ML20094B200

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Proposed Tech Spec Changes Re Source Range Neutron Flux Monitors During Shutdown Conditions
ML20094B200
Person / Time
Site: Callaway Ameren icon.png
Issue date: 08/01/1984
From:
UNION ELECTRIC CO.
To:
Shared Package
ML20094B197 List:
References
NUDOCS 8408060287
Download: ML20094B200 (6)
v • d • e


Text

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11g EC

>$ TABLE 3.3-1 ge5O ">

Km 5 REACTOR TRIP SYSTEM INSTRUMENTATION 8*8 s*4 MINIMUM

$$ e TOTAL NO. CHANNFLS CHANNELS APPLICABLE

@@ g FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION -

140 Eg" " "

1. Manual Reactor Trip 2 1 2 1, 2 1 2 1 2 3*,4*,5* 10
2. Power Ratige, Neutoori ilux
d. High Setpoint 4 2 3 1, 2 2#
b. Low Setpoint 4 2 3 l###, 2 2#
3. Power Range Neutron Flux 4 2 3 1, 2 2#

High Positive Rate

4. Power Range, Neutron Flux, 4 2 3 1, 2 2#

High Negative Rate

{ 5. Intermediate Range, Neutron Flux 2 1 2 l###, 2 3

6. Source Range, Neutron Flux a Startup 2 1 2 2## 4
b. Shutdown 2 2 3,4,5 1 5,12 l
7. Overtemperature al
a. Four Loop Operation 4 2 3 1, 2 6#
b. Three Loop Operation ** ^^ ** ** ** -
8. Overpower al
a. Four Loop Operaticn 4 2 3 1, 2 6#
b. Three Loop Operation ** ^^ ** ^^ **

Rp p -

9. Pressurizer Pressure-Low 4 2 3 7:d O 1 6# ggo
10. Pressurizer Pressure-liigh 4 2 3 1, 2 6#

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TA8LE 3.3-1 (Centinuid) Enclosure 1 ULNRC-889 ACTION STATEMENTS (Centinuid} g/1/g4 ACTION 4 - With the nuacer of OPERABLE channels' one less than the Minimum Channels OPERA 8LE requirement, suspend all operations involving positive reactivity changes. The boron dilution flux doubling signals from the source range instrumentation may be blocked

'during reactor startup.

ACTION 5 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the 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 open the Reactor trip breakers, suspend all operations involving positive reactivity changes and verify Valves BG-V178 and BG-V601 are closed and secured in position within the next hour.

ACTION 6 - With the number of OPERABLE channels one less than the Total

. Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:

a. The inoperable channel is placed in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, ard
b. The Minimum Channels OPERABLE requirement is met; however, the inop7 table channel may be bypassed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing of other channels per Specification 4.3.1.1.

ACTION 7 - With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed until performance of the next required ANALOG CHANNEL OPERATIONAL TEST provided the inoperable channel is placed'in the-tri ped?

condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

ACTION 8 - With less than the Minimum Number of Channels OPERABLE, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> determine by observation of the associated permissive annunciator window (s) that the interloc4 is in its required state for the existing plant condition, or apply Specification 3.0.3.

ACTION 9 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, be in at least HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; however, one channel may be bypassed for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for surveillance testing per Specification 4.3.1.1, provided the other channel is OPERABLE.

ACTION 10 - With the number of OPERABLE channels one less tha'n the Minimum Channels OPERABLE requirement, restore the 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 open the Reactor trip breakers within the next hour.

ACTION 11 - With the number of OPERABLE channels less than the Total Number i

of Channels, operation may continue provided the inoperable channels are placed in the tripped condition within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />.

Action 12 - With the number of OPERABLE channels two less than the Minimum Channels requirement, verify the Reactor trip breakers are open, suspend all operations involving positive reactivity changes, verify compliance with the SHUTDOWN MARGIN requirements of Specification 3.1.1.1 or 3.1.1.2, as applicable, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, and verify valves BG-V178 and BG-V601 are closed and secured in position within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.

CALLAWAY - UNIT 1 3/4 3-6

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J Enclosure 2 ULNRC-889 8/1/84 SAFETY EVALUATION Callaway Plant, Unit.1 Technical Specification-Table 3.3-1

, This amendment request is for revision of Technical Specification Table 3.3-1 to include an action statement if two channels of the source range neutron flux monitors are not operable in Modes 3, 4 and 5 and allows the block of both channels of flux doublir.g in Mode 2 in order to

. perform a reactor startup.

Mode 2 Below P-6 p (Table 3.3-1, Item 6.2 requires 2 source range channels to be OPERABLE in

-Mode'2 below P-6.

A statement has been added to Action 4 to allow the block of both source range flux doubling channels in order to'do a normal reactor startup.

Block switches are provided on the main control board to perform this H function. - ' By ~ design, this action disables only the automatic switchover of the charging pump. suction.from the VCT to the RWST. The Reactor Trip and all alarms generated from the source range channels are neither bypassed nor blocked._ Therefcre no reduction in safety margin is

. experienced, and the change is consistent with the safety. analysis as u 1 described,in: Chapter 15 of the FSAR.

Modes 3, 4, 5

! Table 3.3-1, Item 6.b requires 2 source range channels'to be operable

' including the Reactor trip feature'as well as the boron dilution flux

' doubling signal.

If 1' channel of source range becomes inoperable then Action 5, which

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allows 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> to repair, or within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> open the reactor trip breakers, suspend positive reactivity changes, and verify valves BG-V178 and BG-V601

,, are closed and secured in position, would apply. This' action, if carried

'past the 48 hour5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> time limit, would place the plant in the same lineup as in-Mode 6 with only-1 source range OPERABLE and is consistent with Standard Technical Specifications.

(There is currently no action statement for loss of both channels.

The Standard Technical Specifications (STS) allow only 1 source range

,, channel operable in Modes 3, 4, 5 if the Reactor Trip breakers are

>open.- If that channel is lost, SHUTDOWN MARGIN must be verified within 1

hour and then once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter. The Standard Technical Specifications do not.take into account the boron dilution accident.

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Enclosure 2 ULNRC-889 8/1/84

' The real concern for an accident in Mode 3, 4 or 5 with the Reactor Trip breakers open, is the boron dilution accident. In Mode 6, it is deemed appropriate to prevent this accident by iso'ating all sources of dilution. Since the Callaway Technical Specifications currently have no action for loss of both source range channels, the proposed technical specification would place the plant in the same configuration as is required in Mode 6 with loss of both source range channels. Based on tb3 following analysis, this is considered acceptable.

IF both source range channels are lost:

A. Verifying the reactor trip breakers are open prevents positive reactivity additien via the control rods. (i.e., provides

. appropriate compensation for Hi Flux Shutdown Trip)

B.. Suspension of all operations involving positive reactivity changes will ensure the plant is stabilized.

C. Verifying SHUTDOWN MARGIN will ensure the appropriate boron concentration.

D. Verifying the Makeup Water Valves BG-V178 and BG-V601 are closed isolates all sources of dilution (i.e., provides appropriate compensation for the Flux Doubling Valve realignment).

These actions place the plant in a safe-condition consistent with the assumptions for the boron dilution accident analysis contained in Chapter 15 of the FSAR for Modes 3, 4 and 5.

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i Enclosure 3 ULNRC-889 8/1/84 SIGNIFICANT HAZARDS CONSIDERATION Callaway Plant, Unit 1 Technical Specification-Table 3.3-1 This amendment request revises Technical Specification Table 3.3-1 to include an action statement if two channels of the source range neutron flux monitors are not operable in Modes 3, 4 and 5 and allows the block of.both channels of flux doubling in Mode 2 in order to perform a 1eactor startup.

' The Commission has provided guidance concerning the application of the standards in 10 CFR 50.92 by providing certain examples (48FR14870).

. This amendment request is similar to the exaeple of an administrative change to technical specifications for correction of an error. In this case the Technical Specifications are not consistent with the plant design and would not allow plant startup.

This amendment request does not involve a significant increase in the

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probability or consequences of an accident or other adverse condition over previous evaluations; nor create the possibility of a new or different kind of accident or condition over previous evaluations; nor

. . involve a significant reduction in a margin of safety. Based on the foregoing,' the requested amendment does not present a significant hazard.

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Enclosure 4 ULNRC-889 8/1/84 ENVIRONMENTAL ASSESSMENT Callaway Plant Unit 1 Technical Specification - Table 3.3-1 This amendment request revises Technical Specification Table 3.3-1 to include an action statement if two channels of the source range neutron flux. monitors are not' operable in Modes 3, 4, and 5 and allows the block

- of both channels of flux doubling in Mode 2 in order to perform a

. reactor startup.

In accordance with 10 CFR 51.30, an environmental assessment has been performed. . This amendment request does not involve a significant

. increase in the probability or consequences of an accident or other adverse condition over previous evaluations; nor create the possibility of a new or different kind of accident or condition over previous evaluations; nor does_it pose any adverse environmental effects. This amendment has been discussed with Ron Kucera, Deputy Director, Missouri Department of Natural Resources. Based on the foregoing, the requested amendment poses no significant impact on the environment.

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