ML20205P302
| ML20205P302 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 11/02/1988 |
| From: | Warembourg D PUBLIC SERVICE CO. OF COLORADO |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, RTR-REGGD-01.097, RTR-REGGD-1.097 P-88326, NUDOCS 8811080054 | |
| Download: ML20205P302 (23) | |
Text
.t O M4 7 e .' ,
h Public Service- Eh 2420 W. 26th Avenue, Suite 1000, Denver, Colorado 80211 November 2, 1988 Fort St. Vrain Unit No. 1 P-88326
- 11. S. Nuclear Regulatory Comission Attn: Document Control Desk Washington, DC 20555 Docket No. 50-267 SU8 JECT: Emergency Response C6pabilities Regulatory Guide 1.97
REFERENCES:
- 1) PSC letter from Warembourg to NRC, dated March 14, 1988 (P-88088)
- 2) NRC Memorandum frou Heitner to Calvo, dated June 8, 1988 (G-88256)
Gentlemen:
In the Reference 1 letter, Public Service Company of Colorado (PSC) submitted a revised RG 1.97 list to the NRC. In a subsequent meeting on June 2, 1988, FSC informed NRC that some areas were still under review as part of our overall NUREG-0737 approach, and revisions to that list were possible.
In Reference 2. NRC requested that PSC supply a revised Sumary Table of RG 1.97 instrumentation.
Enclosed is the revised RG 1.97 Summary Table. Only four changes have been made with regard to the list submitted with Reference 1:
Variable 81: The neutron flux power range channel detectors a) and indicators have been replaced with the start-up channel instrumentation. The start-up channel instrumentation will be the primary source of operator infonnation regarding the flux rate of the reactor at low power to confirm reactor shutdown. In addition, the range of the power ra r.ge instrumentation was redundant to that available from the log / linear range channels. O es1iceg%2h p
S$k6c' PDB 1 P
. P-88326
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- ) N'ovember 2, 1988 s
b) Variable D18a: The neutron flux start-up channel instrumentation was added for the same reason discussed above.
c) Variable D31: Add two more limit switches for indication of Control Room damper valve position, d) Variables B4, B26, and C4: The sensing elements have been changed from TE-11101-1 through TE-11137-1 to TE-11101-2 through TE-11137-2. The new sensors measure cora ourlet temperatures at the same location as thosa V are replaced. However, the control room display for L...e have a greater range. In addition, the new sensors are also included as a SPDS variable.
The attached list is considered final, and we believe contains enough information for NRC to conclude their review of our RG 1.97 instrumentation.
If you have any questions in this matter, please contact Mr. M. H. Holmes at (303) 480-6960.
Very truly yours, 42tr / % ~/
D. W. Warembourg, Man er Nuclear Engineering Division DWW/SM:pa Attachment cc: Regional Administrator, Region IV Attn: Mr. T.F. Westerman, Chief Projects Section B Mr. Robert Farrell Senior Resident Inspector Fort St. Vrain
Page 1 cf 21 ,
POST ACCIDENT MONITORING INSTRUMENTATION NOTES TO TABLE -
l NOTE 1 - VARIABLE types and definition are taken straight out of Regulatory Guide. l.97. The ar. notated headings in the table represent the FSV High Temperature Gas Cooled Reactor collaries to the Regulatory Guide 1.97 ' types and * '
definitions. '!
NOTE 2 - CATEGORY listings are divided into one of the following groups:
CATEGORY 1 - This denotes a redundant, fully environmentally and seismically qualified instrument channel which cod. plies with existing Quality Assurance criteria and which is powered from a Class 1E power supply. ,
CATEGORY 2 - This denotes a single-channel, fully environunentally, qualified instrument channel powered from a highly reliable power source with indication available in the control room. .
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CATEGORY 3 - This denotes a high-quality, comercial-grade instrument channel powered from offsite power.
NOTE 3 - INSTRtNENT N0. column provides the sensing element identification.
NOTE 4 - RANGE indicates the range of the control room indicator.
l NOTE 5 - CONTROL ROOM DISPLAY provides the instrument identification in the control room.
l l NOTE 6 - E0F/TSC indicates that this variable is also available in the Technical Support Center and will be available -
l in the Forward Command Post.
NOTE 7 - SPDS CSF c:eans that the variable is a Safety Parameter Display System Critical Safety Function.
NOTE 8 - DAMPER LIMIT SWITCHES and indicating lights in the Control Room will be added to indicate proper damper lineup. (Variable 031).
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Paga 2 cf 21 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 acticns 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).
INSTP.UMENT CTL ROOM YARIABLE CAT NO. RANGE DISPLAY E0F/TSC (NOTE 2) (NOTE 3) (NOTE 4) (NOTE 5) (N0IE 6) PURPOSE COMMENTS Plant Specific A1. Prestressed Concrete 1 PE-1108 0-1000 PI-1108 YES Provide infor-Reactor Vessel PE-1109 psia PI-1109 mation to oper-(PCRV) Pressure PE-1110 PI-1110 ator to indicate when depres-surization should terminate.
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O Paga 3 of 21 ,
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POST ACCIDENT MONITORING INSTRUMENTATION .
l TYPE B: (NOTE 1) Those variables that provide information to indicate whether plant safety functions are being accomplished. Plant safety functions are (1) reactivi ty 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 qualification requirements. Key variables are indicated by design and qualification Category 1. (NOTE 1).
INSTRUMENT CTL ROOM VARIABLE CAT NO. RANGE DISPLAY EOF /TSC (NOTE 2) (NOTE 3) (NOTE 4) (NOTE 5) (NOTE 6) PURPOSE COMMENTS Reactivity Control (SPDS-CSF) (NOTE 7)
Bl. Neutron Flux 1 NE-1133-1 10-7 to NI-1133-1 YES Indicate neut-NE-1134-1 10+3% NI-1134-1 ron flux rate NE-1135-1 Full Power NI-1135-1 of the core (SPDS Variable)
NE-1133-1 0 to 150% NI-1133-3 NE-1134-1 Full Power NI-1134-3 NE-1135-1 NI-1135-3 NE-1131 1 to 3X105 NI-1131-1 Approxiggte range is NE-1132 counts per NI-1132-1 8 X 10- to 8 X 10 %
second of full power.
o Pag 3 4 cf 21 ,
POST ACCIDENT MONITORING INSTRUMENTATION ,
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INSTRLEENT CTL ROOM VARIABLE CAT NO. RANGE DISPLAY EOF /TSC (NOTE 2) (NOTE 3) (NOTE 4) (NOTE 5) (NOTE 6) PURPOSE COMMENTS Reactivity Control (SPDS CSF) Cont'd B2.a Control Rod Position 3 ZSL-1211-1 Full in or ZIL-1211-1 N0 Verification thru not full thru of Rod Position ZSL-1211-37 in ZIL-1211-37 B2.b Control Rod Position 3 ZT-1233-1 0-192" ZI-1233-1 YES Verification One thru thre of Rod Position indicator ZT-1233-37 ZI-1233-37 for each control rod pair.
B3. Reserve Shutdown 3 PT-2409 0-1500 PI-2409 YES Verification System Bottle Pressure psig of System Pressure Core Cooling (SPDS CSF)
B4. Core Outlet Temp. 3 TE-11101-2 100-2300 F XI-9000 YES Function de-thru tection (SPDS TE-11137-2 Variable)
B5. Maximum Region Outlet 3 Computer N/A XI-9000 YES Verification Temperature Mismatch Calc. and prevention of hot spots (SPDS Variable)
B6. Helium Circulator 3 TE-1171 100-1000 F TI-1187 YES Status of Cool- Two thermo-Inlet Temperature thru ing (SPDS couples at TE-1178 Variable) each of four circulator i nlets.
i B7. PCRV Pressure 1 PE-1108 0-1000 PI-1108 YES Verification Same as A1.
PE-1109 psia PI-1109 of cooling PE-1110 PI-1110 l
Ptga_5 of 21' .,-
POST ACCIDENT MONITORING INSTRUMENTATION ,
INSTRUMENT CTL ROOM VARIABLE CAT N0. RANGE DISPLAY EOF /TSC (NOTE 2) (NOTE 3) (NOTE 4) (NOTE 5) (NOTE 6) PURPOSE COPMENTS . ,
B8. Helium Circulator 3 SE-2105-1 0-12,000 SI-2109 YES Verification of One for each Speed SE-2106-1 RPM SI-2110 primary coolant .of 4 circ- .l SE-2111-1 SI-2115 flow (SPDS ulators SE-2112-1 SI-2116 Variable)
B8.a Stean Generator EES 1 TE-22121 0-1200*F TI-22121 YES Indicate proper Outle.t (Main Steam) TE-22122 TI-22122 operation (SPDS H Temperature Variable)
B8.b Steam Generator EES 1 PT-22129-1 0-3000 PR-22129 YES Indicate existence Outlet (Main Steam) PT-22130-1 psig PR-22130 of steam at outlet Pressure (SPDS Variable)
E8.c Steam Generator EES 3 FT-2205 0-1.250 FR-2205 YES Indicate adequate Inlet (Feedwater) FT-2206 M-lb/hr FR-2206 flow-of water for heat removal (SPDS variable)
Reactor Coolant System Integrity (NOTE 1)
(liner and primary closure)
B9. PCRV Pressure 1 PE-1108 0-1000 PI-1108 Verify pressure Same as Al-PE-1109 psia PI-1109 is within design PE-1110 PI-1110 limits (SPDS Variable)
B10. Penetration Inter- 3 FE-11253 0-4.3 ACFM FI-11263 YES Indication of space Flow primary closure integrity Bil. Helium Circulator 3 ZS-21191-2,-4 Seal set ZI-21191-2,-4 YES Indicate primary Seal Status ZS-21192-2,-4 or not ZI-21192-2,-4 barrier integrity ZS-21193-2,-4 set ZI-21193-2,-4 when circulator 25-21194-2,-4 ZI-21194-2,-4 is stopped
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POST ACCIDENT MONITORING INSTRUMENTATION 1 i INSTRUMENT CTL ROOM L
VARIABLE CAT NO. RANGE -DISPLAY EOF /TSC (NOTE 2) (NOTE 3) (NOTE 4) (NOTE 5) (NOTE 6) PURPOSE C0pt4ENTS B12. Hot Reheat Steam 3 RT-93250-10 . 1-1,000 RI-93250-10 YES Indicate breach Three per Loop Radiation RT-93251-10 mr/hr RI-93251-10 of hot reheat ,
RT-93252-10 RI-93252-10 portion of RT-93250-11 RI-93250-11 steam genera-RT-93251-11 RI-93251-11 ter tubes RT-93252-11 RI-93252-11 B13. Helium Circulator 3 PSH-11177 0-1500 XA-9325 YES Indicate breach Three per.
Penetration Inter- thru psig thru of piping with- each of.
space Pressure Switch PSH-11188 XA-9328 in interspace four (Alarm Only) (SPDS Variable) circulator penetrations B14. Steam Generator 3 PSH-11219 0-1500 XA-9323 YES . Indicate breacii - 'Three per Penetration thru psig XA-9324 of piping with- - Loop-l Interspace PSH-11224 (Alarm Only) in interspace Switches (SPDS Variable) 815. Reactor Building Vent 3 RT-7324-1,-2 30-2x10I RR-93539 YES Indicate breach-l Exhaust Radiation CfM of primary cool-l Monitor RT-73437-1,-2 10-10" CPM RR-73437 any rystem bound-ary l B16. PCRV Satety Valve 3 RT-93252-12 . 1-10,000 RR-93252-12 YES Indicate status Discharge Radiation mr/hr of safety valve Monitor l Reactor Containment Integrity (PCRV concrete and secondary closure) i B17. PCRV Cooling Water 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 TI-46210 design temp-erature limits b
-,----..--,---w.--,,,--ww ..,- --e. y, w,-,,,--,,--w,r. -e -,-.--y,v-,, , , - - - - - --m-- -,
3 - -- ,y-- - - .,_, - , - ,,w-~--- v,- --- v-
Pag 2 7 cf 21 ,
POST ACCIDENT MONITORING INSTRUMENTATION .
INSTRUMENT CTL ROOM VARIABLE CAT NO. RANGE DISPLAY EOF /TSC (NOTE 2) (NOTE 3) (NOTE 4) (NOTE 5) (NOTE 6) PURPOSE COMMENTS B18. PCRV Cooling Water 3 See Comment 0-1S00 F XI-9000 YES Iridicate con- One TE for Outlet Temperature crete being each of 535 kept within channels input design temp- to scanner erature limits for indication B19. PCRV Surface Concrete 3 TE-73336-1 50-150 F TR-4637 YES Indicate con-Temperature 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 Al PE-1109 psia PI-1109 sure is within PE-1110 PI-1110 design limits B21. Penetration Inter- 3 ZS-1128 Open/Close ZI-1128 NO Indication of space Flow Isola- breach second-tion Valve Status ary penetra-Indication tion B22. Penetration Inter- 3 FE-11263 0-4.3 acfm FI-11263 YES Indication of Same as BIO space Flow breach of secondary penetration closure l
B23. PCRV Repture Disk 3 ZS-1197-1 Open/Close ZI-1197-1 NO Indicate the One per Isolation Valve ZS-1197-2 ZI-1197-2 status of Isolation Position secondary Valve boundary valves B24. Circulator Penetra- 3 PSH-11177 0-1500 XA-9325 YES Indicate Same as B13 l tion Interspace thru psig thru integrity i Pressure PSH-11188 ZA-9328 of secondary
( (Alarm Only) penetration
! closure l __- _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _
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O POST ACCIDENT MONITORING INSTRUMENTATION .
INSTRUMENT CTL ROOM VARIABLE CAT NO. RANGE DISPLAY E0F/T5C (NOTE 2) (NOTE 3) (NOTE 4) (NOTE 5) (NOTE 6) PURPOSE COMMENTS B25. Steam Generator 3 PSH-II219 0-1500 XA-9323 YES Indicate Same as B14 Penetration Inter- thru psig XA-9324 integrity space Pressure PSH-11224 (Alarm Only) of outer Switches penetration B26. Core Outlet 3 lE-11101-2 100-2300*F XI-9000 YES Verify temp- Same as B4 Temperature thru erature is TE-11137-2 within design limits (SPDS Variable) i l
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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 are (1) fuel cladding, (2) primary coolant pressure boundary, and (3) containment. (NOTE 1)
Fuel Particle Coating Integrity l
C1. PCRV Pressure 1 PE-1108 0 - 1"c PI-1108 YES Indicate Same as Al l PE-1109 ps.a PI-1109 potential l PE-1110 PI-1110 for fuel damage i f adequate flow)
! C2. Reactor Coolant 2 RT-9301 30-2x107 RR-93256 YES 4dicate circ-System Activity CPM e 'ating activity
.iPDS Variable) l C3. Helium Circulator 3 SE-2105-1 0-12,000 SI-2109 Indicate Same as B8 Speed SE-2106-1 RPM SI-2110 potential for SE-2111-1 SI-2115 fuel damage SE-2112-1 SI-2116 (adequate flow) l C3a. Steam Generator EES 1 TE-22121 0-1200 F TI-22121 YES Indicate proper l Outlet (Main Steam) TE-22122 TI-22122 operation (SPDS Temperature Variable) l C3b. Steam Generator EES 1 PT-22129-1 0-3000 PR-22129 YES Indicate existence l Outlet Pressure PT-22130-1 psig PR-22130 of steam at outlet (Main Steam) (SPDS Variable)
C3c. Steam Generator EES 3 FT-2205 0-1.250 FR-2205 YES Indicate adequate Same as B8.c Inlet (Feedwater) FT-2206 M-lb/hr FR-2206 flow of water for Flow heat removal (SPDS l variable) l C4. Core Outlet 3 TE-11101-2 100-2300*F XI-9000 YES Indicate Same as B4 Temperature thru potential for TE-11137-2 fuel damage (SPDS Variable) l C5. Helium Circulator 3 TE-1171 100-1000 F TI-1187 YES Indicate Same as B6 Inlet Temperature thru potential for TE-1178 fuel damage (SPDS Variable)
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INSTRUMENT CTL ROOM VARIABLE CAT NO. RANGE DISPLAY E0F/TSC (NOTE 2) (NOTE 3) (NOTE 4) (NOTE 5) (NOTE 6) PURPOSE COMMENTS C6. Maximum Region Outlet 3 Computer N/A X1-9000 YES Indicate Same as B5 Temperature Mismatch Calc potential for fuel damage C6a. Analysis of Primary 3 N/A N/A N/A NO Provide estimate Grab sample Coolant of fuel damage via HV-93486 (Gamma Spectrum)
Reactor Coolant System Pressure Boundary (liner & primary closures)
C7. PCRV Pressure 1 PE-1108 0-1000 PI-1108 YES Indicate Same as Al PE-1109 psia PI-1109 potential for PE-1110 PI-1110 rupture of boundary l
C8. Penetration Inter- 3 FE-11263 0-4.3 acfm FI-11263 YES Indicate breach Same as B10 space Flow of inner pene-tration
! 09. Circulator Seal 3 ZS-21191-2,-4 Set or not ZI-21191-2,-4 YES Indicate bound- Same as B11 Status ZS-21192-2,-4 Set ZI-21192-2,-4 ary status ZS-21193-2,-4 ZI-21193-2,-4 around circu-( ZS-21194-2,-4 ZI-21194-2,-4 lator shaft I when it is stopped C10. Reactor Building 3 RT-7324-1&2 30-2x10 RR-93539 YES Indicate breach Same as BIS Ventilation Exhaust 6 CPM of liner or Stack System Radiation RT-73437-1&2 10-10 CPM RR-73437 primary closures C11. Steam Jet-Air Ejector 3 RT-31193 30-2x10 RR-93538 YES Indicate breach Radiation CPM of steam gener-ator tube
Paga 11 cf 21 .
o POST ACCIDENT MONITORING INSTRUMENTATION ,
INSTRUMENT CTL ROOM YARIABLE CAT NO. RANGE DISPLAY E0F/TSC (NOTE 2) (NOTE 3) (NOTE 4) (NOTE 5) (NOTE 6) PURPOSE COMMENTS ,
C12. Hot Reheat Steam 3 RT-93250-10 0.1-10,000 RI-93250-10 YES Indicate breach Same as B12 Radiation RT-93251-10 mr/hr RI-93251-10 of reheat sec-RT-93252-10 RI-93252-10 tion of steam RT-93250-11 RI-93250-11 generator RT-93251-11 RI-93251-11 RT-93252-11 RI-93252-11 C13. PCRV Safety Valve 3 RT-93252-12 0.1-10,000 RR-93252-12 YES Indicate status Same as B16 Discharge Radiation mr/hr of safety valve Monitor Reactor Containment Pressure Boundary (PCRV concrete & secondary closure)
C14. PCRV Cooling Water 3 TE-4637-1 50-150*F TR-4637 YES Indicate the Same as B17 Inlet Terperature TE-4638-1 TR-4638 potential for TE-46209 TI-46209 failure of the TE-46210 TI-46210 secondary boundary C15. PCRV Cooling Water 3 See Comment 0-1800 F XI-9000 YES Indicate the Same as B18 Outlet Temperature potential for failure of the secondary boundary C16. PCRV Pressure 1 PE-1108 0-1000 PI-1108 YES Indicate the Same as Al PE-1109 psia PI-1109 potential for PE-1;10 PI-1110 failure of the l secondary I bcundary l C17. PCRV Rupture Disk 3 IS-1197-1 Open/Close ZI-1197-1 NO Indicate the Same as B23 l Isolation Valve 25-1197-2 ZI-1197-2 status of l Position secondary l boundary valves
Pag 212 cf- 21 .
l c POST ACCIDENT MONITORING INSTRUMENTATION ,-.
INSTRUMENT CTL ROOM l VARIABLE CAT h0. RANGE DISPLAY E0F/TSC l (NOTE 2) (NOTE 3) (NOTE 4) (NOTE 5) (NOTE 6) PURPOSE COMMENTS i
l C18. Reactor Building 3 RT-7324-1,-2 30-2x 10 7 RR-93539 YES Indicate a Same as BIS Exhaust Stack CPM breach of Ventilation System PT-73437-1,-210-Id5 CPM RR-73437 secondary Radiation Monitor closure Final Fission Product Cleanup System (Reactor Building) i C19. Penetration Inter- 3 ZS-1128 Open/Close ZS-1128 NO Indicate Same as B21 l space Flow Isolation failure of l Valve Position outer pene-Indication tration C20. Louver Position via 2 PS-7377-1 Closed or Alarm Only NO Indicate Status Pressure Indication thru Not Closed of louvers PS-7377-20 C21. Reactor Building 2 PDT-73335 0-1.5 psid PDR-73335 NO Indicate Pressure potential for louvers opening C22. Deleted
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o POST ACCIDENT MONIMRING INSTRUMENTATION
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TYPE D: (NOTE 1) Those variables that provide information to indicate the operation of individual safety. '
systems and other systems important to safety. These-variables are to help the operator make appropriate decisions in esing the individual systems important to safety in mitigating the ,
consequences of an accident. (NOTE 1)
INSTRUMENT CTL ROOM YARIABLE CAT NO. RANGE DISPLAY EOF /TSC (h0TE 2) (NOTE 3) (NOTE 4) (NOTE 5) (NOTE 6) PURPOSE COMENTS Primary Heat Ranoval Auxiliaefes
- 01. Helina Circulator 3 SE-2105-1 0-12,000 SI-2109 YES Indicate primary Same as B8' Speed SE-2106-1 RPM SI-2110 coolant being .i SE-2111-1 SI-2115 circulated ~
SE-2112-1 SI-2116 -
D2. Helium Circulator 3 ?T-21243 0-3,200 PI-21243 NO Indicate One per Loop" Water Turbine Drive PT-21244 psig PI-21244 operation of Header Pressure booster pump .!
I and ability to drive circ-ulator pelton wheel l D3. Turbine Water Drain 2 LT-21129 0-72" LI-21129 NO Indicate proper
' Tank L? vel H2O operation and-ensure pelton wheel cavity does not become packed D4. Bearing Water Surge 2 PDT-2147 +50 to -50 PDI-2147 YES Indicate proper One per Loop:
Tank to PCRV PDT-2148 psid PDI-2148 operation and Differential Pressure proper pressure
! of cover gas D5. Bearing Water Surge 2 LT-21135 0-48" LI-21135 YES Indicate adequate One per Loop-Tank Level LT-21136 H2C LI-21136 supply for proper operation
.of bearing water pumps l
i
. --,---.....,m..--- , , - , , - _ _ . . - - _ - , - - . , - - - - - - - - - _ _ --
. ~ _ - - - _.. . .. _. _ _ - -
Pag: 14 cf 21 .
O POST ACCIDENT MONITORING INSTRUMENTATION ,
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INSTRUMENT CTL ROOM VARIABLE CAT NO. RANGE DISPLAY EOF /TSC (NOTE 2) (NOTE 3) (NOTE 4) (NOTE 5) (NOTE 6) PURPOSE COMMENTS s
D6. Searing Water Flow 2 FT-2183 0-200 gpm FI-2183 YES Indicate adequate One per FT-2185 FI-2185 supply of circulator FT-2184 F1-2184 bearing water FT-2186 FI-2186 D7. Deleted
- 08. Storage Basin Level 2 LT-4iO2-1 0-100 LI-4102-3 NO Indicate adequate Million water supply for Gals circulator drive and heat removal from core Secondary Heat Removal (SPDS CSF)
- 09. Steam Generator EES 2 FT-2205 0-1.250 FR-2205 YES Indicate adequate Same as B.8c Inlet (Feedwater) FT-2206 M-lb/hr FR-2206 flow of water Flow for heat removal (SPDS Variable)
D10. D leted 011. Steam Generator EES 3 TE-2205 0-500'F TI-2205 YES Indicate proper One per Loop Inlet (Feedwater) TE-2206 TI-2206 operation (SPDS)
Temperature Variable) 012. Steam Generator EES 2 TE-22121 0-1200*F TI-22121 YES Indicate proper Category 1 for Outlet (Main Steam) TE-22122 TI-22122 operation (SPDS variables B8a Terperature Following Variable) and C3a DBA1 or MCA D13. Deleted l
D14. Deleted
i Pag? 15 cf 21 .
o P0iT ACCIDENT MONITukiNG INSTRUMENTATION ,
INSTRL%Ei4T CTL ROOM VARIABLE CAT NO. RANGE DISPLAY EOF /TSC (NOTE 2) (NOTE 3) (NOTE 4) (f!0TE 5) (NOTE 6) PURPOSE COMMENTS l D15. Steam Generator EES 2 PT-22129-1 0-3000 PR-22129 YES Indicate exist- Category 1 for Outlet (Main Steam) PT-22130-1 psig PR-22130 ence of steam variables 88b Pressure Following at outlet (SPDS and C4a DBA1 or MCA Variable)
D16. Deleted D17. Storage Basin Level 2 LT-4102-1 0-100 LI-4102-3 NO Indicate adequate Same as D8 Million supply of water Gals for steam generator Reserve Shutdown System D18. System Status-Bottle 3 PT-2409 0-1500 PI-2409 YES Indicate adequate Same as B3 Pressure psia pressure for reserve shutdown system actuation D18a. Neutron Flux -7 2 hE-1133-1 10 to NI-1133-1 YES Indicate successful Same as 81 NE-1134-1 10+3% NI-1134-1 actuation of reserve NE-1135-1 Full Power NI-1135-1 shutdown system NE-1131 1 to 3X10A NE-1131-1 NE-1132 counts per NE-1132-1 second Re ctor Plant Cooling System D19. PCRV Subheader Flows 2 See Comment 14-250 XI-9001 NO Indicate proper Total of 36 gom distribution of flow trans-flow mitters input to scanner for indica-tors D20. PCRV Cooling Water 3 See Comment 0-1800 F XI-9000 NO Indicate proper One TE for Outlet Temperature operation each of 535 channels input to scanner for I indication.
Same as 018.
w-
Page 16 cf 21 .
POST ACCIDENT HONITORING INSTRUMENTATION ,
INSTRUMENT CTL ROOM VARIABLE CAT NO. RANGE DISPLAY EOF /TSC (NOTE 2) (NOTE 3) (NOTE 4) (NOTE 5) (NOTE 6) PURPOSE COMMEETS D21. PCRY Botton Penetra- 2 TE-4637-1 50-150*F TR-4637 YES Indicate proper One per Loop tions, Bottom Head, 1E-4638-1 TR-4638 operation Barrel and Top Head, Circuit Inlet Header Tenperature D22. PCRV Top Penetrations 3 TE-46209 50-150*F TI-46209 NO Indicate proper One per Loop Circuit Inlet Header TE-46210 TI-46210 operation Temperature D23. Purification Cooling 2 TE-2321-1 0-800"F TR-2321 NO Indicate proper For both Loops Water Heat Exchanger TE-2321-2 (Multipoint) operation of Outlet Temperature system Helium Purification System D24. Helium Purification 3 TE-2321-5 0-8G0*F TR-2321 NO Indicate proper For both loops High Temperature TE-2321-6 (Multipoint) operation Absorber Outlet Terperature D25. Helium Purification 3 TE-2319 0-200 F TI-2319 NO Indicate proper For both Loops Cooler Outlet TE-2320 TI-2320 operation Temperature D26. Helium Purification 2 TE-23105 0-700*F TI-23105 NO Indicate proper For both Loops Dryer Outlet TE-23106 TI-23106 operation Temperature D27. Helium Purification 2 TE-2322-3 0-800*F TR-2322 F0 Indicate proper For both Loops Low Temperature TE-2322-4 (Multipoint) operation Absorber Outlet l
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POST ACCIDENT MONITORING INSTRUMENTATION .
INSTRUMENT CTL ROOM VARIABLE CAT NO. RANGE DISPLAY EOF /TSC (NOTE 2) (NOTE 3) (NOTE 4) (NOTE 5) (NOTE 6) PURPOSE COMMENTS Service Water System D28. Service Water Pump 2 LT-4218 -10 to +4 LIC-4218-1 NO Indicate adequate Pit Level inches water supply for service water system D29. Service Water Pump 2 PT-4229 0-50 psis PI-4229 YES Indicate Header Discharge operation of Pressure pump D30. Storage Tank Level 2 LT-2519-1 200-1200 LI-2519 YES Indicate adequate gallons supply of liquid N2 for proper operation of low temperature absorber Ventilation System D31. Damper Position for 2 See Comments Open/Close See Comments NO Indicate status A total of 13 Control Room of dampers limit switches Emergency Air Flow and 13 indicating lights D32. Reactor Building Vent 2 FT-7320 0-60,000 FT-7320 NO Indicate exhaust Exhaust Flow CFM flow l
Page 18 cf 21. .
POST ACCIDENT MONITORING INSTRUMENTATION ,
l INSTRUMENT CTL R00M l VARIABLE CAT NO. RANGE DISPLAY EOF /TSC l
(NOTE 2) (NOTE 3) (NOTE 4) (NOTE 5) (NOTE 6) PURPOSE COMMENTS l
Power Supplies D33. Essential 480V Bus 2 ES-9273, 0-600 EI-9273, NO Indicate system Voltage ES-9274 Volts AC EI-9274, status ES-9275 EI-9275 D34. Essential 480V Bus 2 YES 0-500 II-9244 YES Indicate system l
Current (N0 Nutr.ber) Amps AC II-9248 status
! D35. Essential 125V Bus 2 LI-92220 0-150 El-92220 NO Indicate system Voltage EI-92221 Volts EI-92221 status l D36. Instrument Air 2 PT-8212 0-1?.5 PI-8212 YES Indicate system Receiver Pressure PT-8254 psig PI-8254 s tatus D37. Hydraulic Gil Loop 2 FT-91141 2000-3500 PI-91141 NO Indicate system Pressure VI-91142 psig PI-91142 status l
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P:g: 19 of 21 .
POST ACCIDENT MONITORING INSTRUMENTATION ,
TYPE E: (NOTE 1) Those variables to be mcnitored as required for use in determining the magnitude of the '
release of radioactive materials and continually assessing such releases.
INSTRt' MENT CTL ROOM VARIABLE CAT NO. RANGE DISPLAY EOF /TSC (NOTE 2) (NOTE 3) (NOTE 4) (NOTE 5) (NOTE 6) PURPOSE COMMENTS Airborne Radioactive Material Released From Plant El. Reactor Building vent 2 FT-7320 0-60,000 FI-7320 N0 Verification Same as D32 Exhaust Flow CFM of exhaust flow E2. Reactor Building Vent 3 RT-7324-1,-2 30-2X107 RR-93539 YES Detection of Same as BIS Exhaust Radiation CPM significant Monitor RT-73437- 1,-2 10-106 CPM RR-73437 releases E3. PCRV Safety Valve 2 RT-93252-12 .1-10,000 RR-93252-12 YES Detection of Same as B16 Discharge Radiation mr/r.r significant releases E4. PCRV Pressure 1 PE-1108 0-1000 PI-1108 YES Detection of Same as Al PE-1109 psia PI-1109 significant PE-1110 PI-1110 releases E.4a.1 RX Plant Exhaust 3 RT-93252-1 .1R to RIS-93251-1 N0 Verify signifi- High Range Filter Rm - Tb IE+4R cant releases Monitor and local Turbine Bldg.
magnitudes E.4a.2 South Stairwell-Rx 3 RT-93252-2 .1 mR to RIS-93252-2 Reactor Bldg.
1E+4mR 1
E.4a.3 Mn Ctl Pm-Tb 3 RT-93250-5 1 mR to RIS-93250-5 Turbine Bldg.
IE+4mR E.4a.4 Gas blaste Filters 3 RT-93251-5 .1 mR to RIS-93251-5 Reactor Bldg.
1E+4mR E.4a.5 South Stairvell-Rx 3 RT-93252-6 .1 mR co RIS-93252-6 Reactor Bldg.
IE+6nR
Pag] 20 cf 21 . ,I POST ACCIDENT MONITORING INSTRUMENTATION .
INSTRUMENT CTL ROOM VARIABLE CAT NO. RANGE DISPLAY EOF /TSC (NOTE 2) (NOTE 3) (NOTE 4) (NOTE 5) (NOTE 6) PURPOSE COMMENTS .
E.4a.6 Valve Oper Stat. - 3 RT-93251-7 .1 mR to RIS-93251-7 Reactor Bldg.
West - Rx IE+4mR E.4a.7 Valve Oper Stat. - 3 RT-93252-7 .1 mR to RIS-93252-7 Reactor Bldg.
East - Rx IE+4mR E.4a.8 NE Walkway 9.x 3 RT-93 F e .1 mR to RIS-93250-8 Reactor Bldg.
1E+4mR E.4a.9 Buffer Hel Dryer 3 RT-93251-9 .1 mR to RIS-93251-9 Reactor Bldg.
Stairwe11 1E+4mR Loop 1 - Rx E.4a.10 Condensate Cemin.- 3 RT-93250-13 .1 mR to RIS-93250-13 Turbine Bldg.
Tb 1E+4mR E.4a.11 E. Wall Refueling 2 RT-93250-14 .1 mR to RIS-93250-14 High Range Floor - Rx IE+4R Monitor Rx Building Environs Radiation and Radioactivity E.5 Portable Radiation 3 R0-5 1mR-200R NO N0 Very signiificant Instrumentation / R0-7 200R- NO N0 releases and local Sensors SAM-II 20,000R N0 N0 magnitudes 1E-10 to SE-5 micro Ci/cc Iodine Meteorology E6. Wind Direction 9 58M 3 XT-93107 0-540 XR-93574-1 YES Release Assess-0 10M XT-93109 0-540 XR-93574-2 ment E7. Wind Speed 0 58M 3 XST-93106 0-100 MPH XR-93574-1 YES Release Assess-0 10M XST-93108 0-100 MPH XR-93574-2 ment
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P::ge 21 Sf 21 . -
's POST ACCIDENT P.ONITORING INSTRUMENTATION ,
~~
INSTRUMENT CTL ROOM VARIABLE CAT NO. RANGE DISPLAY E0F/TSC (NOTE 2) (NOTE 3) (NOTE 4) (NOTE 5) (NOTE 6) PURPOSE COMMENTS E8. Estimate of Atmo- 3 Release Assess-spheric Stability ment Temp. Differential TT-93110-2 -5'T to XR-93574-3 between 58M & IOM tS*F Accident Sampling Capability E9. Primary Ccolant 3 N/A ti/A N/A Release Assess- Grab Sample
-gross activity ment; verifi- via HV-93486
-gaar.a spectrum cation Same as C6a.
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