ML20115G423

Summary Rept on Reg Guide 1.97,Rev 3,Post-Accident Monitoring Sys

ML20115G423
Person / Time
Site:	Summer
Issue date:	04/15/1985
From:	SOUTH CAROLINA ELECTRIC & GAS CO.
To:
Shared Package
ML20115G390	List: ML20115G387 ML20115G403 ML20115G423
References
RTR-REGGD-01.097, RTR-REGGD-1.097 NUDOCS 8504220198
Download: ML20115G423 (52)

Text

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ENCLOSURE II VIRGIL C. SUMMER NUCLEAR STATION

SUMMARY

REPORT ON REGULATORY GUIDE 1.97, REVISION 3 POST ACCIDENT MONITORING SYSTEMS 4

M F

r-PREFACE The following document has been developed to accomplish two objectives. The first is to provide in tabloid form a complete list of the Virgil C. Summer Post Accident Monitoring Instrumentation. Table 1-1 summarizes the following information for each variable identified:

A.

Instrument Range or Status B.

Type and Category C.

Environmental Qualification D.

Seismic Qualification E.

Number of Channels F.

Control Room Indicating Device G.

Implementation Date Included as footnotes to the table are statements of clarification or supporting justifications / alternatives to any deviations to Regulatory Guide 1.97. For those variables that require modification, except for the Neutron Flux Monitors, completion will be accomplished by the end of SCE&G's third refueling outage, scheduled for Spring 1987. The Neutron Flux Monitors will be installed by the end of the fourth refueling outage, scheduled for Fall 1988.

The second objective of this document is to provide a summary of the design basis from which Table 1-1 was developed.

Section 2.0 provides definitions or relevant terminology and each variable function. Section 3.0 develops design criteria for each variable category including qualification interface requirements. Sections 4.0 - 8.0 describe Type A - E variables respectively.

m TABLE OF CONTENTS SECTION PAGE 1.0

-INFORMATION SYSTEMS IMPORTANT TO SAFETY 1 l '.1 SAFETY RELATED DISPLAY INSTRUMENTATION INTRODUCTION 1

1.2 DESCRIPTION

OF INFORMATION SYSTEMS 1-2 TABLE 1-1 1-5 2.0 DEFINITION OF VARIABLE TYPES

'2-1 2.1 DEFINITIONS 2-1 2.2 VARIABLE FUNCTIONS 2-3 3.0 CRITERIA 3-1 3.1 VARIABLE CATEGORIES 3-1 3.2 CATEGORY 1 3-1 3.3 CATEGORY 2 3-5 3.4-CATEGORY 3 3-7 3.5 EXTENDED RANGE INSTRUMENTATION QUALIFICATION 3-8 CRITERIA TABLE 3-1

SUMMARY

OF SELECTION CRITERIA 3-10 TABLE 3-2

SUMMARY

OF DESIGN, QUALIFICATION, AND 3-11 INTERFACE REQUIREMENTS 4.0 TYPE A VARIABLES 4-1 5.0 TYPE B VARIABLES 5-1 6.0 TYPE C VARI ABLES 6-1 7.0 TYPE D VARIABLES 7-1 8.0 TYPE E VARIABLES 8-1

1.0 INFORMATION SYSTEMS IMPORTANT TO SAFETY 1.1 SAFETY-RELATED DISPLAY INSTRUMENTATION INTRODUCTION An analysis was conducted to identify the appropriate variables and to establish the appropriate design bases and qualification criteria for instrumentation employed by the operator for monitoring conditions in the reactor coolant system, the secondary heat removal system, and the containment, including engineered safety functions and the systems employed for attaining a safe shutdown condition.

The instrumentation is used by the operator to monitor the VC SummerStation throughout all operating conditions including anticipated operational occurrences and accident and post-accident conditions.

f h

a 1 -1

1.2 DESCRIPTION

OF INFORMATION SYSTEMS The plant safety analyses and evaluations define the design basis accident (DBA) event scenarios for which preplanned operator actions are required.

Accident monitoring instrumentation is necessary to permit the operator to take required actions to address these analyzed situations. However, instrumentation is _also necessary for unforeseen situations (i.e., to ensure that, should plant conditions evolve differently than predicted by the safety analyses, the control room operating staff has sufficient information to evaluate and monitor the course of the event). Additional instrumentation is also needed to indicate to the operating staff whether the integrity of the fuel cladding, the reactor coolant pressure boundary (RCP8), or the reactor containment has degraded beyond the prescribed limits defined as a result of the plant safety analyses and other evaluations.

Five classifications of variables have been identified to provide this instrumentation:

A.

Those variables that provide information needed by the operator to perform manual actions identified in the operating procedures that are associated with DBA events are designated type A.

These variables are restricted to preplanned actions for DBA events.

B.

Those variables needed to assess that the plant critical safety functions are being accomplished or maintained, as identified in the plant safety analysis and other evaluations, are designated type B.

C.

Those variables used to monitor for the gross breach or the potential for gross breach of the fuel cladding, the RCPB, or the containment are designated type C.

l D.

Those variables needed to assess the operation of individual safety systems and other systems important to safety are designated type D.

1 E.

Those variables that required for use in determining the magnitude of l

the postulated releases and continually assessing any such releases of radioactive materials are designated type E.

1-2

i The five classifications of variable are not mutually exclusive, in that a given variable (or instrument) may be included in one or more types. When a variable is included in one or more of the five classifications, the equipment monitoring this variable is specified in accordance with the highest category identified.

Three categories of design and qualification criteria have been identified.

The differentiation is made in order that an importance of infonnation hierarchy can be recognized in specifying accident monitoring instrumentation. Category 1 instrumentation has the highest performance requirements and should be utilized for information which cannot be lost under any circumstances.

Category 2 and Category 3 instruments are of lesser importance in determining the state of the plant and do not require the same level of operational assurance.

l i

The primary differences between category requirements are in qualification, application of single failure, power supply, and display requirements.

Category 1 requires seismic and environmental qualification, the application of a single failure criteria, utilization of emergency power, and an 4

j immediately accessible display. Category 2 requires environmental and seismic qualification consensurate with the required function but does not require the single failure criteria, emergency power, or an immediately accessible display. Category 2 requires, in effect, a rigorous performance verification for a single instrument channel. Category 3, which is high quality commercial grade, does not require qualification, single failure criteria, emergency power, or an immediately accessible display.

Table 1-1 sumnarizes the following information for each variable identified:

A.

Instrument range or status.

8.

Type and category.

C.

Environmental qualification.

e i

..i-1-3 i

.n-

_n. - -. _, _, -,,. _ _ _ -

n.-,,,--

_.n.,_-_-

l D.

Seismic qualification.

E.

Number of channels.

F.

Control Room Indication Device G.

Implementation date.

9 1-4 s

TABLE 1-1 POST ACCIDENT MonITottuG INSTRUMENTATION Qualification control Room 1

Type /

Environ-Number of Indication Implementa-Power E0F/TSC Yariable Ranee / Status Category mental Seismic Channels Device tion Date Samalv Indication Conformance RCs pressure 0-3000 psig A1. 31 Yes Yes 2 per plant 2 meters Complete IE Yes Note A (Wide Range)

82. C1 2 recorders C2. D2 Wide Range TNot 50* to 100*F A1. B1, Yes Yes 1 per loop 2 meters 1E Yes Conforms to B2 3 channels Third Reg. Guide recorded Refueling 1.97. Rev. 3 Wide Range T old 50* to 700*F A1. B1 Yes Yes 1 per loop 2 meters 1E Yes Conforms to C

B2 3 channels Third Reg. Guide i

recorded Refueling 1.97. Rev. 3 Wide Range Steam 0-100 percent A1. B1 Yes Yes 1 per Steam 3 meters Complete 1E Yes Conforms to Generator Water of span 52, 82 Generator 3 channels Reg. Guide tevel recorded 1.97. Rev. 3 4

l marrow Reage Steam 0-100 percent A1 Bl.

Yes Yes 3 per steam 9 meters Complete IE Yes Conforms to Generator Water of span 82 generator 1 recorder /56 Reg. Guide m

Level 1.97. Rev. 3 4 Pressurizer Level 0-100 percent A1. Bl.

Yes Yes 3 per plant 3 meters Complete 1E Yes Conforms to l

of span D2 1 channel Reg. Guide recorded 1.97. Rev. 3 J

Containment 0-15 psig A1. Bl.

Yes Yes 3 per plant 4 meters Coglete lE Yes Note B Pressere (design pressure 92. 82 1 channel l

57 psig) recorded I

steamline Pressure 0-105 percent A1. B1 Yes Yes 3 per loop 9 meters Complete IE Yes Conforms to pressure R2 1 recorder /5G Reg. Guide 1

1.97. Rev. 3 l

Refueltag Water 0-100 percent A1 D2 Yes Yes 3 per plant 4 meters IE Yes Conforms to i

Storage Tank Level of Span 1 channel Third Reg. Guide recorded Refueltag 1.97. Rev. 3 Containment Water 0-Level of A1. Bl.

Yes Yes 4 per plant 2 meters Complete IE ies Conforms to j

Level (upper and RCS, CST, and

82. C2 I recorder Reg. Guide Lower Ranges)

RWST volumes 02 1.97. Rev. 3 i

l Condensate storage 0-100 Percent D2 Yes Yes 2 per tank 2 meters Complete IE Yes Note C Tank Level of Level 1 recorder i

e

TASLE 1-1 (Continued)

POST ACCIDENT N0u1Toelm6 INSTRU KNTATION Qualificatten Control neos Type /

Environ-Nueer of Indication Iaplementa-Power EOF /TSC variable Benet/ States Cateeory mental Seismic Chamaels sevice tion Bate Suselv Indicatten Ceaforanace Energency 0-1000 gpa A1. 51 Yes Yes 2 per loop 6 meters Ceaplete IE Yes Note 3 Feedn.ater Flow 0-300 gym 02 primary Centa1 ament 2.2 to 2.2x108 A1. 31 Yes Yes 2 per plant 2 meters Caglete 1E Biesel No confenes to Radiation Level t/hr and E2 2 chamaels Backed Beg. Guide 1.0 to 1.0101 recorded 1.97, Rev. 3 t/hr uste E 5teamitee 0.1-1'07 at E2 Yes Yes 1 per loop 3 meters Ceaplete 1E 01essi Yes teafarms to Radiation 3 channels Becked Seg. Guide recorded 1.97. Rev. 3 mete E Care Entt 166-2500*F A1. pl.

Yes Yes' 51 Thermo-Digital 31 splay Caglete IE Yes Acceptable Temperature C1 couples ICCI Safety per train Evaluatten; U5mc Letter to SCE&G.

Sated August 3, 1994 i

ee BCS Satcasites 200*F subceol-A2. 82 Yes Yes 1 per plant Digital bisplay Complete 1E Yes Acceptable ing to 2000*F ICCI Safety Evaluation; superheat USNC Letter to SCE84, Sated August 3, 1984

., ed.g neutron Flux 10-8 to 100 E1 Yes Yes 2 per plant Olgital^91 splay Geth IE Yes Ceafones to percent of full Refueling teg. Guide 1.97 Rev. 3 power Contataneet Hydrogen 0-10 percent

31. C1 Yes Yes 2 per plant 2 meters Third IE Yes Conforms to Concentrattom partial pressure Refueling teg. Guide 1.97 Rev. 3 Note F seacter vessel 60-110 percent B2. C2 Yes Yes 1 per plant 6 meters complete IE Tes Acceptable Water Level ar.d 0-110 percent 3 channels ITCI Safety vessel Level recorded Evaluation; USMC Letter to SCE&G, Bated August 3, 1944 Coat:1 ament Closed / mot Closed C2 Yes Yes 1 per valve 1 pair of lights Third IE Yes Conforms to Isolatica valve per valve, Scfueling Reg. Guide 1.97, Bew. 3 5t:tus e

TAetE 1-1 (Continued)

POST ACCIBENT MonITORlWG INSTRMNENTATION Qualification control Boon Type /

Enviroa-Number of Indication laplementa-Power EOF /TSC variatie Ranee / Status (Ategory amatal Seismic Channels Device tien late Susely Indication Conformance A. B. Bruantag 1 x 104 to E3 No note H 1 per plant I meter Ceaplete IE No Conforms to Area poetter ar/hr (note L)

Slese)

Beg. Guide Backed 1.97, Rev. 3 A. 3. Weste Noldap 1 x 10-4 to E3 50 mote N 1 per plait 1 meter Complete IE No Conforms to Tank Area monitor ar/hr (note L)

Slesel Reg. Guide Backed 1.97, Bew. 3 A. B. Chargtag 1 x 10-4 to E3 no note N 1 per plant 1 meter Caglete 1E No Conforms to pump Area monitor ar/kr (note L)

Diese)

Reg. Guide Backed 1.97 Rev. 3 B. 3. In-Core 1 x 10-4 to E3 no note N 1 per plant 1 meter Complete IE no Conforms to Instrument Area ar/hr (Note L)

Diesel Reg. Guide maatter Backed 1.97 Rev. 3 Turttae Bellitag 1 x 10-4 to E3 no mete N 1 per plaat I meter Complete IE No Conforms to mesitor ar/hr (note L)

Blesel Reg. Guide Backed 1.97, Rev. 3 Q mon Needered went 10-3 to 102 E2 Yes Yes 1 set per vent 2 meters Complete IE Yes Conforms to Radioperticulate pC1/cc (antient 2 channels Beg. Guide and Malogen only) recorded 1.97 Rev. 3 Concentrattaa (R. B. Purge vent)

Note E Gas:

2 x 104 to 105 pC1/cc Iodine:

2 x 10-11 to 4 x 10-I pC1/cc Particulate:

4.1 a 10-11 to 10-1 aC1/cc Effluent Fath Flow 1-1101 destga E3 no no 1 per path NWAC Panel Complete Non-1E Yes Conforms to Rate flow (note N)

Reg. Gelde 1.97 Rev. 3 meteorological m/A E3 no no N/A N/A Complete non-1E Yes Conforms to Parameters Reg. Guide 1.97, Rev. 3 e

TABLE 1-1 (Contimmed)

POST ACCISEmi memIT0eIns Im5TeumENTAT10m t>naltfIcatten Centrol teen Type /

Environ-numer of Indicatten Implementa-Power EOF /15C variable Rames/ States Cateepry mental Se15eic Chama*15 Sevice tien bate Seas 1r ladicatten Conformance Area Radiatten 1 a 10-4 to E3 se mete a 1 per area 1 meter /rma 1

Complete 1E elesel me Ceaferes to mentters i a 10 aAr necked seg. smide 1.97. Rev. 3 Badtecneatstry Lat 10-1 to 134 E3 no mete a 1 per plaat 1 meter Complete 1E Slesel me Conferes to maatter arAr (note L)

Secked Beg. Guide 1.97. Rev. 3 Feel mandilag 10-I to 104 E3 No note a 1 per plant I meter Ceaplete IE Blesel me Ceaforms to antiding mentter arAr (note L)

Socked Reg. Guide 1.97. Rev. 3 Sampling toea 10-1 to 104 E3 no mete m 1 per plaat 1 meter Ceaplete IE Blesel me Canferas to montter arAr (mete L)

Socked Beg. Guide 1.97. Rev. 3 Ret machlae 10-1 to 104 E3 no mete a 1 per plant I meter Complete IE 01esel me Ceaferms to Shop mesitor arAr (note L)

Socked Beg. Emide 1.97. Rev. 3 T

3. 3. personnel 10-1 to 104 E3 no mete a 1 per plant 1 meter Ceaplete IE Slesel me Conferas to Access maatter arAr (mete L)

Secked Bog. Emide 1.97. Bew. 3

3. B. aefueltag 10-1 to 104 E3 no mete a 1 per plant 1 meter Ceaplete 1E 01esel me Ceafenes to Bridge maatter arAr (mete L)

Bacted Beg. Emide 1.97. Rev. 3 E. S. migh aange 10-1 to 104 E3 me mete a 1 per plaat 1 meter Ceaplete IE Slesel no Ceaferas to monitor arAr (mete L)

Socked Beg. Emide 1.97. Rev. 3:

Fht Fuel 1 a 104 to E3 no mete a 1 per plaat 1 meter Complete IE me Conferes to mandling Bridge ar A r (mete L)

Stese)

Beg. Golde maatter Becked 1.97. Bew. 3 0.3. Seetseral-1 a 10-4 to E3 to mete a 1 per plant 1 meter Ceeplete IE no Ceaforms to tratten Area ar A r (mete L)

Slesel Reg. Guide maatter Becked 1.97. Bew. 3 Q. S. teaste Gas 1 m 13-4 to E3 no note a 1 per plant 1 meter Complete IE me Conferes to Secar Tant Area ara r (mete L)

Blesel Beg. Emide montter Becked 1.97. Rev. 3 W

i 1AttE 1-1 (Centlawed)

POST MCIMai ImnITOB1mE leSTOWENTATIgu Omallficatlea Centrol aose i

Type /

Environ-shaber of ladicattaa Implementa-Power EOFITSC

)

variable Eamer/ States Cateeory aestal Seisele _Chamaels Device tien Bate Samalv ladication Confermance sua valse states Closed / mot Closed 82 Yes no 1 per valve 1 pair of lights Complete aca-1E Yes/no Ceaforms to per valve Reg. Gelde 1.97 Sev. 3 seactor Trip /Beass Trip / mot Tripped 82 Yes 2e 1 per breaker 1 pair of 11@ts Ceaplete non-1E Ves Ceaforms to Bred er Posittaa (amelent) per breaker seg. Gelde 1.97, Rev. 3 j

motor-drivee Om/Off 82 Yes Yes 1 per pump 1 pair of lights Ceaplete IE Tes Canforms to Emergency Feeemater per peep Dog. Golde Pume Status 1.97, sev. 3 Steae Sepply to Closed / met Closed 32 Yes Ves 1 per valve i pair of lights Complete IE Yes Conforms to l

Terstae-Ortwee per valve Reg. Gelde l

Emergency Feeemater 1.97, Bew. 3 Puus Tertime Stop 1 Opee 82 Yes no 1 per valve 1 pair of lights Complete non-1E ho Conferes to value Posities (ambient per valve beg. Guide cn only) 1.97, sev. 34 Taralne Throttle 1 Open B2 Yes no 1 per valve 1 pair of lights C g lete hen-1E No Ceaforms to Valve Pesttles (aantent per valve Beg. Emide only) 1.97 Rev. 3 SI Pump Status on/off B2 Yes Yes 1 per pump 1 pair of lights Complete 1E Yes Ceaforms to I

per pump seg, seide l

1.97 Rev. 3 Service teater on/0ff 82 Yes Yes 1 per pump 1 pair of lights Complete IE Yes Conforms to Pump Status (amelest per pump Reg. Guide only) 1.91, Bew. 3 CCW pump States on/off 32 Yes Yes 1 per pump 1 pair of lights Complete IE/ Booster Yes Ceaforms to (amelent per pesup Pumps hoe-1E Reg. Guide only) 1.97, sev. 3 e

9 TaSLE 1-1 (Centiawed) p0ST aCCitEgT 8ElmlT0BleG Im57assiteTaTieu Qualification Castrol asem Type /

Environ-meuter of Indicatten laplomaata-power EOF /ISC seriante maner/5tates Cateeory mental Se15ste,Chamaels Device tien Sate Seasiv Indicatise Comformance CCW header Pressare O to 200 psig 32 Yes Yes 1 per neader 2 meters Ceeplete moa-1E ves Ceaforus to (ambient Reg. Emide only) 1.97, Rev. 3 Ctw meader 0-300*F B2 Yes Yes I per header 2 arters Third hen-1E no Conforms to Temperature (asetent Befueltag Reg. Eulde only) 1.97 Rev. 3 CCW Sarge Tank 0-100 percent 52 Yes Yes 1 per train 2 meters Third mee-1E Yes/mo Ceaforms to Level of level (ambient Gefueltag Reg. Emide only) 1.97, Bew. 3 CCW Flow to ESF 0-7000 gym 32 Yes Yes 1 per header 2 meters Third non-1E ves Conforms to Ceapenests (ambient Sefmellag Reg. Eulde only) 1.97 Rev. 3 CCW valve Status Closed / mot Closed 82 Yes Yes 1 per valve 1 pair of lights Third IE Yes Conforms to (antient per valve Refueltag Reg. Guide only) 1.97, Rev. 3 g Service teater System 0-5000 gem 32 Yes Yes 1 per trata 2 meters Complete IE Yes Ceaforms to 4 Flow 2 recorders Bog. Eulee 1.97, Bew. 3 NWAC to Essential open/ Closed or 82 Yes Yes I per compo-1 pair of lights Third IE/ mon-lE Yet/mo Conforms to Components open/ mot Open meat per component Befueltag Reg. Gelde 1.97, Gev. 3 aC. SC, Vital bus 32 Yes Yes 1 per bus I meter per bus Ceaplete IE Switch-Yes ronforms to lastrument voltage specific (amelent gear; non-1E Reg. Emide only)

Isloted 1.97, Bew. 3 Voltaeter ama meat Exchanger 50* to 400*F B2 Yes no 1 per heat-2 recsrders Third non-1E ves Conforms to 31scharge Tempera-exchanger Refueltag Reg. Golde tore 1.97, Rev. 3 amt flow 0-5000 gen D2 Yes no 1 per trata 2 meters Third non-1E Yes Conforms to Refueltag Reg. Guide 1.97 Rev. 3 O

e

I Tattr 1-1 (:entinued) f POST ACCIREeT NDnITOelmG tusTatsIENTATION i

Qualif1 cation Coatrol Room Type /

Environ-munter of Indication Implementa-Power EDF/TSC Variatie Ramee/5tatus Category mental Seiseic Ch - 15

_ Device tien Sate Suselv Indication Confermance steam Generator Closed / mot Closed 82 Yes Yes 1 per loop 1 natr of lip %ts Complete IE Yes Conforms to Blana.eue Isolation per valve Reg. Guide valve States 1.97, Rev. 3 Total les51 Flow 0-100 percent 02 Yes Yes 1 par 51 2 meters Third Non-1E Yes Conforms to Design Flow train Refueling Reg. Guide 1.97, pov. 3 Total LIGI Flow N/A 02 N/A N/A N/A N/A r/A N/A N/t.

Note J ECC5 Valve States Closed / mot Closed D2 Yes Yes 1 per valve 2 pairs of lights Third IE Yes Conforms to and Open/not Open per valve Refueling Reg. Gelde 1.97. Rev. 3 Emergency Feedwater Clos 2d/ hot Closed D2 Yes Yes 1 per valve 1 pair of lights Complete IE Yes Conforms to Valve States per valve Reg. Guide M

1.97, Bew. 3 Containment spray 0-110 percent D2 Yes Yes 1 per train 2 meters Complete IE Yes Conforms to Flow Design Flow Beg. Guide 1.97. Rev. 3 Containment Spray Closed / mot Closed D2 Yes No 1 per vs!ve 2 pairs of lights C g lete IE Yes Conforms to Valve Status and open/ mot open per valve Reg. Guide 1.97. Rev. 3 Containment spray On/Dff D2 Yes Yes 1 per pump 1 pair of lights Complete IE Yes Conforms to Pump Status per breaker and Reg. Guide meneter 1.97, Rev. 3 Fan Cooler stator Run/ Tripped D2 Yes Yes 1 per fan Note K t.caplete Non-1E Yes Conforms to Speed motor Reg. Gutde 1.97, Rev. 3 O

9

e TABLE 1-1 (Continued)

POST ACCIDENT NONITORING INSTRUNENTATION t

Qualification Control Room Type /

Environ-Number of Indication Implementa-Power E0F/TSC Variable Ranee /Statut Catecorv mental _ Seiset:

Channels tevice tion Date Suselv Indicatten Conformance Pressurizer Heater 0-75 amps and D3 No No 1 per heater 3 ammeters Coglete 1E (safety-No Conforms to Current 0-50 ag bank related banks Reg. Guide only) 1.97 Rev. 3 Charging System 0-110 percent 02 Yes No 1 per plant 1 meter Complete Non-1E Yes Conforms to Flow Design Flow (ambient Reg. Guide only) 1.97 Rev. 3 Lr.tdown Flow 0-110 percent D2 Yes no 1 per plant 1 meter Co'aplete Non-1E Yes Conforms to

~

Design Flow (ashient Reg. Guide only) 1.g7. Rev. 3 volume Control 0-100 percent D2 Yes No 1 per tank 2 meters Complete Non-1E Yes Conforms to Tank Level level (ambient Reg. Guide only) 1.97, Rev. 3 RCP Seal Injection 0-20 gym D2 Yes No 1 per pump 3 meters Complete Non-lE Yes Conforms to flow (ambient Reg. Guide g

only) 1.97, Rev. 3 7

Main Steamline Closed /Nct Closed 82 D2 Yes Yes 1 of each I pair of lights Complete 1E Yes Conforms to Isolation /typass per loop per valve Reg. Guide valve Status 1.97, Rev. 3 S/G Atmospheric Closed / Net Closed 92 Yes Yes 1 per valve 1 pair of lights Complete IE Yes Conforug to PORV Status per valve Reg. Guide 1.97 Rev. 3 Steam Generator Closed / Net closed D2 Yes Yes 1 per valve 1 pair of lights Third Non-1E No Conforms to Safety Valve Status per valve Refueling Reg. Guide 1.97 Rev. 3 Note I Main Feedwater

. Closed /mct Closed D2 Yes Yes 1 per valve 1 pair of lights Complete 1E Yes Conforms to Isolation valve per valve Reg. Gelde 1.97, Rev. 3 Status Main Feedwater 0-110 percent D2 Yes No 2 per S/G 6 meters Complete 1E Yes Conforms to Flow Design Flow (ambient 3 recorders Reg. Guide only) 1.97 Rev. 3 e

a

TABLE l-1 (Continued)

POST ACCIDEt!T "CNIT0klNG INSTRUNENTATION I

Qualification Control Room Type /

Environ-Number of Indication Implementa-Power EOF /TSC Variable Ranee / Status Category mental Seismic Channels Device tion Date Supply Indication Conformance Containment Pressure 0 psig to 3 Al, 82 Yes Yes 2 per plant 2 meters Complete 1E Yes conforms to (Extended Range) times Design C1, C2 1 channel recorded Reg. Guide Pressure 1.97, Rev. 3 RCS Sampling Post-Accident C3 No No N/A N/A N/A Non-1E N/A Note G Sampling used Common Plant Vent 2x10-6 to 105 C2, E2 Yes Yes/No 4 per plant 2 meters (noble Complete 1E Diesel Yes Conforms to Radiation Level pC1/cc (ambient (2 noble gas) 1 meter Backed Reg. Guide (Noble Gases) only) gas, 1 each particulate 1.97, Rev. 3; 4.1x10-II to 10-7 particulate and iodine, all Notes E & H pC1/cc and 1 todine) channels recorded (particulate) 2x10-Il to 4x10-7 pC1/cc (1odine)

Adjacent Bu11 ding 0.1 to 10-4 C2, C3 Yes Yes 1 per area N/A Complete Non-1E No Conforms to m

Radiation Level R/Hr Reg. Guide 7

1.97, Rev. 3

,-4 Note E Site Environmental 1 to 100 mR/Hr C3, E3 No No 8 per Plant Computer Complete Non-lE Yes Conforms to Radiation Level 10-2 to Display Reg. Guide 10 R/Hr 1.97, Rev. 3 Pressurizer PORV Closed /Not Closed D2 Yes Yes 1 per valve 1 pair of lights Third Non-lE Yes Conforms to Status per valve Refueling Reg. Guide 1.97, Rev. 3 Pressurizer PORV Closed /Not closed D2 Yes Yes 1 per valve 1 pair of lights Third Non-lE Yes Conforms to Block Valve Status per valve Refueling

. Reg. Guide 1.97, Rev. 3 Pressurizer Safety Closed /Not Closed 02 Yes Yes 1 per valve Series of LEDs Third IE Yes Conforms to V',1ve Status Refueling Reg Guide j

1.97 Rev. 3 Pressurizer Heater Open/ Closed 02 Yes No 1 per bank I pair of lights Complete Non-1E Yes Conforms to Breaker Position (ambient per bank Reg. Guide only) 1.97 Rev. 3 l

l O

l TABLE 1-1 (Continued)

.L,

POST ACCIDENT MONITORING INSTRUMENTATION I

A.

Pressurizer Pressure (1700 to 2500 psi) will be used to resolve ambiguities above 1700 psi. Below 1700 psi, Safety Injection Flow versus Associated Pump Curves will be used.

l i

B.

Design pressure is 57 psig. Extended Range Pressure provides indication when pressure exceeds 15 psig.

1 C.

This variable is Category 2 since protection grade auto switch over to Service blater is available.

l D.

Recording of one narrow range and one wide range level for each steam generator provides trending l

information required for verification of secondary heat sink function.

e E.

Virgil C. Summier Radiation Monitoring Systems Presently meet the intent of Regulatory Guide 1.97 based 7

on the pre-licensing modifications performed to meet Nuclear Regulatory Commission requirements under NUREG 0578.

(Reference SER Items 1.8.30 and 7.5.2).

i F.

Trending capability is provided using the Technical Support Center (TSC) Computer System for 30 minute j

trending.

i 6.

RCS Sampling will be used to address this variable.

V. C. Summier's Nuclear Sampling System meets the I

j requirements of NUREG-0737. The points of extraction are: RHR Loop A and Loop B, Pressurizer Liquid and Steam Spaces, RCS Loop B Hot Leg, and RCS Loop C Hot Leg. Sampling Valves are: 9350A, 93508, j

9356A, 93568, 9357, 9364C, 9365B, and 9365C.

Portable Sampling can be used to address sampling requirements from Containment Sump, ECCS Pump Room Sumps, and Auxiliary Building Sumps.

4

)

I ef.!%

TABLE l-1 (Continued)

POST ACCIDENT MONITORING INSTRUMENTATION (Continued)

H.

Rate meters and recorders are seismically qualified in control room panel number XCP6200. All equipment is in mild environment. H1 range detectors are seismically supported.

I.

Main steamline flow instrumentation with a range of approximately 0-15% of nominal loop steam flow is used to detect the position of the steam generator safety valves.

l j

J.

This variable covered by RHR Flow.

i i

K.

The " Post-Accident" motor on each fan has a green light and an alarm on the Main Control Board (MCB)

~

to indicate tripped condition, a red light on the MCB to' indicate fan running, and an Emergency Support Facility (ESF) status light on the ESF MCB to indicate fan running.

'T, i

VA ?

L.

Existing Area Gamma Monitors (1.0E-04 to 1.0E-1 R/HR)' aust be augmented by high range portable survey l

instrumentation to meet range requirements.

I i

i M.

Monitor mounted on a non-seismic stack.

l l

l e

I

~

c

,..., z

2.0 DEFINITION OF VARIA8LE TYPES 2.1 Definitions 2.1.1 Design Basis. Accident Events Those events, any one of which may occur during the lifetime of a particular plant, and those events not expected to occur but postulated because their consequences would include the potential for release of significant amounts of radioactive gaseous, liquid, or particulate material to the environment. Excluded are those events (defined as "norinal" and " anticipated operational occurrences" in 10 CFR 50) expected to occur more frequently than once during the lifetime of a particular plant. The limiting accidents that were used to determine instrument functions are:

1) LOCA, 2) Steamline Break,

3) Feedwater Line Break, and 4) Steam Generator Tube Rupture.

2.1.2 Safe Shutdown (Hot Standby)

The state of the plant in which the reactor is suberitical such that Kg, is less than or equal to 0.99 and the reactor coolant system temperature is greater than or equal to 350*F.

2.1.3 Cold Shutdown The state of the plant in which the reactor is subcritical such that Kg, is less than or equal to 0.99, the reactor coolant system temperature is less than 200'F, and the reactor coolant system pressure is less than or equal to 10 CFR 50 Appendix 6 limits.

2.1.4 Controlled Condition The state of the plant that is achieved when the ' subsequent action' portion of the plant emergency procedures is implemented and the critical safety functions are being accomplished or maintained by the

• control room operator.

2-1

2.1. 5 Critical Safety Functions Those safety functions that are essential to prevent a direct and inmediate threat to the health and safety of the public. These are the accomplishment or maintenance of:

1) reactivity control

2) reactor coolant system integrity 3) reactor coolant inventory control 4) reactor core cooling

5) heat sink maintenance

6) primary reactor containment environment.

2.1.6 - Immediately Accessible Information Inforination that is visually available to the control room operator immediately (i.e., within human response time requirements), af ter he -

has made the decision that the information is needed.

2.1.7 Primary Information Information that is essential for the direct accomplishment of the pre-planned manual actions specified in the Westinghouse Owners' Group (WDG) ERG's; it does not include those variables that are associated with contingency actions.

2.1.8 Contingency Actions

{

Those manual actions specified in the WOG ERG's that address f

conditions beyond the Design Basis Accident Events.

l l

2.1. 9 Key Variables i'

l Those variables which provide the most direct measure of the inforination required.

1 l

U' 9

2-2

2.1.10 Preferred Backup Information That information, made up of additional variables beyond thos6 classified as key, that provides supplemental and/or confirmatory information to the operator. Backup variables do nai provide an indication which is as reliable or complete as that provided by primary variables, and they should not be relied upon as the sole source of information.

2.1.11 Backup Information Information that is not required by the control room operator to perform actions following an accident. The operator should use this information cautiously since these variables do not provide an indication as reliable or complete as that provided by key and preferred backup variables, and are not relied upon as the sole source of information.

2.1.12 Categories 1, 2 and 3 References to Categories 1, 2 and 3 are as stated in Regulatory Guide 1.97 Category classifications.

2.2 Variable Functions The accident monitoring variables and information display channels are those that are required to enable the Control Room Operating Staff to perform the functions defined by Types A, B, C, D, and E below.

2.2.1.

Type A Those variables that provide the primary information required to permit the Control Room Operating Staff to:

Peform the diagnosis specified in the WOG ERG's which are used as the basis for the Virgil Summer plant-specific Emergency Response Procedures t

2-3

Take the specified pre-planned manually controlled actions, for which no automatic control is provided, that are required for safety systems to accomplish their safety function in order to recover f rom the Design Basis Accident Event, and Reach and maintain a cold shutdown condition.

Consistent with the definition of Type A in Regulatory Guide 1.97 Revision 2, the verification of the actuation of safety systems has been excluded from the definition of Type A.

The variables which provide this verification are included in the definition of Type D.

Variables in Type A are restricted to pre-planned actions for Design Basis Accident Events. Contingency actions and additional variables which might be utilized in these procedures will be in Types B, C, 0, and E.

2.2.2 Type 8 Those variables that provide to the Control Room Operating Staff information to assess the process of accomplishing or maintaining critical safety functions, i.e., reactivity control, reactor coolant system integrity, reactor coolant inventory control, reactor core cooling, heat sink maintenance, and primary reactor containment environment.

2.2.3 Type C l

Those variables that provide to the Control Room Operating Staff information to monitor (1) the extent to which variables, which

(

indicate the potential for causing a gross breach of a fission product barrier, have exceeded the design basis values and (2) that the in-core fuel clad, the reactor coolant system pressure boundary or the primary reactor containment may have been subject to gross breach.

'These variables include those required to initiate the early phases of the emergency plan.

Excluded are those associated with monitoring of radiological release from the plant which are included in Type E.

i 2-4 l

Type C variables used to monitor the potential for breach of a fission product barrier have an arbitrarily determined, extended range. The extended range shall be chosen to minimize the probability of instrument saturation even if conditions exceed those predicted by the safety analyses.

2.2.4 Type 0 Those variables that provide to the Control Room Operating Staff suf ficient information to monitor the performance of:

1) plant safety systems employed for mitigating the consequences of an accident and subsequent plant recovery to attain a cold shutdown condition. These include verification of the automatic actuation of safety systems, and

2) other systems normally employed for attaining a safe shutdown condition.

2.2.5 Type E Those variables that provide to the Control Room Operating Staff information to:

1) Monitor the habitability of the control room,

2) Monitor plant areas where access may be required to service equipment necessary to monitor or mitigate the consequences of an

accident, I

l i

3) Estimate the magnitude of release of radioactive materials through identified pathways, and continually assess such releases, and

4) Monitor radiation levels and radioactivity in the environment surrounding the plant.

l 2-5

4 1

3.0 CRITERIA 3.1 Variable Cateeories The qualification requirements of the Type A, 8, C, D and E accident monitoring instrumentation are subdivided into three categories (1, 2, 3).

Descriptions of the three categories are given below. Table 3-1 briefly summarizes the selection criteria for Type A, 8. C, D and E variables into each of the three categories. Table 3-2 briefly summarizes the design and qualification requirements of the three designated categories.

I 3.2 Category 1 3.2.1 Selection Criteria for Category 1 The selection criteria for Category 1 variables have been subdivided <

according to the variable type. For Type A, those key variables used; for diagnosis or providing information for necessary operator action -

have been designated Category 1.

(This does not include all Type A variables). For Type 8, those key variables which are used for monitoring the process of accomplishing or maintaining critical safety functions have been designated Category 1.

For Type C, those key variables which are used for monitoring the potential for breach of a fission product barrier have been designated Category 1.

There are no Type D or Type E Category 1 variables.

3.2.2 Qualification Criteria for Category 1 The instrumentation is environmentally and seismically qualified in accordance with Sections 3.11 and 3.10, respectively, of the FSAR.

Instrumentation shall continue to read within the required accuracy following but not necessarily during a seismic event. At least one instrumentation channel is qualified from sensor to display. For the balance of instrumentation channels, qualification applies up to and includes the channel isolation device.

(Refer to section 3.5 in regard to extended range instrumentation qualification).

e 3-1

__=

i 3.2.3 Design Criteria for Category 1 i

(1) No single failure within either the accident-monitoring l

instrumentation, its auxiliary supporting features, or its power sources, concurrent with the failures that are a condition of or j

result from a specific accident, will prevent the operator from j

being presented the required information. Where failure of one

{

accident-monitoring channel results in information ambiguity (e.g., the redundant displays disagree), additional information l

shall be provided to allow the operator to deduce the actual conditions in the plant. This may be accomplished by providing

)

additional independent channels of information of the same variable (addition of an identical channel), or by providing independant channels which monitor different variables which bear l

known relationships to the multiple channels (addition of a j

diverse channel (s)). Redundant or diverse channels are i

electrically independent and physically separated from each other, to the extent practicable with two train separation, and l

from equipment not classified important to safety in accordance with Regulatory Guide 1.75, " Physical Independence or Electric Systems.

i For situations such as isolation valves in series, the intent is generally to verify the isolation function.

In such a situation a single indication on each valve is sufficient to satisfy the single failure criterion if those indications are from different trains (i.e., unambiguous indication of isolation).

1 1

j If ambiguity does not result from failure of the channel, then a third redundant or diverse channel is not required.

(2) The instrumentation is energized from station emergency standby power sources, battery backed where momentary interruption is not tolerable, as discussed in Regulatory Guide 1.32, " Criteria for Safety-Related Electric Power Systems for Nuclear Power Plants.

3-2 I

(3) The out-of-service interval is based on normal Technical Specification requirements for the system it serves where applicable or where specified by other requirements.

(4) Servicing, testing, and calibration programs are specified to maintain the capability of the monitoring instrumentation.

For those intruments where the required interval between testing'is less than the normal time interval between generating station shutdowns, a capability for testing during power operation is provided.

(5) Whenever means for removing channels from service are included in the design, the design facilitates administrative control of the access to such removal means.

(6) The design facilitates administrative control of the access to all setpoint adjustments, module calibration adjustments, and test points.

(7) The monitoring instrumentation design minimize the development of conditions that would cause meters, annunciators, recorders, l

alarms, etc., to give anomalous indications that would be potentially confusing to the operator.

(8) The instrumentation is designed to facilitate the recognition, location, replacement, repair, or adjustment of malfunctioning components or modules.

(9) To the extent practicable, monitoring instrumentation inputs are from sensors that directly measure the desired variables. An indirect measurement is made only when it can be shown by analysis to provide unambiguous information.

(10) Periodic checking, testing, calibration, and calibration verification is done in accordance with the applicable portions of Regulatory Guide 1.118, " Periodic Testing of Electric Power and Protection Systems".

3-3

a (11) The range selected for the instrumentation encompasses the expected operating range of the variable being monitored to the extent that saturation does not negate the required action of the instrument in accordance with the applicable portions of 4

Regulatory Guide 1.105, " Instrument Setpoints".

3.2.4 Information Processing and Display Interface Criteria for Category 1 The interface criteria specified here provide requirements to be implemented in the processing and displaying of the information. The design basis for information processing and displaying will be the subject of a separate document.

. (1) The operator has immediate access to the information from redundant or diverse channels in units familiar to the operator (i.e., for temperature, a reading in degrees, not volts). Where two or more instruments are needed to cover a particular range, i

overlapping of instrument spans are provided.

~

(2) A historical record of a minimum of one inst'rumentation channel for each process variable is maintained. A recorded pre-event history for these channels is required for a minimum of one hour and continuous recording of these channels is required following an accident until such time as continuous recording of such information is no longer deemed necessary. This recording is available when required, but need not be immediately accessible.

One hour was selected based on a representative 1y slow transient which bounds this time requirement. A one-half inch equivalent break area LOCA was selected since the trip occurs at approximately fifty minutes after initiation. Where direct and immediate trend or transient information is essential for operator infonnation or action, the recording is immediately accessible.

3-4

d 3.3 Category 2 3.3.1 Selection Criteria for Category 2 The selection criteria for Category 2 variables have been subdivided according to the variable type. For Types A, B, and C, those

. variables which provide preferred backup information have been designated Category 2. ' For Type D, those key variables that are used for monitoring the performance of safety systems, have been designated Category 2.

For Type E, those key variables to be monitored for use in determining the magnitude of the release of radioactive materials and for continuously assessing such releases, have been designated Category 2.

3.3.2 Qualification Criteria for Category 2 Category 2 instrumentation is qualified from the sensor up to and

[

including the isolation device for at least the environment (seismic and/cr environmental) in which it must operate to perform its intended function.

Instrumentation associated with those safety related systems that are required to operate following an SSE to mitigate a consequential plant incident is seismically qualified, 3.3.3 Design Criteria for Category 2 i

(1)

Instrumentation associated with those safety related systems that are required to operate following an SSE to mitigate a consequential plant incident is energized from a seismically qualified power source, not necessarily the emergency standby power, which is battery-backed where momentary interrytion is not tolerable. Otherwise the instrumentation is energized from a highly reliable on-site power source, not necessarily the emergency standby power, which is battery backed where momentary interruption is not tolerable.

0 3-5

(2) The out-of-service interval is based on normal Technical Specification requirements for the system it serves where applicable or where specified by other requirements.

(3) Servicing, testing, and calibration programs are specified to maintain the capability of the monitoring instrumentation.

For those instruments where the required interval between testing will be less than the normal time interval between generating station shutdowns, a capabiitty for testing during power operation is provided.

1 (4) Whenever means for removing channels from service are included in the design, the design facilitates administrative control of the access to such removal means.

(5) The design facilitates administrative control of the access to all setpoint adjustments, module calibration adjustments, and l

test points.

(6) The monitoring instrumentation design minimizes the potential for l

the development of conditions that would cause meters, annunciators' recorders, alams, etc., to give anomalous i

indications potentially confusing to the operator.

(7) The instrumentation is designed to facilitate the recognition, location, replacement, repair, or adjustment of malfunctioning components or modules.

(8) To the extent practicable, monitoring instrumentation inputs are from sensors that directly measure the desired variables. An indirect measurement are made only when it can be shown by analysis to provide unambiguous information.

(9) Periodic checking, testing, calibration, and calibration verification is in accordance with applicable portions of Regulatory Guide 1.118 ' Periodic Testing of Electric Power and Protection Systems".

l l

3-6 I

(10) The range selected for the instrumentation encompasses the expected operating range of the variable being monitored to the extent that saturation does not negate the required action of the it.strument in accordance with the applicable portions of Regulatory Guide 1.105, " Instrument Setpoints."

3.3.4 Information Processing and Display, Interface Criteria for Category 2 The instrumentation signal is, as a minimum, processed for display on demand. Recording requirements are variable specific and are determined on a case-by-case basis.

3.4 Cateaorv 3 3.4.1 Selection Criteria for Category 3 The selection criteria for Category 3 variables have been subdivided [

according to the variable type. For Types A, 8, and C, those variables which provide backup information have been designated Category 3.

For Types D and E, those variables which provide preferred backup information have been designated Category 3.

3.4.2 Qualification Criteria for Category 3 The instrumentation is high quality commercial grade which is not required to provide information when exposed to a post-accident adverse environment. Only normal and abnormal environments are applicable.

3.4.3 Design Criteria for Category 3 (1) Servicing, testing, and salibration programs shall be specified to maintain the capability of the monitoring instrumentation.

For those instruments where the required interval between testing will be less than the normal time interval between generating station shutdowns, a capability for testing during power operation is provided.

3-7

J o

(2) Whenever means for removing channels from service are included in

~

the design, the design facilitates administrative control of the access to such removal means.

(3) The design facilitates administrative control of the-access to all setpoint adjustments, module calibration adjustments, and test points.

(4) The monitoring instrumentation design minimize the development of conditions that would cause meters, annunciators, recorders, alarms, etc., to give anomalous indications potentially confusing to the operator.

i (5) The instrumentation is designed to facilitate the recognition, location, replacement, repair, or adjustment of malfunctioning components or modules.

b 4

(6) To the extent practicable, monitoring instrumentation inputs are' o

from sensors that directly measure the desired variables. An indirect measurement is made only when it can be shown by

~

analysis to provide unambiguous information.

I t

3.4.4 Information Processing and Display, Interface Criteria for Category 3 The instrumentation signal is, as a minimum, processed for display on demand. Recording requirements are variable specific and are determined on a case-by-case basis.

3.5 Extended Ranee Instrumentation Qualification Criteria The qualification environment for extended range information display channel components is based on the design basis accident events, except the assumed maximum of the value of the monitored variable is the value equal to the specified maximum range for the variable. The monitored variable is assumed to approach this peak by extrapolating the most severe initial ramp associated with the Design Basis Accident Events. The decay for this variable is 3-8 i

)

e

{

considered proportional to the decay for this variable associated with the Design Basis Accident Events. No additional qualification margin needs to be l

added to the extended range variable. All environmental envelopes except that pertaining to the variable measured by the information display channel are those associated with the Design Basis Accident Events. The environmental qualification requirement for extended range equipment does not account for j

steady-state elevated levels that may occur in other environmental parameters associated with the extended range variable. For example, a sensor measuring containment pressure must be qualified for the measured process variable range

.(1.e., 3 times design pressure for concrete containments), but the

)

corresponding ambient temperature is not mechanistically linked to that l

pressure. Rather, the ambient temperature value is the bounding value for design basis accident events analyzed in Chapter 15 of the FSAR. The extended range requirement is to ensure that the equipment will continue to provide i

information if conditions degrade beyond those postulated in the safety analysis. Since extended variable ranges are nonmechanistically determined, extension of associated parameter levels is not justifiable and is therefore '

not required.

4 i

h 5

S 3-9

i i

6 Table 3-1 i

Summary of Selection Criteria TYPE CATEGORY l CATEGORY 2 CATEGORY 3

)

A KEY variables that are used Variables which provide None for diagnosis or providing PREFERRED BACKUP information I

information for necessary l

operator action I

B KEY varlables that are used Variables which provide Variables which provide i

for monitoring the process of PREFERRED BACKUP information BACKUP information accomplishing or maintaining critical safety functions C

KEY variables that are used Variables which provide Variables which provide l

for monitoring the potential PREFERRED BACKUP information BACKUP information for breach of a fission product j

9, barrier 4

.a

{

D None KEY variables which are Variables which provide PREFERRED i

used for monitoring the BACKUP information which are used l

I l

performance of plant for monitoring the performance-of systems plant systems l

E None KEY variables to be monitored Variables to be monitored which i

for use in determining the provide PREFERFED. BACKUP informa-T l

magnitude of the release of tion for use in determining the radioactive materials and magnitude of the release of radio-r for continuously assessing act?ve materials and for continu-l such releases ously assessing such releases l

6 e

e.

I

Table 3-2 Summary of Desian. Qualification and Interface Reauirements Qualification Category 1 Category 2 Category 3 Environmental Yes As appropriate No (Section 3.3.2)

Seismic Yes As appropriate No (Section 3.3.2)

Desian-Single Failure Yes No No r

Power Supply Emergency On-Site As Required Standby (Section 3.4.3)

Channel out of Service Technical Technical As Required Specifications Specifications (Section 3.4.3)

Testability Yes Yes As Required (Section 3.4.3)

Interface Minimum Imediately Demand Demand Indication Accessible Recording Yes As Required As Required (Section 3.3.4)

(Section 3.4.4) 3-11

I i

I SECTION 4.0 TYPE A VARIABLES 4.1 Introduction Type A Variables are defined in Section 2.2.1.

They are the variables which provide primary information required to permit the Control Room Operating Staff to:

1.

Perform the diagnosis specified in the Westinghouse Reference ERG's l

which were used as a basis for the Virgil Summer Emergency Response Procedures.

2.

Take specified pre-planned manually controlled actions for which no automatic control is provided, that are required for safety systems to accomplish their safety function to recover from the Design Basis Accident Event (verification of actuation of safety systems is excluded from Type A and is included as Type 0);

3.

Reach and maintain a safe shutdown condition Key Type A variables have been designated Category 1.

These are the variables which provide the most direct measure of the information required. The KEY Type A variables are:

1.

RCS Wide Range Pressure i

2.

Hot Leg Reactor Coolant Temperature (Wide Range That) i 3.

Cold Leg Reactor Coolant Temperature (Wide Range Tcold) 4.

Wide Range Steam Generator Level 4

5.

Narrow Range Steam Generator Level 6.

Bressurizer Level 4-1

7.

C:ntainment Pressure (N:rmal Range) 8.

Containment Pressure (Extended Range) 9.

Steamline Pressure

10. Refueling Water Storage Tank (RWST)-Level

11. Containment Water Level (Upper Range and Lower Range)

12. Emergency Feedwater Flow

13. Primary Containment Radiation Level

14. Core Exit Temperature Preferred backup Type A Variables have been designated Category 2.

RCS t

subcooling designated as Type A, Category 2.

No Type A Variables have been designated Category 3.

A summary of Type A variables is presented in Table 4-1.

4-2

TABLE 4-1 SUMARY OF TYPE A VARIABLES Variable Variable Tvoe/ Category RCS Pressure (Wide Range)

KEY Al Hot Leg Reactor Coolant Temperature (Wide Range THot)

KEY Al Cold Leg Reactor Coolant Temperature (Wide Range T g)

KEY Al Wide Range Steam Generator Level KEY Al Narrow Range Steam Generator Level KEY Al Pressurizer Level KEY A1 Containment Pressure (Normal Range)

KEY Al Containment Pressure (Extended Range)

KEY Al Steam 11ne Pressure KEY A1 Refueling Water Storage Tank (RWST) Level KEY Al Containment Water Level (Upper Range and Lower Range)

KEY A1 Emergency Feedwater Flow KEY Al Primary Containment Radiation Level KEY A1 Core Exit Temperature KEY Al RCS Subcooling Backup (p)I")

A2 a - Preferred backup i

l l

4 0

4-3

SECTION 5.0 TYPE 8 VARIABLES 5.1 Introduction Type 8 variables are defined in Section 2.2.2.

They are the variables that provide to the Control Room Operating Staff information to assess j

the process of accomplishing or maintaining critical safety functions, 1.e.,

1.

Reactivity Control 2.

Reactor Coolant System Integrity 3.

Reactor Coolant Inventory Control

)

t 4.

Reactor Core Cooling 5.

Heat Sink Maintenance 6.

Reactor Containment Environment Variables which provide the most direct indication (i.e., a KEY variable) to assess each of the 6 critical safety functions have been designated Category 1.

Preferred backup variables have been designated Category 2 or Category 3.

All other backup variables are designated

)

Category 3.

These are listed in Table 5.1.

I

=

i i

l 5-1

,e--- - - -, - - - -.a.,,,-n.,

..,,_,.,__..nn,.,,. _ _,. - - - -..

,,,,,w,

,ny__,__-_

w._.,,,

--wyn

_,_,-an,w.,n,--.,-

TABLE 5-1

SUMMARY

OF TYPE B VARIABLES Function Variable Monitored Variable Function Type / Category Reactivity Control Neuttron Flux KEY B1 Wide Range T Backup (p)

B2 Hot Wide Range T Backup (p)

B2 Cold Reactor Coolant System RCS Pressure (WR KEY B1 Integrity Wide Range THot Wide Range T KEY B1 g

Containment Pressure Backup (p)

B2 Reactor Coolant Pressurizer Level KEY B1 Inventory Control Reactor Vessel Water Level Backup (p)

B2 i

Containment Water Level Backup (p) 82 Wide Range Steam Generator Backup (p) 82 level Reactor Core Cooling Core Exit Temperature KEY B1 Reactor Vessel Water Level Backup (p)

B2 RCS Subcooling Backup (p)

B2 Wide Range T Backup (p)

B2 Hot i

Wide Range T Backup (p)

-B2 Cold RCS Presssure (WR)

Backup (p)

B2 Heat Sink Maintenance Narrow Range S/6 Level KEY B1 l

Wide Range S/G level KEY B1 l

Emergency Feedwater Flow KEY B1 Steamline Pressure KEY B1 Core Exit Temperature KEY B1 Main Steam Isolation /

Bypass Valve Status Backup (p) 82 5-2

1 TABLE 5-1 (Cont)

SUMARY OF TYPE B VARIABLES Function Variable Monitored Variable Function Type / Category Primary Reactor Containment Pressure KEY B1 Containment Environment Containment Radiation Level KEY B1 Containment Water Level KEY B1 Containment Hydrogen Concentration KEY B1 9I I

5-3

SECTION 6 Tvoe C Variables

6.1 INTRODUCTION

Type C variables are defined in Section 2.2.3.

Basically, they are the variables that provide to the Control Room Operating Staff information to monitor the potential for breach or actual gross breach of:

1.

In-core fuel clad; 2.

Reactor Coolant System Boundary; or 3.

Primary Reactor Containment Boundary.

(Variables associated with monitoring of radiological release from the plant are included in Type E).

~

Those Type C key variables which provide the most direct measure of the i

potential for breach of one of the 3 fission product boundaries have been designated Category 1.

Preferred backup information indicating potential for breach is designated Category 2.

Variables which indicate actual breach and have been designated as preferred backup information have been designated Category 2.

All other backup information has been designated Category 3.

Table 6-1 summarizes the selection of Type C variables.

6-1

TABLE 6-1

SUMMARY

OF TYPE C VARIABLES Function Variable Monitored Variable Condition Function Type / Category In-Core Core Exit Temperature Potential for breach KEY C1 Fuel Clad Reactor Vessel Water Level Potential for breach Backup (p)

C2 RCS Sampling Actual breach Backup C3 RCS Boundary RCS Pressure (WR)

Potential for breach KEY C1 RCS Pressure (WR)

Actual breach Backup (p)

C2 Containment Pressure (Extended Range) Actual breach Backup (p)

C2 Containment Water Level Actual breach Backup (p)

C2 y

Containment Containment Pressure (Extended Range)

Potential for breach KEY C1 Boundary Containment Hydrogen Concentration Potential for breach KEY C1 Common Plant Vent Radiation Level Actual breach Backup (p)

C2 Containment Isolation Valve Status Actual breach Backup (p)

C2 Containment Pressure (Extended Range) Actual breach Backup (p)

C2 Auxiliary Building Radiation Level Actual breach Backup (p)

C2 Site Environmental Radiation Actual breach Backup C3

SECTION 7.0 TYPE D VARIABLES

7.1 INTRODUCTION

Type D variables are defined in Section 2.2.4.

Basically, they are those variables that provide sufficient information to the control room operating staff to monitor the perforwance of:

1.

Plant safety systems employed for mitigating the consequences of an accident and subsequent plant recovery to attain a safe shutdown condition, including verification of the automatic actuation of safety systems; and 2.

Other systems normally employed for attaining a safe shutdown condi-tion.

i Type D KEY variables are designated Category 2.

Preferred backup information is designated Type D Category 3.

The following systems have been identified as requiring Type D informa-tion to be monitored:

l 1.

Reactor Coolant System Status (assess status of RCS following an accident) l 2.

Pressurizer Level and Pressure Control (assess status of pressurizer conditions following a return to normal pressure and level control under certain post-accident conditions) 3.

Chemical and Volume Control System (CVCS) (employed for attaining a safe shutdown under certain post-accident conditions) 4.

Secondary Pressure and Level Control _(employed for restoring / main-taining a secondary heat sink under post-accident conditions) 1 l

S.

Emergency Core Cooling System (ECCS) 7-1

6.

Deergency Feedwater 7.

Containment Systems 8.

Component Cooling Water 9.

Service Water

10. Residual Heat Removal (employed for attaining a cold shutdown con-dition under certain post-accident conditions)

11. Heating, Ventilation, Air Conditioning

12. Electric power to vital safety systems

13. Verification of Automatic Actuation of Safety Systems t

Table 7-1 lists the key variables identified for each system listed above. Seismic and environmental qualification for each variable have been specified in Table 1-1.

For the purpose of specifying seismic qualification for Type D Category 2 variables, it is assumed that a seismic event and a break in Category I piping will not occur concurrently. As a result, the limiting event is an unisolable (single failure of a MSIV) break in Class 2 main steam piping.

Instrumentation associated with the safety systems which are required to mitigate and monitor this event should be seismically qualified instrumentation. Similarly, the environmental qualification for Type D Category 2 variables depends on whether the instrumentation i

is subject to a HELB when required to provide information.

7-2

e TABLE 7-1

SUMMARY

OF TYPE D VARIABLES Variable Type /

System Variable Function Catecory Reactor Coolant System Status Pressurizer Level PORY Status Key D2 and Pressure PORV Block Valve Status Key D2 Control Safety Valve Status Key D2 Pressurizer Heater Key D2 Breaker Position Pressurizer Level Key D2 i

Pressurizer Pressure Key 02 RCS Pressure (WR)

Key D2 Pressurizer Heater Current Backup 03 Chemical and Charging System Flow Key D2 Volume Control Letdown Flow Key D2 System (CVCS)

VCT Level Key D2 RCP Seal Injection Flow Key 02 Secondary S/G Atmospheric PORV Key D2 Pressure and Status l

l Level Control S/G Safety Valve Status Key D2 Main Steamline Isolation /

Key D2 Bypass Valve Status Steamline Pressure Key D2 l

l l

7-3 l

TABLE 7-1 (Continued)

SUMMARY

OF TYPE D VARIABLES Variable Type /

System Variable Function Category MFW Isolation Valve Key 02 Status MFW Flow Key 02 Emergency Feedwater Key D2 S/6 Level (WR)

Key D2 S/G Level (NR)

Key D2 S/G Blowdown Isolation Key D2 Valve Status Emergency Core RWST Level Key D2 Cooling System Total HHSI Flow Key D2 (ECCS)

Containment Water Key D2 Level (NR)

Containment Water Key D2 Level (WR)

ECCS Valve Status Key D2 Emergency Feed-Emergency Feedwater Flow Key D2 water Emergency Feedwater Key 02 Valve Status Condensate Storage Tank Key D2 Level Containment Containment Spray Flow Key D2 Containment Water Level Key D2 (WR) and (NR)

Containment Spray Key D2 Valve Status 7-4

[

t t

TABLE 7-1 (Continued)

SUMMARY

OF TYPE D VARIABLES Variable Type /

SV3 tem Variable Function Catecory Fan Cooler Motor Speed Key D2 Containment Pressure Key 02 Component Cooling Header Pressure Key D2 Water System Header Temperature Key D2 (CCW)

Surge Tank Level Key 02 CCW Flow to ESF Components Key D2 CCW Valve Status Key D2 RCP Seal Injection Flow Key D2 t

Service Water System Flow Key D2 System RHR Heat Exchanger Key 02 Discharge Temp.

Valve Status Key D2 RHR Flow Key 02 RCS Pressure (WR)

Key c,

02 l

HVAC HVAC to Essential Key D2 Components l

I i

l 7-s

TABLE 7-1 (C:ntinued)

SUMARY OF TYPE D VARIA8LES Variable Type /

System Variable Function Category Electric Power AC, DC, and Vital Bus Key 02 Voltage Verification of Reactor Trip Breaker / Bypass Key D2 Automatic Actu-Breaker Position ation of Safety SI Activation Key D2 Systems Turbine Stop Valve Key D2 Position Turbine Throttle Valve Key 02 Position i

h Main Feedwater Isolation Key 02 Valve Status Main Feedwater Control Key 02 Bypass Valve Status Emergency Feedwater Key D2 Pump Status SI Pump Status Key D2 l

(

Service Water Pump Key D2 l

Status j

CCW Pump Status Key D2 l

Containment Isolation Key D2 Valve Status l

Containment Fan Key D2 Cooler Status 7-6

=

Section 8.0 Type E Variables 8.1 Introduction Type E variables are defined in Section 2.2.5.

They are those variables that provide the control room operating staff with information to:

1) Monitor plant areas where access may be required to service equipment necessary to monitor or mitigate the consequences of an

accident,

2) Estimate the magnitude of release of radioactive materials through identified pathways, and

3) Monitor and estimate radiation levels and radioactivity in the environment surrounding the plant.

Key Type E variables are qualified to Category 2 requirements.

Preferred backup Type E variables are qualified to Category 3 requirements.

Table 8-1 presents a summary of Type E variables.

(

s-1

i TABLE 8-1

SUMMARY

OF TYPE E VARIABLES Variable Type /

Variable Function Category Primary Containment Radiation Level Key E2 Steamline Radiation.

Key E2 Common Plant Vent Radiation Level Key E2 Non-Headered Vent Radioparticulate Key E2 and Halogen Concentration (Reactor Building Purge Vent)

L Effluent Path Flow Rate Key E2 Area Radiation Monitors Control Room Monitor Preferred E3 Backup Radiochemistry Lab Monitor Preferred E3 Backup Sampling Room Monitor Preferred E3 l

Backup l

f 8-2

TABLE B-1 (Continued)

SUMMARY

OF TYPE E VARIABLES Variable Type /

Variable Function Category Hot Machine Shop Monitor Preferred E3 Backup Reactor Building Personnel Access Preferred E3 Monitor Backup Reactor Building Refueling Bridge Preferred E3 Monitor Backup Reactor Building High Range Monitor Preferred E3 Backup Fuel Handling Building Fuel Handling Preferred E3 Bridge Monitor Backup Auxiliary Building Demineralization Preferred E3 Area Monitor Backup Reactor Building Waste Gas Decay Preferred E3 Tank Area Monitor Backup Auxiliary Building Drumming Preferred E3 Area Monitor Backup Auxiliary Building Waste Holdup Preferred E3 Tank Area Monitor Backup l

B-3 i

6 TABLE 8-1 (Continued)

SUMMARY

OF TYPE E VARIA8LES Variable Type /

Variable Function Category Auxiliary Building Charging Pump Preferred E3 j

Area Monitor Backup Reactor Building In-Core Instrument Preferred E3 Area Monitor Backup Turbine Building Monitor Preferred E3 Backup

.i Control Room Radiation Preferred E3 p

Backup Site Environmental Radiation Level Preferred E3 Backup Neteorological Parameters Preferred E3 Backup l

l l

l l

8-4

.