ML20147H707

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Amend 108 to License NPF-3,revising Tech Spec Section 3/4.3.1,Tables 3.3-1 & 4.3-1,to Address Action & Surveillance Requirements Re Reactor Trip Breaker Diverse Trip Devices
ML20147H707
Person / Time
Site: Davis Besse Cleveland Electric icon.png
Issue date: 03/02/1988
From: Perkins K
Office of Nuclear Reactor Regulation
To:
Shared Package
ML20147H710 List:
References
NUDOCS 8803090046
Download: ML20147H707 (10)
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Text

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UNITED STATES

[

g NUCLEAR REGULATORY COMMISSION

E WASHINGTON, D. C. 20655 g
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TOLEDO EDISON COMPANY AND THE CLEVELAND ELECTRIC ILLUMINATING COMPANY DOCKET NO. 50-346 DAVIS-BESSE NUCLEAR POWER STATION, UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 108 License No. NPF-3 1.

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

The application for amendment by the Toledo Edison Company)and A.

The Cleveland Electric Illuminating Company (the licensees dated March 27, 1987, complies with the standards and require-ments of the Atomic Energy Act of 1954, as amended (the Act),

and tne Comission'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 Comission; C.

There is reasonable assurance (1) 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 Comission's regulations; D.

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

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

2.

Accordingly, the license is amended by changes to the Technical Specifi-cations 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:

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2 Technical Specifications The Technical Specifications contained in Aspendices A and B, as revised through Amendment No.108, are here)y incorporated in the license. The Toledo Edison Company shall operate the facility in accordance with the Technical Specifications.

3.

This license amenda.ent is effective as of its date of issuance and shall be implemented not later than April 1, 1988 FOR THE NUCLEAR REGULATORY COMMISSION Kenneth E. Perkins, Director Project Directorate III-3 Division of Reactor Projects III, IV, V

& Special Projects

Attachment:

Changes to the Technical Specifications Date of Issa nce:

March 2, 1988 if a

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FACILITY OPERATING LICENSE NO. NPF-3 DOCKET NO. 50w346 Replace the following pages of the Appendix "A" Technical Specifications with the attached pages.

The revised pages are identified by Atendment number and contain vertical lines indicating the area of change.

The corresponding overleaf page(s) are also provided to maintain document conpleteness.

Remove Insert 3/4 3-2 3/4 3-2 3/4 3-5 3/4 3-5 3/4 3-Sa 3

3/4 3-7 3/4 3-7 l

3/4 3-8 3/4 3-8 i

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a 3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTECTION SYSTEM INSTRUMENTATI0tl LIMITING CONDITION FOR OPERATION 3.3.1.1 As a minimum, the Reactor Protection 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 4.3.1.1.1 Each Reactor Protection System instrumentatian 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.

4.3.1.1.2 The total bypass function shall be demonstrated OPERABLE at least once per 18 months during CHANNEL CALIBRATION 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 times 18 months where N is the total number of redundant chcnnels 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

.m.

- =. _ -.

TABLE 3.3-1 REACTO:I PROTECTION SYSTr1 INSTRUMENTATION MINIMUM g

TOTAL NO.

CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION T

g

1. Manual Reactor Trip 2

1 2

1, 2 and

  • 1 p
2. High Flux 4

2 3

1, 2 2#

3. RC High Temperature 4

2 3

1, 2 3#

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4. Flux - A Flux - Flow 4

2(a)(b) 3 1, ' 2 2#

5. RC Low Pressure 4

2(a) 3 1, 2 3#

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6. RC High Pressure 4

2 3

1, 2 3#

7. RC Pressure-Temperature 4

2(a) 3 1, 2 3#

s 1

8. High Flux / Number of Reactor Coolant Pumps On 4

2(a)(b) 3 1, 2 3#

9; Containment High Pressure 4

2 3

1, 2 3#

Y

-10. Intermediate Range, Neutron Flux

(;>

and Rate 2

0 2(c) 1, 2 and

  • 4 u
11. Source Range, Neutron Flux and Rate A. Startup 2

0 2

2## and

  • 5 B. Shutdown 2

0 1

3, 4 and 5 6

12. Contr.>l Rod Drive Trip Breakers 2 per trip 1 per trip 2 per 1, 2 and
  • 7#,9#

l system system trip system.

13. Reactor. Trip Module 2 per trip 1 per trip 2 per 1,'2 and'*

7#

system system trip system E

14. Shutdown Bypass High Pressure 4

2 3

2**, 3**

6#

k 4**, 5**

15. SCR Relays 2

2 2

1,2 and

  • 10#

e 5

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t TABLE 3.3-1_-(Continued) r r

ACTION STATEMENTS (Continued)

ACTION 5 -

With' the number of channels OPERABLE ~one less than required by.the Minimum Channels 0PERABLE requirement and with the THERMAL POWER level:

-10 a.

$ 10 amps on the Intermediate Range'-(IR) instru-mentation, restore the inoperable channel to OPER g r

status prior to increasing THERMAL POWER above 10 l

amps on the'IR instrumentation.

b.

> 10 amps on the IR instrumentation', operation may

-10 continue.

ACTION 6.-

With 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.

l ACTION 7 -

With the number of OPERABLE channels one less than the i

Total Number of Channels STARTUP and/or POWER OPERATION I

may proceed provided all of the following conditions are i

satisfied:

i a.

Within 1 hour:

2 1.

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

Remove power supplied to the control rod trip

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device associated with the inoperative channel.

I 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 l

l bypassed for up to 30 minutes in any 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period l

I when necessary to test the trip breaker associated l

with the logic of the channel being tested per

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Specification 4.3.1.1.1.

The inoperable channel above

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l may not be bypassed to test the logic of o thannel of the trip system associated with the inoperable channel, i

j ACTION 8 -

With the number of channels OPERABLE less than required by-j the Minimum Channels OPERABLE requirement, be in at least i

L HOT STANDBY within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

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1 DWIS-BESSE, UNIT 1 3/4 3-5 Amendment No. 108 I

-(Next page is 3/4 3-54.)

3-i

-6 l

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TABLE 3.3-1 (Continued) l ACTION STATEMENTS (Continued) i ACTION 9 -

With one of the Reactor Trip Breaker diverse trip features f

(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 10 -

With-one or both channels of SCR Relays inoperable, l

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 />.

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DAVIS-BESSE, UNIT 1 3/4 3-5a Amendment No. 108 1

(Next page is 3/4 3-6.)

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TABLE 3.3-2 g

REACTOR PROTECTION SYSTEM INSTRtMENTATION RESPONSE TIMES l=

FUNCTIONAL UNIT RESPONSE TIMES **

m k

~

(seconds) g 1.

Manual Heactor Trip Not Applicable

~[

2.

High Flux *

< 0.266 i

3.

RC High Temperature Not Applicable 4.

Flux - a flux - Flow * - Variable Flow

< 1.77

- Constant Flow g 0.266 5.

RC Low Pressure

< Q.341 i

w 1

6.

RC High Pressure 1 0.341 w

A 7.

RC Pressure - Temperature - Constant Temperature Not Applicable 1

{

8.

Hfgh Flux / Number of Reactor Coolant Pumps On*

1 0.451***

1 9..

Containment High Pressure Not Applicable i

i 1

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F Neutron detectors are exempt from response time testing. Response time of the neutron flur.

s

,{

signal portion of the channel shall be aeasured from detector output or input of first electronic g

component in channel.

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I Including sensor (except as noted), RPS instrument delay and the brerier delay.

A 0.24 sec delay time has been assumed for p;mip contact monitor.

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', ~. _. _ _ _ _ _ _ _.. _ _..

i TABLE 4.3-1 REACTOR PROTECTION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS E'

CHANNEL MODES IN WHICH l

y CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE j

FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED l

[

l 1.

Manual Reactor Trip N.A.

N.A.

S/U(1)

N.A.

h 2.

High Flux S

D(2), and Q(7)

M 1, 2 a

3.

RC High Temperature S

R M

1, 2 1

4.

Flux - AFlux - Flow S(4)

M(3) and Q(7,8)

H 1, 2 5.

RC Low Pressure S

R M

1, 2 l

6.

RC High Pressure S

L M

1, 2 l

u 7.

RC Pressure-Temperature S

R M

1, 2 s

u 8.

High Flux / Number of Reactor O

Coolant Pumps On S

R H

1, 2 1

9.

Containment High Pressure S

R H

1, 2 10.

Intermediate Range, Neutron i

Flux and Rate S

R(7)

S/U(5)(1) 1, 2 and*

I f

11.

Source Range, Neutron Flux o

and Rate S.

R(7)

M and S/U(1)(5) 2, 3, 4 and 5 l

k 12.

Control Rod Drive Trip Breakers N.A.

N.A.

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

[

13.

Reactor Trip Module Logic N.A.

N.A.

M 1, 2 and*

l 14.

Shutdown Bypass High Pressure S

R M

2**,3**,4**,5**

w 15.

SCR Relays N.A.

N.A.

R 1,2 and

  • O CD i

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TABLE 4.3-1 (Continued)

NOTATION (1)

If not performed in previous 7 days.

(2)

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

(3)

When THERMAL POWER [TP) is above 30% of RATED TH

[RTP), compare out-of-core measured AXIAL POWER IMBALANCE Recafibrateif:[ API ] to incore measured AXIAL POWER I g

R

[ API, - API ) > 3.5%

y (4)

AXIAL POWER IMBALANCE and loop flow indications only.

(5)

Verify at least one decade overlap if not verified in previous 7 days.

(6)

Each train tested every other month.

(7)

Neutron detectors may be excluded from CHANNEL CALIBRATION (8)

Flow rate measurement sensors may be excluded from CHANNEL CALIBRATION.

calibrated at least once per 18 months.However, each flow measur 1

(9)

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

With any control rod drive trip breaker closed.

t When Shutdown Bypass is actuated.

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DAVIS-BESSE, UNIT 1 3/4 3-8 "i

Amendment No. $), 108 l

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