ML20091K793

Forwards Advance FSAR Change Re Accident Monitoring Program, Reflecting That Remote Manual Containment Isolation Valve Position Indication on Emergency Response Facility Computer Not Required,In Ref to NUREG-0797, SER, Suppl 23

ML20091K793
Person / Time
Site:	Comanche Peak
Issue date:	01/17/1992
From:	William Cahill, Walker R TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC)
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
RTR-NUREG-0797, RTR-NUREG-797 TXX-92006, NUDOCS 9201270079
Download: ML20091K793 (28)

Text

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, s Log (/ 1XX 92006 l' ,  : File // 10010 C C 907.5 ggg TUELECTRIC 929 Ref. # 10CFR50.34(b)

Wmlam J. Cablil Jr.

January 17 1992 U. S. liuclear Regulatory Commissica Attn Document Control Desk

' Washington, D.C. 20555

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STAT 10ft (CPSES)

DOCKET I405. 50 445 AND 50 446 i ADVANCE FsAR SUBMITTAL ACCIDENT MONITORING CONTAINMENT ISOLATION VALVE POSITION INDICATION REF: NUREG 0797. " Safety Evaluation Report." Supplement 23 (SSER 23)

Gentlemen:

Attached is an advance FSAR change regarding the CPSES Accident Monitoring Program. The change corrects the FSAR to reflect that Remote Manual Containment isolation Valve (CIV) position indication on the Emergency Response facility (ERF)' Computer is not required. These valves do not receive an automatic containment isolation signal, The valves are event driven and  ;

opened or closed by the operator based on the post-accident plant conditions.  !

Note that positim indication for these valves is available in the Main Control Room "us lights on- the control switches and/or on the monitor light boxes in the referenced 55L... the Staff indicated that the CPSES CIV position indication meets the US NRC Regulatory Guide (RG) 1.97. Revision 2 Category 1 requirements. The RG 1.97 Revision 2 reautrement for Category I accident monitoring indication is that the information be continuously displayed and at least one redundant channel be recorded. Although the remote manual CIVs are continuously displayed via MLDs and/or lights at the control switches, ERF display is not.available for recording nor is it considered required for these type valves. ValvM that operate automatically upon receipt of a containment isolation signal have ERF display, and meet the intent of the Regulatory Guide anf the Staff's SSER regarding Catepry I criteria for containment isolation vai a position indicction.

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g Ql 9201270079 920117 4 con.ouve stree: Ls. si D.nu. Tex.: moi PDR ADOCK 05000445 /-

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• 1XX-92006 Page 2 of 2 lo facilitate NRC Staff review o' then changes, the att achnient is organized as follcws:

1. A tr,ar ked up copy of the revised FSAR pages (additional pages immediately preceding and/or f ollowing the revised pages are provided if needed to understand the change).

2. A description / justification of each item involved.

3. A copy of related SER/55tR sections.

A 10CfR50.59 evaluation was performed for the above change. The evaluation revealed that no unreviewed safety question is created as a result of the position indication for the subject valves not being wired to the iki computer. This change will be included in a future amendment to the fSAR.

If you have any questions regarding this submittal, please contact Veronica Cornell at (214) 812 8806.

Sincerol ,

,h

• William il. Cahill, ilr.

ny d?e' f.f/ w Roger D. Walker Manager of Nuclear t.icensing Attachment VPC/vid c - Mr. R. D. Hartin, Region IV Resident inspectors. CPSES (2)

Mr. Tom Bergman (NRR)

Mr. Nel Fields (NRR)

_ _ _ . _ _ _ = _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ...w

< o AT'i ACHMENT TO TXX 92006  ;

i

1. Marked up copy of revised FSAR pages pages 1 thru 21 ,

2. Description / justification pages 22 thru 24

3. Related SER/SSER sections pages 25 thru 28 -

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CPSES/r5AR

,. RE5FONSE TO NRC ACTION PLAN 27' l The data set av ilable to the TSC Data System will be complete l enough to permit a:cusate assessment of an aclident without i interfererice with the cont rol room enargency operation.

' C r, i and.

68 l The data set available to the ERF Ccmputer System includesg _ M

, l Type A B, C and E Accident finnitoring variables (as described

'M E l in FSAR 3ection 7.5) and the type D Accident Monitoting #

t  ; variables ,,hich are also identitled at type 0 wariables in

! Reculatory Guide 1.97, Rev. 2. Table !.

' 4h , All sen5cr data aild calculated variables ust) in the dat a set l for 3P05, EOF, or for transatission to of f site locations t ill be I available for display. The accu"acy of the data displayed will 27 l be substantielly the same as the accuracy of comprable data n 36 l 1 displeyed its the control room. The time resolution of data

' acquisition will be tuffic19nt to provice data without loss of

/ , 1 inforniation during tranjient conditions where that data is l necessary for operator action. The time resolution of each l sensor signal will respond on the potential transient behavior

} rd the variable being measured.

[ 27 l Visk and tape storage anc recall capability will be provided for j the TSC data set. Twe hours of pra event and 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> of post

'l even: iiata will be recorded.

07 I TM samolt frequency will be consistent with the use of the l data. Capacity to record two weeks of additional post event data will be provided. Archival data storage will be provided I automatically, and retrieval will be accomplished without 30 l interrupting the TSC data acquisition function. The ERF l t!isplays (3 of which will be provided in the CPSES TSC) if used l for data retrieval, will not br available for real time l parameters, but can be returned to on line display service very l quickly.

Amendmut rchcoose., , e 68 It!.A-12 omam _ _ _ _ _ _ . _ _ _ _ _ _ . _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ .

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Attach ent to TXX-9'2006

',= 'Page 20 of 28-CPSES/FSAR TABLE 032.110 3 Notes for Table 032.110-1 and 032-110-2 (Sheet 3)

Instrumentation Sumary Data 18, **Various" for Range means that different positions are monitored 66 for different valves including open/not open and/or closed /not closed and/or intennediate positions.

l.ocA1 19.

All valves listed in FSAR Table 6.2.4-2 exceptgmanual, check, 66 relief and safety valves.

20. ERFCS displays the valve position requirerents (e.g. Closed /Not 66 Closeu) of Reg. 1.97, Rev. 2 Table 2.

21. Deleted.

l76

22. These parameters are 02 variables as they monitor other systems 66 normally employed for safe shutdown but are not required during or following an accident iper section 7.5.1.1.1). When required, these-instruments are in a mild environment and therefore do not require environmental qualification.

23. Only CR Ventilation dampers are listed on Table 032.110-1 because 66

[ we understand that the intent of the variable " Emergency-Ventilation Dampers" in' Table 2 of Regulatory Guide 1.97, Rev.

2, was limited to the dampers required to realign the Control Room Ventilation System for its post-accident emergency ventilation modes. At CPSES, we have included additional ESF ventilation carameters as eccident monitoring variables (See Table 032.110-2).

24. Table 032.110-2 does not identify which variables are displayed 66 in the Control Room, on the ERF Control Console, in the TSC or in l the EOF as these displays are not required by Reg. Guide 1.97, Rev. 2, Table 2.

ARENDMENT 78

' MAY 1,1989

.- - - ._. - - -_ _ . . . . . - ~ _ _ - - - - - - .... _ . . -

. Attachitent to TXX 92006

-. ,Page 21 of 28 CPSES/FSAR TABLE 032.110-3 Notes for Table 032.110-1 and 032-110 2 (Sheet 4)

-Instrumentation Summary Dan

25. For Category 2 and 3 non lE instrumentation, environmental. l66

. qualification -seismic qualification and quality assurance l requirements are not listed if not required by the accident l monitoring program.

l

26. -QA is provided as necessary to support Environmental l66

-Qualification. (

.pa$moyh*P*@

27 f% l7.'VE ltJDicAT(oN is NoT Rs.sutR.Eb IN WE E.R F don 1PuT Eit. FoR REMOTE MfNUAL VALVEE*

28. 'sE E RESPotJSE To %E NRC ACTION fL AN DEVELoPEb AS A RE5utT oy W G Tm1-2 A ccibE NT SECTioM E . A . l . ). .

l l

l Amendment *66 January 15, 1988

.. . = .. - . . . - . .

Attach cnt to.TXX 92006 Page 22 of 28. CPSES FSAR AMENDHENT 84 a'

• DETAILED DESCRIPTION Page 1 FSAR Page (H Mt04td) ELE.RynJ D scription THI !!!.A-12 2 Accident monitoring position indication for containment isolation valves Correction:

Revised FSAR to clarify the accident monitoring instrumentation data set which is available on the ERF computer. The data set includes Category 1 and applicable Category 2 Type A B, C, and E accident monitoring variables and Type D accident monitoring variables as identified in Table 2 of RG 1.97 Revision 2. A specific listing of each accident monitoring parameter available on the ERF computer is identified in the existing FSAR accident ronitoring tables.

FSAR Change Request Number: 91-179.6 Related SSER Section: SSER23 7.5.2 SER/SSER Impact: No 05R Table 032.110-1 2 See Sheet No(s):01 thru 10 Accident monitoring position indication for containment isolation valves Correction:

Adds Note 28 to clarify the requirements for accident monitoring instrumentation displays for the TSC and EOF.

FSAR Chance Request Number: 91 179.1 Related SSER Section: SSER23 7.5.2 SER/SSER 1mpact: No

-Q&R Table 032.110-1 2 See Sheet No(s):03 Accident monitoring position indication for containment isolation valves Correction:

Added " Note 27" to containment isolation valve accident monitoring control room displays to reflect that remote manual valves do not have ERF displays.

FSAR Change Request Number: 91-179.2 Related SSEP Section: SSER23 7.5.2 SER/SSER 1mpact: Yes SSER 23 section 7.5.2 indicates that containment isolation valve position indication instrumentation meets the RG 1.97 Category 1 criteria.

OhR Table 032.110 3 3 See Sheet No(s):03 Accident monitoring position indication for containment isolation valves Correction:

Revised Note 19 to clarify that " local" manual versus

" remote" manual valves are excluded from the containment isolation valves listed in FSAR Table

Attach:snt:to-TXX+92006 L.: " N Page 23 of'28 CPSES FSAR AMENDHENT 84 DETAILED DESCRIPTION Page 2 ,

FSAR Page.-

=(n macaded) St9MD Descriptio!)

6.2,4-2, FSAR Change Request Nun.ber: 91 179.3 Related SSER Section: SSER23 7.5.2 l SER/SSER Impact: Yes d SSER 23.Section 7,5,2 references manually operated containment isolation valves, but does not specifically differentiate between " local" and " remote" manual valves.

l0&R Table 032.110 3. 2 See Sheet No(s):03 -

Accident monitoring positiot Indication for containment l isolation valves Correction: '

~Added Note 27 to reflect _that position indication

on. the ERF computer for ren ote manual containment isolation valves (CIVs)

is not required. The remote manual CIVs do not receive an automatic containment

' isolation signal. These valves are event driven and controlled.by the operator. based on the post accident conditions. The RG 1.97 requirement for Category 1 accident monitoring indication-is that the information be continuously displayed and at-least one redundant channel be recorded,- Although these. valves are continuously displayed via MLDs and/or status lights at-the control switches ERF-display is not

-avai_lable for recording nor is it considered required.

Containment-isolation valves which operate automatically upon receipt of a containment isolation--

signal have'ERF displays in the control room,_TSC and EOF, For remote manual CIVs, direct and immediate trend or transient information~is considered not. essential for Loperator.-information~ or action short-term. -Long "

term the operator maintains awareness of the valve position-via control board displays. The TSC and EOF-staffs are only_ concerned with the affect of valve position on the respective system performanca,-The TSC .

and EOF staffs would be aware of manipulations of-the remote manual CIVs via the control room interface -

required as part of_the Emergency Response organization,- Thus, ERF computer position indication for the remote manual CIVs is not required for essential functions of the TSC or EOF,

, .FSAR Change' Request _ Number: 91-179,4 Related SSER Section: SSER23 7.5.2 SER/SSER Impact: Yes p

SSER 23 section 7.5.2 indicates that containment

. isolation ~ valve position indication instrumentation meets the RG 1,97 Category 1 criteria.

0&R Table 032,110 3 2 See Sheet No(s):04 Accident-monitoring _ position indication for containment isolation valves

Attachment to TXX 92006 s

'Page-24 of 28 CPSES FSAR AMENDMENT 84 DETAILED DESCRIPTION Page 3 FSAR Page (11 amended) Dr_ upun piscriptiga Correction:

Adds Note 28 to clarify the accident monitoring instrumentation display requirements for the TSC and EOF. Note 28 cross references THI Section lit.A,1,2 which provides the basis for the accident monitoring instrumentation data available to the TSC and EOF staf fs, which includes Category 1 and applicable Category 2. Type A, 8. C and E accident monitoring ,

variables and Type 0 accident monitoring variables that  !

are identified as such in RG 1.97, Revision 2 Table 2.

FSAR Change Request Numbcr: 91 179.5 Related SSER Section: SSER23 7,5.2 SER/SSER Impact: No

L Attach;ent to TXX 92006 e' ' 'Pags '25 of 28 has'a range of 50'F to 700*F. Revision 3 of RG 1.97 recommends a range of 50*F to 700*F for'this-instrumentation. Therefore, the range suppliec ey the apoli-

~ cant for.this instrumentation is acceptable.

Reactor Coolant System Ho Leo Water Temperature

~

RG 1.97 recommends a control room display with a range frum 50'F to 750'F for this variable. The instrumentation provided by the apolicant for this variable has a range of 50'F to 700'F. Revision 3 of RG 1.57 recommends a range of 50'r tt 700*F for this instrumentation. Therefore, the range supplied by the acoli-cant for tnis instrumentation is acceptable.

Reactor Coolent level RG 1.97 recommends reactor coolant level instrumentation with a range from the bottom of the core to the top of the reactor vessel. The instrumentation oro-vided by the applicant has a range covering from the upper core plate to the top of the reactor vessel.

Revision 3 of RG 1.97 recommends a range from the bottom of the hot leg to the tcp of the reactor vessel for this instrumentation.

The iestrumentation provided by the applicant meets this range. Therefore, the range supplied by the applicant for this instrumentation is acceptable.

Containment Sump Water Level RG 1.97: recommends-both narrow-range and wide-range (up to 600,000 gal) instru-mentation for containment sump water level. The applicant has proviced wice-range instrumentation that has indication from 80E f t to 817 f t 6 in. There is no separate narrow-range instrumentation for this variable. The aoolicant sta-ted that the wide range instrumentation displays the entire range of excectec-postracident levels in the containment and includes the information that tne recommended narrow-range instruments would display, Because the wice-range instruments are inclusive of the narrow-range recommendations, the staff fi os

, .the instrumentation supplied for this variable acceptable.

Containment Isolation valve ?osition The applicant identified an exception to RG 1.97 for this variable in tnat tne ,

manually operated containment isolation valves do not nave tne recommenced valve position-indication instrumentation.- Those containment isolation valves tnat are operated automatically have the recommended position-indication instrumen-tation for each v41ve. The applicant provided documentation which states tnat all manually-operated containment isolation valves are administrative 1y controi-led and locked in the closed position. Thus, the operator is aware of the posi-tion of these valves in a postaccident situation. Because the operator is aware that these valves are locked closed and has indication for the automatically operated isolation valves, the staff finds tne-instrumentation proviced for L containment isolation valve position acceptable.

Additionally, the applicant's containment isolation valve position-indication instrumentation deviates from a strict interpretation of tho Category-1 recom-

-mendation for redundant instrumentation. There 1s one open/ closed limit switen

, per automatic valve uith indication at the control switch and at monitor light boxes. Since redundant isolation valves are provided, the staff finds that tne

. regulatory guide does not intend redundant u dication per valve. There is re-dundant indication of the isolation function. The cantainment isolation valve Comanche Peak SSER 23 7-7 i

maa Attachment to TXX 92006 i*

• Page 26 of 23 position-indication instrumentation meets the Category 1 criteria. Therefore, the staf f finds that the instrumentation provideo is acceptaole.

Residual Haat Removal Exchancer Outlet Temoerature RG-1,97 recosuends instrumentation with a range from 32*F to 350'F for this variable. The instrumentation Drovided by the applicant for this variable nas a range of 50*F to 400*F, an 18' deviation in the lower limit of the range.

The applicant provided documentation which states that the 50*F-to-400'F range covers the anticipated recuirements for normal operation, anticipatec coerational eccurrences, and accident conditions. On the basis of this statement, the staff finds the provided range acceptable.

Accumulator Tank level and pressure RG 1.97 recommends instrumentation with ranges from 10 percent to 90 percent of -

the accumulator tank volume for level and from zero to 750 psig for tne accumu-lator tank pressure. The applicant has designated pressure as the key instru-mentation for,this variable and has supplied Category 2 aressure instrumentation.

Category 3 level instrumentation is acceptable as backup instrumentation to tne Category 2 pressure instrumentation.

p The supplied instrumentation has ranges from zero to 100 percent (level) and zero to 700 psig (pressure). The applicant provided documentation which states that ooth ranges cover the anticipated re-quirements for' normal operation, anticipated operational occurrences, and acci-dent conditions. On the basis of this statement, the staff finds the provided ranges acceptable.

_ Flow in Low-pressure Injecti

n System RG 1.97 recommends Category 2 instrumentation for this variable. Section L 5 of tne FSAR does not address this variable; however, from previously suomittec material for the CP3ES design, low-pressure iniection is a residual heat remova!

(RHR) system function. The RHR flow is monitored oy Category-2 instrumentar or In accordance with RG Guide 1.97. Therefore, the staff fines the instrumentati:n provided for this safety-injection function acceptable.

Boric Acid Chargino Flow

- RG 1.97 recommands Category 2 instrumentation for this variable to monitor lL safety-injection flow. Section 7.5 of the FSAR states that in the CPSES design.-

this safety-injection flow is established by the centrifugal charging pumo.

The centrifugal chfrging pump flow is monitored by Category 2 instrumentation-in accortiance with RG 1.97. ' Therefore, the staff finds the instrumentation l -

provided for this safety-injection function acceptable.

Quench Tank Temperaty,ry, RG 1.97 recommends-instrumentation with a range f on 50"F to 75f)'F for this variable. The instrumentation provided by the applicant for this variable has

, a range from 50*F to 350*F. The applicant provided documentation which states

,T that the 50'F-to-350'F range covers the-anticipated requiroments for normal operation, anticipated coerational occurrences, and accident conditions. This u

h related to the design pressure (100 psig) of the tank and the corresponding taturated steam temperature at this pressure. On the t'rsh of this statement, the staff finds the provided range acceptable.

Comanche Peak SSER 23 1-8

Attach ent to TXX 92006 l < ' ,, " **Paga 27 of 28 Accident Samoling (Primary Coolant, Containment Air, and Sumo)

The postaccident sampling system provided by the applicant includes samoling and analysis as recommended by RG 1.97 except for tne following deviations.

(1) Boron content--The minimum observaele concentration is 500 ppm.

(2) thloride content--The minimum observable concentration is 25 cen.

--The maximum coborvable concentration is 5 com.

(3) Dissolved nydrogen--The minimum obtsrvable concentration is 0.5 c:/kg.

(4) Dissolved oxygen--The minimum observable concentration is 0.1 ppm.

(5) Hydrogen content--The minimum observable concentration is 0.1 percent.

(6) Oxygen content--The minimum observable concentration is 0.1 percent.

Additionally, there is no display in the control room.

The applicant deviates from RG 1.97 with respect to postaccident samoling capability. The staff addressed this deviation in its review of NUREG-0737, Item II.B.3, and finds it acceptable.

Environmental Oualification, Indig tion, and Recording Table 7.5.-1 o' the FSAR statt5 that environmental cualification will be *o-vided "as appropriate" for. Category 2 variables. The aoolicant pro.iceo clari-fying documentation which indicated that the instrumentation sutplied f:r Cate-gory 2 variables is eicer environmentally qualified (per 10 CFR 50,49) or 's located in a mild environment for the length of time tnat the instrumentat':n was cesigned to function. The applicant also indicP.ed that Category 2 inst'-

ments are either environmentally qualified or located in a mild environrert :-

accordance witn the recommendations of RG 1.97. Thit, it in ar.corcance ait9 RG 1.97 and is acceptable.

Table 7.5.1 of the FSAR states that the it dication for Cat.egory 1 variaeles is "immG:iately accessible." RG 1.97 recommends continuous indication for Category 1 variables. The applicant provided documentation stating that ss a minimum, all Category 1 variables are continuously displayed or are available for display on demand. The applicant also provided documentation stating tnat each channel of Category 1 instrumentation has a dedicated indicater, recorcer, or display device satisfying this recommendation. With this clarification, the staff finds the Category 1 indicators, recorcors, snd display cevices acceptable.

Table 7.5-1 and Section 7.5.1.3.1.4 of the FSAR state tntt the emergency re-sponse facility (ERF) computer is the device use for recording the Category 1 variables. The applicant provided docunientation describing this capability, t-2nstrumentation/ computer isolation is provided by qualified Class 1E optical isolation devices for Class 1E equipment. The ERF computer was designed to meet the requirements of Supplement 1 of NUREG-0737. On the basis of tnis ce-scription of the recording capability of tne ERF computer and tne described isolation between Category 1 and Category 2 instrumentation and the ERF compu-ter, the staff finds the recording capability provided acceptable.

Comanche Peak SSER 23 7-13 1

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Attach ent to TXX 92006

~ '" O Page 28 of 28 I The CIV status indication is provided by unicle monitor light boxes located on the main contr'ol board and oy indicator lighw that are part of each CIV con-i trol switch assembly. Pattern recognition (as ' monitor light boxes lit or i=

unlit) quickly alerts the aperator to the valve *osition. The CIV control switches are already color coded in accordance with the associated safaty train and power source. Additional color coding is deemed by tht applicant to be potentially confusing. On the basis of this justification, the staff finds the identified deviations in instrument identification acceptable.

Isolation of Category 2 Inctrumentation The applicant provided documentation stating that those Category 2 instrument loops that are powered by Class 1E power and feed signals to other systems nave approved isolation devices. Those Catagory 2 instrument loops that are powerec by other Category 2 (but not Class 1E) oower sources either do not feed signals to other systems or have similar isola 1.fon devices. On the basis of the ce-scribed isolation devices where signals cross from Categsry 2 instrumentation to other systems, the staff finds the isolation provided for these Category 2 instrument channels acceptable.

Containment Atmospher; Tem eea g RG 1.97 recceends instrumentation for this variable with a range f rom 40'F to 400*F. The instrumentation provided by the applicant has a range from zero to 360'F. The applicant provided documentation stating that the peak postaccident containment temperature is 345'F. On this basis, the staff finds the proviced zero to 300*F range acceptable.

Containment pressure RG 1.97 recommtods instrumentation for this variable with a range of 10 osig to 3 times the design pressure of 50 psig. The applicant provided documenta-tion stating that this range is covered by two sets of instruments--the inter-mediate-range instruments that have a range of -5 to 60 psig and the wice-range instruments that have a range of zero to 150 psig. With the use of these t o sets of instruments, the staff finds the ranges provided for this variable ac-

.ceptable.

Radiation Level in Circulatina Primary Coolant The applicant statgd in its March 31, 1989 letter that radiation level measure-ments to indicate fuel cladding failure are provided by the postaccident samo-ling system, which has been reviewed by the NRC as part of the staff's review of NUREG-0737, Item II.B.3. The staff finds thi:; alternative instrumentation acceptable for meeting the recommendations of RG 1.97.

7.5.4 Conclusions On the basis of its review of the tubmittals provided by the applicant, the staff concludes that the CPSES Units 1 and 2 design is acceptable with respect to conformance to RG 1.97, Revision 2. Outstanding Issue 2 in SSER 22 is, therefore, resolved.

Comanche Peak $5ER 23 7-15