ML20087J197

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Proposed Tech Specs Re Required Operable Channels of Core Exit Thermocouples
ML20087J197
Person / Time
Site: South Texas  STP Nuclear Operating Company icon.png
Issue date: 04/27/1995
From:
HOUSTON LIGHTING & POWER CO.
To:
Shared Package
ML20087J195 List:
References
NUDOCS 9505080004
Download: ML20087J197 (8)
v • d • e


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1 ATTACHMENT 3 ,

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ANNOTATED TECHNICAL SPECIFICATION PAGES  :

AND REVISED BASES  ;

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9505080004 950427 PDR ADOCK 05000498

,P PDR T90 0%9%4 t7 901 ,

e _ TABLE 3.3-9'(Continued) g '

M REMOTE SHUTDOWN SYSTEM b TOTAL NO. MINIMUM-3 READOUT OF CHANNELS i INSTRUMENT LOCATION CHANNELS OPERABLE.

C

$ 8. Auxiliary Feedwater Flow Rate ASP-QDPS 4-1/ steam 1/ steam generator -

v generator 3 steam generators #

o- 9. Auxiliary Feedwater Storage . ASP-QDPS 3 ~2 m Tank Water Level

10. C:re rvD he-eceup'er  ?SP-Q0rs ## ^ ther-eceuplc:/-
r 42 dr nt (DEW RED) w TOTAL NO. MINIMUM.

1 TRANSFER SWITCHES AND TRANSFER SWITCH CONTROLS OF' CHANNELS.

ASSOCIATED CONTROLS LOCATIONS LOCATION CHANNELS OPERABLE

1. Steam Generator PORVs ZLP-653 (Train A) ASP 4 2#

ZLP-654 (Train B)

ZLP-655.(Train C) -

ASP (Train D) .

2. Reactor Head Vent Throttle ZLP-700 (Train A) ASP 2 1 Valves ZLP-701 (Train B)
3. Reactor Head Vent Isolation ZLP-700 (Train A) ASP 2 pair 1 pair Valves ZLP-701 (Train B)
4. AFW Pumps and Valves ZLP-653 (Train A-AFW Pump)~ ASP 4 2#.

ZLP-700 (Train A-AFW Valves)

ZLP-654 (Train B-AFW Pump)

ZLP-701 (Train B-AFW Valves)

ZLP-655 (Train C-AFW Pump)

ZLP-709 (Train C-AFW Valves) 2DA ASP (Train D) %R&

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v, TABLE 3.3-9 (Continued) *

.8 g REMOTE SHUTDOWN SYSTEM h TOTAL NO. MINIMUM

$; TRANSFER SWITCHES AND TRANSFER SWITCH CONTROLS OF CHANNELS

, ASSOCIATED CONTROLS LOCATIONS LOCATION CHANNELS OPERABLE E

M 12. EAB HVAC Fans ZLP-709 (Train C) ZLP-709 (Train C)

- (Continued) ZLP-655 (Train C- ZLP-655 (Train C-

e. Battery Room and Battery Room

~ Electrical Penetration and Electrical Space Fans) Penetration Space Fans) u, 13. Reactor Containment Fan ZLP-700 (Train A) ZLP-700 (Train A) 6 3 2: Coolers ZLP-701 CTrain B) ZLP-701 (Train B) u, ZLP-709 (Train C) ZLP-709 (Train C) h

  • ASP - Auxiliary Shutdown Panel
    • QDPS - Qualified Display Processing System
  1. Must be in the same OPERABLE RCS loop / secondary loop.

-f#A-tota 4--cf 50 thui...;;euples are previded "ith 25 thermacesples e. codi vi iwu i.ra i ri> . Quodi oiii.3 5 ciid -

-O"have 6 UiesmeGGuplCO PCT train COOh. QU0drants a 3nd C e3cp 3;g; ; thg7;gegeple; 33 gn; tr;ja snd 7 thnrmee99nic3 33 th; gthtp tp3jr, Thg. p(ggj3jgg3 gf ,*,CTION b, ;7; ggt gpp]j ggb];- 3; ]Ong gg garh

-quedient has 4 ther;;;;uplc; per trsin OPE"AOLE.

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TABLE 4.3 .

o . REMOTE' SHUTDOWN MONITORING INSTRUMENTATION .

y SURVElLLANCE_ REQUIREMENTS M CHANNEL CHANNEL CALIBRATION'

$ ~ INSTRUMENT CHECK _

[ 1. Neutron Flux - Extended Range 5

g a. Startup Rate M R

[ b. Flux Level M R

2. Reactor Trip Breaker Indication M N.A.
3. Reactor Coolant Temperature--

Wide _ Range 3 a. Hot Leg M R a b. Cold Leg M R e

4. Reactor Coolant Pressure-Wide Range / Extended Range M R
5. Pressurizer Water Level M .R 7
6. Steam Line Pressure 'M R
7. Steam Generator Water Level-Wide Range _ M R-
8. Auxiliary Feedwater Flow Rate M R-
9. Auxiliary Feedwater Storage Tank Water Level M R
10. S n Erit W :;s;cupic3 u o .

[ay

., "s a

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.. , ,__,, .- ,, -,_..-.--,- . .- -- ..,-.,.. .. .,.-..-. . . . . . . ---. -., . . . . _ . , . , . . . . . . . _ . .w. .. . . _ . , _ _ - . . . _ . - ~ - ..i-________ _ - - . -

~.

TABLE 3.3-10 (continued)_ .

9 .

ACCIDENT HONITORING_ INSTRUMENTATION .

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TOTAL NO. OF MINIMUM CHANNELS OPERABLE ACTION

, INSTRUMENT' CHANNELS

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5 13. Containment" Water Leve F 2, 1 36 G (Narrow Range) ' "

Containment Water Level (Wide Range) 3- 1 37 3 14

<x t

15. Core Exit Thermocouples ** f i th:= ::uple:/ core
  • 42 Aua28aC 1/ steam line 1/ steam line 40
16. Staam line Radiation Monitor w

'; 17. Containment - High Range Radiation 2 1 39 w Monitor

$ 2* 1*

41

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18. Reactor Vessel Water Level (RWL) .

1 36

19. Neutron Flux (Extended Range) 2 1 36
20. Containment Hydrogen Concentration 2

+

Containment Pressure (Extended Range) 2 1 36 21.

22. ~ Steam Generator Blowdown Radiation 40 Monitor 1/ blowdown line 1/ blowdown line
23. Neutron Flux - Startup Rate 2 1 36 (Extended Range)
  • A channel is eight sensors in a probe. A channel is OPERABLE if four or more sensors, one or more in the uoper section and three or more in the lower section, are OPERABLE. m cn
    • f total of 50 tnermocouples are provided witn a thermocouples on each of two trains. Quadrants 8 and D have 6 thermocouples per train each. Quadrants A and C each have 6 thermocouples on one train ds a >E =5 and 7 thermocouples on the other train. No ACTION is required as long as each quadrant has 4 ^(C

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thermocouples per train OPERABLE. y A ebannel is CPERAEAE if at least b/o core edi- fhermocouples F com c{uadrant are { (> PE e

ed d leosi ore ctuadroM 'hos at leost -rcor orenAnie we<mee oeles. e

}

- -- . . , . - . - - . - ~ - . . .~.. , - . .

~

ST-11L-AE-5079 Attachment 3

  1. E

, TABLE 3.3-10 (Continued) ,

ACTION STATEMENTS (Continued)

ACTION 39 - a. With the number of OPERABLE channels one less.than the Total Number of Channels requirements, restore one inoperable channel '

to OPERABLE status within 7 days, or be in at least HOT i 5HUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. >

b. With the number of OPERABLE-channels less than the Minimum Channels Operable requirements, restore at least one inoperable  ;

channel to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, or be in at least t HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

ACTION 40 - With the number of OPERABLE channels less than the Minimum Channels Operable requirements, restore at least one inoperable channel to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />, or be in at least H0T SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

ACTION 41 - a. With the number of OPERABLE channels one less than the Required  :

Number of Channels, either restore the system to OPERABLE t I

status within 7 days if repairs are feasible without shutting

down or prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within 30 days following the event outlining the action taken, the cause of the inoperability ,

and the plans and schedule for restoring the system to OPERABLE  ;

status,

b. With the number of OPERABLE Channels one less than the Minimum  !

Channels OPERA 9tE in Table 3.3-10, either restore the inoperable  ;

channel (s) to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> if repairs are feasible without sh,utting down o.. ,

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1. Initiate an alternate method of monitoring the reactor i vessel inventory; i Prepare and submit a Special Report to the Commission i 2.

pursuant to Specification 6.9.2 within 30 days following -

the event outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status; and L I

3. Restore the system to OPERABLE status at the next scheduled refueling.

ouples ACTION 42 per -[With the per quadrant number of OPERABLE train, restore channels.

these thermocou less than 4 the to OPERABLE  ;

status within 31 days, or be in at least H

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UTDOWN within RERNE the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

mTa alSERT

b. With the number of OPERfdEE channels less than 6 thermocouples per quadrant, restorF these thermocouples to OPERABLE status n &( N be in at least HOT SHUTDOWN witbin the'next SOUTH TEXAS - UNils 1 & 2 3/4 3-71

ST-HL-AE-5079 Attachment 3 Page 6 of 7 INSERT FOR ACTION 42:

a. With one required channel inoperable, restore the required channel to OPERABLE -

status within 30 days; otherwise, a report shall be prepared and submitted in accordance with Specification 6.9.2 within the next 14 days or as otherwise approved by the Region. The report shall outline the preplanned alternate method of monitoring, the cause of the inoperability, and the plans and schedule for restoring the instrumentation channels to OPERABLE status.

b. With two required channels inoperable, restore one required channel to OPERABLE status within 7 days; otherwise, be in liOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and in IIOT SIIUTDOWN in the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

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ST-HL-AE-5079 Attachment 3 Page 7 of 7 P

REVISED BASES i 3/4.3.3.6 ACCIDENT MONITORING INSTRUMENTATION The OPERABILITY of the accident monitoring instrumentation ensures that sufficient information is available on selected plant parameters to monitor and assess these variables '

following an accident. This capability is consistent with the recommendations of Regulatory Guide 1.97, Revision 2, " Instrumentation for Light-Water-Cooled Nuclear Power Plants to Assess Plant Conditions During and Following an Accident," December 1980 and NUREG-0737, " Clarification of TMI Action Plan Requirements," November 1980. The instrumentation listed in Table 3.3-10 corresponds to the Category 1 instrumentation for which selection, design, qualification and display criteria are described in Regulatory Guide 1.97, Revision 2.

Consistent with the requirements of NUREG-0737, an evaluation was made of the minimum number of valid core exit thermocouples necessary for measuring core cooling. The evaluation determined the reduced complement of core exit thermocouples necessary to detect initial core recovery and trend the ensuing core heatup. Based on this evaluation, adequate ,

core cooling is ensured with two valid core exit thermocouple channels per quadrant with two core exit thermocouples per required channel. The core exit thermocouple pair are oriented radially to permit evaluation of core radial decay power distribution. Core exit temperature is ,

used to determine whether to terminate Safety Injection, if still in progress, or to reinitiate Safety injection if it has been stopped. Core exit temperature is also used for unit stabilization and cooldown control.

Two OPERABLE channels of core exit thermocouples are required in each quadrant to provide indication of radial distribution of the coolant temperature rise across representative regions of the core. Two randomly selected thermocouples are not sufficient to meet the two thermocouples per channel requirement in any quadrant. The two thermocouples in each channel must meet the additional requirement that one is located near the center of the core and the other near the core perimeter, such that the pair of core exit thermocouples indicate the radial temperature gradient across their core quadrant. The unit specific response to Item II.F.2 of NUREG-0737 further discusses the core exit thermocouples. Two sets of two thermocouples ensure a single failure will not disable the ability to determine the radial temperature gradient. The subcooling margin monitor requirements are not affected by allowing 2 thermocouples/ channel / quadrant as long as each channel has at least four operable thermocouples in any quadrant (e.g., A Train has four operable thermocouples in one of the quadrants, and C Train has four operable thermocouples in the same quadrant or any other quadrant.). This preserves the ability to withstand a single failure.

TT( 9%90 t 17 001

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