Terminal Blocks Installed in Various Instrument Loops

ML20100R383
Person / Time
Site:	Farley
Issue date:	02/20/1992
From:	Hairston W ALABAMA POWER CO.
To:
References
CIVP-A-059, CIVP-A-59, NUDOCS 9204080137
Download: ML20100R383 (24)

Text

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APCo Exhibit 59

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• k9 #-'92 MR 13 P4 :44 AlabamaPower i e t .. r - u : . e annm l Justification For Continued OperatiMM

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i (JCO) Unit 1-Terminal Blocks Used In l 5*** ct Instrument Circutt om NOV 24 W i

! F rom W. G. Hairston, 111 l

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Mr. J. D. Woodard At Vice President, Nuclear Generation l

!. Evlosed is a justification to allow continued operation of Farley Unit 1

! at**. *.crm r'ai olocas installeo in various instrument loops. A copy of this i

i JC0 should be placed in tne EQ Central File under States, GE and Foxboro l- tertainal blocks.

I l ,,,, if you have any questions, please advise.

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Justificattor for Continued Operatim 0064078 J. M. Farley - Unit 1

! Terminal Blocks Used in Instrument Circuits l

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! 1. BACKGROUND l The qualification of the Farley Nuclear Plant Terminal Blocks used in j instrument circuits was based on type test information for the States ZWM

- Terminal Blocks, the GE CR 151B Terminal Blocks, and the Foxboro Terminal l

Blocks. Each terminal block tested was identical to that installed in the l Ft-ley Nuclear Plants. The terminal blocks were tested under simulated LOCA l conditions in a configuratics similar to that installed at FNP. Each test.

l resulted in the terminal block successfully performing the intended j function. However, although these tests substantiate the acceptability of

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f using terminal blocks under 1.0CA conditions, the performance parameters tnat l would additionally support their acceptability for use in FMP instrument l

circuits were not measured. On the basis of sne 10CFA50.49 pro,;sion t'.at l _ permits type test plus analysis for establishing qualification, an analysis was performed to demonstrate that tne FNP terminal blocks could have f

l r~":r.ad as 'atanded for the instrument application. The analysis l demonstrated It turth *y size, sa:;% M Nction to a terminal block tnt I was type tested under sicilar FM7 LOCA conditions dere insulation resistence f (IR) was measured to determine leakage current. The analysis further assuned, based on review of the Sandia NudIG/CR-3814 report that the input or l

change in insulation resistance was attributable to a surface film mechanisa j - and not material dependant. Tne corresponding values recorded during the l test of the similar terminal cloca (Conam Test neport tra-107 Co. .w...

l Terminal Block) provided a worst case IR value of 3 x 107 ohns. Allowance of further margin was provided by accepting a lower value of insulation resistance (i.e., 1 x 107 ohns) for use and input into the FMP setpoint analysis for loop accuracy. (Reference WCAP-1165tl, Evaluation of the Impact j of Cable and Terminal diock Leakage on RPS/ESFAS and ERG Setpoints, November j 13,1987). Tne 1 x 107 ones insulation resistance was provided to j Westinghouse for all terminal blocks used in FMP instrument circuits.

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Justification for Continued Operation J. M. Farley - Unit 1 0064079 Terminal Blocks Used in Instrument Circuits Page 2 A review conducted by the NRC during the week of hovember 16 through 20th indicated that the technical analysis approach used to justify the 1 x 10 7 ohms insulation resistance value was not acceptable to the NRC Staf f. APCo believes that the methodology employed for the analysis along with the resulting values are technically sound and justified. However, to further exenplify the amount of conservation built into the setpoint analysis, dditical reviews and studies were performed.

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!!. EVALUATION A tnorough review of the Sandia IEJREG report uns performed *ich resulted in 7

? confirmation of basic assumptions such as the insensttivity of the terni.'.di

-. blocks to chemical spray, the lacA of surface film dependancy on roughness, and the recovery of IR's as teeq>erature is diminished. Additional discussW. is pecvi:ed in Attachment I to this report. As explained in Attachner.L i, corrthiion or the "4. " *est --s. its to the post acc: cent performance of terminal olocks at FhP can not be made in a quantitative manner.

The previous evaluation of the tapact of casle and terminal block leatage on

. - - APS/ESFAS and ERP setpoints (Ref nCAP-11656, hoveeer 13, 1987) considered a conservative value of 1 x 107 onas for terminal otoct IR eno, c%ined with otner contributors to channel inaccuracy, confirmed that the RPS/ESFAS

, functions will occur as required in the plant safety analysis. Furtnernore, tne use of existing ERP setpoints (without revision) was confirmed to not impact plant safety. At the time of reactor trip and during post accident monitoring, tnere mere no uncertainty increases amica could cause the operator to be mislead into performing inappropriate actions. In view of tne continuing concerns raised by the ILRC regarding the terminal block insulation resistance values currently demonstrated in the Fl@ EQ documentation and used in instrument inaccuracy studies, an evaluation has been performed to assess the impact of reduced IR values on the ability to achieve and maintain safe shutdown following design. basis events. . Tne .

results of this evaluation are described tn,.Attachse.nt 2. .

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• Justification for Continued Operation J. M. Farley - Unit 1 0064080 Terminal Blocks Used in Instrument Circuits Page 3 N- The evaluation described in Attachment 2 considered the postulated design basis events of large and small break LOCA and secondary pipe breaks. A minimum set of safe shutdown instruments and their functions, potentially j exposed to a harsh environment were identified. The evaluation determined j that if a terminal block IR value of 5 x 105 ohms were conservatively assumed as the worst case value for that minimum set of instruments, the n

resulting instemnt inaccuracy will allt>< the current ERP values to be used without change.

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Terminal block testing performed by Sandia National Laboratories (SNL) is Si documented in kJREG/CR-3416. As discussed in Attachment 1, correlation of

.. the Sar,$ta test results to the post addent performance of terminal blocks W ,

at FMP can not de directly made. However, in recognition of the concerns that the Sandia tests nave introduced, an evaluation was made of design basis LOCA anc secondary pipe breat using IR values derived from the Sandia

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results. Figure

% resents a correlation Deteeen temperature and IR d conservatively assuming a logaritrusic relationship between temperature and if IR. Tnts data is based on Id values for GE EB25 terminal clocks measured at u

175'C and 9b'C. Accitional discussion on the relationship of IR to temperature is contained in Attachment 3. The methodology employed by Attacnment 2 was to deterzine tne containment tenaperature at which the IR value uOuld decrease Delow tree Vilwe of

• X 1[ tM. At 541J'1 Of 6 3 10b onms and above the operator can use his instruments with confidence under

? the existing ERP's and setpoints. Having determined this containment temperature, the Fhp temperature profile is used to define the pericJs of 5 time when IR is below tnis tnreshold value, tnereoy defining the periods p curing DBE's unen inaccuracy would be postulated to be greater than that accounted for in tne ERP's. . Tne results are shown in Figure 3.0-1 of

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1 Attachment 2. This period of interest occurs at a time when no operator action is reautred based on instruments exposed to the postulated narsh

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<rminal Blocks Used In Instrument Circuits 0064081' - '

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environment. For large and small LOCA, no mitigative or recovery operator Iq, actions are required using instrumentation in a harsh environment. For secondary breaks, safety in,jection termination (the required manual operator ,

recovery action) will occur after the instrument accuracy returns to an I U

acceptable value. The onset of excessive instrument inaccuracies as shown in Figure 3.0-1 is not expected during a DBA since the following conservative assumptions were considered:

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1. The test profile shows in Figure 1 of Attachment 3. used to obtain the #

IR values assumed in Figure 1 greatly exceed the maximum calculated design basis LOCA/MSL5 temperature profile for FW.

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2. The physical configuration of Phase I specimens in the StWe test produced more severe conditions than would occur at Fr. The conduit was routed up the exterior of the enclosure and terminated in the test l O che-bec approximately 12 inches below the steam inlet port and the l

spray header. Ythar cza or che conduit was sealed. (See Attachment l 1.)

3. Sufficient test data exists to familcate that #12 AMG conductors will exhibit lower IR values than smaller #16 AMG conductors with the same insulation systas. The Sandia testing used #12 AME cables wereas #16 r AWG is used in FW field cables for Rio c:J tra.v.uitter aa,-lication-l (See Attacnaent 1.)

4. Tne containment temperature penfile assumed is derived from worst cese ,

assumptions described in FSAR Chapter 6.2 including 1021 pouer, minimum ESF, and only one containment cooler. The profile which would result from more realistic assumptionr would be signtficantly lower.

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5. The minimum values of IR and corresponding high leakage currents recorded in the referenced SNL test results are conservative, and are not representative of values that would be expected at FNP during LOCA/MSLB' design basis events. Minkm values of tenninal block 1R values higher tt3n those recorded in the SNL report are supported by CONAX Text Report IPS-107, and Wyle Report Nos. 17775-1 and 17733-1 for

., MSLB/LOCA temperatures relevant to FhP. (See Attachment 3.)

111. CONCLUSION Based on the above Alabama Power Company concludes that there is

~~ reasonable assurance that the instrument icops will pe.-form t Mir safety function een called upon to sitigate the accident for adhich they are needed. However, to further remove the point of contention regarding g

te~:inal black performance and thereby increase the margin of the elestingho.::: etpc!st analysis. Pro wip replace the terstnal blocks of concern in Unit 2. during the fifth refueling outage, with galified splices not relying cm terminal blocks and APCo will take the same measure for Unit 1 prior to startup from the eighth refueling outage, currently scheduled for March 1988.

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z QF b' 0064084 h ATTACHMENT 1 Additional Clarifications Regarding the  ?

Qualification of States NT/ZWM and 8.E. i gi CR1519 Terminal-Blocks at Farley Nuclear Plant (FNP) Units i and 2 , j in Low Voltage RPS/ESFAB and ERP -

Transmitter and RTD Circuits QUALf Ff CATf DN REQUf REMENTE AND ETATUS 3 5

States terminal blocks mounted in NEMA 4 enclosures, and G.E. CR1519 terminal blocks provided with the S.E. Series 100 electrical penetration assembly terminal boxes were _' -

stes .411 a," in ecntataert saf ety related instrumentation  ;,

circuits at FNP durie.g construction. As such these blocks , c including their performance and installed configuration were required to be and are qualified to the DOR Suidelines for FNP Unit #1 and to NURE % 0589. Cat. 2, for FNP Unit 42. In

• accordance with 10CFRSo,49, Par. K, requalification of this electric equipment is not required.

EFFECTS OF LOCA /MSLP EW78tC>pfMT DN @f NAL BLOCK LEdeKaOE CURRENTS AND PERFOmnANCE 1E Information Notice No. 44-47 indicated that as a result of testing performed by Sandia Natismal Laboratories (SNL) -

'-- the N#C it was shown that a moisture film will form on I W sarface of tere:-

• blocks uurang the slaw

• ation of LDOAntELB events. gew f s N#tErs/J-C S .3 3 S. N -1617 Printed Aug.ist 1984. Note that this reference esas not provided in IEN S4-47). This film will result in the reduction of m )

insulation resistance between terminal points and ground.

and thus will alle= scoe leakage currents to flose to ground.

IEN 84-47 further states that the petC staf f recognizes that leakage currents do exist during LOCA/MEL3 simulations and T that the leakage currents may be of sigriificance in some a p plis.e tionw .

No written response to the notice was required, and it esas suggested that licensees:

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1. Review their facilities to determine if terminal  :

blocks are used in toer-voltage applications, such as trans*1tters and RTD circuits, and

2. Review terminal block gualification documents to ensure that the functional requirements and associated loop accuracy of circuits utilizing terminal blocks will not degrade to an unacceptable level due to the flow of leakage currents that might occur during design basis

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O The notice further stated that the NRC staff considers this review to be part of the on-going activities'that licensees 7 -

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are currently undertaking to resolve other environmental  ;

o geficiencies per 10CFR30.49 deadlines and requirements. I IEN 84-47 indicated that where existing terminal block

• qualification testing does not provide supporting data for.' ".

instrumentation leakage currents, the following possible 'l corrective action could be considered .

Obtain documentation from va!!d qualif acation tests  !

already performed with s'abstantiated data for leakage currents, and perform appropriate analysis to  :

demonstrate that acceptable loop accuracy and -

c' OsM*!ated response times for instrument circuits .;

2 t.:'.111:ir.g terminal elocks are being maintained throughout various operating conditions. ,';

Tsee other possible corrective actions worn also stated which 8, involved either additional qualification testing of installed terminal blocks with provisions for continuous penitoring of leakage currents throughout the test with $f analysis of loop accuracies, or replacement of installed terminal blocks with qualified splices.

O Of* S.W41, TON OF_. TERMINAL BLDC$' LEAKAGE CUR 9 TENTS States terminal bler.is in :.OtA 4 oncla w-se wers w alified 107i v e ineirwivitativ and Control circuits instee c ontainment by Wyle Report No. 44354-1. Post ~LOCA simuistion of insulation Resistance (IR) values were '

recorded, but no leakage current or IR values more recorded during the LOCA test phase to permit quantification of the p

surface moisture film leakage currents discussed in IEN e..

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94-47. CR151 and States NT terminal blocks installed in 8.

E. Series 100 Low-Voltage Instrumentation and Control I d

Penetration NEMA 4 terminal boxes inside containment were I.c qualified f or FNP by G.E. as stated in O.E. Qualification h. r.. 2-Test Summary Report 994-75-011, dated March 27,.1975.- This ..M report provides one minimum value for IR associated with ' "

(rj LOCA simulation testing of the CR151 and States blocks, but

' insufficient leakage current or 1R values recorded durJng w2. .

the LOCA test phase exist to permit quantification of the .$

surface muisture film leakage currents discussed in IEN g 84-47.

Due to the lack of data recorded in the DOR Suideline and

• !'JRFG-OS66 Cat. 2 :;=11f.4cetion reports for the FNP States 1 &

and CR1518 termir.a! Mocks installed in NEMA 4 enclosures, a .

documentation search was conducted to obtain documentation *

?.V from already performed valid qualification tests of I identical or similar terminal blockc which could - provide +

leakage current er IR data recorded during the simulated

• LOCA steam conditions. Of the test report documents sk'.

evaluated, including the SNL test documentation upon which 7 IEN 84-47 was based, the e ast representative test of FNe in containment terminal block and enclosure conf aguratior. -l -

which provided IR readings during simulated LOCA/MSLB steam .

conditions was Conax Report No. 1*S-107, dated 10/5/73. M O Minimum IR values contained in this report which were

• iced del ? LOct simulated steam conditions were p QJ r . iswec anc' i c ca s . . ;'.ively. low 1R value was provided to p C.

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Westinghouse for determination at c.. res.?t**p leakage currents and their af fects on RPS/ESFAS and ERP setpoint ',

accuracies.

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and WCAP-11656 addreeses the results of this evaluation response to APCo E. C. Action Itees 018 and 047, addresses hy. "

the methodology used for the selection of the terrainal block - g-1R value used in the Westinghouse evaluation.

i BASIS FOR NOT USING SPL T R St 18'AKA&E CLFtRENT vat _tX Ff.sn .

WCap-11658 EVALUATION All the following comments are based on a review of NUMEG/CR-3418. SANDSO-1617 entitled " Screening Tests of -

Tereinal 31ock Performance in a Simulated LOCA Environment" printed August 1994 and are,in reference to sections of that document (Attachment 41A to this clarification report). It is important to note that only Phase I testing was performed ,

on G.E. CR1519 (Manufacturer 1. Model 3) and States ZWM (Manufacturer !!!, Model D)-terminal blocks as shown in .

Table 1. Pg. 12.

o Environmental Test Temperature and Pressure

" 0115 - As sh in Figure 1, Pg. 8, the terst temperature and pressure peaks ,as see11 as profile O durations greatly exceeded ,the maxisaum calculated

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• l 0064087 2n DBE LOCA/MBLB surface temperature conditions for FNP in containment terminal block applications. As stated in the last paragraph on Pg. 52 of Sect.

4.3.4, " Terminal blocks 6,11, and 12 (States ZWM) experienced a terporature effect. Their inter-terminal barrier softened almost to the i liquid melt point, and flowed from between the l terminals. The melted material covered some of the lower posts of the terminals, encasing the wires and drooping below the tomrinal block in large globules. Surprisingly, as Figure 20 shows, the terminal-to-terminal insulation resistances

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f or terminal blocks 6, 11, and 12 were among the nighewt seasared. We have no reasonable ,

nypothesis to explain this behavior. We can speculate that the phase change of the inter-terminal barrier material prevented in someway the formation of a continuous film between

• terminals, or that changing gnometry somehow affected the process of conduction between adjacent terminals". 8ecentrical changes of the inter-terminal barr Aer occured in Pyle Tast 44354-1, but complete melting did not occur.

8 o Nc chemical spray was introduced in Phase 1 LOCA Testing. (However, Section 3.5, Pg. 126 of the

-- ec3clusic.n statte that little change in the

-t sturs fil raafuctivity may be expected as a

' result of chemical spray anc theref ore, cheatcal spray would appear to not be a significant issue.)

o Physical Configuration of Phase 1 Specimens -

Three 6-pole CRiSiB and three 6-pole States ZWN terminal blocks were all mounted vertically in the same Pe m 4 enclosure ~(Enclosure 2) as shuwn in

igure 4 Pg. 11. Cables were brought into the sies of the enclosure thro ,. 3/4 ic.:P. :Mec t.e r l liquid tight metal hose using elboes conduit tereinators to penetrate the 9EMA 4 onclosure walls. The conduit was routed up the exterior of the enclosure, and terminated in the test chamber head approximately 12 inches below the steam intet port and the spray header. Neither and of the conduit we sealed. (See bottoe Pg. 16, and top of Pg. it.)

All cables used to connect the terminal block test circuitry were 812 AWG, either 1-conductor or 3-conductor. The direct steam Jetting espesure into the open conduit from the steam inlet port is not representative of installed instrumentation conduit configurations at FNP, and the use af 912 AWG single conductor and multi-conductor cable is not representative of the FNP installed 4

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oo84o88 O 4j instrumentation cable. Installed instrumentation cables at FNP for RTD and transmitter applications

[3.l are #16 AW3.

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Sufficient test data exists which appears to II indicate that #12 AW3 conductors will exhibit i.

Iower 3R values than smaller #16 AW3 conductors y2-with the same insulation system when exposed to LOCA steam conditions. As the #12 AWD cable is a Tr part of the test circuit and its contribution to IO IR and leakage currents resulting from steam coisture is included in the terminal block enessured data, additional error may have been

antroouced. ((f l-4%

o Electrical Configuration of Phase ! Test-(Sect. ff 3.4, Pg. 10, Figure 10, Sect. 4.1, Pg. 29 and last -%

' paragraph Pg. 94). h p p.

A serpentine connection of alternate terminal Y.

block (TP) poles was used which did not result in d the measurecent o' e unida pole-t& pole resistive path. As stated in Sect. 4.1 "The serpentine s:-

M O connection of the 6-pole terminal blocks actually provided 5 parrallel resistive paths. Ecch of these paths, indicated R through R in Figure 16, 4f 76

. s ie- i.arn a carallel t:odsurface.8' b ination ok an infinite "In sessuring i'

.nce ~ pat'c, i.e...e -

the leakage currents the equivenerit ras.ittance of these 5 surf aces is actually measured. Without W further data or assumption the individual values of the surface equivalent resistances, R g through y R 5 cannot be determined".

Also as stated in Sect. 3.4 *only one ground @

m

• etur: path existed for all 12 phase i terminal blocks, 4 blocks per enciosure. "2r the *f9-ity of the Phase I test, all blocks were powered ..

simultaneously, and hence only pole-to-pole d leakage current data is relevant".

As stated in Section 4.4.3, Pg. 94, last ~

paragraph, "If the conduction paths were uniformly distributed over the terminal block surface, the differences in wiring between Phase 1 (serpentine) and Phase !! (straight through), would cause the Phase 1 1R s to be less than the Phase !! 1Rs.

This result is a simple consequence of euttiple parallel conducting paths. For our experimental configuration there was approximately five times the pretested conducting surf ace available on the O Phase I terminal blocks as compared t6~TMe Phase

!! terminal blocks. Consequently, the insulation resistance for the Phase I terminal blocks could

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reasonably be expected to be one fifth of the Phase !! 1R's. Except for the A path of Phase !!

N terminal ilock 4, the 45Vdc data and the 125 Vdc j e 4

.l support m3 hypothesis or uniformly distributed '-

conduction."

The serpentine test circuitry used to measure the [

States and CRiSiB test specimen leakage currents e

(

• and IR's did not yield direct individual '

N.

pole-to-pole or pole to ground values of IR during , ,

the 1.0C4 steam environment simulation, and are subject to hypothesis in order to arrive at , )

required pole-to-pole values. 9 o General Applicability of Phase !!' Test Data - As '

stated above, no Phase !! testing was performed on The only block r CR1519 or States terminal blocks.

tested in Phase !! based on present available information which appears to be stallar to the 6

CRiS1B and States blocks with regard to, block L $

material, pole-to-pole spacing, the presence of a '

barrier between poles and a one-piece non channel g mounted block is the S.E. E323 (Manuf acturer I, It should be noted that Table, 1 Pg.

O Model A).

12, incorrectly states that the States IndM block is a sectional block. Six E323 blocks esere tested L < #

iv.

• esse !!. Although, the electrical test _ -; d in et cutter . the Phase Il test yielde, more realistic values of team y currP*e and IR's than k

l Phase I test, other electrical test anamo11es, and ,I the configuration and environmental test profile ,

are not representative of the instetled ce6dition -

at FPF. l It is interesting to note that the only physical .

design ef fects analysed were related to whether or not the blocks esere cettioret or one piece as stated in Sect. 4.4.1.3, Pg. St.- No apparen,.

attempt was made to correlate leakage current performance to geometrical considerations such as the presence of barriers and height of blocks with barriers boteseen poles or pole-to-pole spacing.

Perhaps the conclusion stated in Sect. 4.4.1.3 that " Figures 34 through 39 show about one to two orders of segnitude difference beteseen the performance of terminal blocks Se e, and 12 and the one piece blocks, the one piece blocks being better." is not singularly related to the sectional block design, but to other geometrical considerations. For the Phase !! tests, the one l piece blocks referenced here tre S.E. E325 blocks

• which have similar pole spectn, ie ;a M . M1518 '

and States IndM one piece blocks and do possess barriers between poles. .,

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• 0064090 ATTACrMENT 2 -

Westinghouse Partr a7 stems **** 1*WWW Sectric Cwpation #" ***

i l L$

EPmrwume.s A1A-47-442 y SafI 5 87-1000

}

f IIwasbar 23,1987 I t

Mr.1r. G. Mairste, It2, vias Primident Nxlear Ganaraticrs l

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600 Nceth E14.i d.h h ,

aindn@sa,Al 33291 4400 ,

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Onits leo. 1 A 2 -

Den 1.L =Ta'  ;

Daar Mr. shNerets 71.w24 is asiaitieral .

e aka== m enesq +fihi.ica -

--le wo, e ttus tireW4ittichten wes y of gerieruted cable erd for hW1 Eleck Imakaga art 398/2 Ems and 35tP gem W estad Etwumber )

1947. This M -i.ian was generstad as a resalt of the 18C Eigziginarit 0="% 3andit litdst 1sas held charing tbn week at atwember is,1987.

hm sq Mticaml pentlans zagurating ttda plause exzstact the .

w truly years, i enemmes.m Exar.asczC asiksesrztm  :

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w. The attached table contains a listing of Farley Unit i Eastgency Responsa y Procedure (ERP) harsh environment instrur.ents, significant safety related B functions of each instrument, and time usage factors and diverse Q instruments for each function. The purpose of tbs table is to list the r instruments potentially subject to a harsh savironment for lhe Parley i design basis events. These irttruments have an environmental allowance in F their calculated uncertainties used in the ERPa. The design basis events are large and small toCA and secondary systaa pipe breaks! 1.e , steam .

line and feed line breaks.

A review of this table results in identification of a miniaun set of instrumants, and their functions, subject to a harsh anvironment and also

. m nc:t::try fer safa shutdevn from design basis eventa. These are RCS i

X Oance. sling, Wide Range Fressure, and Warrow Range steam Generator-Water t Inval. Backup instruments have been identified where available. Other L instruments necessary for safe shutdown are located in a mild environment

$ or are not affected by current leakage. Other instruments used in the ERPs y - are not used to base any required actions within the Farley design basis

{ events or will not cause any actions to be taken detrimental to pire.t g safety if the instuaant uncartal.nty arceeds the allowance prenantly in the Farley ERPs. i For Res subcooling, staaa canerator Narrow Range !avel and Wide Range Pressure, it is recommanded that for Farley Unit 1 that a containment D tarperature criterion be defia$d that is indicative of current leaka5e 3 resistance of less than S X 10 ohma. A value of greater than 5 X 10 T 'ss results in an ins % mant inaccuracy that will allow the current ERP values to be /.a by *..s ope 4ete t: t "ta z-tion as poecified in the ERPs.

1 The temperature or a carresponding aantainment pressure criterion should be used as guidance to the operator using the IRPe on whan to consider i that additional arror above that already accounted for in the ERPs may l arist. Under conditiona exceeding these critaria no actions which could

. reduce the margin of safety, specifically tarsination.of safety injection

based on RCS subcooling or stopping of all auxiliary feedvatar based on steam Generator Warrow Range tavel or et ing of RER pu mps based on Wide Ranga pr

ssure, shocid be perforzad since a errors may exceed those-accounted for in the ERPs. After containment conaations nave return 64 to below these criteria the operator can safely roeune the use of the ERP

}

specified in rease tavalues, above 5prwidgd X 10 abas. thatThe the tamparature leakage surrent criterion resistance based on wills I f

10 ohns would also apply to Pressuriser Level use in conjunction with I

RCS Subcooling for Safety Injection termination and reinitiation. If the l ERP values for RCS subcooling are changed for Safety 2nj$ction I terminatica, than a laakage carrent resistance of 1 X 10 or greater j would be acceptable for use.

Rased on a review of Figure 1 and Figure 3.0-1, the instrument inaccursey l

that exceeds the value that the operator can utilise with confidence

. occurs at a time when no operator action based on instrumentation in a harsh environment as required for the design basis events describsd above.

For large and small ICCA, no mitigative or recovery operator actie.% e.e required based on inetumentation in a harsh environment. For secondary

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0064092 breaks, Safety Injection termination (the required manual operator recovery action' will occur after the instruasnt accuracy returns to an 1 accote. tis value. There!cn, the eperater 115 itatien dmecribed in t.be

~

previous paragraph will not prevent any necessary operator actions tras being parformed.

A review of the Reactor Protection System and Esargency Safeguards Features functions has determined that the significant functions required for harsh environment events (pressuriant pressure - Imv 87 and steam are required only before 5 minutes after generator water the event occurrence for pressur level - WIow)iser pressure = 1mv SI and 40 seenda for

'*- cis.1: generator water level = tow-law. This early time of use in the event sho.21d anaure that the tunction nacassary will be parformed before a significant errer from leakage currant develops.

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0064098 -:

O ATTicH8tni 3 November 24, 1987 TOs JOHN GARLINGTON }

FROM: JESSE LOVE .. ,

IR vs TEMPERATuer aguppemytys tNrcemATION FOR 3C0 As documented in numerous valid test reports, conducted by Wyle, SNL and other industrial test orgonisations, electrical . able and -

terminal blocks exhibit generic char scteristics with regard to snsula tio.. re si sta-':= (le) versus toeperature during simulated /,

• LOCA/h56B test conditions. The generic characteristic is that IR

=

values are inversely proportional to - tereperature i.e.10we-temperature yields higher value of IR. Conversely with regard to -

J leakage current, leakage current is - directly proportional to

~

toeperature. SNL Report SAND $3-1617 provides numerous data representations which demonstrate thic accepted phenomenon. ,,.

Figure i of Westinghouse letter dated 11/23/97 taas made from plots of SMC33-1617 (SNL) Phase !! ten data for supSours of G.E. ET23 tereinal blocks to the SNL Phase 11 simulated LOCA/MSLB s e m* * ' - H Attac hed Figure 2 Pg . 9 of SANDS 3* M17 ) . IR tett data for an ER25 block esas used f ree the SP4. report as there were no 8 are 1_ States Zhe1, or CR1318 blocks tested Dy ShL in Phase !!, and the a ~5 micek as simitee to these MP installed blocks. Phase I data which eft. *sc0*o oesus p cueronte and IR values for States - "

2WM and CRISAS blocks mas not used owe to sna 2.accera ise associated with the St. electrical test circuitry that measured a leakage current values during Phase I testing.

The minimum values of IR and coe* responding high leakage currents .

recorded in the referenced Spe. test results are entromely T conservative, and are not representative of. values that would be espected at FM' durAng LOCAtteLS design basis events. Minimum values of terminal block 1R val e hig5ee thee these recoesed in the 24. report are oupoorted by CONA1 Teat Report IPS-107, ens wyle Report No.s 17775-1 and 17733-1 1 Toc MSLS/LOCA temperatures relevant ta FNP.

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