ML20086R765
| ML20086R765 | |
| Person / Time | |
|---|---|
| Site: | South Texas  |
| Issue date: | 07/24/1995 |
| From: | Alexion T NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20086R770 | List: |
| References | |
| NUDOCS 9507310275 | |
| Download: ML20086R765 (15) | |
Text
-
- i d*c'w
)+
g *i UNITED STATES T.
>f_;f f E E
NUCLEAR REGULATORY COMMISSION.
L.,
(*g-
' ~-
WASHINGTON, D.C. 20566 0001 R '.%s*,.+,/
r HOUSTON LIGHTING & POWER COMPANY CITY PUBLIC SERVICE BOARD OF SAN ANTONIO CENTRAL POWER AND LIGHT COMPANY CITY OF AUSTIN. TEXAS DOCKET NO. 50-498 SOUTH TEXAS PROJECT. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 77 License No. NPF-76 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Houston Lighting & Power Company *
(HL&P) acting on behalf.of itself and for the City Public. Service Board of San Antonio (CPS), Central Power and Light Company (CPL),
and City of Austin, Texas (COA) (the. licensees), dated April 27, 1995, as supplemented by. letters dated May 4 and 25, 1995, complies.
with the standards and requirements of the Atomic Energy Act of l
1954, as amended (the Act), and the Commission's rules and regulations set.forth in 10 CFR Chapter.I; B.
The facility will operate in conformity with the application, as amended, the provisions of the Act, and the rules. and regulations of the Commission; C.
There is reasonable assurance:
(i) that the. activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities.will be conducted in compliance with the Commission's regulations; D.
The issuance of this license amendment will not be' inimical to the common defense and security or to the health' and safety'of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have
[
been satisfied.
I
- Houston Lighting & Power Company is authorized to act for. the City Public h
Service Board of San Antonio, Central Power and Light Company and City of Austin, Texas and has exclusive responsibility and control over the physical construction, operation and maintenance of the facility.
9507310275 950724 PDR ADOCK 05000499 P
PDR,,
g h
hlC
- 2.
Accordingly, the. license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment j
and Paragraph 2.C.(2) of Facility Operating License No. NPF-76 is hereby amended to read as follows:
6 2.
Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 77, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated in the license.
The licensee shall operate the facility'in accordance with the Technical Specifications and the Environmental Protection Plan.
3.
The license amendment is effective as of its date of issuance to be implemented within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION
,' - t sg
- !u /
Thomas W. Alexion, Project Manager Project Directorate IV-1 1
Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical j
Specifications i
Date of Issuance: July 24,1995 I
i i
=
1
,l
- 0844, l'
?*,
' UNITED STATES
-[;
1
-j.
NUCLEAR REGULATORY COMMISSION.
1
- .g f.
WASHINGTON, D.C. 2055fM001
% n.
j HOUSTON LIGHTING & POWER COMPANY CITY PUBLIC SERVICE BOARD OF SAN ANTONIO CENTRAL POWER AND LIGHT COMPANY CITY OF AUSTIN. TEXAS DOCKET NO. 50-499 SOUTH TEXAS PROJECT. UNIT 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 66 j
License No. NPF-80 1.
The Nuclear Regulatory Commission (the Commission) has found that:
j A.
The application for amendment by Houston Lighting & Power Company *
(HL&P) acting on behalf of itself and for the City Public Service Board of San Antonio (CPS), Central Power and Light Company (CPL),
j and City of Austin, Texas (C0A) (the licensees), dated April 27, 1995, as supplemented by letters dated May 4 and 25, 1995, complies with the standards and requirements.of the Atomic Energy Act'of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.
The facility will operate in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance:
(i) that'the activities authorized i
by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this license amendment will not be inimical to the 4
common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in at.cordance with 10 CFR Part 51' of the Commission's regulations and all applicable requirements have been satisfied.
- Houston Lighting & Power Company is authorized to act for the City Public Service Board of San Antonio, Central Power and Light Company and City of Austin, Texas and has exclusive responsibility and control over the physical construction, operation and maintenance of the facility.
t_
+ -
t 9-f m.=
' q 2.
Accordingly,_the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment i
and Paragraph 2.C.(2) of Facility Operating License No. NPF-80 is hereby
}
amended to read as follows:
i 2.
Technical Specifications l
The Technical Specifications contained in Appendix A, as-revised i
through Amendment No. 66, and the Environmental Protection Plan contained in Appendix B, are hereby' incorporated in the license.
The licensee shall operate the facility in accordance with the
-l Technical Specifications and the Environmental Protection Plan.
i 3.
The license amendment is effective as of its date of issuance to be l
implemented'within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION r,
1 l
Thomas W. Alexion, Project Manager Project Directorate IV-1 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications
.Date of Issuance: July 24, 1995 l
ATTACHMENT TO LICENSE AMENDMENT NOS. 77 AND A6 FACILITY OPERATING LICENSE NOS. NPF-76-AND NPF-80 DOCKET N05. 50-498 AND 50-499 Replace the following pages of the Appendix A Technical Specifications with the attached pages.
The revised pages are identified by Amendment number and contain marginal lines indicating the areas of change.
The corresponding overleaf pages are also provided to maintain document completeness.
REMOVE INSERT-3/4 3-63 3/4 3-63 3/4 3-65 3/4 3-65 3/4 3-66 3/4 3-66 3/4 3-69 3/4 3-69 3/4 3-71 3/4 3-71 3/4 3-72 3/4 3-72 8 3/4 3-5 B 3/4 3-5 8 3/4 3-6 8 3/4 3-6 l
s-,-
TABLE 3.3-9 (Continued)
REMOTE SHUTDOWN SYSTEM TOTAL NO.
MINIMUM READOUT OF CHANNELS INSTRUMENT LOCATION CHANNELS OPERABLE 8.
Auxiliary Feedwater Flow Rate ASP-QDPS 4-1/ steam 1/ steam generator -
generator 3 steam generators #
9.
Auxiliary Feedwater Storage ASP-QDPS 3
2 Tank Water level 10.
(DELETED)
-l TOTAL NO.
MINIMUM-TRANSFER SWITCHES AMD 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.0) 2.
Reactor Head Vent Throttle ZLP-700 (Train A)
'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)
ASP (Train D)
SOUTH TEXAS - UNITS 11L 2 3/4.3-63 Unit 1 - Amendment No. 77 Unit 2 - Amendment No '66
g TABLE _3.3-9'(Continued)
O h_
REMOTE SHUTDOWN SYSTEM -Q TOTAL NO
. MINIMUM y,: TRANSFER SWITCHES AND TRANSFER SWITCH CONTROLS OF CHANNELS ASSOCIATED CONTROLS LOCATIONS L_0 CATION CHANNELS OPERABLE-3 5.
Centrifugal Charging Pumps ZLP-653,(Train A)
ASP 2
l' d
ZLP-655 (Train C) 6.
Boric Acid Transfer Pumps ZLP-653 (Train A)
ASP 2
1 ZIP-655 (Train C)
,2 7.
Pressurizer PORVs and Block ZLP-700 (Train'A)
ASP 2
'l-Valves ZLP-701 (Train B) 8.
' Accumulator Discharge ZLP-653 (Train A)
ASP 3
3-m2 Isolation Valves and Power ZLP-654 (Train B)
Lockouts ZLP-655 (Train C) w d
9.
Letdown Stop Valves ZLP-700 (Train A)
ASP 2
1.
ZLP-709 (Irain C)
- 10. CCW Pueps and Heat Exchanger-ZLP-653 (Train A)
- ZLP-653 (Train A) 3
_2 Outlet Valves ZLP-654-(Train B)
ZLP-654 (Train'B)
ZLP-655 (Train C)
ZLP-655 (Train C)
- 11. ECW Pumps ZLP-653 (Train A)
ZLP-653 (Train A) 3 2
ZLP-654 (Train B)
ZLP-654 (Train B)-
i ZLP-655 (Train C)
ZLP-655 (Train C) i
- 12. EAB HVAC Fans ZLP-700 (Train A)
ZLP-700 (Train A) 3 2-ZLP-653 (Train A '
ZLP-653 (Train A-Battery Room and Battery Room 7
Electrical Penetration and Electrical Space Fans)
Penetration Space fans) zip-701-(Train B)
ZLP-701 (Train B)'
ZLP ea4 (Train B-ZLP-654 (Train B-
- Batterj Room.and Battery Room Electrical Penetration and Electrical
' Space Fans)
Penetration Space Fans)
9a TABLE ~3.3-9 (Continued)
REMOTE SHUTDOWN SYSTEM TOTAL NO.
MINIMUM TRANSFER SWITCHES AND TRANSFER SWITCH CONTROLS OF CHANNELS ASSOCIATED CONTROLS _
LOCATIONS LOCATION CHANNELS OPERABLE 12.
EAB HVAC Fans ZLP-709 (Train C)
ZLP-709 (Train C)
(Continued)
ZLP-655 (Train C-ZLP 655 (Train C-Battery Room and Battery Room Electrical Penetration and Electrical Space Fans)
Penetration Space Fans)
- 13. Reactor Containment Fan ZLP-700 (Train A)
ZLP-700 (Train A) 6 3
Coolers ZLP-701 (Train B)
ZLP-701 (Train B)
ZLP-709 (Train C)
ZLP-709 (Train C)
- ASP - Auxiliary Shutdown Panel
- QDPS - Qualified Display Processing System
SOUTH TEXAS - UNITS.1 & 2 3/4 3 Unit 1 - Amendment No. 77 Unit ' 2 - Amendment No. 66
1_
TABLE-4.3-6 REMOTE SHUTDOWN MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS
-CHANNEL CHANNEL INSTRUMENT CHECK CALIBRATION 1.
Neutron Flux - Extended Range a.
Startup Rate M
R b.
Flux Level M
R 2.
Reactor Trip' Breaker Indication M
N.A.
3.
Reactor Coolant Temperature-Wide Range a.
Hot leg M
R b.
Cold leg-M R
4.
Reactor Coolant Pressure-Wide Range / Extended-Range.
M R
5.
Pressurizer Water level M
R 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.
(DELETED) l i
' SOUTH TEXAS - UNITS 1 & 2 3/4 3-66 Unit 1.-- Amendment No.477 t
Unit 2 - Amendment No. 66 1-
~,_
u
TABLE 3.3-10 (Continued)
ACCIDENT MONITORING INSTRUMENTATION TOTAL MINIMUM NO. OF CHANNELS INSTRUMENT CHANNELS OPERABLE ACTION
- 13. Containment Water Level (Narrow Range) 2 1
36
- 14. Containment Water Level (Wide Range) 3 1
37 15.
- 2
- 1 42 l
16.
Steam Line Radiation Monitor 1/ steam line 1/ steam line 40
- 17. Containment - High Range Radiation Monitor 2
1 39 18.
Reactor Vessel Water level (RVWL) 2*
1*
41
- 19. Neutron Flux (Extended Range) 2 1
36 20.
Containment Hydrogen Concentration 2
1 36
- 21. Containment Pressure (Extended Range) 2 1
36
- 22. Steam Generator Blowdown Radiation Monitor 1/ blowdown line 1/ blowdown line 40 23.
Neutron Flux - Startup Rate (Extended Range) 2 1
36
- A channel is eight sensors in a probe. A channel is OPERABLE if four or more sensors, one or more in the upper section and three or more in the lower section, are OPERABLE.
- A channel is OPERABLE if at least two core exit thermocouples per core quadrant are OPERABLE, and at least one quadrant has at least four OPERABLE thermocouples.
1 SOUTil TEXAS - UNITS 1 & 2 3/4 3-69 Unit 1 - Amendment No. 77 Unit 2 - Amendment No.66
=
' TABLE 3.3-10 (Continued)
ACTION STATEMENTS ACTION 35 -
With the number of OPERABLE channels less than the Minimum Channels Operable requirement, restore at least one inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, or be in at least j
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 />.
j ACTION 36 - a. With the number of OPERABLE channels one less than the Total i
Number of Channels requirements, restore one inoperable channel to OPERABLE status within 7 days, or be in at least HOT SHUTDOWN l
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 l
channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, or be in at least 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 37 - a. With the number of OPERABLE channels one less than the Total ~
Number of Channels requirements, restore the inoperable channel j
to OPERABLE status within 31 days, or be in at least 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 />.
?
- b. With the number of OPERABLE channels two less than the Total-Number of Channels requirement, restore at least one inoperable channel to OPERABLE status within 7 days, or be in at least-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 />.
- c. With the number of OPERABLE channels less than the Minimum i
Channels Operable requirement, restore at least one inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in at least 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 38 - a. With the number of OPERABLE channels one less than the Total Number of Channels requirements, restore the inoperable channel l
to OPERABLE status within 90 days, or be in at.least 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 />.
- b. With the number of OPERABLE channels two less than the Total i
I Number of Channels requirements, restore the inoperable channel to OPERABLE status within 31 days, or be in at least 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 />.
- c. With the number of OPERABLE channels'three less than the Total Number of Channels requirement, restore at least'one inoperable-channel to OPERABLE status within 7 days, or be in at least 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 />.
- d. With the number of OPERABLE channels less than the Minimum Channels Operable requirement, restore at least one inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in at least 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 />.
SOUTH TEXAS - UNITS 1 & 2 3/4 3-70 l
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 SUUTDOWN 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 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 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 41 - a.
With the number of OPERABLE channels one less than the Required Number of Channels, either restore the system to OPERABLE 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 i
system to OPERABLE status.
]
b.
With the number of OPERABLE Channels one less than the Minimum Channels OPERABLE 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 shutting down or:
1.
Initiate an alternate method of monitoring the reactor vessel inventory; 2.
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; and 3.
Restore the system to OPERABLE status at the next scheduled refueling.
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. 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 HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />, and in HOT SHUTDOWN in the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
SOUTH TEXAS - UNITS 1 & 2 3/4 3-71 Unit 1 - Amendment No. 77 Unit 2 - Amendment No. 66
?.
TABLE 3.3-10 (Continued)
ACTION STATEMENTS (Continued) y l
-ACTION 43 - a.
With the number of OPERABLE channels two less than the Total Number.of Channels requirements, restore the inoperable channel'to OPERABLE status within 31 days, or be in at.least 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 />.
b.
With the number of OPERABLE channels three less than the Total.
. Number of Channels requirement, restore at least one inoperable channel to OPERABLE status within 7 days,~or be in at least 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 />.
With the number of.0PERABLE channels less than the Minimum c.
Channels Operable requirement, restore 'at' least one inoperable channel to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be in at least' 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 />.
l l
l l
SOUTH TEXAS - UNITS 1 & 2 3/4 3-72 Unit 1 - Amendment No. 14, 77 Unit 2 - Amendment'No.
4, 66,
I INSTRUMENTATION BASES REMOTE SHUTDOWN SYSTEM (Continued)
The OPERABILITY of the Remote Shutdown System ensures that a fire will not preclude achieving safe shutdown. The Remote Shutdown System instrumentation, control, and power circuits and transfer switches necessary to eliminate effects of the fire and allow operation of instrumentation, control and power circuits required to achieve and maintain a safe shutdown condition are independent of areas where a fire could damage systems normally used to shutdown the reactor.
This capability is consistent with General Design Criterion 3 and Appendix R to 10 CFR Part 50.
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 s
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 complement of core exit thermocouples necessary to detect initial core recovery and trend the ensuing core heatup.
The evaluations account for core nonuniformities, including incore effects of the radial decay power distributions, excore effects of condensate runback in the hot legs, and nonuniform inlet temperatures.
Based on this evaluation, adequate core cooling is ensured with two valid core exit thermocouples 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 OPERAELE 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.
Power distribution symmetry was considered in determining the specific number and locations provided for diagnosis of local core problems.
Two randomly selected thermocouples are not sufficient to meet the i.wo 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 thersocouples indicate the radial temperature gradient across their core
~
SOUTH TEX 45 UNITS 1 & 2 B 3/4 3-5 Unit 1 - Amendment No.16, 77, Unit 2 - Amendment No.
6, 66,
L 1.
' INSTRUMENTATION BASES 3/4.3.3.6 ' ACCIDENT MONITORING INSTRUMFNTATION (Continued) 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 sate quadrant or any other quadrant.). This preserves the ability to withstand a single failure.
3/4.3.3.7 (Not Used) 3/4.3.3.8 (Not Used) 3/4.3.3.3.9 (Not Used) 3/4.3.3.10 DELETED 3/4.3.3.11 EXPLOSIVE GAS MONITORING INSTRUMENTATION This instrumentation includes provisions for monitoring (and controlling) the concentrations of potentially explosive gsa mixtures in the CASE 0VS WASTE PROCESSING SYSTEM.
3/4.3.4 TURBINE OVERSPEED PROTECTION This specification is provided to ensure that the turbine overspeed protection instrumentation and the turbine speed control valves are OPERABLE and will protect the turbine from excessive overspeed.
Protection from turbine excessive overspeed is required since excessive overspeed of the turbine could generate potentially damaging missiles which could impact and damage safety-related components, equipment, or structures.
SOUTH TEXAS - UNITS 1 & 2 B 3/4 3-6 Unit 1 - Amendment No. 47 76,77, 7
Unit 2 - Amendment No. &&r65,66,
- - _ _ _ - _ _ _ _ _ _ _ _