ML20236S688

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Forwards Progress Update on Equipment Installation,Including Clarification of Util Position on Separation Criteria & SPDS for Each Position,Per Rev 2 to Reg Guide 1.97
ML20236S688
Person / Time
Site: Fort Calhoun 
Issue date: 11/24/1987
From: Andrews R
OMAHA PUBLIC POWER DISTRICT
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
RTR-REGGD-01.097, RTR-REGGD-1.097 LIC-87-657, NUDOCS 8711300037
Download: ML20236S688 (23)
v • d • e


Text

- - _ _ -

Omaha Public Power District 1623 Harney Omaha. Nebraska 68102 402/536 4000 November 24, 1987 LIC-87-657 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 l

References:

1.

Docket No. 50-285 2.

NUREG-0737, Supplement 1 (Generic Letter 82-33) dated December 17, 1982 3.

Letter OPPD (W. C. Jones) to NRC (R. A. Clark) dated April 15, 1983 (LIC-83-093) 4.

Letter NRC (E. J. Butcher) to OPPD (R. L. Andrews) dated July 19, 1985 5.

Letter OPPD (R. L. Andrews) to NRC (D. E. Sells) dated October 21, 1986 (LIC-86-532) 6.

Letter OPPD (R. L. Andrews) to NRC (Document Control Desk) dated January 12, 1987 (LIC-86-700) 7.

Letter NRC (F. J. Miraglia) to OPPD (R. L. Andrews) dated February 20, 1987 8.

Letter NRC (W. A. Paulson) to OPPD (R. L. Andrews) dated April 22, 1987 (SER)

Gentlemen:

SUBJECT:

Compliance with Regulatory Guide 1.97, Revision 2 Please find attached a progress update on equipment installation.

This update also includes clarification of Omaha Public Power District's (0 PPD) position on i

separation criteria, and what constitutes the Safety Parameter Display System f

(SPDS) as each relates to OPPD's commitment to meet the requirements of l

Regulatory Guide 1.97 Revision 2.

)

If you have any questions or require additional information, please contact us.

Sincerely,

/$ W R. L. Andrews Division Manager Nuclear Production 8711300037 871124 RLA/me hDR ADocM 05000285 PDR Enclosure Ip3 l

c:

LeBoeuf, Lamb, Leiby & MacRae R. D. Martin, NRC Regional Administrator A. Bournia, NRC Project Manager P. H. Harrell, NRC Senior Resident Inspector l

l 4

4s sm r muu,umenmni e cuampoonunau Ma!e F ema,e

1 i

The following discussions are to:

I 1.

Clarify OPPD's position on redundancy as it applies the requirement f

to meet the guidance of Regulatory Guide 1.75 " Physical Independence l

of Electrical Systems".

1 2.

Provide an update on the status of open items or modifications which I

require resolution or installation to be in full compliance with Regulatory Guide 1.97 Rev. 2.

3.

Clarification of the Regulatory Guide 1.97 Rev. 2 (abbreviated R.G.

1.97) variable indication as it relates to the SPDS and ERF computer.

1.

Clarify OPPD's Position on Redundancy Section 1.3.lb of R.G.

1.97 requires that for Category I variables, Redundant or diverse channels should be independent and ohysically separated from each other and from eauipment not classified imoortant to safety in accordance with Reaulatory Guide 1.75 " Physical Independence of l

Electric Systems" up to and includino an isolation device.

Regulatory Guide 1.75 (R.G.

1.75) provides an acceptable method of complying with IEEE Standard 279-1971 Criteria-for Protection Systems for Nuclear Power Generatina Stations.

The Fort Calhoun Electrical

System, including the original control panels, was designed and installed to meet the standards delineated in IEEE 279-1968 as discussed in Section 7 (Instrument and Control) and Section 8 (Electrical) of the Fort Calhoun Station USAR. Newer control panel s which themselves may achieve a higher degree of separation are still interfaced to the existing cable tray and conduit system designed and installed to IEEE 279-1968.

It is OPPD's belief that the existing level of independence and separation is adequate to meet the intent of the Category I variable redundancy requirement, and the intent of IEEE 279-1971.

Based on the preceding discussion which established adequate separation and independence, OPPD takes exception to the requirements of meeting R.G.

1.75 (IEEE 279-1971) in the original control panels and the cable tray and conduit separation for Category I variables.

2.

Status of open items or installation to achieve compliance with R.G.

1.97.

Note:

The section numbers referenced are from Section 6 of OPPD's R.G.

1.97 submittal Revision I dated October 21, 1986.

This submittal is reference II of SER issued to OPPD on R.G. 1.97 dated April 22, 1987, Walter A. Paulson to R. L. Andrews.

1 1

1

e e,.<

I f

y i

1 a.

6.1.4 RCS Pressure The high range pressure (to 2900 psia):was installed and made -

operational during.the.1987 refueling. outage.

Please note that completion of the ATWS rule -diverse scram system is-planned for the 1988 refueling 1 outage ~pending.NRC approval.of OPPD's, ATWS rule diverse reactor trip.

b.

-6.2.1 Quench' Tank' Pressure Installed and made. operational during the 1987 refueling outage.

c.

6.2.2 Radioactive Gas Decay Tank Pressure Installed and made operational during the 1987 refueling outage.

d.

6.2.3 Containment. Atmosphere Temperature

. Installed and made operational during the 1987 refueling outage.

e.

_6.2.4 Shutdown Cooling Flow Installed 'and made operational during the 1987 refueling outage, f.

6.2.5 Shutdown Cooling Heat Exchange Outlet Temperature Installed and made operational during the 1987 refueling outage.

g.

6;2.6 Containment Sump Temperature Sche'duled for installation during the 1988 refueling outage.

h.

6.3.1 Wind Speed Calibration completed.

Uncertainty is now within the required tolerance.

1.

Pressurizer Level Modification is scheduled for the 1988 refueling outage to upgrade the separation and isolation to meet the Category I criteria as approved in Modification of Commission Order, Reference 7.

J.

Safety Injection Tank Level and Pressure Per the SER, Reference 8 the SI accumulators tank level and pressure remain an open item pending NRC review of the generic issue.

OPPD at present plans no modification of the existing instrumentation until the review is completed, i

2

p 1

3.

l Clarification of R.G.1.97 variable displays on.the SPDS/ERF computer.

.The Fort Calhoun Station ERF computer (designated ERF because of its location. in an Emergency Response Facility) serves as the plant computer asJ well as generating the Safety Parameter. Display System (SPDS)

'displ ays.

The: SPDS consists. of eight (8) displays (seven bar graph-screens: containing several bargraphs on each screen and one safety function matrix).

These eight displays are defined as top level display (the safety function matrix) and the midlevel displays (the seven bar graph screens). -These eight displays are accessible on the ERF CRT's via

.a single key _ stroke.

A third level of displays- (Piping and Instrument Drawing updated with real time variable data) are linked to each midlevel display and are. directly accessible from the related midlevel display.

Below these three levels of display are the individual analog and digital variables which may be addressed from the keyboard as required.

i 1

The top level dis' play condenses: the information of many variables via algorithms Lto provide the user a summary of critical parameters during normal and off normal operating conditions. The midlevel displays use a

-combination of direct display of data and certain algorithms to provide numerical details of the top level display.

In1 OPPD's: previous submittal s, the acronyms SPDS and ERF were used interchangeably.. ~Tabl e I (attached) will better define the computer access- (if available) to the R.G. 1.97 variables in the context of the four' levels (top level, mid level, drawing, and computer point) discussed

. previously.

4 l

1 3

i

g*

TABLE 1 Computer Display of R.G.1.97 Variables Type A Variables SPDS SPDSL

'TogLeve}-

MigLeve}-

ERF.

ERF-D

'Ayawing A or.D A or D or D2 Compyter[oint

Variable A or-

'I'

' REACTIVITY CONTROL

-1.

Neutron Flux A

A-D D

.(NT-001,001, 0

'003,.004)

,II.

RCS INVENTORY / PRESSURE CONTROL-1.

Pressurizer Level A

D D

D (LT-101X/Y).

2'.

.RCS Pressure A.

D D

D

.(PT-105,:115)

,(PT-120A,PT-1208) 3 3.

Degrees of Sub--

A D

D D

cooling-(SPDS)

III. CORE & RCS HEAT REMOVAL 1.

Cold Leg Temperature A D

D D-3 2.

Hot Leg Temperature A D

D D

3.

Core Exit Temper--

A D3 D

D ature (RC-7D),(I-28)

Al used in'an algorithm; actual value is not displayed 2

'D

- direct display / read out' of the value 3

.D the v'alue displayed is the average, highest, lowest etc. of redundant channels 4

r

I'I-

.l, c

.y.

I' TABLE'I u.

. Computer Display of R.G.-'1'.97 Variables

. Type A Variables-1 i '

SPDS SPDS ERF ERF

'TgpLevg1;

-A{dLevg1

'Ayawing

.M D

or.D

. or D or D2 Cogpute'rPoint' A or D2

' Variable

.A 3

3 4.

Degrees of'Sub-A D

D-A cooling-

'5.

RV Level.

A D

D D

(Y-116A/B).

6.

_S/G. Level A-D-

0 D

(LT-911 A/B)'-

-(LT-912'A/B)

III.

CORE & RCS HEAT REMOVAL (continued)-

7' S/G Pressure Af D

D D

(PT-913 A/B)

(PT-914.A/B)

IV.

CONTAINMENT COMBUSTIBLE

. GAS CONTROL 3

Containment A

D D

D-H. Concentration (2VA-81A/B).

'V.

CONTAINMENT RADIATION 1.

Containment High A

A D

D Range Radiation (RM-091A,RM-0918) lA' used.in an algorithm; actual value is not displayed

.D2 - direct ' display / read out of the value D3 - the value displayed is the average, highest, lowest etc. of redundant channels 5

TABLE 1 Computer Display of R.G.1.97 Variables Type B Variables SPDS SPDS ERF ERF TgpLevgl AjdLevgl Drgwing 2 CompyterPgint M

Variable A

or D or D A or D A or D 1.

REACTIVITY CONTROL

1. Neutron Flux See Type A Variable 1.1
2. Control Rod A

A D

D Position (CEDM's)

3. RCS Soluble D

D Boron Concen tration (SL-25)

D D

4. RCS Cold Leg D

Water Temperature (TT-113 TT-123)

II. CORE COOLING

1. RCS Hot Leg Temp. See Type A Variable III.2
2. RCS Cold Leg.

See Type A III.1 Temp.

3. RCS Pressure See Type A II.2
4. CET See Type A III.3 lA - used in an algorithm; actual value is not displayed D2 - direct display / read out of the value 3D - the value displayed is the average, highest, lowest etc. of redundant channels 6

h I

TABLE'11

' d u

Computer Display. of R.G.1.97 ' Variables l

b Type B Variables p

)

SPDS SPDS ERF ERF TgpLevglJ

~A{dLevgl Dpawing2 CogputerPoint

)

M 2

Variable A or D.

or D A or D A or D

-5. RV Level See. Type A-111.5 Monitoring

6. Degrees of Sub-See Type A II.3 9

cooling l

s l

III. MAINTAINING REACTOR COOLANT SYSTEM INTEGRITY I~

RCS Pressure _

See Type A Variable II.2 2a. Containment A

'D3 3

D D

i Sump Water j

a Level (Narrow).

'3 (LT-599,600)

L 2b.

Containment.

D D

Sump Water Level (Wide)

(LT-387 A/B/C/D LT-388 A/B/C/D) 1:

J 3

3 l

3.

Containment D

D D

l L

Pressure Il

~

(PT-783,784)

)

Al - used in an algorithm; actual value is not displayed I

i D2 direct display / read out of the value I

- the value displayed is the average, highest, lowest etc. of redundant chaibels 3

D

'\\

7 s

.1

- _ = _ -

I j

'p a

+

1, i

7

n

.TMlf-_1 1

s k'

Computer Display of R.G.1.97 Variables t

a

\\

+ Type B Variables s

7,:

Il V 4

SPDS SPDS ERF ERF T

C

[

AgpLevgl MjdLevgl Dgndr g,,

AgmputegPoint g

3 Variable t or D A or D A c/ D' or D R

LW[lTAININECONTAINMENT

.IV.

1N_T[GRITY,.

I 1.

Containment A

A D

i D

Isolatiort Valve Position Note:

Item IV.1 is a summary of valve positions l!-

Items IV.1, A through MM which have

\\

identical readouts.

V 2.

Containment Set Type 8 Variable, Item III.3'

+f

[,,,,, ',

Pressure I;

FbELCLADDiNG i

1. CET See Type A Variable 111.2 i

s[

2. Radioactivity 1

Concentration'n in Primary Coolant (SL-I6,4b);

\\

ls 3.> Analysis sf

'Prird y

\\,

l

(:"

Coolant (Garma i

Spy.trum) (SL 17 l

GrdS $h3ples) 1 c J' l

'j 3

i

(

i

/

(

lA - used in an alp /rfthm!:,7ctual value is not displayed y

i 1

2D - direct display / read 06t of the va'ue jj 3

D - the value displayed is the aver &ge, highest, lowest etc. of redundmt channels

/

e

)\\

s

't

$~

f

'\\

1(

l s

l*

},3. )a! i

' n s,

i a

1

.l

.yy I' ' l/

V v

Coniputer Display of R.G. _1.97 Variables -

4 Type B Variables t e, 7

'SPDS

  • SPDS ERF ERF jih Tgp1.evgl' "M{dLevg1 Ajawingor D,2CgmputegPoint l

D M

Var,ia,ble A or D

, A, or D A or D I

II.; BEACTOR C00MN.I PRESSURE BE N9AREr l

p r

o

1. RCS Pressure See Type A Variable II.2
2. Containment See Type B Variable III.?u q.

f.

Pret.sure

)

l 3a, Containment See Type B Variable III.2A 1

' ' " Surrn Water

)

? Level (Narrow) d L

3b. Containment See Type B Variable III.2b Sump Veter Level pide)

4. Containment A

A D

D 1

Area Radiation (RM-070 thru 075)

5. Effluent Radio-A

'A D

)

D activity Noble Gas (RM-057)

Condenser Off Gas a 1

Al - used in an algorithm; actual value is not displayed D2 - direct disp ~ lay / read out of the value

'D3 - tha value displayed is the average, highest, lowest etc. of redundant channels 9

f

)

i __

TABLE 1 Computer Display of R.G. 1.97 Variables Type B Variables h

l SPDS SPDS ERF ERF L

TgpLevgl MigLeve{

Dgawing2 AgmputegPoint C

Variable A or D A or D A or D or D III. CONTAINMENT

1. RCS Pressure See Type A Variable 11.2
2. Containment-See Type A Variable IV.2 H2 Concentration 3

3

3. Containment A

D D

0 Pressure (PT-783,784)

4. Containment D

D Effluent Radioactivity (Noble Gases)

(RM-063)

5. R.G.1.97 Rev. 3 Deleted Requirement for Radiation Exposure Rates
6. Effluent Radio-activity (Aux. Bldg.)

(RM-063) i I.

RESIDUAL HEAT REMOVAL

1. RHR System Flow F-326 IA - used in an algorithm; actual value is not displayed

-D2 - direct display / read out of the value 3D - the value displayed is the average, highest, lowest etc. of redundant channels 10 i

i+ f

'l TABLE'1

Computer Display of.R.G.1.97. Variables.

Type B Variables-

r SPDS-SPDS ERF-ERF AgpLevg1 A{dLevg1 Agawing T

M D

CgmputepPoint 2

iVariable or D or D

. or D A or D

2. RHR System D

D HX Outlet-Temp, T-342, 343-II. SAFETY INJECTION SYSTEMS-D D

-la.

S.I. Tank Open Pending NRC Resolution of the Generic ' Issue Level (LT-2904, 2924~,2944, 2964).

I b.'

S.I. Tank Open Pending NRC Resolution of the Generic Issue Pressure (PT-2901,'2921, 2941,'2961) 2.

S.I.' Tank Isolation Valve Position (HCV-2914, 2934, 2954,.2974) 3.

Boric Acid Charging D

D Flow (FT-236)

Al - used in an algorithm; actual value is not displayed D2 - direct display / read out of the value 3D - the value displayed is the average, highest, lowest etc. of redundant channels l

11 i

b__.____.

TABLE 1-Computer Display of R.G.1.97 Variables Type B Variables SPDS SPDS ERF ERF T p Lev 1 M{dLev1 D awing C mpute Point A or D A or D2 Variable A or D A or D 4.

Flow in HPSI A

D D

(FT-313,316, 319,322) 5.

Flow in LPSI A

D D

(FT-328,330, 332,334) 6.

SIRWT Level D(L-381)

D D

(LT-381,382)

IV.

PRIMARY COOLANT SYSTEM 3

1.

RC Pump D

D D

Status (Y-3268,3269, 3270,3271) 2.

Primary System Relief Valve Position (PORV) or Flow Through (FT-141,

{

142) (F102-1, l

102-2) 3.

Pressurizer See Type A Variable 11.1 Level Al _ used in an algorithm; actual value is not displayed D2 - direct display / read out of the value D3 - the value displayed is the average, highest, lowest etc. of redundant channels 12

l j

TABLE 1 Computer Display of R.G.1.97 Variables Type B Variables i

SPDS SPDS ERF ERF TpLevgl AjdLevg1 A[ awing M

D AgmputepPoint C

2 Variable A or D or D or D or D 4.

Pressurizer D

D D

Heater l

Status (Y-3272) 5.

Quench Tank D

D Level (LT-132) 6.

Quench Tank D

D Tempature

((E-133) 7.

Quench Tank D

D Pressure (PT-130) i V.

SECONDARY SYSTEM 1.

. Steam Genera-tor Level See Type A Variable III.6 l

2.

Steam Genera-tor Pressure See Type A Variable III.7 3.

Relief Valve -

Position l

(MS-291,292) d I

Al - used in an algorithm; actual value is not displayed I

2D - direct display / read out of the value 3D - the value displayed is the average, highest, lowest etc. of redundant channels i

13 l

1

TABLE 1 Computer Display of R.G.1.97 Variables Type B Variables i

SPDS SPDS ERF ERF AgpLevgl MjdLevgl Apawing T

D AgmputepPoint C

2 Variable or D A or D or D or D 4.

Main Feed-D D

D water Flow (FT-1101,1102)

VI. AUX. FEEDWATER l

l 1.

Aux. Feed-D D

D water Flow-(FT-1109, 1110) 2a. Condensate Storage Tank l

Water Level (LT-1191) 2b.

Emergency D

D Feedwater Tank Level (LT-1183, 1188)

VII. CONTAINMENT COOLING SYSTEMS 1.

Containment D

D D

1 Spray Flow 1

(FT-342,343)

Al - used in an algorithm; actual value is not displayed D2 _ direct display / read out of the value D3 - the value displayed is the average, highest, lowest etc. of redundant channels l

14

\\

m :m: :',

3

_f s

TABLEi,l e

Computer Display of R.G.1.97 Variables -

(;

L

' Type B Variables SPDS SPDS' ERF-ERF

.Tgp Levgl' A{dLevgl Dgawing M

AgmputegPoint; C

2

. Vari abl e.

A. or D or D A or'D.

or D.

2.

' Heat Removal.--

by the Con-tainment-Fan H

(FT-416,'417, 418,419)'

3

. 3.

Containment D

D D

-Atmosphere Temperature

,4..

Containment To be Installed in the 1988 Refueling' Outage

_ Sump'. Water-Temperature,

VIII CHEMICAL AND VOLUME'

-CONTROL-1.

. Makeup Flow-See. Type D Variable 11.3

-2.

' Letdown Flow:

D D

D (FT-212) m.

3.

' Volume Con-0 D

trol Tank Level (LT-219)

Al - used in an algorithm; actual value is not displayed D2 _.' direct display / read out of the value 3

-D

- the value displayed is the average, highest, lowest etc. of redundant channels 15

--u__.____-________.___

j 1

i t

9-i t

LTABLE 1 Computer: Display of R.G.1.97-Variables Type B Variables SPDS.

SPDS

.ERF-ERF:

AgpLevg1 M{dLevg1-Dyawing2

..Cgmputeg. Point.-

T A or D A or D A or D I

Variable or D IX. COOLING WATER SYSTEM

-1;

' Component.

i Cooling l

Water. Temp--

i erature (TE-493, 494,495,496).

-2..

Component Cooling 1

. Water Flow-

-X.

'RADWASTE SYSTEMS 1.

.High. Level

)

Rad. Liquid Tank Level (LT-577, 578; 579) 2.

Rad.; Gas D

D Holdup Tank.

(PT-517,'518, 519,520) i AI - used in an algorithm; actual value is not displayed.

D2 - direct. display / read out of the value 3D '- the value displayed is the average, highest, lowest etc. of redundant channels 16 l

i l

l

3 J

TABLE 1-Computer Display of R.G. -1.97 Variables ~

Type.B. Variables

-SPDS SPDS ERF.

ERF.

d TypLevgl

'A{d-Levgl A{ awing M

D Cgmpute{ Point 2

Variable j

A or D

-or D or D A or D

-XI.

VENTILATION SYSTEMS-1.-

Emergency D'

Ventilation Damper Position (HCV-724 A/B' l

HCV-725 A/B)

XII. POWER SUPPLIES 1.

Status of Standby' Power a.

4kVAC buses' A

D D

D l

' b.

480VAC buses c.

125VDC buses A-

.D D

D d.

120VAC busses (vital bus inverters)

e. -EDG Status-D. Volt, Amps, Watts D Volt, Amps,' Watts f.

EDG Speed D Volt, Amps, Watts D Volt, Amps, Watts l

l

- Al - used in an algorithm; actual value is not displayed.

D2.: direct display / read out of the value 3

D - the value displayed is the average, highest, lowest etc. of redundant channels 17 i

I

.. _ =___ --_ _ ---- __ - ______ _

'~'

e,

)

f

, f '

L IABLE 1

' Computer Display of R G. -1.97. Variables Type B Variables L

SPDS SPDS ERF ERF:

TogLeve}

AjdLevgl.

Agawing M

D l

'A or D or D '

or D2 CgmputegPoint Variable A or D

- I '.

' CONTAINMENT RADIATION 1.

Containment _

See Type A Variable V.1 Area Radiation i

(High Range).

II. AREA RADIATION 1.

Radiation Ex-See Type C Vartable*iI.4 posure Rate III. AIRBORNE RADI0 ACTIVE MATERIALS RELEASED A.

Noble Gases 1.

Noble Gases See Type C Variable III.4 Containment 2.

Noble Gases See Type C Variable III.4 Reactor Bldg.

3.

Noble Gases See Type C Variable III.4 Aux. Bldg.

4.

Noble Gases Discharge Effluent Through Common Plant Vent, Thus Not Condenser Required as Per Reg. Guide)

Air Removal 1

AI - used in an algorithm; actual value is not displayeci 2D - direct display / read out of the value D3 - the value displayed is the average, highest, lowest etc. of redundant channels 18

i 1

l i

TABLE 1

' Computer Display of R.G.1.97 Variables i

Type B Variables SPDS SPDS ERF ERF TogLeve}

M{dLevgl Drgwing 2 CogputerPoint j

A or D A or D A or D A or D2 Variable t

I 5.

Noble Gases See Type Variable III.4

' Common Vent 6.

Vent for S/G Safety Relief Valves

& Atmosphere Dump Valve,

& Feedwater Turbine (RM057)(RM064)

B.

P_ articulates & Halocens 1.

All Iden-A A

D D

tified Plant RM063 RM063 Release (RM050, Not Used Not Used 060,061,063)

In The In The 1

Algorithm Algorithm IV.

ENVIRONS RADIATION AND RADI0 ACTIVITY 1.

Reg. Guide 1.97 Rev. 3 deleted the requirement for continuous indications at Fixed Location Al - used in an algorithm; actual value is not displayed.

l D2 - direct display / read out of the value 3D - the value displayed is the average, highest, lowest etc. of redundant channels 19 i

I i

TABLE 1 i'

Computer Display of R.G.1.97 Variables Type B Variables i

SPDS SPDS ERF ERF Tog.Leve{

MijLeve{

Draying A or D A or D A ' or D2 CgmputepPoint Variable A or D 2.

Airborne Radio Halogens I

and Particulate j

(Portable) 3.

Plant and Environs Radiation (Portable) 4.

Plant and Environs 1

Radioactivity METEOROLOGY l

i 1.

Wind Direc-tion -

0 (F0031,0032, 0033, 0034, 0043, 0044, 0045) 2.

Wind Speed D

(0036,0037,0038) 3.

Estimation D

Atmospheric Stability (F0039, 0040, 0041, 0042)

Al - used in an algorithm; actual value is not displayed.

2D - direct display / read out of the value D3 - the value displayed is the average, highest, lowest etc. of redundant channels l

20

,w l5 TABLE 1

. Computer Display. of R.G. ~1.97 Variables Type B Variables-SPDS.

'SPDS ERF' ERF Top (evel 2 MijorD}.

Leve Drawjng Cgmpute. Point l

- Variable.

A or D A-A or D -

A or D VI.-

ACCIDENT ~ SAMPLING l

CAPABILITY A.

Primary Coolant Sump 1.

Gross Activity-(Provided by' PASS)-

~

(SL-16,40) 2.

Gamma Spectrum-(Provided by PASS) j

(SL-17)

'3.

Borons.

See Type B Variable 3.1 Content-4.

Chloride Content

-(Provided by. PASS)-

1 (SL-25) 5.

Dissolved Hydrogen or Total Gas (Provided

.j by PASS) (SL-24) 4 Al - used in an algorithm; actual value is not displayed.

2D - direct display / read'out of the value 3D - the value. displayed is the average, highest, lowest etc. of redundant channels r

21 1

l

w;,,

o,; +,.

{ $

'l: e c 1

T'ABLE 1'

' Computer ~ Display. of R.G. l'.97 Variables Type B Variables.

SPDS

.SPDS ERF ERF..

Togor-D{

Mif~orD{-

Leve Leve Drawigg-CgmputegPoint l

. Variable-A A

A or D A or D 6.

Dissolved Not Required-

'0xygen 7.

pH (Provided by: PASS)

(PHE-6742)

B.

Containment Air h'.

1.

Hydrogen See Type A Variable IV-1 Content 2.

0xygen.

Not Required oer SER for PASS dated January 31, 1983.

Content'

.and September-1, 1983 3.

Ganna a

Spectrum

'(Provided by: PASS)

(SL-35,40) 1 1

I t:v

[

'Al - used in an algorithm; actual value is not displayed.

I D2 - direct display / read out of the value D3 - the value displayed is the average, highest, lowest etc. of redundant channels 22 r

.

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