Text

Safety Evaluation Accepting Licensee 831108 & 850905 Responses to Generic Ltr 83-28,Items 4.1,4.2.1 & 4.2.2 Re Reactor Trip Sys Reliability.Related Info,Including Draft Tech Specs,Encl
	ML20214J716
Person / Time
Site:	Millstone
Issue date:	11/19/1986
From:	; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20214J608	List: ML20214J605; ML20214J655; ML20214J683; ML20214J712; ML20214J716;
References
	GL-83-28, NUDOCS 8612010408
	Download: ML20214J716 (18)
	v • d • e

. . . - . - - .

SAFETY EVALUATION REPORT MILLSTONE NUCLEAR POWER STATION, UNIT 3 REACTOR TRIP SYSTEM RELIABILITY ITEMS 4.1, 4.2.1 AND 4.2.2 0F GENERIC LETTER 83-28

1.

Introduction:

On July 8, 1983, the Nuclear Regulatory Commission (NRC) issued Generic Letter (GL) 83-28. This letter addressed intermediate-term actions to be taken by licensees and applicants aimed at assuring that a comprehensive program of preventive maintenance and surveillance testing is implemented for the reactor trip breakers (RTBs) in pressurized water reactors. In particular, Item 4.1 of the letter required licensees and applicants to verify that all vendor recomended reactor trip breaker modifications have been implemented. Item 4.2 required them to submit a description of their preventive maintenance and surveillance program to ensure reliable reactor trip breaker operation. The description of the submitted program was to include the following:

GL, Item 4.1 Peview of all vendor-recommended reactor trip breaker modifications to verify that either: each modification has, in fact, been implemented, or a written evaluation of the technical reasons for not implementing a modification exists.

GL, Iten 4.2.1 A planned program of periodic maintenance, including lubrication, housekeeping, and other items recommended by the equipment supplier.

GL, Item 4.2.2 Trending of parameters affecting operation and measured '

during testing to forecist degradation of operation.

l 8612010408 861119 PDR ADOCK 05000423 l P PDR l l

Northeast Utilities, the licensee for Millstone 3, responded to the Generic Letter on November 8,1983, September 5,1985. This report presents an evaluation of the adequacy of the licensee's responses and of his preventive maintenance and surveillance programs for RTBs.

2. EVALUATION CRITERIA 2.1 Periodic Maintenance Program The primary source for periodic maintenance program criteria is Westing-house Maintenance Program Manual for DS-416 Reactor Trip Circuit Breakers, Rev. O. This document was prepared for the Westinghouse Owners Group and is the breaker manufacturer's recommended maintenance program for the DS-416 breaker. It provides specific direction with regard to schedule, inspection and testing, cleaning, lubricaticn, corrective maintenance and record keeping.

The document was reviewed to identify those items that contribute to breaker trip reliability consistent with the generic letter. Those items identified for maintenance at six month intervals (or when 500 b'reaker operations have been counted, whichever comes first) that should be included in the licensee's RTB maintenance program are:

1. General inspection to include checking of breaker's cleanliness, all bolts and nuts, pole bases, arc chutes, insulating link, wiring and auxiliary switches;

2. Retaining rings inspection, inciur ;.7 '. .se on the undervoltage trip attachment (UVTAI;

3. Arcing and main contacts inspection as specified by the Westing-house Mafi.tenance Manual; l

l

I 4 UVTA check as specified by the Westinghouse Maintenance Manual, including replacement of UVTA f f dropout voltage is greater than 60% or less than 30% of rated UVTA coil voltage;

5. Shunt Trip Attachment (STA) check as specified by the Westinghouse Maintenance Manual;

6. Lubrication as specified by the Westinghouse Maintenance Manual;

7. Functional check of the breaker's operation prinr to returning it to service.

The licensee's RTB periodic maintenance should also include, on a refueling interval basis:

1. Pre-cleaning insulation resistance measurement and recording;

2. RTB dusting and cleaning;

3. Post-cleaning insulation resistance measurement and recording, as specified by the Westinghouse Maintenance Manual; 4 Inspection of main and secondary disconnecting contacts, bolt tightness, secondary wiring, mechanical parts, cell switches, instruments, relays and other panel mounted devices;

5. UVTA trip force and breaker load check as specified by the Westing-house Maintenance Manual;

l l

l

6. Measurement and recording of RTB response time for the undervoltage trip; 4

7. Functional test of the breaker prior to returning to service as specified by the Westinghouse Maintenance Manual.

2.2 Trending of Parameters Generic Letter Item 4.2.2 specifies that the licensee's preventative maintenance and surveillance program is to include trending of parameters affecting operation to forecast degradation of operation. The parameters measured during the maintenance program described above which are applicable for trending are undervoltage trip attachment dropout voltage, trip force, response time for undervoltage trip and breaker insulation resistance. The staff position is that the above parameters are acceptable trending parameters to forecast breaker operation degradation or failure. If subsequent experience indicates that any of these parameters is not useful as a tool to anticipate failures or degradation, the licensee may, with justification and NRC approval, elect to remove that parameter from those to be tracked.

3. Evaluation:

3.1 Evaluation of the Licensee's Position on Item 4.1 The licensee has comfirmed that all vendor-recommended modifications have been completed. The staff finds the licensee position on Item 4.1 to be acceptable.

o .

3.2 Evaluation of the Licensee's Position on Item 4.2.1 The licensee has confirmed that his periodic maintenance program will include those items listed in Section 2.1 of this SER at the specified frequency. The staff finds the licensee position on Item 4.P.1 to be acceptable.

3.3 Evaluation of the Licensee's Position on Item 4.2.2 The licensee has stated that Millstone 3 will perform trend analysis on UVTA dropout voltage and breaker response time, and will record trip force and breaker insulation resistance. The licensee has identified the organization which will perform trend analysis, how often it will be performed and how the information derived from the analysis will be used to affect periodic maintenance. The staff finds the licensee position on Item 4.2.2 to be acceptable.

4

Conclusions:

Based on a review of the licensee responses, the staff finds the licensee's position on Items 4.1, 4.2.1 and 4.2.2 of Generic Letter 83-28 to be acceptable.

TECHNICAI. SPECIFICATIONS, GENERIC LETTER 83-28 ITEM 4.3. T.S (MPA B-90) AND GENERIC LETTER 85-09 MILLSTONE NUCl. EAR POWER STATION, UNIT 3 The staff recently reviewed a copy of Table 3.3-1 of the Millstone Unit 3 Technical Specifications and noticed a discrepancy as compared to Generic letter 85-09 and to the Westinghouse Standard Technical Specifications. Table 3.3-1 for Millstone 3 contains a Functional Unit 21 (Reactor Trip Bypass Breakers) with action statements 10 and 11 calling for (in addition to other actions) bypassing of the channel for surveillance testing and opening of the reactor trip breakers. Action statement 10 and 11 are appropriate for the reactor trip breakers, but not for the reactor trip bypass breakers.

Since this existing Technical Specification is inapplicable, we could only speculate on its health and safety risk. Presumably, a licensee would not try to implement such inapplicable actions. In any event, we believe that Functional Unit 21 (Reactor Trip Bypass Breakers) of Table 3.3-1 for Millstone 3 should either be removed, consistent with Generic l.etter 85-09 and the Westinghouse Standard Technical Specifications or modified similar to Functional Unit 22 (Reactor Trip Bypass Breakers _ of Table 3.3-1 of the Shearon Parris Final Draft (applicable pages enclosed).

1 l

. TABLE 3.3-1 (Continued) 9 REACTOR TRIP SYSTEM INSTRUMENTATION 8

MINIMUM

@ TOTAL NO. CHANNELS CHANNELS APPLICABLE E FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION

20. Reactor Trip Breakers 2 1 2 1, 2 8, 11 e 2 'l 2 3*., 4*, 5* 9 i'i

21. Automatic Trip and Interlock 2 1 2 1, 2 8

Logic 2 1 2 3*,4*,5* 9

22. Reactor Trip Bypass Breakers 2 1 1 ** 12 Y

w

FINAL HAFT TABLE 3.3-1 (Continued)

TABLE NOTATIONS

When the Reactor Trip System breakers are closed and the Control Rod Drive System is capable of rod withdrawal.

- Whenever Reactor Trip Breakers are to be tested.

The provisions of Specification 3.0.4 are not applicable.

1. Below the P-6 (Intermediate riange Neutron Flux Interlock) Setpoint.

1. 1. Below the P-10 (Low Setpoint Power Range Neutron Flux Interlock) Setpoint.

(1)The applicable MODES and ACTION statement for these channels noted in Table 3.3-3 are more restrictive and, therefore, applicable.

ACTION STATEMENTS ACTION 1 - With the number of OPERABLE channels one less than the Minimum C'hannels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . .

ACTION 2 - 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 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ,

b. The Minimum Channels OPERABLE requirement is met; however, the inoperable channel may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing of other channels per Specification 4.3.1.1, and

c. Either, THERMAL POWER is restricted to less than or equal to 75% of RATED THERMAL POWER and the Power Range Neutron Flux Trip Setpoint is reduced to less than or equal to 85% of RATED THERMAL POWER within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; or, the QUADRANT POWER TILT RATIO is monitored at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months per Specification 4.2.4.2.

l 1

SHEARON HARRIS - UNIT 1 3/4 3-6 l

l

FINAL HAFT l TABLE 3.3-1 (Continued)

ACTION STATEMENTS (Continued)

ACTION 8 - With the number of OPERABLE channels one less than the Minimum j Channels OPERABLE requirement, be in at least HOT STANDBY within ;

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; however, one channel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months i for surveillance testing per Specification 4.3.1.1, provided the other channel is OPERABLE.

\

I ACTION 9 - 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 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or open the Reactor Trip System breakers within the next hour.

ACTION 10 - With the number of OPERABLE channels less than the Total Number ,

of Channels, operation may continue provided the inoperable j channels are placed in the tripped condition within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

ACTION 11 - With one of the diverse trip features (undervoltage or shunt trip attachment) inoperable, restore it to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or declare the breaker inoperable and apply ACTION 8. The breaker shall not be bypassed while one of the diverse trip features is inoperable except for the time required fo'r performing maintenance to restore the breaker to-OPERABLE status.

ACTION 12 - No additional corrective actions are required.

SHEARON HARRIS - UNIT 1 3/4 3-8

~-

~

TABLE 3.3-1 (Continued)

REACTOR TRIP SYSTEM INSTRUMENTATION vs U MINIMUM M TOTAL NO. CHANNELS CHANNELS APPLICABLE i FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION

17. Reactor Trip System Interlocks (Continued)

c. Power Range Neutron ,

Flux, P-8 4 2 3 1 8

d. Power Range Neutron 4 2 3 1 8 Flux, P-9

e. Power Range Neutron Flux, P-10 4 2 3 1,2 8 Y

18. Reactor Trip Breakers 2 1 2 1, 2 10, 13 T 2 1 2 3*, 4*, 5* 11 a

19. Automatic Trip and Interlock 2 1 2 1, 2 10 Logic 2 1 2 3*, 4* , 5* 11

20. Three Loop Operation 8 2 8 1, 2 1 Bypass Circuitry (1 switch per (From differ-loop in each ent loop train) switches in bypass)

21. Reactor Trip Bypass 2 1 2 1, 2 10 2

Breakers 2 1 2 3*, 4*, 5* 11 /

Oa., -

. o, TABLE 3.3-1 (Continued)

TABLE NOTATIONS

When the Reactor Trip System breakers are in the closed position and the Control Rod Drive System is capable of rod withdrawal.

- Above the P-7 (At Power) Setpoint.

- - Above the P-9 (Reactor Trip / Turbine Trip Interlock) Setpoint.

The provisions of Specification 3.0.4 are not applicable.

8elow the P-6 (Intermediate Range Neutron Flux Interlock) Setpoint.

NBelow the P-10 (Low Setpoint Power Range Neutron Flux Interlock) Setpoint.

(1) The applicable MODES and ACTION statements for these channels noted in Table 3.3-3 are more restrictive and, therefore, applicable. >

ACTION STATEMENTS ACTION 1 - 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 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

1 ACTION 2 - With the number of OPERABLE channels one less than the Total W 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 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ,

b. The Minimum Channels OPERABLE requirement is met; however, the inoperable channel may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing of other channels per Specification 4.3.1.1, and

c. Either, THERMAL POWER is restricted to less than or equal to 75% of RATED THERMAL POWER for four loop operation or 50% of RATED THERMAL POWER for three loop operation and the Power Range Neutron Flux Trip Setpoint is reduced to less than or equal to 85% of RATED THERMAL POWER for four loop operation or 60% of RATED THERMAL POWER for three loop operation within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; or, the QUADRANT POWER TILT RATIO is monitored at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months per Specification 4.2.4.2.

MILLSTONE - UNIT 3 3/4 3-5

TABLE 3.3-1 (Crntinued)

ACTION STATEMEN'TS (Continued)

ACTION 9 - With a channel associated with an operating loop inoperable, restore the inoperable channel to OPERABLE status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . One channel associated with an operating loop may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing per Specification 4.3.1.1.

ACTION 10 - With the number of OPERABLE channels one less than the Mininum Channels OPERABLE requirement, be in at least HOT STANDBY withir.'6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; however, one channel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing per Specification 4.3.1.1, provided the other channel is OPERABLE.

ACTION 11 - 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 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or open the Reactor Trip System breakers within the next hour.

ACTION 12 - 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 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and 4

6/ b. When the Minimum Channels OPERABLE requirement is met, the inoperable channel may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing of the Turbine Control Valves.

ACTION 13 - With one of the diverse trip features (undervoltage or shunt trip attachments) inoperable, restore it to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or declare the breaker inoperable and apply ACTION 10. The breaker shall not be bypassed while one of the diverse trip features is inoperable except for the time required for performing maintenance to restore the breaker to OPERABLE status.

l l

MILLSTONE - UNIT 3 3/4 3-7

~

.A s

. TABLE 3.3-1 (Continued)

E l g REACTOR TRIP SYSTEM INSTRUMENTATION I E z MINIMUM i TOTAL NO. CHANNELS CHANNELS APPLICABLE E

~

FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION I

, Y 20. Reactor Trip Breakers 2 1 2 1, 2 8, 11 I e 2 -1 2 3*., 4*, 5* 9 5

" 21. Automatic Trip and Interlock 2 1 2 1, 2 8

Logic 2 1 2 3 * , 4 * , 5* 9

22. Reactor Trip Bypass Breakers 2 1 1 ** 12 Y.

u

.==,

~

~~

FINAL HAFT TABLE 3.3-1 (Continued)

TABLE NOTATIONS

When the Reactor Trip System breakers are closed and the Control Rod Drive System is capable of rod withdrawal.

- Whenever Reactor Trip Breakers are to be tested.

The provisions of Specification 3.0.4 are not applicable.

1. Below the P-6 (Intermediate Range Neutron Flux Interlock) Setpoint.

1. 1. Below the P-10 (Low Setpoint Power Range Neutron Flux Interlock) Setpoint.

(1)The applicable MODES and ACTION statement for these channels noted in Table 3.3-3 are more restrictive and, therefore, applicable.

ACTION STATEMENTS ACTION 1 - With the number of OPERABLE channels one less than the Minimum C'hannels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . .

ACTION 2 - With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/o'r POWER OPERATION may proceed provided the following conditions are satisfied:

a. The inoperable channel is placed in the tripped condition within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ,

b. The Minimum Channels OPERABLE requirement is met; however, the inoperable channel may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing of other channels per Specification 4.3.1.1, and

c. Either, THERMAL POWER is restricted to less than or equal to 75% of RATED THERMAL POWER and the Power Range Neutron Flux Trip Setpoint is reduced to less than or equal to 85% of RATED THERMAL POWER within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; or, the QUADRANT POWER TILT RATIO is monitored at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months per Specification 4.2.4.2.

SHEARON HARRIS - UNIT 1 3/4 3-6

e FINALDRAFT

, TABLE 3.3-1 (Continued)

ACTION STATEMENTS (Continued)

ACTION 8 - 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 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; however, one channel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing per Specification 4.3.1.1, provided the other channel is OPERABLE. i 1

ACTION 9 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to l OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or open the Reactor Trip System ;

breakers within the next hour. 1 ACTION 10 - With the number of OPERABLE channels less than the Total Number of Channels, operation may continue provided the inoperable

, channels are placed in the tripped condition within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

l ACTION 11 - With one of the diverse trip features (undervoltage or shunt trip attachment) inoperable, restore it to OPERABLE status ;

within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or declare the breaker inoperable and apply ACTION 8. The breaker shall not be bypassed while one of the diverse trip features is inoperable except for the time required fo'r performing maintenance to restore the breaker to OPERABLE status.

ACTION 12 - No additional corrective actions are required.

1 i

i k

i SHEARON HARRIS - UNIT 1 3/4 3-8

s

' f TABLE 3.3-1 (Continued) l 3

r-REACTOR TRIP SYSTEM INSTRUMENTATION G

-.4 o

MINIMUM

$ TOTAL NO. CHANNELS CHANNELS APPLICABLE e FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION

17. Reactor Trip System Interlocks (Continued)

c. Power Range Neutron

~

Flux, P-8 4 2 3

, i 8

d. Power Range Neutron 4 2 3 1 8 Flux, P-9 L

3

e. Power Range Neutron Flux, P-10 4 2 3 1,2 8 I T 4 18. Reactor Trip Breakers 2 1 2 1, 2 10, 13 T

= 2 1 2 3*, 4*, 5* 11

19. Automatic Trip and. Interlock 2 1 2 1, 2 10 Logic 2 1 2 3*, 4*, 5* 11

20. Three Loop Operation 8 2 8 1, 2 1 j Bypass Circuitry (1 switch per (From differ-

loop in each ent loop j

train) switches in bypass) l 21. Reactor Trip Bypass 2 1 2 1, 2 2 10

! Breakers 2 1 2 3* , 4* , 5*

! 11 /

j t 1

'l t

a ,

TA8LE 3.3-1 (Continued) t !

TA8LE NOTATIONS

When the Reactor Trip System breakers are in the closed position and the Control Rod Drive System is capable of rod withdrawal.

- Above the P-7 (At Power) Setpoint.

- - Above the P-9 (Reactor Trip / Turbine Trip Interlock) Setpoint.

The provisions of Specification 3.0.4 are not applicable.

1. 8elow the P-6 (Intermediate Range Neutron Flux Interlock) Setpoint.

ff#8elow the P-10 (Low Setpoint Power Range Neutron Flux Interlock) Setpoint.

(1) The applicable MODES and ACTION statements for these channels noted in

- Table 3.3-3 are more restrictive and, therefore, applicable.

ACTION STATEMENTS ACTION 1 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to CPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

2'l ACTION 2 - With the number of OPERABLE channels one less than the Total

'GF" 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 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ,

b. The Minimum Channels OPERABLE requirement is met; however, the inoperable channel may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing of other channels per Specification l

4.3.1.1, and

c. Either, THERMAL POWER is restricted to less than or equal to 75% of RATED THERMAL POWER for four loop operation or 50% of RATED THERMAL POWER for three loop operation and

the Power Range Neutron Flux Trip Setpoint is reduced to less than or equal to 85% of RATED THERMAL POWER for four loop operation or 60% of RATED THERMAL POWER for three l loop operation within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; or, the QUADRANT POWER TILT i RATIO is monitored at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months per J

Specification 4.2.4.2.

i l

l i

l MILLSTONE - UNIT 3 3/4 3-5

TABLE 3.3-1 (C*ntinued)

. l ACTION STATEMENTS (Continued)

' i ACTION 9 - With a channel associated with an operating loop inoperable, restore the inoperable channel to OPERABLE status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months i or be in at least HOT STAND 8Y within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . One channel associated with an operating loop may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing per Specification 4.3.1.1.

ACTION 10 - With the nu er of OPERA 8LE channels one less than the Minimum Channels OPERABLE requirement, be in at least HOT STANDBY within'6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; however, one channel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing per Specification 4.3.1.1, provided the other channel is OPERA 8LE.

ACTION 11 - With the number of CPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or open the Reactor Trip System breakers within the next hour.

ACTION 12 - With the number of OPERABLE channels one less than the Total i 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 m, within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and

\

/ b. When the Minimum Channels OPERABLE requirement is met, the inoperable channel may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing of the Turbine Control Valves.

ACTION 13 - With one of the diverse trip features (undervoltage or shunt trip attachments) inoperable, restore it to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or declare the breaker inoperable and apply ACTION 10. The breaker shall not be bypassed while one of the diverse trip features is inoperable except for the time required for performing maintenance to restore the breaker to OPERABLE status.

h MILLSTONE - UNIT 3 3/4 3-7

- - - _ - - _ _ - _ - _ _ . _ - _ _ _ - _ - - - _ _ _ _ _ _ .

ML20214J716

Text

Introduction:

Conclusions:

Navigation menu

Search