ML20112G410

Reg Guide 1.97 Rept

ML20112G410
Person / Time
Site:	Fort Saint Vrain
Issue date:	02/28/1985
From:	PUBLIC SERVICE CO. OF COLORADO
To:
Shared Package
ML20112G407	List: ML20112G402 ML20112G410
References
RTR-REGGD-01.097, RTR-REGGD-1.097 TAC-51092, NUDOCS 8504010113
Download: ML20112G410 (27)

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• REGULATORY GUIDE 1.97 REPORT Public Service Company Of Colorado Fort St. Vrain Nuclear Generating Station February 28, 1985 D

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TABLE OF CONTENTS I.-

-PURPOSE

II. -BACKGROUND III. TMETH000 LOGY IV. ANALYSIS SUMARY V .' . SCHEDULE -

VI. CONCLUSION

.VII. TABLE " POST ACCIDENT MONITORING INSTRUMENTATION" I

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I. PURPOSE-

, :The purpose of this document is:

(a) To provide a detailed description of the methodology used L in the determination of plant specific post accident parameters to be monitored for Fort St. Vrain to meet the intent of Regulatory Guide 1.97 (Revision 2) as it is applicable to a High Temperature Gas-Cooled Reactor.

(b) To provide a Post Accident Monitoring (PAM) table for NRC review which delineates the instrumentation required to monitor and display the identified parameters.

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- II. BACKGROUND, The following documents serve as the bases of this report:

Regulatory Guide 1.97, Revision 2 Instrumentation for Light-Water-Cooled Nuclear Power Plants To Assess Plant and Environmental Conditions During and Following an Accident.

NUREG 0737, Supplement 1 (Generic letter 82-33)

Clarification of TMI Action in Requirements.

The NRC required the nuclear utility industry to develop a plant ,

specific table identifying the instrumentation required for post accident monitoring. These documents further delineated the design con,iderations for both the parameters to be selected as well as for the instruments chosen. As these documents and subsequent industry correspondence / meetings pertained to Light Water Reactor (BWR/PWR) designed plants, PSC was required to determine the High Temperature Gas-Cooled Reactor (HTGR) plant specific parameters required to meet the intent of post accident monitoring criteria. The formatting of the attached PAM table reflects guidance criteria in the March 1, 1983 Regional Meeting between the utility industry and the NRC.

F-III. METHODOLOGY =

Without the specific guidance that was provided for LWR's, the selection of R.G. 1.97 instrumentation for HTGR post accident monitoring was unique for Fort St. Vrain. The following steps were taken in the selection process:

(a)' Applicable sections of the Fort St. Vrain FSAR including General Plant Design Criteria (FSAR APPENDIX C) were reviewed to determine the Design Basis Accident conditions which were to be included for post accident monitoring review.

(b) Upon delineation of the applicable accidents to be analyzed, a determination of the systems required to monitor and mitigate each accident condition was completed.

(c) Based on detailed engineering and operations review, the parameters required to determine proper operation of the systems identified in Item (b) for plant safe shutdown were identified. This determination included a detailed review of Emergency Operating Procedures.

(d) The instrumentation required to monitor the identified parameters and the conditions under which the instrumentation was required to operate were determined.

(e) Where existing instrumentation was inadequate to permit proper monitoring of post accident system required operation, modifications / additions were scheduled for plant implementation.

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p IV. ANALYSIS SUP94ARY-The attached PAM table contains the Fort St. Vrain HTGR plant specific monitoring instruments selected by PSC to meet the intent of Reg. Guide 1.97 (Revision 2).

.These parameters were based on detailed analysis of the effects of the accident conditions delineated in DBA 1 (Permanent Loss of Forced Circulation), DBA 2 (Rapid Depressurization/ Blowdown);

the Maximum Credible Accident; or the Loss of Normal Shutdown Cooling as defined in the Fort St. Vrain FSAR. Additional selection criteria were based on the detailed review of the following documents:

(a) NUREG 0737 " Clarification of TMI Action Plan Requirements" Supplement 1.

_(b) ANSI /ANS 4.5-1980 " Criteria for Accident Monitoring Functions in Light-Water-Cooled Reactors."

(c) Fort St. Vrain Technical Specifications, Amendment 46 dated January 30, 1985.

(d) Fort St. Vrain Safety Parameter Di: play System (SPDS)

Safety Analysis Report.

(e) Fort St. Vrain Safety Analysis (Chapter 14 of the Updated FSAR, Revision 2).

(f) Light Water Reactors (BWR/PWR) Owner Groups Generic Positions for the Determination of Parameter Selection.

(g)- Aoplicable Plant Emergency Procedures (1) EP Class, Event and Emergency Classification Overview, Issue 2.

(2) EP G, Extended Loss of Active Core Cooling, Issue 51.

(3) EP H-2, Abnormal Radioactive Gas Release From Plant, Issue 51.

(4) EP H-3, High Activity in the Plant, Issue 51.

(h) Abnormal Procedures for Shutdown Cooling, Issue Number 6.

(1) Procedure for Safe Shutdown and Cooling with Highly Degraded Conditions, Issue Number 13.

(j) Fort St. Vrain General Plant Design Criteria (Appendix C of the Updated FSAR, Revision 2).

The selection process also involved scheduled discussions and meetings with plant operations personnel as well as detailed review of the main control room including considerations of

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thuman factors engineering asl applied to Fort St. Vrain's Control M lRoomDesignReview(CROR). .

1 The: attached PAM table'is'formatt'ed similar to that of Reg.-

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- ; Guide'1.97 to present the information required for each iparameter listed. 'Infaddition to describing the parameter,~this-table includes:- ,

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J(a) :The variablettype classification lof the parameter'(A, B, C, D_or E). ; Note that any parameter can be included in lone or more variable. types.

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(b) 3The. category.(1~, 2, 3) of the instrumentation per page 18

.of this table. This. categorization delineates the environmental qualification,. redundancy, power supply, '

. display,. seismic and QA requirements for each input'.

' li sted. _ s Category selection'was based on guidance

. contained-in Reg. Guide 1.97 (Rev._-2).. .

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'.(c)j(Therangeofthe. display' device. Thi.s' indicates the inumerical range.as well as the engineering units for each

- ' < -- . parameter.

e  ;(d) The primary transmi.tting instrument number. This includes

,, temperature: elements; pressure level transmitters; J

radiation monitors,;; pressure / position swi.tches; etc..

, L(e) The Control Room display device. This includes analog / digital' indicators; multipoint/ strip chart .

recorders;' indicating lights; alarm windows; indicating

, controllers; CRT screens; etc.

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(f) I'The' availability of parameter displays at the Emergency

~Offsite-Facility and Technical Support Center (EOF /TSC).

r Paramett.s'that are-inputs to the plant computer based.

. data logger,' are now available in.the control room and

~TSC. These parameters will be available in the EOF-(Foward Command Post) by the completion of the fourth '

refueling outage,

b. 4 (g) A " Comments" column is included to note individual parameter characteristics such as multi-loop applicability

or_scanni1g-display formatting.

' (h)' The Category 1 and 2 instrumentation is currently or will

.be designated as " safety-related." The Quality Assurance

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. program for safety-related components at Fort St. Vrain is V responsive to-the ANSI Standards addressed by the regulatory guides contained in paragraph 1.3.le. of Regulatory Guide 1.97. .The specific clarifications to tnese ANSI; Standards are contained in section B.5.19 of the FSVl updated'FSAR. The Quality Assurance provisions set forth for Category 1 and 2 instrumentation are p . described in the FSV Operational Quality Assurance Program.

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' V. SCHEDULE ~

With the exception of the wide range PCRV cooling water s e,.

temperature indication (variables B18 and C16) and indication of proper damper position for control room emergency air. flow (variable D31) the instruments listed in the table are currently installed and operable at Fort St. Vrain. This additional u instrumentation will be scheduled for implementation by the completion of the fourth refueling outage.

A Design Document Update Package for variables Al and 81 will be prepared by September 30, 1985. This package will change the designation of these components to safety-related and update our qualification record system for these componets.

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.VI . CONCLUSION Detailed engineering and operations review of the consequences of DBA 1, DBA 2, the Maximum Credible Accident or a loss of Normal Shutdown Cooling Capability, as defined in the Fort St.

Vrain FSAR, has resulted in the following:

(A). The attached PAM table which identifies the instrumentation required fcr Fort St. Vrain to meet the intent of Reg. Guide 1.97 (Rev. 2).

(B) The requirement for Fort St. Vrain to perform the following plant modifications:

(1) addition of wide range temperature indication in the Control Room for PCRV liner coolant monitors.

(2) addition of limit switches to indicate proper damper position in the Control Room for control room emergency air flow.

(c) -The requirement for Fort St. Vrain to perform documentation modifications.

The classification of the following instrumentation will be changed to safety-related and the already existing qualification records will be officially entered into the qualification record system.

(1) PCRV Pressure Indication

, (2) Neutron Flux Indicators i

sy Page 1 of 18 POST ACCIDENT MONITORING INSTRUMENTATION NOTES TO TABLE NOTE 1 - VARI ABLE types and definition are taken straight out of Regulatory Guide 1.97.

The underlined headings in the table represent the FSV High Temperature Gas Cooled Reactor collaries to the Regulatory Guide 1.97 types and definitions.

NOTE 2 - CAT EGORY l i s t ing s a re d ivided into one of the following groups:

CATECORY 1 - This denotes a fully environmentally (as interpreted by PSC to apply to an ifTGR) and seismically qualified instrument channel which complies with existing Quality Assurance criteria and which i s powe red from a Class IE power supply. Redundant indication is provided in the cont rol room.

CATECORY 2 - This denotes a single-channel, fully environmentally, (as inte rp reted by PSC to apply to an HTGR) qualified instrument channel powered f rom a highly reliable power source with indication available in the control in the control room.

CATEGORY 3 - This denotes a high-qua lity, comme rcia l-grade instrument channel powered f rom o f f s i te powe r.

NOTE 3 - INSTRUMENT NO. column provides the sensing element identification.

NOTE 4 - RANGE indicates the range of the control room indicator.

NOTE 5 - CONTROL ROOM DISPLAY provides the instrument identification in the control room.

NOTE 6 - EOF /TSC indicates that this variable is also available in the Technical Support Center and will be ava i l a b l e i n the fo rwa rd Command Post.

NOTE 7 - SPDS CSF means that the variable is a Safety Parameter Display System Critical Safety function.

NOTE 8 - INSTRUMENTATION RANGE will be extended to accommodate expected PCRV circuit outlet temperatures during DBA #1. (Va riables B18 and C16).

NOTE 9 - DAMPER LIMIT SWITCHES and indicating lights i n the Cont ro l Room will be added to indica te p roper damper lineup. (Va riable D31).

NOTE 10 - These are devices for which seismic and environmental qualification records exist but have not yet been officially designated as " safety-related" and had the qualification records input into our qualification record system.

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Page 2 of 18 POST ACCIDENT MONITORING INSTRUMENTATION TYPE: A (NOTE 1)

Those variables to be monitored that provide the primary information required to permit-the control room operator to take specific manually controlled actions for which no automatic control is provided and that are required for safety systems to accomplish their safety functions for design basis accident events. Primary information is information that is essential for the direct accomplishment of the specified safety functions; it does not include those variables that are associated with contingency actions that may also be identified in written procedures. (NOTE 1).

INSTRUMENT CTL ROOM VARIABLE CAT NO. RANGE DISPLAY EOF /TSC (NOTE 21 IMOTE 31 (NOTE 41 INOTE 51 fMOTE 61 PURPOSE COMMENTS Plant Specific A1. Prestressed Concrete 1 PE-1105 0-1000 PI-1108 YES P rovide i n fo r-Reactor Vessel (NOTE 10) PE-1109 psia PI-1109 ma t ion to ope r-( PCRV) Pressu re PE-1110 PI-1110 ator to Indicate when depres-surization should terminate.

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POST. ACCIDENT MONITORINC INSTRUMENTATION' . . _ m

~ TYPE 8: (NOTE 1)

Those variables that provide"information to indicate whether plant safety

, functions are being accomplished. Plant safety functions are (1) . reactivity .-

control, (2) core cooling, (3) maintaining reactor coolant system integrity, and (4) maintaining containment integrity (including radioactive effluent control).

Variables are listed with designated ranges and category for design and quallrication requirements. Key. variables tre indicated by design and quellfication Category 1.

(NOTE 1).

INSTRUMENT CTL ROOM l VARIABl.E CAT - NO . RANCE DISPLAY EOF /TSC.

I fMOTE 21 (NOTE 31 fMOTE 41 fMOTE 51 fMOTE 61 PURPOSE ~ COMMENTS Reactivity Control (SPDS-CSF) (NOTE 71 Q1. Neutron Flux 1 NE-1133-1 10 7 to NI-1133-1 YES Indicate neut '

(NOTE 10) NE-1134-1 10 3% NI-1134-1 ron flux rate NE-1135-1 Full Power NI-1135-1 of the core NE-1133-1 0 to 150% NI-1133-3 NE-1134-1 Ful l - Powe r NI-1134-3 NE-1135-1 Mi-1135-3 NE-1136-1 NI-1136 NE-1137-1 .Mi-1137 NE-1138-1 NI-1138 I

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POST ACCIDENT-MONITORING INSTRUMENTATION.

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INSTRUMENT- 'CTL ROOM VARIABLE -CAT. .

NO. -

-RANGE DISPLAY' EOF /TSC, . . .

- - f980TE 21 '(NOTE 31 'fMOTE 41 (NOTE 51 'fMOTE 61 PURPOSE- C0pWENTS * -

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React tvitv Cont rol - f SPDS CSF) Cont'd

' B2.a Control Rod Position 3 ZSL-1211-1 Full in or ZIL-1211 '. NO R Ve rification Two sets of.37,:

th ru ~ ~not fulI;in 1thru . -. " switches each.'

.ZSL-1211-37 ZIL-1211-37' Two .for each ~

ZSL-1232-1. ~

control' rod.

th ru ' . pair. ...f.. -

- ZSL-2132-37 =

[~ B2.b Control Rod Position 3 ZT-1233-1 192"' Zl-1233-11 YES' Ve ri fica t' ion ' 'One indicator l- thru :thru for each .

l ZT-1233-37 -Zl-1233-37 control rod' -

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! C3, Reserve Shutdown System . 3 PT-2409 0-1500 . PI-2409 YES Verification

[ -. Bottle Pressure psig i~

Core CooIina (SPDS CSF)

B4. Core Outlet Temperature - 3- .TE-11101-1 .100-2000*F XI-9000 YES ' function de-- Two active ~

thru-4 tection (SPDS and two

th ru . Va riab le ) '. spa re i TE-11137-1 the rmocoup l es '

l thru-4 for- each of-37 fuel-regions. -

E5. Maximum Region Outlet .3 Computer N/A :XI-9000

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YES Verification Temperature Mismatch Calc. and prevention of hot spots (SPDS Va riable)

B6. Helium Circulator Inlet 3 TE-1171 1000- TI-1187 YES. . Status of Cool - Two thermo-Tempe ra tu re th ru 1000 F- ' ing (SPDS couples at' TE-1178 Va riab le ) each of four '

c i rcula tor inlets.

87. PCRV Pressure 1 PE-1108 0-1000 ^PI-1108' YES Ve ri fica t ion ~ Same as A1.

(NOTE 10) PE-1109 psia PI-1109 of cobling PE-1110 .P4-1110 i

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.' POST ACCIDENT MONITORING: INSTRUMENTATION-INSTRUMENT. [ CTL' ROOM.

t VARIABLE- CAT .

NO. - RANCE-.. -DISPLAY EOF /TSC~

(NOTE 21 fNOTE 31 (NOTE 41 (NOTE 51 fMOTE 61 PURPOSE ' C08#4ENTS t-

'88. He t lum Circulator ~ ' 1' SE-2109 . 0-12.000- SI-2109 YES Verification or- One for each Speed SE-2110-1 RPM SI-2110 primary coolant of 4 circ-SE-2115-1 Si-2115 riow (SPDS : - ulators SE-2116-1 SI-2116 ' Va riable)

Reactor Coolant System 'Inteority (NOTE-11 (liner and primary closure) -

B9. PCRV Pressure 1 PE-1138. 0-1000 'PI-1108 YES Verify pressure Same as A1.

(NOTE 10) PE-1109 psia PI-1109 is within design PE-1110 PI-1110 limits (SPDS

Va riab le) 1

! B10. Penetration Interspace 3 FE-11263 0-4.3 ACFM F1-11263 YES . indication or Flow prima ry closure integ ri ty B11. Helium Circulator Seal 3 ZS-21191,. Seal' set Zl-21191, 92 'YES. Indicate primary Eight total i

Status 92, 93, or not 93, 94-2 barrier integrity 94-2, 6-4 set when ci rculator is stopped 912. Hot Reheat Steam 3 'RT-93250-10 .1-1,000 RI-93250-10 YES Indicate breach Three per Loop l Radiation RT-93251-10 mr/hr . RI-93251-10 of hot reheat RT-93252-10 RI-93252-10 portion or RT-93250-11 RI-93250-11 steam gener-RT-93251-11 RI-93251-11 stor tubes RT-93252-11 RI-93252-11 813. He t lum ci rculator 3 PSH-11177 0-1500 XA-9325 YES Indicate breach Three per Penetration interspace thru psig thru or piping with- each of Pressure Switch PSH-11188 XA-9328 in interspace four (Alarm Only) (SPDS Variable) c i rcula to r-penet ra t ions B14. Steam Generator 3 PSH-11219 O-1500 XA-9323 YES Indicate breach Three per Loop Penetration inter- th ru psig XA-9324 of piping with-space Pressure PSH-11224 ( Ala rm Only) in interspace Switches (SPDS Variable) 2_r.

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' POST ACCIDENT MONITORING INSTRUMENTATION 1 -

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. . INSTRUMENT) CTL ROOM.

' VARIABLE- CAT . . NO. .

. RANGE. DISPLAY' E0r/TSC , . .

(NOTE 21 -(NOTE 31- (NOTE 41 (NOTE 51 (NOTE 61 ~ PURPOSE- CopetENTS '

B15. ' Roactor. Build sog Vent 3.~ ' R T-7324- 1&2 ' ... 30-10-7 CPM 'RR-93539': YES' indicate breach

' Exhaust Radiation- RT-73437-1&2 10-106 CPM RR-734371 . of prima ry cool-Moni tor :- 2 ant system bound-

.ary.

816. 'PCRV Safety Valve . '3 RT-93252 . 1-10,000 'RR-93252 YES- Indicate status

'.Discha rge _ Radiation _ mr/hr _ of safety va lve .

~ Monitor-Reactor Containment Intearity -

(PCRV concrete and secondary closure)

B17. PCRV Coo l i ng Wa te r ~3 TE-4637-1 ' 50-150*F TR-4637 YES- ' Indicate con- Two per Loop Inlet Temperature TE-4638-1 TR-4638 crete being TE-46209 TI-46209- kept within -

TE-46210 Tl-46210- ~ design-temp .

e ra tu re - l imi ts -

,. B18. PCRV Coo l i ng Wa te r 3 'TE-4637-3 50-150 F -TR-4637 YES Indicate con - One per Loop

Outlet Temperature TE-4638-3 (NOTE 8) .TR-4638 crete beIng i.

kept within.

design temp-erature ^Ilmits B19. PCRV Surface Concrete 3 TE-73336-1 50-150*F TR-4637 'YES Indicate con-Tempe ra tu re TE-73336-2 TR-4638- crete being

'kept within design temp-

!' erature limits B20. PCRV Pressure 1 PE-1108 0-1000 PI-1108 YES Verify pres- Same as A1 (NOTE 10) PE-1109 psia PI-1109 sure is within

! PE-1110 PI-1110 design limits Penetration interspace 3 '

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1ZS-1128 Open/Close Zl-1128 NO Indication of 7 Flow Isolation Valve breach secondary 1

Status indication penetra tion i 8?2. Penetration Interspace . 3 FE-11263 0-4.3 ACFM F1-11263 YES Indication of Same as B10

Flow breach of .

secondary penet ra t ion -

! Closure a

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POST ACCIDENT MONITORING INSTRUMENTATION -

INSTRUMENT- 'CTL ROOM VARIABLE ' CAT, . NO. RANCE DISPLAY -EOF /TSC.

(NOTE 21 fMOTE 31 (NOTE 41 fMOTE 51 (NOTE 61 PURPOSE COMMENTS B23. PCRV Rupture Disk 3 ZS-1197- .Open/Close Zl-1197 . NO Indicate the. One per.

Isolation Valve- 1,2 1,2, ' status of Isolation Position seconda ry , Valve boundary

, valves B?4. Ci rcuIator Penetration 3 PSH-11177: 0-1500 ..XA-9325 ~ YES: Indicate Same as B13-Interspace Pressure 'thru psig' th ru intea rt ty PSH-11188 XA-9328- or secondary-( Ala rm Only) penet ra t ion closure B25. stearn Generator 3 PSH-11219, '0-1500 XA-9323 YES Indicate- Same'as B14 Penet ra t i on - i nte r- thru psig. XA-9324 ' i nteg r i ty :

space Pressure PSH-11224 ' ( Ala rm Only) of. outer.

Switches. ' penetration B?6. Core Outlet Temperature ' 3 TE-11101 100-2000 F' .XI-9000 .YES Verify temp- .Same as B4 1 thru-4 e ra tu re i s thru v{ thin TE-11137 design 1 thru-4 limits b

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. 4 Page'8 o'r(18' POST ACCIDENT MONITORING INSTRUMENTATION TYPE C: (NOTE 1) . ,

Those variables that provide information to indicate.the potential' for being breached or the actual breach of the barriers to fission product releases. 'The barriers a re (1) fuel cladding, (2) prima ry coolant pressure bounda ry, and (3) conta inment. (NOTE 1)-

INSTRUMENT -CTL ROOH VARIADLE CAT NO. . RANCE D I SPLAY - EOF /TSC (NOTE 21 (NOTE 31 fNOTE 41 fNOTE 51 (NOTE 6) PURPOSE COMMENTS Fuel Pa rticle Coatino Inteority C1. PCRV Pressure 1- .

PE-1108 0-1000 PI-1108 .YES. Indicate po- Same as A1 (NOTE 10) PE-1109 psia PI-1109 .tential fo r .

PE-1110 PI-1110 fuel damage

'(adequate flow)

C2. Reactor Coolant 3 RT-9301 30 tg RR-93256 *YES Indicate ci rc-System Activity 2x10f CPM ulating activity (SPDS Variable)

C3. Helium Circulator 1 SE-2109 0-12.000 SI-2109 Indicate po- Same as 88 Speed SE-2110 RPM SI-2110 tential for

-SE-2115 SI-2115 fuel damage SE-2116 SI-2116 (adequate flow)

C4. Core Outlet Temperature 3 TE-11101- 100-2000 0 F XI-9000 YES Indicate po- Same as B4 1 thru 4 tential fo r

.thru fuel damage TE-1113T-1 thru to C5. Helium Circulator 3 TE-1171 100-1000 F TI-1187 YES Indicate po- Same as B6 Inlet Temperature thru tential fo r TE-1178 Fuel damage C6. Maximum Region Outlet 3 Computer N/A XI-9000 YES Indicate po - Same as B5 Temperature Mismatch . Calc 'tential for-fuel damage

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1 EPOST ACCIDENT MONITORING.INSTRUMENTATl'ON

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. INSTRUMENT .. 'CTisROOM.

VARIABLEL CAT . NO. . RANGE ~. .'OISPLAYl . EOF /TSC ' .

. 'fNOTE 21 -(NOTE 31- "fNOTE'41 iNOTE 51 "(NOTE 61 -PURPOSE ~ COMMENTS'

' Reactor Coolant System Pressure Boundary

( l i ne r a: p ri ma ry, c losu re s ) 7

. C7. PCRV ' P ressu re . 1" .PE-1108 1000' .PI-1108' '.. YES ': findicate po- . Same a s ' A1  ;-

PE-1109-

"(NOTE 10) . psia. PI-1109 tentia l for '

?PE-1110 PI 1110. E rup tu re o f '

boundary C8. Penetration Interspace. 3 FE-11263- 0-4.3 ACFM- '

F1-11263:

.YES Indicate breach Same as B10 Flow . of inner pene .-

t ra t i on _' ~

C9. Ci rculator Seal Status 3_ ZS-21191, Set or not Zl-21191, -YES: ' Indicate bound-. .Same as B11

. 92, 93, ' set 92, 93, a ry status 94-2&4 94-2 . a round ci rc-

' ulator shaf t when:it.is' stopped' C10. Reactor But Iding 3 RT-7325-1&2 30-10[ RR-93539 YES Ind ica te' breach . Same as'B15, Ventilation Exhaust RT-73437-1k2 10-10 CPM CPM RR-73437 of liner or Stack System Radiation primary closures .

C11. Steam Jet-Air Ejector 3 RT-31193 .30-2x10~ RR-93538 YES . Indicate breach '

Radiation CPM.- ' o f steam gene r- -

ator tube C12. Hot Reheat Steam 3 RT-93250-10 J0.1-10,000 RI-93250-10 YES Indicate breach - Same a s B12 -

Radiation RT-97.251-10 ' . ar/h r- .RI-93251-10 of. reheat sec-RT-93252-10 RI-93252-10 tion of steam RT-93250-11 RI-93250-11 gene ra to r RT-93251-11 RI-93251-11 RT-93252 RI-93252-11

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POST ACCIDENT: MONITORING" INSTRUMENTATION.

y INSTRUMENT- .

CTL ROOM VARIABLE CAT : NO. . RANCE ' DISPLAY ' EOF /TSC fNOTE'21 iNOTE 31- fNOTE 4l' fNOTE 51 (NOTE 61 . PURPOSE COMMENTS C13. PCRV Safety Valve- 13- RT-93252 0.1-10,000 - RR-93252-12 .YES. Indicate status. Same.as B16 Discha rge Radiation ar/hr - .of safety valve:

Monitor ha_p_ tor Conta inment Pressure Bounda ry

( PCRV conc re te 4 seconda ry . c l o su re ) .

C14. PCRV Coo l i ng Wa te r 3 TE-4637-1 150 F.. TR-4637 ~ YES < indicate the- Same as B17 TE-4638-1 TR-46383 Inlet Temperature potnntial for- s TE-46209.' TI-46209. ra l l u re o f the TE-46210 _

TI-46210 seconda ry -~

boundary

.C15. PCRV Coo l ing Wa t.e r 3 TE-4637-3 50-1500F TR-4637- .YES - Indicate the Same as B18

. Outlet Temperature : TE-4638-3 (NOTE 8)- TR-4638 potential for.

failure of the secondary bounda ry .

C16. PCRV Pressure - 1 . -PE-1108 10-1000. Pl-1108- YES Indicato the, Same as A1 (NOTE 10) 'PE-1109 psia. PI-1109 potential for PE-1110 PI-1110- fa i lure of. the ,

secondary

' bounda ry

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C17. PCRV Rupture Disk 3 ZS-1197-1,2 Open/Close Zl-1197-1,2 NO Indicate the- . Same a s 823 <

Isolation Valve status of Position seconda ry boundary valves C18. Reactor Building 3- RT-7324-l ar2 .30-107 CPM' RR-93539 YES Indicate a Same as B15 Exhaust Stack RT-73437-1&2 '10-106 CPM' RR-73437 breach of Ventilation System seconda ry Radiation Monitor closure.

C19. Penetration interspace 3 ZS-1128 Open/Close ZS-1128 NO Indicate Same as 821 Flow Isolation Valve failure of Position-Indication -outer pene-t ra t i on ~

7 ,

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Page 11'of'.18

.,' -POST ACCIDENT MONITORING lNSTRUMENTATION INSTRUMENT 1 .. 'CTL' ROOM' VARIABLE . CAT . NO. RANGE -DISPLAY. EOF /TSC fNOTE 21' fNOTE 31 (NOTE 41 (NOTE 51 (NOTE 6) PURPOSE-. ' COMMENTS Final Fission Product Cleanup System (Reactor Building)

C20. Louver Position via 3 PS-7377- Closed or . Ala rm Only NO Indicate Status . Two p re s su re .

Pressure Indication I thru 20 Not Closed - of , louvers . switches for PS-7382- each of 20

1. th ru . 20 louvers-C21. Reactor Building 3 .PDT-73335, 0-1.5 psid- _PDR-73335,- NO ' Indicate po-Pre ssu re PDT-73440 PDR-73440 ~tentia l -' fo r thru . thru. l ouve rs . open-PDT-73452' PDR-73452. .Ing.

C22. Refueling Floor to - 3 PDT-7319-1 0 to -2"- PDI-7319 'NO Indicate po-Ambient Differential th ru -4 HO 2 tential fo r Pressu re louvers open-ing.

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,o Page[13'of 18 POST ACCIDENT MONITORING INSTRUMENTATION INSTRUMENT- CTL' ROOM-VARIABLE CAT' .

NO. . RANCE DISPLAY EOF /TSC (NOTE 21 (NOTE'31 (NOTE 41 (NOTE 51 fNOTE 61 PURPOSE ' COMMENTS D7. Fi re Water Pump 2 .PT-4502 150 psig PI-4502 YES Indicate op-Discha rge Pressure eration or fire .

pump and water supply to drive circulator pelton

' wheel and remove heat of SG -

D8. Storage Basin Level 3 LT-4102- 0-100 L1-4102-?- NO Indicate adequate-1,2 Million - water supply for Gals ci rculator drive and hea t . remova i from core SYcondary Heat Removal (SPDS CSF)

D9. Steam Generator EES 2- FT-2205 '0-1.250 FR-2205' YES Indicate ad- For both Loops inlet (Feedwater) Flow FT-2206 M-Ib/hr FR-2206 equate flow or water for heat removaI (SPDS Variable) .

DIO. Emergency Condensate 2 FT-2239 0.1.250 FR-2239 NO Indicate ad- One pe'r Loop to Steam Generator HRH FT-2240 M-lb/hr FR-2240 - equate flow Inlet flow or water for heat removal D11. Steam Generator EES 3 T E-2205 0-500 0 F TI-2205 YES Indicate proper One per Loop Inlet (Feedwater) TE-2206 TI-2206- ope ra t ion -

Tempo ra tu re D12. Steam Generator EES 3 TE-22121 0-1200 F._ TR-22121 YES Indicate proper One per Loop Outlet (Main Steam) TE-22122 TR-22122 operat ion (SPDS -

Tempe ra tu re Va ria b le )

D13. Steam Generator HRH 3 TE-2255-7 0-800 F TR-2232 NO Indicate proper For both Loops -

Inlet Temperature TE-2256-7 ope ra t ion D14. Steam Generator Module 3 TE-2255 0-1200 F TR-2255 YES Indicate proper For both. Loops HRH Outlet Temperature 1 thru 6 operation (SPDS TE-2256 Va ria b le )

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POST. ACCIDENT; MONITORING lNSTRUMENTATIONf -" -

+ a.. ,

_ INSTRUMENT. .

. CTL-- ROOM . - -

VARIABLE' .

CAT. ..NO. , . RANCE- . - DISPLAY' EOF /TSC -

(NOTE'21 (NOTE 31- (NOTE 41 ~fNOTE 51 fMOTE 61 PURPOSE COf#4ENTS Purification Coolina Water System ' <

D23. ' Purification Cooling :3

.- TE-2321-1 ; 0-800*F ' TR-2321. 'NO -i nd i ca te p rope r. ' I For both iL. oops _

Water Heat Exchanger TE-2321-2 '

' (Multipoint).

' ~ '

operation of -

Outlet Temperature system-Helium Purification System D24. Helium Purification .3 TE-2321-5. 0-800*FL TR-2321 ~ NO - -Indicate proper For;both Loops -

High Temperature 7E-2321 ' (Multipoint)- ope ra tion Absorber Outlet Tempe ra tu re D25. Helium Purification 3 TE-2319- ' 0-200 F TI-2319 NO- In' dica'te proper For both Loops ,

Cooler Outlet TE-2320 TI-2320' ' ope ra t ion -

Tempe ra tu re D26. Hellum Purification 3 TE-23105 0-700*F TI-23105 NO I nd i ca te p rope r.,  ? for .both Loops TE-23106- ope ra t ion .

Dryer Outlet TI-23106 Tempe ra tu re D27. Helium Purification 3 TE-2322-3 ~0-800*F TR-2322 NO Indicate proper For both Loops Low Temperature TE-2322-4 (Multipoint) ope ra t ion .

Absorber Outlet Tempe ra tu re S'arvice Wa ter System D28. Service Water Pump Pit 2 LT-4218 -10 to.+4:' LIC-4218-1. NO. I'ndicate ad-Level inches.' equa te .wa te r -

supply'for service water system:

D29. Service Water Pump 3 PT-4229- 0-50 psig PI-4229 YES. Indicate op-Header Discha rge eration of Pressure pump -

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Page 16 ot* 18 L -

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POST ACCIDENT. MONITORING INSTRUMENTATION '

j INSTRUMENT .

'CTL' ROOM

. VARIABLE.. ' CAT .

- NO . RANCE DISPLAY'. EOF /TSC . - . . .

'iNOTE 21 (NOTE 31 iNOTE 41 fNOTE 51 iNOTE 61 . ~ PURPOSE COMMENTS Nitrocen System t

D30. Storage Tank Level 3 LT-2519-1 1200-1200 Ll-2519 'YES- Indicate ad-

. gallons equate. supply '. i of liquid N2 fo r proper operation -

of low temp-:

erature adsorber-

-Ventilation' System D31. ~ Damper Position for - 3 None ~ Open/Close None -- No indicate' status Control Room Emergency ' ' (NOTE 9) (NOTE 9) of dampers Air Flow D32. Reactor Building Vent - 3 FT-7320 0-60,000 FT-7320 .NO Indicate exhaust-Exhaust flow CFM flow Powe r SuDD I les D33. Essential 480V Bus 3 ES-9273A,- 0-600 .

El-9273A NO ' . Indicate system-Voltage - 9274, 9275A- Volts AC 9274, 9275A- status D34. Essential 480V Bus 3 YES .

0-500 YES YES. Indicate system.

Cu rrent (No Number) . Amps AC- (No Number) status D35. Essential 125V Bus 3' ET-92220 0-150 El-92220- .NO . indicate' system Voltage ET-92221 Volts El-92221 status.

D36, instrument Ai r. Receiver 3 PT-8212 0-125- PI-8212 YES Indicate system Pressu re PT-8254 psig PT-8254 status D37. Hydraulic Loop Pressure ' 3 PT-9105 2000-3500 PI-9105- NO Indicate system PT-9106 psig PI-9106 status

= . . ~

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\

2 Pagef17'oT'18 POST ACCIDENT MONITORING INSTRUMENTATION TYPE E: (NOTE'1)

- Those variables to be monitored as required ror use in. determining the magnitude

.00 the release or radioactive materials and continually assessing such releases.

' INSTRUMENT- CTL ROOM .

VARIABLE CAT No. RANGE- DISPLAY LOF/TSC ~*

[ NOTE 21 'fNOTE 31 (NOTE 41 'fNOTE 51 (NOTE'61 . PURPOSE COMMENTS-Ai rborne Radioactive Materia l Released From Plant E1. Reactor Building Vent 2 FT-7320 0-60,000 .F1-7320 NO . Verification- Same as 032-Exhaust Flow CFM or exhaust

.rioW E2. Reactor Bu t tding Vent 3. RT-7324-18e2 3b-107 CPM RR-93539 .YES Detection of Same as BIS Exhaust Radiation RT-73437-1&2 10-106 . CPM RR-73437 significant re lea ses Monitor E3. PCRV Safety Valve 3 RT-93252-12 .1-10,000 RR-93252-12 YES Detection of Same as B16 Discha rpe Radiaticn er/h r significant.

releases E4. PCRV Pressure 1 PE-1108 0-1000 Pi-1108 YES Detection of Same as A1 (NOTE 10) PE-1109 psia PI-1109 significante PE-1110 PI-1110 releases Environs Radiation and Radioactivity E5. Portable Radiation 3 N/A N/A N/A N/A Ve ry s ig -

Instrumentations / nificant releases Sensors and local mag-nitudes Meaeo roloav 0

E6. Wind Di rection @ $8M 3 XT-93107 0-540* XR-93574-1 YES Release Assess-

@ 10M XT-93109- 0-540 XR-93574-2 ment E7. Wind Speed @ 58M 3 XST-93106 0-100 MPH XR-93574-1 YES' Release Assess-

@ 10M XST-93108 0-100 MPH XR-93574-2 -ment-

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I' . ' Page 18 or.18 :

s POST' ACCIDENT MONITORING'.' INSTRUMENTATION-INSTRUMENTc -CTL ROOM

, ._ VARIABLE' . CAT. NO. RANGE- DISPLAY eof /TSC.

(NOTE 21 . INOTE 31 'fNOTE 41 (NOTE S1 (NOTE 61-PURPOSE COMMENTS E8. Estimate or Atmospheric 3 - Release Assess -

StabiIity -ment' 4 Temp.- Di rre rent la l TT-93110-2 -5*F to, XR-9357f4-3 between 58M ac 10M. +5 cF Accident Samolino'Caoability.

l. E9. Primary Coolant 3 N/A~ . N/A .. N/A. Release Assess-' Grab Sample . ' -

- gross activity ment; ve ri ri-

- gamma spectrum catlon.

I i

- . - .1._.