ML20148H840
| ML20148H840 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 03/14/1988 |
| From: | Warembourg D PUBLIC SERVICE CO. OF COLORADO |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| RTR-REGGD-01.097, RTR-REGGD-1.097 P-88088, NUDOCS 8803300093 | |
| Download: ML20148H840 (37) | |
Text
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2420 W. 26th Avenue, Suite 1000, Denver, Colorado 80211 March 14, 1988 Fort St. Vrain Unit No. 1 P-88088 U. S. Nuclear Regulatory Comission ATTN: Document Control Desk Washington, D.C. 20555 Docket No. 50-267
SUBJECT:
Emerget:cy Response Capabilities:
REFERENCES:
See Enclosure 1 Gentlemen:
The purpose of this letter is to identify several changes to Fort St.
Vrain's existing Post Accident Monitoring Instrumentation (PAMI) list, and to clari fy PSC's position regarding the qualification requirements for PAMI.
Post Accident Monitorina Instrumentation List The current PAMI list was submitted originally by Reference 1 and subsequently revised by Reference 2 based on coments contained in Reference 6. The current PAMI list was accepted by the NRC in Reference 3.
The proposed changes to the PAMI list are a result of the following:
This list was not finalized at the time of the submittal of Reference 2.
- 2) Changes in the safe shutdown cocling flow paths as described in Reference 4.
- 3) A more detailed review, by our staff, of the redundancy requirements for various RG 1.97 Rev. 2 categories.
A complete listing of the revisions to the FSV PAMI list, including a discussion on the basis for the revision, is included in Attachment 1. Also included for each revision is a discussion with reference to the Safety Evaluation Report documented in Reference 3.
U 99033%h [C j PDR 1 P
P-88088
, 3 Page 2 March 14, 1988 The composite FSV PAMI list, including the revisions discussed herein, is included as Attachment 2.
PAMI Qualification Criteria RG 1.97 Rev. 2 states that Category I and Category II instrumentation should be environmentally qualified in accordance with RG 1.89 and NUREG-0588.
However, these requirements are more stringent than those contained in the FSV Environmental Qualification Safety Evaluation Report (Reference 5) which states:
... equipment for Fort St. Vrain may be qualified to the criteria specified in either the 00R Guidelines or NUREG-0588, except for replacement equipment.
PSC intends to use the guidelines contained in Reference 5 when establishing the qualification criteria for RG 1.97 Revision 2 Category I and Category 11 instrumentation.
PSC would also like to note that the reference to RG 1.97 Revision 3 contained in the cover letter for the Safety Evaluation Report in Reference 3 should be Revision 2. PSC committed to Revision 2 in Reference 1 and it was Revision 2 that was the basis for the evaluation in the Technical Evaluation Report in Reference 3.
If you have any questions on this matter, please contact Mr. M. H. Holmes at (303) 480-6960.
Very truly yours, b.JT /&mfmn -
D.W. Warembourg, Mar ger Nuclear Engineering Division DWW/SM:pa Attachments cc: Regional Administrator, Region IV Attention: Mr. T.F. Westerman, Chief Projects Section B Mr. R.E. Farrell Senior Resident Inspector Fort St. Vrain
Enclosure 1 to P-88088
REFERENCES:
- 1) PSC Letter, Warembourg to Johnson, dated 02/28/85 (P-85065)
- 2) PSC Letter, Warembourg to Berkow, dated 07/14/86 (P-86460)
- 3) NRC Letter, Heitner to Williams, dated 04/22/87 (G-87143)
- 4) PSC Letter, Williams to Berkow, dated 01/15/87 (P-87002)
- 5) NRC Letter, Heitner to Williams, dated 09/10/86 (G-86494)
- 6) NRC Letter, Heitt.er to Walker, dated 03/12/86 (G-86134)
Attachment 1 to P-88088 Changes to FSV PAMI List
- 1) VARIABLE: B1 (Neutron Flux)
REVISION: Upper range should be 10+3 full power not 10-3 as presently shown.
BASIS: This was a typographical error.
SER EVALUATION: This was not addressed in the SER.
- 2) VARIABLE: B2a (Control Rod Position)
REVISION: Delete ZSL-1232-1 through ZSL-1232-37.
BASIS: These items perform the same function as ZSL 1211-1 through ZLS-1211-37, which are also included for variable B2a. This is a Category 3 variable and does not require redundancy.
SER EVALUATION: This was not addressed in the SER.
- 3) VARIABLE: B3 (Reserve Shutdown Bottle Pressure)
REVISION: Change from Category 2 to Category 3 variable.
BASIS: variable This to theinstrumentation would serve key variable neutron as a backup (variable flux indication B1, Category 1) for reactivity control. Similar to the RG 1.97 requirements for other similar backup variables (control rod position, RCS soluble boron concentration), this variable is required only to be a Category 3 variable.
! SER EVALUATION: This variable was evaluated in Peference 6 as a Category 3, backup variable to neutron flux, and found to be acceptable.
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Attachment 1 to P-88088
- 4) VARIABLE: B4 (Core Outlet Temperature)
REVISION: Change from Category 2 to Category 3 variable. .
Delete TE-11101-2 through -4 through TE-11137-2 ;
through -4.
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BASIS: Current emergency procedures do not utilize core outlet temperature. es an indication of core cooling, and thus containment integrity and fuel particle coating integrity.- As indicated for variable 88a, core cooling is assured by maintaining secondary cooling conditions demonstrated adequate by analysis.
However, core outlet temperature will be retained as a Category 3 variable, to provide backup information.
This is consistent with the Category 3 classification of variable B5 (maximum iwgion outlet temperature mismatch).
The deleted thermocouples perform the same function as TE-11101-1 through TE-11137-1, also listed for i variable 84. Only Category 1 variables require redundancy.
SER EVALUATION: This variable was evaluated in Reference 6 as a Category 3, backup variable to PCRV pressure, and ,
found to be acceptable. ,
- 5) VARIABLE: B6 (Helium Circulator Inlet Temperature)
REVISION: Change from Category 2 to Category 3 variable.
P BASIS: Similar to the revision basis for variable B4, helium ,
circulator inlet temperature should be a Category 3 variable, as a backup variable for indicating adequate core cooling. Key variables for core cooling are for secondary coolant conditions.
SER EVALUATION: Same as variable B4, f
' Attachment 1 :
to P-88088 l i
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- 6) VARIABLE: 88 (Helium Circulator Speed) :
REVISION: Change monitoring instrumentation from SE-2109-1, l SE-2110-1, SE-2115-1, and SE-2116-1 to SE-2105-1, SE-2106-1, SE-2111-1, and SE-2112-1. Change Category !
from Category- 1 to Category 3. :
BASIS: The function of these sensors were recently !
transposed by PSC change notice CH-2253A. The !
category is being changed to reflect use of .
circulator speed as a backup for monitoring core cooling. New variables B8a and B8b and existing .
variable B7 are the key variables used to monitor j core cooling.
SER EVALUATION: This was evaluated in the SER as a Category 1 variable.
- 7) VARIABLE: 88a (Steam Generator EES Outlet Temperature) ;
REVISION: Add this variable. !
BASIS: Current emergency procedures utilize EES temperature and pressure as the primary means of monitoring core ,
cooling. By maintaining secondary cooling water '
outlet pressures and temperatures at conditions which have been demonstrated by analysis to provide adequate decay heat removal during shutdown cooling, adequate core cooling and, thus, fuel particle >
integrity will be assured, instrumentation currently listed is for shutdown following DBA2 and MCA. The instrumentation used to monitor conditions following l HELB's is presently monitored by local indication.
- PSC intends to have control room indication in place by the end of the 5th refueling outage.
SER EVALUATION: This was not evaluated in the SER. -
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- Attachment I to P-88088
- 8) VARIABLE: 68b (Steam Generator EES Outlet Pressure)
REVISION: Add this variable.
BASIS: Same as variable B8a.
SER EVALUATION: Same as variable B8a.
- 9) VARIABLE: 88c (Steam Generator EES Inlet (Feedwater) Flow)
REVISION: Add this variable.
BASIS: Current emergency procedures utilize EES temperature and pressure as the primary means of monitoring core ,
cooling and secondary heat removal (refer to variable B8a). Cooling water ficw rate, n der.crmined by analysis, is specified in the emergency procedures for operator information. Censistent with these procedures, Steam Generator EES Inlet (Feedwater)
Flow has been added as a backup variable.
SER EVALUATION: Same as variable B8a.
- 10) VARIABLE: B18 (PCRV Cooling Water Outlet Temperature)
REVISION: Control Room display should be XI-9000 net TR-4637 and TR-4638 as previously shown. Monitoring instrumentation should be various TEs used for PCRV circuit temperature measurement, not TE-4637-3 and TE-4638-3.
BASIS: Use of TE-4637-3, TR-4637, TE-4638-3 rnd TR-4638 would require replacement of the existing control room instrumentation to accorrmodate an expanded range. An investigation has revealed that expanding the range will result in a reduction of the instrument resolution and may have an adverse effect on plant operation.
Attachment 1 to P-88088 The indication provided by XI-9000 and the associated 535 TEs already provide the range required to monitor this variable. It diso has an advalitage in that it monitors individual tubes rather than the average temperature monitored by TR-4637 and TR-4638.
XI-9000 and associated TE's are also included as variable D20.
SER EVALUATION: This was not addressed in the SER.
- 11) VARIABLE: 826 (Core Outlet Temperature)
CHANGE: Same as variable B4 BASIS: Same as variable 84 SER EVALUATION: Same as variable B4.
- 12) VARIABLE: C3 (Helium Circulator Speed)
REVISION: Same as B8 BASIS: Same as BB SER EVALUATION: This was evaluated in the SER as a Category 1 variable.
- 13) VARIABLE: C3a (Steam Generator EES Outlet Temperature)
REVISION: Same as B8a BASIS: Same as B8a SER EVALUATION: This was not evaluated in the SER.
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Attachment I to P-88088
- 14) VARIABLE: C3b (Steam Generator EES Outlet Pressure)
REVISION: Same as B8b BASIS: Same as 88b SER EVALUATION: This was not evaluated in the SER,
- 15) VARIABLE: C3c (Steam Generator EES Inlet (Feedwater) Flow)
REVISION: Add this variable.
BASIS: Same as B8c.
SER EVALUATION: This was not evaluated in the SER.
- 16) VARIABLE: C4 (Core Outlet Temperature)
REVISION: Same as variable B4 BASIS: Same as variable B4 SER EVALUATION: Same as variable B4.
- 17) VARIABLE: CS (Helium Circulator Inlet Temperature)
REVISION: Same as variable 86.
BASIS: Same as variable B6.
SER EVALUATION: Same as variable B6,
, e- , , . - - -- . , - , --- - - - - ne, ,
Attachment 1 to P-88088
- 18) VARIABLE: C6a (Analysis of Primary Coolant)
REVISION: Added variable BASIS: This is consistent with RG 1.97 which contains an analysis variable for fuel cladding.
SER EVALUATION: This was not addressed in the SER.
- 19) VARIABLE: C10 ' Reactor Building Ventilation Exhaust Stack Systen. Radiation)
REVISION: RT-7325-1&2 should be RT-7324-1&2 BASIS: 1his was a typographical error. This makes tag numbers consistent with variables B15, C18 and E2.
SER EVALUATION: This was not addressed in the SER.
- 20) VARIABLE: CIS (PCRV Cooling Water Outlet Temperature)
REVISION: Same as B18 BASIS: Same as B18 SER EVALUATION: Same as B18,
- 21) VARIABLE: C20 (Louver Position Via Pressure Indication)
REVISION: Delete PS-7382-1 through 20 BASIS: These switches perform the same function as PS-7377-1
- through 20, also listed for C20. This is a Category 2 variable and does not require redundancy.
SER EVALUATION: This was not addressed in the SER.
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Attachment 1 to P-88088
- 22) VARIABLE: C21 (Reactor Building Pressure)
Delete PDT-73440 through PDT-73452 REVISION:
BASIS: These transmitters perfonn the same function as PDT-73335, also listed for C21. This is a Category 2 variable and does not require redundancy.
SER EVALUATION: This was not addressed in the SER.
- 23) VARIABLE: C22 (Refueling Floor to Ambient Differential Pressure)
REVISION: Delete this variable BASIS: These transmitters perform the same function as PDT-70335, listed as variable C21.
SER EVALUATION: This was not addressed in the SER.
- 24) VARIABLE: D1 (Helium Circulator Speed)
REVISION: Same as variable B8 BASIS: Same as variable B8 SER EVALUATION: Same as variable B8.
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Attachment 1-to P-88088
- 25) VARIABLE: 07 (Fire Water Pump Discharge Pressure)
REVISION: Delete this variable.
BASIS: Current emergency procedures do not utilize fire water pump discharge pressure as either a key or backup indication of fire water flow, fire water pump performance or ' recondary heat removal. This is indicated by other variables: secondary cooling water outlet pressure and temperature, circulator speed and reactor pressure.
SER EVALVATION: This was not addressed in the SER.
- 26) VARIABLE: 08 (Storage Basin Level)
REVISION: Delete LT-4102-2 BASIS: This transmitter performs the same function as LT-4102-1. This is a Category 2 variable and does not require redundancy.
SER EVALUATION: This was not aodressed in the SER.
- 27) VARIABLE: D10 (Emerg ncy Condensate to Steam Generator Reheater Inlet Flow REVISION: Delete this variaole BASIS: The reheat section of the steam generator is no longer considered a safe shutdown flow path (Reference 4). Thus, monitoring reheater conditions is not required for safe shutdown cooling.
SER EVALUATION: This was not evaluated in the SER.
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Attachment 1 to P-88088
- 28) VARIABLE: D12 (Steam Generator EES Outlet Temperature)
REVISION: Change accidents this variable monitors to DBA2 and MCA only.
BASIS: As discussed in Reference 4, the flow paths for the EES cooldown have changed. TE-22121 and TE-22122 are no longer used to monitor main steam (EES) temperature following HELB's. The existing safe shutdown flow path temperature for these accidents is presently monitored by local indication. PSC plans to have control room indication in place by the end of the 5th refueling outage.
SER EVALUATION: This was not evaluated in the SER.
- 29) VARIABLE: D13 (Steam Generator Reheater Inlet Temperature)
REVISION: Delete this variable BASIS: Same as variable D10 SER EVALUATION: This was not evaluated in the SER.
- 30) VARIABLE: D14 (Steam Generator Module Reheater Outlet Tempera ture)
REVISION: Delete this variable BASIS: Same as variable D10.
SER EVALUATION: This was not evaluated in the SER.
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Attachment 1 to P-88088
- 31) VARIABLE: D15 (Steam Generator EES Outlet Pressure)
REVISION: Char.ge accidents this variable monitors to DBA2 and MCA only BASIS: As discussed in Reference 4, the flow paths for the EES cooldown have changed. PT-22129-1 and PT-22130-1 are no longer used to monitor main steam (EES) pressure following HELB's. The existing safe shutdown flow path pressure for these accidents is presently monitored by local indication. PSC plans to have control room indication in place by the end of the 5th refueling outage.
SER EVALUATION: This was not evaluated in the SER.
- 32) VARIABLE: 016 (Steam Generator HRH Outlet Pressure)
REVISION: Delete this variable BASIS: Same as variucle D10.
SER EVALUATION: This was not evaluated in the SER.
- 33) VARIABLE: D17 (Storage Basin Level)
REVISION: Same as variable 08.
j BASIS: Same as variable D8.
i SER l EVALUATION: Same as variable D8.
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't Attachment 1 to P-88088
- 34) VARIABLE: 018 (Reserve Shutdown Bottle Pressure)
REVISION: Same as variable B3.
BASIS: Same as variable B3, SER .
EVALUATION: This was previously' upgraded to Category 2 to serve as the key variable for the reserve shutdown system.
As discussed previously for variable B3,.this should be a backup to neutron flux for reactivity control.
Variable B8a is added as the key variable, allowing reduction of variable B18 to Category 3. This meets the intent of RG 1.97, Revision 2.
- 35) VARIABLE: D18a (Neutron Flux)
REVISION: Add this variable BASIS: This is added as a key variable to indicate actuation of the reserve shutdown system.
SER EVALUATION: Same as D18.
- 36) VARIABLE: D35 (Essential 125V Bus Voltage)
REVISION: Change tag number of sensing instrument.
BASIS: The sensing instrument _ is the same as the control room display. There is not a separate device for transmitting the voltage to the display.
SER EVALUATION: This was not addressed in the SER.
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I ATTACHMENT 2 TO P-88088 PAMI LIST l
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Page 1 of.21:
POST ACCIDENT MONITORING INSTRUMENTATION NOTES TO TABLE --
NOTE 1 - VARIABLE types and definition are taken straight out of Regulatory Guide 1.97. The annotated 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 complies with existing Quality Assurance criteria and which is powered from a Class 1E-power supply.
CATEGORY 2 - This denotes a single-channel, fully environmentally, qualified inst'ument r channel powered from a highly reliable power source with indication available in the control room.
CATEGORY 3 - This denotes a high-quality, commercial-grade instrument channel powered from offsite power.
NOTE 3 - INSTRUMENT N0. 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.
WOTE 6 - E0F/TSC indicates that this variable is also available in the Technical Support Center and will be available in the Forward Command Post.
NOTE 7 - SPDS CSF means 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 D31).
Page 2 of 21 ..
POST ACCIDENT MONITORING INSTRUMENTATION.
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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. Prima ry 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 E0F/TSC (NOTE 2) (NOTE 3) (NOTE 4) (NOTE 5) (NOTE 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 1 when depres-surization should d
terminate.
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Page.3 of 21' .
POST ACCIDENT MONITORING INSTRUMENTATION e
j TYPE B: (NOTE 1) Those variables that provide information to indicate whether plant safety functions are'being i 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 qualification requirements. Key variables are indicated by design and qualification Category 1. (NOTE 1).
INSTRUMENT CTL ROOM i VARIABLE CAT N0. RANGE DISPLAY E0F/TSC j (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 i
NE-1135-1 Full Power NI-1135-1 of the core (SPDS Variable)'
1 NE-1133-1 0 to 150% NI-1133-3
- NE-1134-1 Full Power NI-1134-3
] NE-1135-1 NI-1135-3
- NE-1136-1 NI-1136
- NE-1137-1 NI-1137 j NE-1138-1 NI-1138 i
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Page 4 of 21~. ..
POST ACCIDENT MONITORING INSTRUMENTATION INSTRUMENT CTL ROOM VARIABLE CAT NO. RANGE DISPLAY E0F/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 NO 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 thru 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-11101-1 100-2000 F XI-9000 YES Function de-thru tection (SPDS TE-11137-1 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 inlets.
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
Page 5~of-21 ,
POST ACCIDENT MONITORING INSTRUMENTATION INSTRUMENT CTL ROOM VARIABLE CAT N0. RANGE DISPLAY E0F/TSC (NOTE 2) (NOTE 3) (NOTE 4) (NOTE 5) (NOTE 6) PURPOSE C0!EENTS
- 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 cociant of 4 circ-
] SE-2111-1 SI-2115 flow (SPDS ulators
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SE-2112-1 SI-2116 Variable)
B8.a Steam Generator EES 1 TE-22121 0-1200 F TI-22121 YES Indicate proper 4 Outlet (Main Steam) TE-22122 TI-22122 operation (SPDS I Temperature Variable) i 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)
B8.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 A1
- PE-1109 psia PI-1109 is within design i PE-1110 PI-1110 1imits (SPDS j Variable)
B10. Penetration Inter- 3 FE-11263 0-4.3 ACFM FI-11263 YES Indication of space Flow primary closure
, integrity
) B11. 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 ;
4 ZS-21193-2,-4 set ZI-21193-2,-4 when circulator j ZS-21194-2,-4 ZI-21194-2,-4 is stopped I
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Page 6 of 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 B12. Hot Reheat Sta:s 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 i
RT-93252-10 RI-93252-10 portion of RT-93250-11 RI-93250-11 steam genera-RT-93251-11 RI-93251-11 tor 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 j penetrations l
B14. Steam Generator 3 PSH-11219 0-1500 XA-9323 YES Indicate breach Three per Penetration thru psig XA-9324 of piping with - Loop
, Interspace PSH-11224 (Alarm Only) in interspace
] Switches (SPDS Variable)
B15. Reactor Building Vent 3 RT-7324-1,-2 30-2x107 RR-93539 YES Indicate breach i Exhaust Radiation CP of primary cool-Monitor RT-73437-1,-210-10pCPMRR-73437 any system bound-
- ary B16. PCRV Safety Valve 3 RT-93252-12 .1-10,000 RR-93252-12 YES Indicate status Discharge Radiation mr/hr of safety valve
- Monitor Reactor Containment Integrity (PCRV concrete and secondary closure) l B17. PCRV Cooling Water 3 TE-4637-1 50-150 F TR-4637 YES Indicate con- Two per Loop i
- Inlet Temperature TE-4638-1 TR-4638 crete being l l TE-46209 TI-46209 kept within TE-46210 TI-46210 design temp-erature limits
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POST ACCfDENT MONITORING INSTRUMENTATION 4
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 0-1800 F XI-9000 YES Indicate con- One TE for Outlet Temperature crete being each of 535 kept within channels input '
i design temp- to scanner i 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 ;
j kept within design temp- i 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 l PE-1110 PI-1110 design limits i
l B21. Penetration Inter- 3 ZS-1128 Open/Close ZI-1128 NO Indication of space Flow Isola- breach second-i tion Valve Status ary penetra- !
i Indication tion 4 B22. Penetration Inter- 3 FE-11263 0-4.3 acfm FI-11263 YES Indication of Same as B10 space Flow breach of secondary penetration
- closure i B23. PCRV Rupture Disk 3 ZS-1197-1 Open/Close ZI-1197-1 NO Indicate the One per
- Iso'ition Valve ZS-1197-2 ZI-1197-2 status of Isolation Pos'. cion secondary Valve boundary valves i ;
B24. Circulator Penetra- 3 PSH-11177 0-1500 XA-9325 YES- Indicate. Same as B13 tion Interspace thru psig thru integrity Pressure PSH-11188 ZA-9328 of secondary
- (Alarm Only) penetration closure
LPage'8 of 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 B25. Steam Generator 3 PSH-11219 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 TE-11101-1 100-2000 F XI-9000 YES Verify temp- Same as B4 Temperature thru erature is TE-11137-1 within. design limits-
Page 9-of.21 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 C1. PCRV Pressure 1 PE-1108 0-1000 PI-1108 YES Indicate Same as A1.
PE-1109 psia PI-1109 potential PE-1110 PI-1110 for fuel damage (adequate flow)
C2. Reactor Coolant 2 RT-9301 30-2x107 RR-93256 YES Indicate circ- .,
System Activity CPM ulating activity '
(SPDS Variable)
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)
C3a. Steam Generator EES 1 TE-22121 0-1200 F TI-22121 YES Indicate proper Outlet (Main Steam) TE-22122 TI-22122 operation (SPDS Temperature Variable)
C3b. Steam Generator EES 1 PT-22129-1 0-3000 PR-22129 YES Indicate existence 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 variable)
C4. Core Outlet 3 TE-11101-1 100-2000*F XI-9000 YES Indicate Same as B4 Temperature thru. potential for TE-11137-1 fuel damage 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
.Page 10 of.21 ..
POST ACCIDENT MONITORING INSTRUMENTATION -
INSTRUMENT CTL ROOM VARIABLE CAT NO. RANGE DISPLAY E0F/TSC '
j (NOTE 2) (NOTE 3) (NOTE 4) (NOTE 5) (NOTE 6) PURPOSE COMMENTS C6. Maximum Region Outlet 3 Computer N/A XI-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) 1
- Reactor Coolant System Pressure Boundary ,
I (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 i PE-1110 PI-1110 rupture of boundary 5
, C8. Penetration Inter- 3 FE-11263 0-4.3 acfm FI-11263 YES Indicate breach Same as BIO
- space Flow of inner pene-tration
- C9. 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 i ZS-21193-2,-4 ZI-21193-2,-4 around circu-l ZS-21194-2,-4 ZI-21194-2,-4 lator shaft j when it is stopped i C10. Reactor Building 3 RT-7324-1&2 30-2x107 RR-93539 YES Indicate breach Same as BIS Ventilation Exhaust CPM of liner or Stack System Radiation RT-73437-1&2 10-106 CPM RR-73437 primary closures C11. Stack Jet-Air Ejector 3 RT-31193 30-2x107 RR-93538 YES Indicate breach Radiation CFM of steam gener-ator tube t
, l l
Page 11 of 21 ,
POST ACCIDENT MONITORING INSTRUMENTATION INSTRUMENT CTL ROOM VARIABLE CAT N0. 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 Temperature 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-1110 PI-1110 failure of the secondary boundary C17. PCRV Rupture Disk 3 ZS-1197-1 Open/Close ZI-1197-1 NO Indicate the Same as B23 Isolation Valve ZS-1197-2 ZI-1197-2 status of Position secondary boundary valves
Page 12 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 COMMENTS C18. Reactor Building 3 RT-7324-1,-2 30-2x 107 RR-93539 YES Indicate a' Same as' BIS
-Exhaust Stack CPM breach of Ventilation System RT-73437-1,-2 10-106 CPM RR-73437 secondary Radiation Monitor ' closure Final Fission Product Cleanup System (Reactor Building)
C19. Penetration Inter- .3 ZS-1128 Open/Close ZS-1128 NO Indicate- Same.as B21 space Flow Isolation failure of 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
Page 13 of 21 ,
POST ACCIDENT MONITORING INSTRUMENTATION 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 using the individual systems important to safety in mitigating the .
consequences of an accident. (NOTE 1)
INSTRUMENT CTL ROOM VARIABLE CAT NO. RANGE DISPLAY E0F/TSC (NOTE 2) (NOTE 3) (NOTE 4) (NOTE 5) (NOTE 6) PURPOSE COMMENTS Primary Heat Removal Auxiliaries DI. Helium Circulator 3 SE-2105-1 0-12,000 SI-2109 YES Indicate primary Same as 88 Speed SE-2106-1 RPM SI-2110 coolant being SE-2111-1 SI-2115 circulated SE-2112-1 SI-2116 D2. Helium Circulator 3 PT-21243 0-3,200 PI-21243 NO Indicate One per Loop Water Turbine Drive PT-21244 psig PI-21244 operation of j Header Pressure booster pump and ability 3 to drive circ-
] ulator pelton 1 wheel J
i D3. Turbine Water Drain 2 LT-21129 0-72" LI-21129 NO Indicate proper
- Tank Level H2O operation and i 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 l Tank to PCRV PDT-2148 psid PDi-2148 operation and Differential Pressure proper pressure of cover gas DS. Bearing Water Surge 2 LT-21135 0-48" LI-21135 YES Indicate adequate One per Loop i Tank Level LT-21136 H2O LI-21136 supply for l proper operation j of bearing water pumps 4
Page 14 of 21 ,
POST ACCIDENT MONITORING INSTRUMENTATION w
INSTRUMENT CTL ROOM VARIABLE CAT NO. RANGE DISPLAY E0F/TSC
{ (NOTE 2) (NOTE 3) (NOTE 4) (NOTE 5) (NOTE 6) PURPOSE COMMENTS D6. Bearing Water Flow 2 FT-2183 0-200 gpm FI-2183 YES Indicate adequate One per j FT-2185 FI-2185 supply of circulator 1
FT-2184 FI-2184 bearing water l FT-2186 FI-2186
] D7. Deleted i 08. Storage Basin Level 2 LT-4102-1 0-100 LI-4102-3 NO Indicate adequate
! Million water supply for Gals circulator drive
! and heat removal 1
from core l
): Secondary Heat Removal (SPDS CSF) j' D9. 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) 4 D10. Deleted i
! D11. Steam Generator EES 3 TE-2205 0-500 F TI-2205 YES Indicate proper One per Loop
! Inlet (Feedwater) TE-2206 TI-2206 operation
! Temperature l D12. 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 l Temperature Following Variable) and C3a
- DBA1 or MCA l
l D13. Deleted i
j D14. Deleted J
i
Page 15 of 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 D15. Steam Generator EES 2 PT-22129-1 0-3000 PR-22129 YES Indicate exist- Category I for Outlet (Main Steam) PT-22130-1 psig PR-22130 ence of steam variables B8b 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 suppl" 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 2 NE-1133-1 10- to NI-1133-1 YES Indicate successful Same as B1 NE-1134-1 10+3% actuation of reserve HE-1135-1 Full Power shutdown system Reactor Plant Cooling System D19. PCRV Subheader Flows 2 See Comment 14-250 XI-9001 NO Indicate proper Total of 36 gpm 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 indication.
Same as B18.
Page 16 of 21 ,
POST ACCIDENT MONITORING INSTRUMENTATION _
INSTRUMENT CTL ROOM VARIABLE CAT N0. RANGE DISPLAY E0F/TSC (NOTE 2) (NOTE 3) (NOTE 4) (NOTE 5) (NOTE 6) PURPOSE COMMENTS D21. PCRV Bottom Penetra- 2 TE-4637-1 50-150 F TR-4637 YES Indicate proper One per Loop tions, Bottom Head, TE-4638-1 TR-4638 operation Barrel and Top Head, Circuit Inlet Header Temperature 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 0-800'F TR-2321 NO Indicate proper For both Loops High Temperature TE-2321-6 (Multipoint) operation Absorber Outlet Temperature D25. Helium Purification 3 TE-2319 0-20(P F TI-2319 NO Indicate proper For both Loops Cooler Outlet TE-2320 TI-2320 operation Tempera ture D26. Helium Purification 2 TE-23105 0-700 F TI-23105 NO Indicate proper For both Loops Dryer Outlet TE-23106 TI-23106 operation Tempera ture D27. Helium Purification 2 TE-2322-3 0-800 F TR-2322 NO Indicate proper For both Loops Low Temperature TE-2322-4 (Multipoint) operation Absorber Outlet
Page 17 of.21 ,
~
POST ACCIDENT MONITORING INSTRUMENTATION' - ~L:
$s
, INSTRUMENT CTL ROOM i
VARIABLE CAT N0. RANGE DISPLAY E0F/TSC . .
(NOTE 2) (NOTE 3) (NOTE 4) (NOTE 5) (NOTE 6) PURPOSE . COMMENTS Service Water System 4
D28. Service Water Pump 2 LT-4218 -10 to +4 LIC-4218-1 NO Indicate adequate i Pit Level inches water supply for l service water system i
- D29. Service Water Pump 2 PT-4229 0-50 psig PI-4229 YES Indicate
! Header Discharge operation of j Pressure pump i
D30. Storage Tank Level 2 LT-2519-1 200-1200 LI-2519 YES Indicate adequate j gallons supply of liquid j N2 for proper operation cf low temperature absorber
, Ventilation System i
{ D31. Damper Position for 2 See Comments Open/Close See Comments NO Indicate status A total of 11 l Control Room of dampers. . limit switches i Emergency Air Flow and 11 4 indicating-l lights .
j D32. Reactor Building Vent 2 FT-7320 0-60,000 FT-7320 NO Indicate exhaust j Exhaust Flow CFM flow i i
't 1
I I
i
Page 18 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 COMENTS -
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- VES Indicate system Current (N0 Number) Amps AC II-9248 status D35. Essential 125V Bus 2 EI-92220 0-150 EI-92220 NO- Indicate system Voltage EI-92221 Volts EI-92221 status 036. Instrument Air 2 PT-8212 0-125 PI-8212 YES Indicate system Receiver Pressure PT-8254 psig PI-8254 status D37. Hydraulic Oil Loop 2 PT-91141 2000-3500 PI-91141 NO Indicate. system Pressure PT-91142 psig PI-91142 status
Page 19 of 21 - ,
POST ACCIDENT MONITORING INSTRUMENTATION .r y;,s TYPE E: (NOTE 1) Those variables to be monitored as required for use in determining the magnitude of the.
release of radioactive materials and ccntinually assessing such releases.
INSTRUMENT CTL ROOM VARIABLE CAT NC. RANGE DISPLAY E0F/TSC (NOTE 2) (NOTE 3) (NOTE 4) (NOTE 5) (NOTE 6) PURPOSE COMMENTS Airborne Radioactive Material Released From Plant E1. 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 6 RT-73437-1,-2 10-10 CPM RR-73437 releases E3. PCRV Safety Valve 3 RT-93252-12 .1-10,000 RR-93252-12 YES Detection of Same as B16 Discharge Radiation mr/hr 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 'I RT-93251-1 .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 E.4a.3 Mn Ctl Rm-Tb 3 RT-93250-5 .1 mR to RIS-93250-5 Turbine Bldg.
1E+4mR E.4a.4 Gas Waste 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 to RIS-93252-6 Reactor Bldg.
IE+4mR h
Page 20 of 21 POST ACCIDENT MONITORING INSTRUMENTATION - a 9p.
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.
Wesc - Rx IE+4mR E.4a.7 Valve Oper Stat. - 3 RT-93252-7 .1 mR to RIS-93252-7 Reactor Bldg.
East - Rx 1E+4mR E.4a.8 NE Walkway - Rx 3 RT-93250-8 .1 mR to RIS-93250-8 Reactor bldg.
IE+4mR E.4a.9 Buffer Hel Dryer 3 RT-93251-9 .1 mR to RIS-93251-9 Reactor Bldg.
Stairwell 1E+4mR Loop 1 - Rx E.4a.10 Condensate Demin.- 3 RT-93250-13 .1 mR to RIS-93250-13 Turbine Bldg.
Tb IE+4mR E.4a.11 E. Wall Refueling 2 RT-93250-14 1 mR to RIS-93250-14 High Range Floor - Rx 1E+4R Monitor Rx Building Environs Radiation and Radioactivity E.5 Portable Radiation 3 R0-5 ImR-200R NO N0 Very signiificant Instrumentation / R0-7 200R- NO N0 releases and local Sensors SAM-II 20,000R NO N0 magnitudes lE-10 to 3E-5 micro Ci/cc Iodine Meteorology E6. Wind Direction 0 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 E8. Estimate of Atmo- 3 Release Assess-spheric Stability ment Temp. Differential TT-93110-2 -5 F to XR-93574-3 between 58M & 10M +5 F
Paga 21 of 21 e
P03T ACCIDENT MONITORING INSTRUMENTATION : o T'
INSTRUMENT CTL ROOM VARIABLE CAT NO. RANGE DISPLAY E0F/TSC (NOTE 2) (NOTE 3) (NOTE 4) (NOTE 5) (NOTE 6) PURPOSE COMMENTS Accident Sampling Capability E9. Primary Coolant 3 N/A N/A N/A Release Assess- Grab Sample
-gross activity ment; verifi- via HV-93486
-gamma spectrum cation Same as C6a.
f