ML19317D218

Proposed Changes to Tech Specs 2.3 & 4.1-2 Re Reactor Protective Sys Trip Setting Limits & Min Equipment Test Frequency

ML19317D218
Person / Time
Site:	Oconee
Issue date:	09/14/1977
From:	DUKE POWER CO.
To:
Shared Package
ML19317D215	List: ML19317D214 ML19317D218
References
NUDOCS 7911190607
Download: ML19317D218 (5)

Text

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• 2.3 LIMITING SAFE.). SYSTEM SETTINGS, PROTECTIVE . .aTRUMENTATION

' Appi1cobility

({} ,

Applies to instruments monitoring reactor power, reactor power imbalance, reactor coolant system pressure, reactor coolant outlet temperature, flow, number of pumps in operation, and high reactor building pressure.

Objective To provide automatic protective action to prevent any combination of process variables from exceeding a safety limit.

Specification The reactor protective system trip setting limits and the permissible bypasses for the instrument channels shall be as stated in Table 2.3.lA-Unit 1 and 2.3-13-Unit 2 2.3-lC-Unit 3 Figure 2.3-2A-Unit 1 2.3-2B-Unit 2 2.3-2C-Unit 3 The pump monitors shall produce a reactor trip for the following conditions:

a. Loss of one pump during four-pump operation if power level is greater than 80% of rated power

b. Loss of two pumps and reactor power level is greater than 55% of rated power. (Power /RC pump trip setpoint is reset to 55% for operation with

~

one pump in each loop).

c. Loss of two pumps in one reactor coolant loop and reactor power level is greater than 0.0% of rated power.

d. Less of one or two pumps during two-pump operation.

l Bases The reactor protective system consists of four instrument channels to monitor each of several selected plant conditions which will cause a reactor trip if any one of these conditions deviates from a pre-selected operating range to the degree that a safety limit may be reached.

The trip setting limits for protective system instrumentation are listed in Table 2.3-1A-Unit 1. The safety analysis has been based upon these protective 2.3-13-Unit 2

( 2.3-lC-Unic 3 l system instrumentation trip setpoints plus calibration and instrumentation errors.

Nuclear Overcover A reactor trip at high power level (neutron flux) is provided to prevent damage to the fuel cladding frem reactivity excursions too rapid to be detected by pressure and temperature measurements.

l 2.3-1 4911190bO7

Table 2.3-1A Unit 1 Beactor rotective System Trip Settina Limits Two Reactor One Reactor Four Reactor Three Reactor Coolant Pumps Coolant Pump Coolant Pumps Coolant Pumps Operating in A Operating la Operating Operating Single Loop Each Loop (Operating Power (Operating Power (Operating Power (Operating Power Shutdown RPS Segment -1001 Rated) -75Z Rated) -461 Rated) -49Z Rated) Bypses

1. Nuclear Power Ham. 105.5 105.5 105.5 105.5 5.0(3)

(1 Rated) )

1.055 times flow l.055 t imes flow 0.949 times flow I.055 times flow Bypassed

2. Nuclear Power Ham. Based on Flow (2) and Imbalance, micus reduction minus reduction minus reduction minus reduction (I Rated) due to imbalsace due to imbalance due to imbalance due to imbalance

3. Nuclear Power Ham. Eased NA 80% 55x (5)(6) 55r (5) Bypassed on Pump Honitors. (I, Rated)

4. tilgh React or Coolant 2355 2355 2355 2355 1720(*)

System Pressure, psig, Ham.

n

5. Low Reactor Coolant 1800 1800 1800 1800 Bypassed i h p System Pressure, pais, Min.

6. Variable Low Neactor ( l l .14 T,, 4704g III ( l l .14 Tout - 4706 )( } (11.14 Tout- 4706)(l} (11.14 T out - 4706 )( BTPassed Coolent System Pressure peig, Hin.

619 619 61S (6) 619 619 s

7. Reactor Coolant Temp.

F., Han. )

4 4

• 4 4 4

8. High Beactor Building Pressure, pels. Ham.

(1) is in degrees Fahrenheit ("F). (5) Beactor power level trip set point produced

' T*"" by pump contact monitor reset to 55.01.

(2) Reactor Coolant System Flow, 1.

(6) Specification 3.1.8 applies. Trip one of the (1) Administrative 1y controlled reduction set two protection channels receiving outlet temper-only during reactor shutdown. ature information from sensors in the idle loop.

(4) Automatically set when other segments of the RPS are bypassed. ,

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Table 2.3-1B Unit 2 Beactor Protective System Trip Settina Limits Two Reactor One Reactor Four Reactor Three Reactor Coolant Pumps Coolant Pump Coolant Pumps Coolant Pumps Operating in A Operating in Operating Operating Single Loop Each Loop (Cr rating Power (Operating Power (Operating Power (Operating Shutdown RPS segment -100% Rated) -75% Rated) -46% Rated) -49% Rated) Bypass

1. Nuclear Power Max. 105.5 105.5 105.5 105.5 5.0 I3I (I Rated)

2. Nuclear Power Max. Based 1.055 times flow 1.055 times flow 0.949 times flow 1.055 times flow . Bypassed \-s on Flow (2) and labalance, minus reduction af nus reduction minus reduction . minus reduction (I Rated) due to imbalance ' due to imbalance due to imbalance due to imbalance *

3. Nuclear Power Max. Based NA 80% 55% (5) (6) 552 sypass 3 on lump Honitors, (I Rated) l

4. High Reactor Coolant 2355 2355 2355 2355 1720I '}

System Pressure, psig. Max.

5. Low Reactor Coolant 1800 1800 1800 1800 Bypassed System Preasure, peig, Min.

6. Variable Low Reactor (11.14 T" -4706)III (11.14 7"-4706)III (11.14 7" -4706)III (11.14 7" -4706)II) Bypassed

!* Coolant System Pressure y psig. Min.

m

7. Reactor Coolant Temp. 619 619 619 (6) 619 619 F., Max.

B. High Reactor Building 4 4 4 4 4 )

Pressure, psig. Max, '~'

,- (I) T """ in in degtees Fahrenheit ( F). (5) Reactor power level trip set point produced by pump contact monitor reset to 55.01.

(2) Reactor Coolant System Flow, 1. *

(6) Specification 3.1.8 applies. Trip one of the (3) Administratively controlled reduction set two protection channels receiving outlet only during reactor shutdown. temperature information from sensors in the J.(4) Automatically set when other segments of

• the RPS are bypassed.

Tsble 2.3-lC Unit 3 ,

Reactor Protective System Trip Setting Limits ,

One Reactor Four Reactor Three Reactor Coolant Pump Coolant Pumps Coolant Pumps Operating in Operating Operating Each Loop (Operating Power (Operating Power (Operating Shutdown RPS Segment -100% Rated) -75% Rated) -49% Rated) Bypass

1. Nuclear Power Max. 105.5 105.5 105.5 5.0( } .

(% Rated)

. 2. Nuclear Power Max. Based 1.055 times flow 1.055 times flow 1.055 times flow Bypassed on Flow (2) and Imbalance, minus reduction minus reduction minua reduction

(% Rated) due to imb.alance due to imbalance due to imbalance i", 3. Nuclear Power Max. Based NA 80% 55% Bypassed y on Pump Monitors, (% Rated)

4. liigh Reactor Coolant 2355 2355 2355 1720 I4)

System Pressure, psig, Max.

5. Low Reactor Coolant 1800 1800 1800 Bypassed System Pressure, psig, Min.

} -4706)I ) Bypassed

6. Variable Lou Reactor (11.14 T "

-4706)( }(11.14 T -" 4706) (11.14 T "

Coolant Svatem Pressure ']

psig, Min'. ' -

7. Reactor Coolant Temp. 619 619 619 619 F . , Ma x . .

4 4 4 4

8. liigh Reactor Building Pressure, psig, Max.

l (1) T is in degrees Fahrenheit ( F).

(2) RSNetor Coolant System Flow, %.

(3) Administrative 1y controlled reduction set I only during reactor shutdown.

(4) Automatically set when other segments of I the RPS are bypassed.

Tcbic 4.1-2

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... MINIMLH EQUIPMENT TEST FREQUENCY

. Item Test Frequency

1. Control Rod Movement ( } Movement of Each Rod Bi-Weekly

2. Pressurizer Safety Valves Setpoint 50% Annually

, 3. Main Steam Safety Valves Setpoint 25% Annually

4. Refueling System Interlocks Functional Prior to Refueling

5. Main Steam Stop Valves (1) Movement of Each Stop Monthly Valve

6. Reactor Coolant System ( Evaluate Daily Leakage

7. Condenser Cooling Water Functional Annually Sy: tem Gravity Flow Test

8. High Pressure Service Functional Monthly Water Pumps and Power Supplies

9. Spent Fuel Cooling System Functional Prior to Refueling

10. HydraulicSn[bberson Visual Inspection Annually Safety-Related Systems

11. High Pressure and Low ( } Vent Pump Casings Monthly and Prior Pressure Injection System to Testing (1) Applicable only when the reactor is critical

(2) Applicable only when the reactor coolant is above 200 F and at a steady-l state temperature and pressure.

l

! (3) Operating pumps excluded.

i i

l 4.1-9 i

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