ML20087P363

Tech Spec Change Request 119 Correcting Typographical Errors Re Scram Discharge Vol Settings

ML20087P363
Person / Time
Site:	Oyster Creek
Issue date:	03/23/1984
From:	GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20087P356	List: ML20087P355 ML20087P363
References
NUDOCS 8404060339
Download: ML20087P363 (6)

Text

O O 3.1-4 isolation, initiate automatic depressurization in conjunction with low-low-low-reactor water level, initiate the standby gas treatment system and isolate the reactor building. The scram function shuts the core down during the loss-of-coolant accidents. A steam leak of about 15 gpm and a liquid leak of about 35 gpm from the primary system will cause drywell pressure to reach the scram point; and, therefore the scram provides protection for breaks greater than the above.

High drywell pressure provides a second means of initiating the core spray to mitigate the consequences of a loss-of-coolant accident. Its set point of 2 psig initiates the core spray in time to provide adequate core cooling. The break-size coverage of high drywell pressure was discussed above. Low-low water level and high drywell pressure in addition to initiating core spray also causes isolation valve closure. These settings are adequate to cause isolation to minimize the offsite dose within required ifmits.

It is permissible to make the drywell pressure instrument channels inoperable during performance of the integrated arimary containment 1eakage rate test provided the reactor is in the cold slutdown condition. The reason for this is that the Engineered Safety Features, which are effective in case of a LOCA under these conditions, will still be effective because they will be activated by low-low reactor water level.

The scram discharge volume has two separate instrument volumes utilized to detect water accumulation. The high water level setting is based on the design that 18.36 gallons (59 inches) of water, detected by either set of level instruments will permit the 137 control rods to scram. To provide further margin, an accumulation of 9 gallons (29 inches) of water detected in either instrument volume will result in a rod block and an alarm, while an accumulation of 3.76 gallons (12.1 inches) of water detected in either instrument volume results in an alarm.

Detailed analyses of transients have shown that sufficient protection is provided by other scrams below 45% power to permit bypassing of the turbine trip and generator load rejection scrams. However, for operational convenience, 40% of rated power has been chosen as the setpoint below which these trips are bypassed. This setpoint is coincident with bypass valve capacity.

A low condenser vacuum scram trip of 23" Hg has been provided to protect the main condenser in the event that vacuum is lost. A loss of condenser vacuum would cause the turbine stop valves to close, resulting in a turbine trip-transient. The low condenser vacuum trip anticipates this transient and scrams the reactor. The condenser is capable of receiving bypass steam until 7" Hg vacuum thereby mitigating the transient.and providing a margin.

8404060339 840323 PDR ADOCK 05000219

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3.1-7

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TABLE 3.1.1 FROTECTIVE INSTRUMENTATION REQUIREMENTS Reactor Modes Min. No. of Min. No.of in which Function Operable or Instrument

. Must Be Operable Operating Channels Per

[ tripped. Operable Action Function Trip' Setting Shutdown Refuel Startup Run- Trip systems Trip Systems Required

• A. Scram Insert control rods

1. Lllanual Scram X X X X 2 1

2. High Reactor ** X(s) X X 2 2 Pressure

3. High Drywell $2psig X(u) X(u) X 2 2 Pressure

4. Low Reactor ** X X X 2 2 Water Level

'5. a. High Water f 18.36 gal. X(a) X(z) X(z) 2 4 Level in Scram Discharge Volume North Side

b. High Water f.18.36 gal. X(a) X(z) X(z) 2 4 Level.in Scram Discharge. Volume South Side

6. Low Condenser- -> 23" hg. X(b) X(b) X 2 2 Vacuum

F et

' ' ~

3.1-7a-s-

~

Reactor Hodes Min. No. of Min.'No.of

-in which Function ' Operable or - Instrumente 20 Must Be Operable Operating- Channels Per-

[ tripped] Operable, Action Function Trip Setting Shutdown Refuel Startup Run Trip systems Trip Systems Required *

17. ;High Radiat'on. i *( 10 x normal ' X(s)' X- X 2 2' Insert

'in Main Steam Fackgromid control rods Line Tunnel 81 Average Power- ** X(c,s) X(c) X(c). 2 3 Rage Monitor-

- ( APM) '

m, 9 .~ Intermediate ** X(d) X(d) 2 3

' -Range Monoitor (IRM).

U~ ~

10. Main Steamline - ** X(b,s) X(b) X 2 4

~' Isolation.:

Valve. Closure-I

11. Turbine Trip '** X(j) 2 4

_ Scram 12.~ Generator Load '** - X(j). 2 2 Rejection Scram w-I'

-Change No,?$.

Amen h nt,No. 44

.g n y _. -,-a -- , _ _ - ,,r, , --_ , - . . - -

1

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3.1-11 '

/)p Reactor Iodes Min. No. of Min. No.of in which Function Operable or Instrument Must Ea Operable Operating Channels Per

[ tripped. Operable Action Function Trip Setting Shutdown Refuel Startup Run Trip systems Trip Systems. Required

• K. Rod Block No control rod with-drawals per-

1. SRf1 Upscale 65 x 105 X X(1) 1 3(y)

2. SRM Downscale 3I00 cps (f) X X(1) 1 3(y)

3. .IRf1 Downscale 25/125 fullscale(g) X X 2 3

4. APRM Upscale ** X(s) X X 2 3(c)

5. april Downscale a2/150 fullscale X 2 3

6. .IRM Upscale 6 108/125 fullscale X X 2 3

7. a) water level. <9 gallons X(z) X(z) X(z) l 1 per high scram instrum, discharge volume volume North b) water level 5 9 gallons. X(z) X(z) X(z) l 1 per high scram instrum.

discharge volume.

~ volume South L. Condenser Vacuum Pump Insert Isolation Control Rods

1. High Radia- :E10 x Normal During Startup and 2 2

-ation in !!ain background Run when vacuum pump 1 Steam Tunnel operating Amendment No. 14, 44, 63

f 3.1-110

-Reactor liedes  !!in. No. of !!in. No.of '

in which Function Operable or Instrument 11ust Be Operable Operating Channels Per

[ tripped. Operable Action Function _ Trip Setting Shutdown Refuel. Startup Run Trip systems Trip Systems Required

• H. Diesel Generator. Tim delay Consider con-Load Sequence Timers after energi- tainment zation of relay spray loop inoperable and comply with Spec.

3.4.C (See

1. Containment 40 sec + 15%

X X X X 2(m) 1(n)

Spray Pump

2. CRD pump 60 sec 1 15% X X X X 2(m) 1(n) Consider the pump inoper-able and comply with Spec. 3.4.D (See Note q)

3. Emerg. Service 45 sec. + 15%

X X X X 2(m) 1(n) Consider the Water Pump (r) loop inoper-able and comply with Spec. 3.4.C (See Note q)

4. Service Water 120 sec. + 15% (SK1A) X X X X 2(o) 2(p) Consider the Pump (aa) 10 sec. E 15% (SK2A) pump inoper-(SK7A) able and (SK8A) comply within 7 days (See Note q)

5. Closed Cooling 166 Sec. i 15% X X X X 2(m) 1(n) Consider the Water Pump (bb) pump inoper-able and comply within 7 days (See Amendment'No. 14, 60 Note q)

4.2-la F. At specific power operation conditions, the actual control rod configuration will be compared with the enected configuration based upon appropriately corrected past data. T11s comparison shall be made every equivalent full power month. The initial rod inventory measurement performed when equilibrium conditions are established after a refueling or major core alteration will be used as base data for reactivity monitoring during subsequent power operation throughout the fuel cycle.

G. At power operating conditions, the actual conrtrol rod density will be compared with the 3.5 percent control rod density included in Specification 3.2.B.6. This comparison shall be made every equivalent full power month.

H. The scram discharge volume drain and vent valves shall be verified open at least once per 31 days, except in shutdown mode *, and shall be cycled at least one complete cycle of full travel at least quarterly.

I. All withdrawn control rods shall be determined OPERABLE by demonstrating the scram discharge volume drain and vent valves OPERABLE. This will be done at least once per refueling cycle by placing the mode switch in shutdown and by verifying that:

a. The drain and vent valves close within 30 seconds after receipt-of a signal for control rods to scram, and

b. The scram signal can be reset and the drain and vent valves open when the scram discharge volume trip is bypassed.

Basis: The core reactivity limitation (Specification 3.2.A) requires that core reactivity be limited such that the core could be made subcritical at any time during the operating cycle, with the strongest operable control rod fully withdrawn and all other operable rods' fully. inserted. Compliance with his requirement can be demonstrated conveniently only at the time of refueling. Therefore, the demonstration must be such that it will apply to the entire subsequent fuel cycle. The demonstration is performed with the reactor in the cold, xenon-free condition and will show that the reactor is sub-critical at that time by at least R + 0.25% a k with the highest worth. operable control rod fully withdrawn.

• These valves may be closed intermittently for testing under administrative control.

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