ML20065C766

Amend 185 to License NPF-3,revising TS 3/4.3.1,RPS Instrumentation & TS 3/4.3.2.3. ARTS Instrumentation

ML20065C766
Person / Time
Site:	Davis Besse
Issue date:	03/28/1994
From:	West G Office of Nuclear Reactor Regulation
To:
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ML20065C768	List: ML20065C766 ML20065C779
References
NUDOCS 9404060024
Download: ML20065C766 (8)

Text

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UNITED STATES

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E NUCLEAR REGULATORY COMMISSION 3-

~f WASHINGTON, D.C. 20666-0001

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TOLEDO EDISON COMPANY CENTERIOR SERVICE COMPANY 8!E THE CLEVELAND ELECTRIC ILLUMINATING COMPANY DOCKET NO. 50-346 DAVIS $ESSENUCLEARPOWERSTATION.UNITNO.1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.185 License No. NPF-3

-1.

The Nuclear Regulatory Commission (the Comission) has found that:

A.

The application for amendment by the Toledo Edison Company, Centerior Service Company, and the Cleveland Electric Illuminating Company (the licensees) dated November 13, 1992, as supplemented on July 15 and November 10, 1993, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.

The issuance of this amendment will not be inimical to the common defense ano security or to the health and safety of the putilic; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-3 is hereby amended to read as follows:

9404060024 940328 DR ADOCK 050003 6

. l (a) Technical Specifications l

The Technical Specifications contained in Appendix A, as revised through Amendment No.185, are hereby incorporated in the license.

The Toledo Edison Company shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of its date of issuance and shall be implemented not later than 90 days after issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

& 6 4,yrt o w N A Garmon West, Asst. Project Manager Project Directorate III-3 I

Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation i

Attachment:

Changes to the Technical Specifications Date of issuance:

March 28, 1994 l

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ATTACHMENT TO LICENSE AMENDMENT NO.185 FACILITY OPERATING LICENSE NO. NPF-3 i

DOCKET N0. 50-346 Replace the following pages of the Appendix "A" Technical Specifications with the attached pages. The revised pages are identified by amendment number and l

contain vertical lines indicating the area of change. The corresponding overleaf pages are also provided to maintain document completeness.

Remove Insert i

3/4 3-2 3/4 3-2 3/4 3-3 3/4 3-3 3/4 3-4 3/4 3-4 3/4 3-Sa 3/4 3-Sa 3/4 3-7 3/4 3-7 3/4 3-8 3/4 3-8 3/4.30c 3/4 3-30c 3/4 3-30d 3/4 3-30d i

l

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3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PRO) SiON SYSTEM INSTRUMENTATION r

LIMITING CONDITICs F2d OPERATION 3.3.1.1 As a minimum, the Reactor Pro'.ection System instrumentation channels and bypasses of Table 3.3-1 shall be OPERABLE with RESPONSE TIMES as shown in Table 3.3-2.

APPLICABILITY: As shown in Table 3.3-1.

ACTION:

As shown in Table 3.3-1.

SURVEILLANCE REQUIREMENTS s 4.3.1.1.1 Each Reactor Protection System instrumentation channel shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations during the MODES and at the frequencies shown in Table 4.3-1.

1

4. 3.1.1. 2 The total bypass function shall be demonstrated OPERABLE at least once per 18 months during CHANNEL CAllBRATION testing of each channel affected by bypass operation.

4. 3.1.1.'3 The REACTOR PROTECTION SYSTEM RESPONSE TIME of each reactor trip function shall be demonstrated to be within its limit at least once per 18 months. Each test shall include at least one channel per function such that all channels are tested at least once every N tines 18 months where N is the total number of redundant channels in a specific reactor trip function as shown in the " Total No. of Channels" column of Table 3.3-1.

DAVIS-BESSE, UNIT 1 3/4 3-1

TABLE 3.3-1 REACTOR PROTECTION SYSTEM INSTRUMENTATION E$

MINIMUM m

TOTAL NO.

CHANNELS CHANNELS APPLICABLE g

FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION w

1.

Manual. Reactor Trip 2

1 2

1, 2 and

• 1 2.

High Flux-4 2

3 1, 2 2f, 10 3.

RC High Temperature 4

2 3

1, 2 3#, 10 4.

Flux - AFlux - Flow 4

2(a)(b) 3 1, 2 2#, 10 5.

RC Low Pressure 4

2(a) 3 1, 2 3#, 10 6.

RC High Pressure 4

2 3

1, 2 3#, 10 7.

RC Pressure-Temperature 4

2(a)-

3 1, 2 3#, 10 Y

8.

High Flux / Number of Reactor Coolant Pumps On A

2(a)(b) 3 1, 2 3#, 10 9.

Containment High Pressure-4 2

3 1, 2 3#, 10 10.

Intermediate Range, Neutron Flux and Rate 2

N/A 2(c) 1, 2 and

• 4 y

11.

Source Range, Neutron Flux and Rate g

A.

Startup 2

N/A 2

2ff and

• 5 g.

B.

Shutdown 2

N/A 1

3, 4 and 5.

6 e5

12. Control Rod Drive Trip Breakers 2 per trip 1 per trip 2 per 1, 2 and

• 7#, 8f g

system system trip system 13.

Reactor Trip Module 2 per trip 1 per trip.

2 per 1, 2 and

• 7#

L system system trip. system M

8 14.

Shutdown Bypass High Pressure 4

2 3

2**, 3 **

6#

-4**, 5**

15.

SCR Relays 2

2 2

1, 2 and

• 9#

i i

l*

~

l TABLE 3.3-1 (Continued) l TABLE NOTATION

• With the control rod drive trip breakers in the closed position and the control rod drive system capable of rod withdrawal.

• • When Shutdown Bypass is actuated.

1. The provisions of Specification 3.0.4 are not applicable.

l l

M High voltage to detector may be de-energized above 10'" amps on both Intermediate. Range channels.

l (a)

Trip may be manually bypassed when RCS pressure $ 1820 psig by actuating Shutdown Bypass provided that:

l (1) The High Flux Trip Setpoint is s 5% of RATED THERMAL POWER, l

(2) The Shutdown Bypass High Pressure Trip Setpoint of s 1820 psig is imposed, and (3) The Shutdown Bypass is removed when.RCS pressure > 1820 psig, i

l (b)

Trip may be manually bypassed when Specification 3.10.3 is in effect.

(c)

The minimum channels OPERABLE requirement may be reduced to one when Specification 3.10.1 or 3.10.2 is in effect.

ACTION STATEMENTS l

ACTION 1 With the number of channels OPERABLE one less than required by 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 be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and/or open the control rod drive trip breakers.

ACTION 2 With the number of OPERABLE channels one less than the Total Number of Channels STARTUP and/or POWER OPERATION may proceed provided both of the following conditions are satisfied:

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a. The inoperable channel is placed in the bypassed or tripped

[

condition within one hour.

b. Either, THERMAL POWER is restricted to s 75% of RATED THERMAL POWER and the High Flux Trip Setpoint is reduced to s 85% of RATED THERMAL POWER within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or the QUADRANT l

POWER TILT is monitored at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

l DAVIS-BESSE, UNIT 1 3/4 3-3 Amendment No.185 1

TABLE 3.3-1 (Continued)

ACTION STATEMENTS (Continued)

ACTION 3 With the number of OPERABLE channels one less than the Total l

Number of Channels STARTUP and POWER OPERATION may proceed provided.the inoperable. channel.is placed in the bypassed or tripped condition within one tour.

ACTION 4 With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement and with the THERMAL POWER level:

t

a. s 5% of RATED THERMAL POWER restore the inoperable channel to OPERABLE status prior to increasing THERMAL POWER above 1

5% of RATED THERMAL POWER.

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b. > 5% of RATED THERMAL POWER, POWER OPERATION may continue.

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DAVIS-BESSE, UNIT 1 3/4 3-4 Amendment No. J35,185 l

4 TABLE 3.3-1 (Continued)

' ACTION STATEMENTS (Continuedl ACTION 5 -

Vith the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement and with the THERMAL POWER level:

< 10-10 amps on the Intermediate Range (IR) instru-a.

mentation,restoretheinoperablechanneltoOPERAggE status prior to increasing THERMAL POVER above 10-amps on the 'iR instrumtintation.

b.

> 10-10 amps on the IR instrumentation, operation may continue.

ACTION 6 -

Vith the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement, verify compliance with the SHUTDOWN MARGIN requirements of Specification 3.1.1.1 within one hour and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter.

ACTION 7 -

Vith the number of OPERABLE channels one less than the Total Number of Channels STARTUP and/or POVER OPERATION may proceed provided all of the following conditions are satisfied a.

Vithin 1 hour:

1.

Place the inoperable channel in the tripped condition, or 2.

Remove power supplied to the control rod trip device associated with the inoperative channel.

b.

One additional 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 4.3.1.1.1, and the inoperable channel above may be bypassed for up to 30 l

minutes in any 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period when necessary to test the trip breaker associated with the logic of the channel being tested per Specification 4.3.1.1.1.

The inoperable channel above may not be bypassed to test the logic of a channel of the trip system associated with the inoperable channel.

DAVIS-BESSE, UNIT 1 3/4 3-5 Amendment No. /VQ% 135 (Next page is 3/4 3-5a.)

TABLE 3.3-1 (Continued)

ACTION STATEMENTS (Continued)

With one of the Reactor Trip Breaker diverse trip features ACTION 8 (undervoltage or shunt trip devices) inoperable, restore it to OPERABLE status in 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or place the breaker in trip in the next hour.

ACTION 9 With one or both channels of SCR Relays inoperable, restore the' channels to OPERABLE status during the next COLD SHUTDOWN exceeding 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

ACTION 10 With the number of channels OPERABLE one less than the Minimum Channels OPERABLE requirement, within one hour, place one inoperable channel in trip and the second inoperable channel in bypass, and restore one of the inoperable channels 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 be in HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and open the reactor trip breakers.

DAVIS-BESSE, UNIT 1 3/4 3-Sa Amendment No.108,135J85 (Next page is 3/4 3-6.)

TABLE 4.3-1

~.

REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE RE0VIREMENTS c3 E

G CHANNEL MODES IN WHICH E3 CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE G FUNCTIONAL UNIT CHECK CALIBRATION TEST REOUIRED M1 1.

Manual Reactor Trip N.A.

N.A.

S/U(1)

N.A.

EZ 2.

High Flux S

D(2), and Q(6,9)

N.A.

1, 2 3.

RC High Temperature S

R SA(9) 1, 2 4.

Flux - AFlux - Flow S(4)

M(3) and Q(6,7,9)

N.A.

1, 2 5.

RC Low Pressure S

R SA(9) 1, 2 6.

RC High Pressure S

R SA(9) 1, 2 7.

RC Pressure-Temperature S

R SA(9) 1, 2 8.

High Flux / Number of Reactor Coolant Pumps On S

Q(6,9)

N.A.

1, 2 9.

Containment High Pressure S

R SA(9) 1, 2 10.

Intermediate Range, Neutron Flux and Rate S

R(6)

N.A.(5) i, 2 and

• l "E

$@ 11.

Source Range, Neutron Flux and Rate S

R(6)

N.A.(5) 2, 3, 4 and 5 E

" 12.

Control Rod Drive Trip Breakers N.A.

N.A.

M(8,9) and S/U(1)(8) 1, 2 and

• E h 13.

Reactor Trip Module Logic N.A.

N.A.

M(9) 1, 2 and *

14. Shutdown Bypass High Pressure S

R SA(9) 2**,

3**,

4**, 5**

'g 15.

SCR Relays N.A.

N.A.

R 1, 2 and

• ya.

y

TABLE 4.3-1 (Continued)

Notation (1) -

If not performed in previous 7 days.

(2) -

Heat balance only, above 15% of RATED THERriAL POWER.

(3) -

When THERMAL POWER [TP] is above 50% of RATED THERMAL' POWER [RTP),

and at steady state, compare out-of-core measured AXIAL POWER IMBALANCE { API,] to incore measured AXIAL POWER IMBALANCE [ API ] as 3

follows:

RTP (API, - APl ) = Offset Error i

TP Recalibrate if the absolute value of the Offset Error is 2 2.5%

(4) -

AXIAL POWER IMBALANCE and loop flow indications only.

(5) -

CHANNEL FUNCTIONAL TEST is not applicable. Verify at least one decade overlap prior to each reactor startup if not verified in previous 7 days.

(6) -

Neutron detectors may be excluded from CHANNEL CALIBRATION.

(7) -

Flow rate measurement sensors may be excluded from CHANNEL CALIBRATION.

However, each flow measurement sensor shall be calibrated at least once per 18 months.

(8) -

The CHANNEL FUNCTIONAL TEST shall independently verify the OPERABILITY of both the undervoltage and shunt trip devices of the Reactor Trip Breakers.

(9) -

Performed on a STAGGERED TEST BASIS.

With any control rod drive trip breaker closed.

When Shutdown Bypass is actuated.

DAVIS-BESSE, UNIT I 3/4 3-8 Amendment No. A3,MB.123, 135,185

TABLE 3.3-17 (Continued)

ACTION STATEMENTS ACTION 18 With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirements, restore the l

inoperable channel to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or i

reduce reactor power to less than 45 percent of RATED l

' THERMAL POWER within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

]

ACTION 19 With the number of channels OPERABLE one less than required i

by the Minimum Channels-OPERABLE requirements, restore the inoperable channel to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

j ACTION 20 With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided both of the following conditions are satisfied:

i l

a)

The control rod drive trip breaker associated with the inoperable channel is placed in the tripped condition within one hour.

b)

The Minimum Channels r? RABLE requirement is met; however, one additior.

control rod drive trip breaker associated with another channel may. be tripped 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 4.3.2.3, after reclosing the control rod drive trip breaker opened in a) above.

t I

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DAVIS-BESSE, UNIT 1 3/4 3-30c Amendment No. 73,J25,J33,185 i

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TABLE 4.3-17 ANTICIPATORY REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS o

E i

~m CHANNEL MODES IN WHICH da CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE IS

]

FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED 1.

Turbine Trip (*)

S Not Applicable SA(*)

1 (b)

~

Ep 2.

Main Feed Pump Turbine Trip S

Not Applicable SA(*)

1 3.

Output logic Not Applicable Not Applicable M

1 w

b a

4 1

\\

R E

s Trip automatically bypassed below 45 percent of RATED THERMAL POWER

,+

(b)

Applicable only above 45 percent of RATED THERMAL POWER

(*'

Perform on a STAGGERED TEST BASIS 1

~

Lg L

M i

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