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{{#Wiki_filter:* ATTACHMENT Consumers Power Company Palisades Plant Docket 50-255 PROPOSED PAGES TECHNICAL SPECIFICATIONS CHANGE REQUEST CORE EXIT THERMOCOUPLES November 25, 1987 -. --------.
{{#Wiki_filter:*
__ 1-r
ATTACHMENT Consumers Power Company Palisades Plant Docket 50-255 PROPOSED PAGES TECHNICAL SPECIFICATIONS CHANGE REQUEST CORE EXIT THERMOCOUPLES November 25, 1987 r
----< I r 871 1300137* a11125JJ'
_ _1-r ---=-:-:::=::--=::;~~W::*
*1 \ \ ADOCK  
871 1300137* a11125JJ' *1
\ . 4 Pages OC1187-0206-NL02-NL04 3.17 INSTRUMENTATION AND CONTROL SYSTEMS (Contd) If the bypass is not effected, the out-of-service channel (Power Removed) assumes a tripped condition (except high rate-of-change of power, high power level and high pressurizer pressure), (l) which results in a one-out-of-three channel logic. If, in the 2 of 4 logic system of either the reactor protective system or the engineered safeguards system, one channel is bypassed and a second channel manually placed in a tripped condition, the resulting logic is 1 of 2. At rated power, the minimum operable high-power level channels is 3 in order to provide adequate flux tilt detection.
                                  ----<\      I
If only 2 channels are operable, the reactor power level is reduced to 70% rated power which protects the reactor from possibly exceeding design peaking factors due to undetected flux tilts and from exceeding dropped rod peaking factors in the event that a turbine runback signal is required from the power range channels.
\   ~DR    ADOCK   050~~~j    \             .
The engineered safeguards system provides a 2 of 4 logic on the signal used to actuate the equipment connected to each of the 2 emergency diesel generator units. Two start-up channels are available any time reactivity changes are deliberately being introduced into the reactor and the neutron power is not visible on the log-range nuclear instrumentation or above -4 10 % of rated power. This ensures that redundant start-up instrumentation is available to operators to monitor effects of reactivity changes when neutron power levels are only visible on the start-up channels.
4 Pages OC1187-0206-NL02-NL04
In the event only one start-up range channel is available and the neutron power level is sufficiently high that it is being monitored by both channels of log-range instrumentation, a startup can be performed in accordance with footnote (d) of Table 3.17.4. S_ixteen (four per core quadrant) environmentally qualified core ---exit thermocouples (cable and connectors) with readout from 0 to / 2300&deg;F are provided for monitoring the potential approach to I inadequate core cooling. The core exit thermocouples are an I integral part of the incore detector assembly and are located at I the top of each incore assembly to measure primary coolant outlet I temperatures.  
 
/ References (1) Updated FSAR, Sections 7.2.2 and 7.2.7. 3-77 Amendment No. <<. OC1187-0206-NL02-NL04
3.17     INSTRUMENTATION AND CONTROL SYSTEMS   (Contd)
. J' e Table 3.17.4 (Cont'd) Minimum Minimum Permissible Operable Degree of Bypass No _Fun..ctional Unit Channels Redundancy Conditions  
If the bypass is not effected, the out-of-service channel (Power         ~
: 8. Pressurizer Water 2 1 Not required in Level (LI-0102)
Removed) assumes a tripped condition (except high rate-of-change of power, high power level and high pressurizer pressure), (l) which results in a one-out-of-three channel logic. If, in the 2 of 4 logic system of either the reactor protective system or the engineered safeguards system, one channel is bypassed and a second channel manually placed in a tripped condition, the resulting logic is 1 of 2. At rated power, the minimum operable high-power level channels is 3 in order to provide adequate flux tilt detection. If only 2 channels are operable, the reactor power level is reduced to 70% rated power which protects the reactor from possibly exceeding design peaking factors due to undetected flux tilts and from exceeding dropped rod peaking factors in the event that a turbine runback signal is required from the power range channels.
Cold or Refuel-ing Shutdown 9. Pressurizer Code 1 per None Not Required Safety Relief Valves Valve below 325&deg;F Position Indication (Acoustic Monitor or Temperature Indication)  
The engineered safeguards system provides a 2 of 4 logic on the signal used to actuate the equipment connected to each of the 2 emergency diesel generator units.
: 10. Power Operated Relief 1 per None Not required when Valves (Acoustic Valve PORV isolation valve Monitor or Temperature is closed and Indication) indication system is operable 11. PORV Isolation Va*lves 1 per None Not required when Position Indication Valve reactor is depressurized and vented through a vent G:l.3 sq.in. 12. Subcooling Margin 1 None Not required Monitor below 515&deg;F 13. Auxiliary Feed Flow 1 per flow(h) None Not required Rate Indication Control below 325&deg;F Valve 14. Auxiliary Feedwater 2 per stetW) 1 Not required Actuation System generator below 325&deg;F Sensor Channels 15. Auxiliary Feedwater 2 (f) 1 Not required Actuation System below 325&deg;F Actuation Channels 16. Excore Detector l(g) None None 17. Core Exit 2/core I/core Not required Thermocouples Quadrant (i) Quadrant in cold or Refueling Shutdown (e) Auxiliary Feedwater System Actuation System Sensor Channels coritain pump auto initiation circuitry.
Two start-up channels are available any time reactivity changes are deliberately being introduced into the reactor and the neutron power is not visible on the log-range nuclear instrumentation or above
If two sensor channels for one steam generator are inoperable, one of the steam generator low level bistable modules in one of the inoperable channels must be in the tripped condition.
            -4 10 % of rated power. This ensures that redundant start-up instrumentation is available to operators to monitor effects of reactivity changes when neutron power levels are only visible on the start-up channels. In the event only one start-up range channel is available and the neutron power level is sufficiently high that it is being monitored by both channels of log-range instrumentation, a startup can be performed in accordance with footnote (d) of Table 3.17.4.
3-Bla Amendment No. OC1187-0206-NL02-NL04 I I I I No 8. 9. 10. 11. 12. 13. 14. 15. Func-t-ional Unit Pressurizer Water Level (LI-0102)
S_ixteen (four per core quadrant) environmentally qualified core exit thermocouples (cable and connectors) with readout from 0 to       /
Pressurizer Code Safety Relief Valves Position Indication (Acoustic Monitor or Temperature Indication)
2300&deg;F are provided for monitoring the potential approach to           I inadequate core cooling. The core exit thermocouples are an             I integral part of the incore detector assembly and are located at       I the top of each incore assembly to measure primary coolant outlet       I temperatures.                                                           /
Power Operated Relief Valves (Acoustic Monitor or Temperature Indication)
References (1)   Updated FSAR, Sections 7.2.2 and 7.2.7.
PORV Isolation Valves Position Indication Subcooling Margin Monitor Auxiliary Feed Flow Rate Indication Auxiliary Feedwater Actuation System Sensor Channels Auxiliary Feedwater Actuation System Actuation Channels 16. Excore Detector 17. Core Exit Thermocouples Table 3.17.4 (Cont'd) Minimum Operable Channels 2 1 per Valve Minimum Degree of Redundancy 1 None 1 per None Valve 1 per None Valve 1 None 1 per flow(h) None Control Valve 2 per stetW) generator l(g) 2/core Quadrant (i) 1 1 None I/core Quadrant
3-77 Amendment No. <<.
* Permissible Bypass Conditions Not required in Cold or ing Shutdown Not Required below 325&deg;F Not required when PORV isolation valve is closed and its indication system is operable Not required when reactor is depressurized and vented through a vent :?:1.3 sq.in. Not required below 515&deg;F Not required below 325&deg;F Not required below 325&deg;F Not required below 325&deg;F None Not required in.cold or Refueling Shutdown I I I I (e) Auxiliary Feedwater System Actuation System Sensor Channels contain pump auto initiation circuitry.
OC1187-0206-NL02-NL04
If two sensor channels for one steam generator are inoperable, one of** the steam generator low level bistable modules* in one of the inoperable channels must be in the tripped condition.
 
3-8la Amendment No. OC1187-0206-NL02-NL04
J' e
* * < Table 3.17.4 (Cont'd) (f) With one auxiliary Feedwater Actuation System Actuation Channel in lieu of the requirement of 3.17.2, provide a second licensed operator in the control room within 2 hours. With both inoperable, in lieu of following the requirements of 3.17.2, start and maintain in operation the turbine driven auxiliary feed pump. (g) Calculate the Quadrant Power Tilt using the excore readings at least once per 12 hours when the excore detectors deviation alarms are inoperable. (h) With two flow rate indicators inoperable for a given control valve, the control valve shall be considered inoperable and the requirements of 3.5.2(e) apply. (i) The core exit thermocouples in core locations (H2, G7, J7, JlO), (Q4, R7, R8, Nll), (M13, X14, Ql6, R17) and (Bl3, H13, J16, Gl7) are to be used in determining the minimum channels operable requirement.
Table 3.17.4 (Cont'd)
3-8lb Amendment No. OC1187-0206-NL02-NL04 I I I TABLE 4 .'l. 3 Minimum Frequencies for Checks, Calibrations and Testing of Miscellaneous Instrumentation and Controls (Contd) Channel DescriEtion Function Frequency Surveillance Method 23. Core Exit a. Check M a. Comparison of Channels b. Calibrate (6) b. Known voltage substituted for thermocouple (6) Only applicable to core thermocouple in core locations H2, G7, J7, JlO, Q4, R7, R8, Nll, Ml3, Xl4, Ql6, Rl7, Bl3, Hl3, Jl6 and Gl7. These thermocouples will be calibrated on a refueling cycle frequency.
Minimum       Minimum       Permissible Operable       Degree of       Bypass No   _Fun..ctional Unit       Channels       Redundancy     Conditions
4-llb Proposed OC1187-0206-NL02-NL04  
: 8. Pressurizer Water           2             1         Not required in Level (LI-0102)                                       Cold or Refuel-ing Shutdown
.. *.'l* *' "": .. I I I e.}}
: 9. Pressurizer Code         1 per         None           Not Required Safety Relief Valves     Valve                         below 325&deg;F Position Indication (Acoustic Monitor or Temperature Indication)
: 10. Power Operated Relief   1 per         None           Not required when Valves (Acoustic         Valve                         PORV isolation valve Monitor or Temperature                                 is closed and ~ts Indication)                                           indication system is operable
: 11. PORV Isolation Va*lves   1 per         None           Not required when Position Indication     Valve                         reactor is depressurized and vented through a vent G:l.3 sq.in.
: 12. Subcooling Margin           1         None           Not required Monitor                                               below 515&deg;F
: 13. Auxiliary Feed Flow     1 per flow(h) None           Not required Rate Indication         Control                       below 325&deg;F Valve
: 14. Auxiliary Feedwater     2 per stetW)       1         Not required Actuation System         generator                     below 325&deg;F Sensor Channels
: 15. Auxiliary Feedwater         2 (f)           1         Not required Actuation System                                       below 325&deg;F Actuation Channels
: 16. Excore Detector             l(g)       None           None
: 17. Core Exit               2/core         I/core         Not required         I Thermocouples           Quadrant (i)   Quadrant       in cold or           I Refueling           I Shutdown             I (e)   Auxiliary Feedwater System Actuation System Sensor Channels coritain pump auto initiation circuitry. If two sensor channels for one steam generator are inoperable, one of the steam generator low level bistable modules in one of the inoperable channels must be in the tripped condition.
3-Bla       Amendment No. ~1. ~S.  ~~.
OC1187-0206-NL02-NL04
 
Table 3.17.4 (Cont'd)
Minimum        Minimum
* Permissible Operable      Degree of        Bypass No    Func-t-ional Unit         Channels      Redundancy    Conditions
: 8. Pressurizer Water             2              1          Not required in Level (LI-0102)                                         Cold or Refuel-ing Shutdown
: 9. Pressurizer Code           1 per          None          Not Required Safety Relief Valves       Valve                        below 325&deg;F Position Indication (Acoustic Monitor or Temperature Indication)
: 10. Power Operated Relief     1 per          None          Not required when Valves (Acoustic           Valve                        PORV isolation valve Monitor or Temperature                                   is closed and its Indication)                                             indication system is operable
: 11. PORV Isolation Valves     1 per          None          Not required when Position Indication       Valve                        reactor is depressurized and vented through a vent :?:1.3 sq.in.
: 12. Subcooling Margin              1         None           Not required Monitor                                                  below 515&deg;F
: 13. Auxiliary Feed Flow        1 per flow(h) None           Not required Rate Indication            Control                       below 325&deg;F Valve
: 14. Auxiliary Feedwater        2 per stetW)       1          Not required Actuation System          generator                     below 325&deg;F Sensor Channels
: 15. Auxiliary Feedwater                          1         Not required Actuation System                                        below 325&deg;F Actuation Channels
: 16. Excore Detector                l(g)      None          None
: 17. Core Exit                  2/core        I/core        Not required       I Thermocouples              Quadrant (i)  Quadrant      in.cold or          I Refueling          I Shutdown            I (e)  Auxiliary Feedwater System Actuation System Sensor Channels contain pump auto initiation circuitry. If two sensor channels for one steam generator are inoperable, one of** the steam generator low level bistable modules* in one of the inoperable channels must be in the tripped condition.
3-8la       Amendment No. ~7. ~S. 9~,
OC1187-0206-NL02-NL04
 
Table 3.17.4 (Cont'd)
(f)   With one auxiliary Feedwater Actuation System Actuation Channel
    ~~noperable,  in lieu of the requirement of 3.17.2, provide a second licensed operator in the control room within 2 hours. With both inoperable, in lieu of following the requirements of 3.17.2, start and maintain in operation the turbine driven auxiliary feed pump.
(g)   Calculate the Quadrant Power Tilt using the excore readings at least once per 12 hours when the excore detectors deviation alarms are inoperable.
(h)   With two flow rate indicators inoperable for a given control valve, the control valve shall be considered inoperable and the requirements of 3.5.2(e) apply.
(i)   The core exit thermocouples in core locations (H2, G7, J7, JlO), (Q4,   I R7, R8, Nll), (M13, X14, Ql6, R17) and (Bl3, H13, J16, Gl7) are         I to be used in determining the minimum channels operable requirement. I 3-8lb Amendment No. ~~;  ~S, OC1187-0206-NL02-NL04
 
                                                                                                      ..  *.'l* *' "": ..
TABLE 4 .'l. 3 Minimum Frequencies for Checks, Calibrations and Testing of Miscellaneous Instrumentation and Controls (Contd)
Channel DescriEtion               Function         Frequency           Surveillance Method
: 23. Core Exit Thermoc~uples( )
6
: a. Check                   M   a. Comparison of Channels
: b. Calibrate             (6)   b. Known voltage substituted for   I thermocouple e.
(6) Only applicable to core thermocouple in core locations H2, G7, J7, JlO, Q4, R7, R8, Nll, Ml3, Xl4, Ql6, Rl7, Bl3, Hl3, Jl6 and Gl7. These thermocouples will be calibrated on a refueling    I cycle frequency.                                                                                    I 4-llb                                   Proposed OC1187-0206-NL02-NL04}}

Latest revision as of 12:11, 3 February 2020

Proposed Tech Specs,Modifying Operability & Surveillance Requirements for Qualified Core Exit Thermocouples to Be Consistent w/in-core Calibr Requirements
ML18052B392
Person / Time
Site: Palisades Entergy icon.png
Issue date: 11/25/1987
From:
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
To:
Shared Package
ML18052B391 List:
References
NUDOCS 8711300137
Download: ML18052B392 (6)


Text

ATTACHMENT Consumers Power Company Palisades Plant Docket 50-255 PROPOSED PAGES TECHNICAL SPECIFICATIONS CHANGE REQUEST CORE EXIT THERMOCOUPLES November 25, 1987 r

_ _1-r ---=-:-:::=::--=::;~~W::*

871 1300137* a11125JJ' *1


<\ I

\ ~DR ADOCK 050~~~j \ .

4 Pages OC1187-0206-NL02-NL04

3.17 INSTRUMENTATION AND CONTROL SYSTEMS (Contd)

If the bypass is not effected, the out-of-service channel (Power ~

Removed) assumes a tripped condition (except high rate-of-change of power, high power level and high pressurizer pressure), (l) which results in a one-out-of-three channel logic. If, in the 2 of 4 logic system of either the reactor protective system or the engineered safeguards system, one channel is bypassed and a second channel manually placed in a tripped condition, the resulting logic is 1 of 2. At rated power, the minimum operable high-power level channels is 3 in order to provide adequate flux tilt detection. If only 2 channels are operable, the reactor power level is reduced to 70% rated power which protects the reactor from possibly exceeding design peaking factors due to undetected flux tilts and from exceeding dropped rod peaking factors in the event that a turbine runback signal is required from the power range channels.

The engineered safeguards system provides a 2 of 4 logic on the signal used to actuate the equipment connected to each of the 2 emergency diesel generator units.

Two start-up channels are available any time reactivity changes are deliberately being introduced into the reactor and the neutron power is not visible on the log-range nuclear instrumentation or above

-4 10 % of rated power. This ensures that redundant start-up instrumentation is available to operators to monitor effects of reactivity changes when neutron power levels are only visible on the start-up channels. In the event only one start-up range channel is available and the neutron power level is sufficiently high that it is being monitored by both channels of log-range instrumentation, a startup can be performed in accordance with footnote (d) of Table 3.17.4.

S_ixteen (four per core quadrant) environmentally qualified core exit thermocouples (cable and connectors) with readout from 0 to /

2300°F are provided for monitoring the potential approach to I inadequate core cooling. The core exit thermocouples are an I integral part of the incore detector assembly and are located at I the top of each incore assembly to measure primary coolant outlet I temperatures. /

References (1) Updated FSAR, Sections 7.2.2 and 7.2.7.

3-77 Amendment No. <<.

OC1187-0206-NL02-NL04

J' e

Table 3.17.4 (Cont'd)

Minimum Minimum Permissible Operable Degree of Bypass No _Fun..ctional Unit Channels Redundancy Conditions

8. Pressurizer Water 2 1 Not required in Level (LI-0102) Cold or Refuel-ing Shutdown
9. Pressurizer Code 1 per None Not Required Safety Relief Valves Valve below 325°F Position Indication (Acoustic Monitor or Temperature Indication)
10. Power Operated Relief 1 per None Not required when Valves (Acoustic Valve PORV isolation valve Monitor or Temperature is closed and ~ts Indication) indication system is operable
11. PORV Isolation Va*lves 1 per None Not required when Position Indication Valve reactor is depressurized and vented through a vent G:l.3 sq.in.
12. Subcooling Margin 1 None Not required Monitor below 515°F
13. Auxiliary Feed Flow 1 per flow(h) None Not required Rate Indication Control below 325°F Valve
14. Auxiliary Feedwater 2 per stetW) 1 Not required Actuation System generator below 325°F Sensor Channels
15. Auxiliary Feedwater 2 (f) 1 Not required Actuation System below 325°F Actuation Channels
16. Excore Detector l(g) None None
17. Core Exit 2/core I/core Not required I Thermocouples Quadrant (i) Quadrant in cold or I Refueling I Shutdown I (e) Auxiliary Feedwater System Actuation System Sensor Channels coritain pump auto initiation circuitry. If two sensor channels for one steam generator are inoperable, one of the steam generator low level bistable modules in one of the inoperable channels must be in the tripped condition.

3-Bla Amendment No. ~1. ~S. ~~.

OC1187-0206-NL02-NL04

Table 3.17.4 (Cont'd)

Minimum Minimum

  • Permissible Operable Degree of Bypass No Func-t-ional Unit Channels Redundancy Conditions
8. Pressurizer Water 2 1 Not required in Level (LI-0102) Cold or Refuel-ing Shutdown
9. Pressurizer Code 1 per None Not Required Safety Relief Valves Valve below 325°F Position Indication (Acoustic Monitor or Temperature Indication)
10. Power Operated Relief 1 per None Not required when Valves (Acoustic Valve PORV isolation valve Monitor or Temperature is closed and its Indication) indication system is operable
11. PORV Isolation Valves 1 per None Not required when Position Indication Valve reactor is depressurized and vented through a vent :?:1.3 sq.in.
12. Subcooling Margin 1 None Not required Monitor below 515°F
13. Auxiliary Feed Flow 1 per flow(h) None Not required Rate Indication Control below 325°F Valve
14. Auxiliary Feedwater 2 per stetW) 1 Not required Actuation System generator below 325°F Sensor Channels
15. Auxiliary Feedwater 1 Not required Actuation System below 325°F Actuation Channels
16. Excore Detector l(g) None None
17. Core Exit 2/core I/core Not required I Thermocouples Quadrant (i) Quadrant in.cold or I Refueling I Shutdown I (e) Auxiliary Feedwater System Actuation System Sensor Channels contain pump auto initiation circuitry. If two sensor channels for one steam generator are inoperable, one of** the steam generator low level bistable modules* in one of the inoperable channels must be in the tripped condition.

3-8la Amendment No. ~7. ~S. 9~,

OC1187-0206-NL02-NL04

Table 3.17.4 (Cont'd)

(f) With one auxiliary Feedwater Actuation System Actuation Channel

~~noperable, in lieu of the requirement of 3.17.2, provide a second licensed operator in the control room within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. With both inoperable, in lieu of following the requirements of 3.17.2, start and maintain in operation the turbine driven auxiliary feed pump.

(g) Calculate the Quadrant Power Tilt using the excore readings at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when the excore detectors deviation alarms are inoperable.

(h) With two flow rate indicators inoperable for a given control valve, the control valve shall be considered inoperable and the requirements of 3.5.2(e) apply.

(i) The core exit thermocouples in core locations (H2, G7, J7, JlO), (Q4, I R7, R8, Nll), (M13, X14, Ql6, R17) and (Bl3, H13, J16, Gl7) are I to be used in determining the minimum channels operable requirement. I 3-8lb Amendment No. ~~; ~S, OC1187-0206-NL02-NL04

.. *.'l* *' "": ..

TABLE 4 .'l. 3 Minimum Frequencies for Checks, Calibrations and Testing of Miscellaneous Instrumentation and Controls (Contd)

Channel DescriEtion Function Frequency Surveillance Method

23. Core Exit Thermoc~uples( )

6

a. Check M a. Comparison of Channels
b. Calibrate (6) b. Known voltage substituted for I thermocouple e.

(6) Only applicable to core thermocouple in core locations H2, G7, J7, JlO, Q4, R7, R8, Nll, Ml3, Xl4, Ql6, Rl7, Bl3, Hl3, Jl6 and Gl7. These thermocouples will be calibrated on a refueling I cycle frequency. I 4-llb Proposed OC1187-0206-NL02-NL04