ML20033E101

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Amend 27 to License NPF-73,revising Tech Specs to Delete All Setpoint Operability & Surveillance Requirements on Steam/ Feedwater Mismatch Trip Function
ML20033E101
Person / Time
Site: Beaver Valley
Issue date: 02/20/1990
From: Stolz J
Office of Nuclear Reactor Regulation
To:
Cleveland Electric Illuminating Co, Duquesne Light Co, Ohio Edison Co, Toledo Edison Co
Shared Package
ML20033E102 List:
References
NPF-73-A-027 NUDOCS 9003090011
Download: ML20033E101 (9)
v • d • e


Text

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'O UNITED STATES

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NUCLEAR REGULATORY COMMISSION l

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I DUQUESNE LIGHT COMPANY--

OHIO EDISON COMPANY y

THE CLEVELAND ELECTRIC __ ILLUMINATING. COMPANY THE TOLEDO EDISON. COMPANY DOCKET NO. 50-412 i

.r BEAVER. VALLEY POWER STATION. UNIT NO.u2 AMENDMENT.TO FACILITY.0PERATING_.LlCENSE Amendment No. 27 License No.'NPF-73 1

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

'I A.

The application.for amendment by Duquesne Light Company, et al.-

(the. licensee)datedAugust 25, 1989 complies with the standards and

-i requirements of the Atomic Energy Act of 1954, as amended (the Act)

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and.the: Commission's rules and regulations set forth in 10 CFR Chapter I;-

J B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of j

the Comission; 4

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C.

Thereisreasonableassurance(1)thattheactivitie'sauthorized j

by this amendment can be conducted without endangering the health _

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'and safety of the public, and-(ii) that such activities will be w

conducted _in compliance with the Commission's regulations;

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D.

The issuance of this amendment will not be inimical to the comon 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

.I have been satisfied, g*gtAM$12 9

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2.

Accordingly, the license is amended by changes to-the Technical Specifications-as indicated in the attachment to this license i

amendment,andparagraph~2.C.(2)of-Facility-OperatingLicense No. NPF-73 is hereby amended to read as follows:

~(2).TechnicalSpecifications The Technical Specifications contained:in Appendix A, as revised through Amendment No. 27, and the Environmental Protection Plan.

contained in Appendix B, both of which are attached bereto are hereby incorporated in the license. DLC0 shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

This license amendment is effective on issuance, to be implemented within 60 days of issuance.

FOR THE NUCLEAR REGULATORY COWISSION 5

Th

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z J n F. Stolz. Director Project Directorate 1-4 4

Division of Reactor Projects

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Office of Nuclear Reactor Regulation

Attachment:

Charges to the Technical Specifications Date of. Issuance:

February-20, 1990

g lu ATTACHMENT TO LICENSE. AMENDMENT.NO. 27 FACILITY.0PERATING LICENSE NO. NPF-73

<a DOCKET NO. 50-412 i

~ Replace the following pages of the Appendix A (Technical Specifications)

with the enclosed pages as indicated. The revised pages are. identified by
amendment number and contain vertical. lines indicating-the areas of change.

Remove Insert' 2-5 2-5 2-10 2-10 B2-6 B2 3/4 3-3 3/4 3-3 3/4 3-8 3/4 3-8 3/4 3-11 3/4 3-11 N

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' TABLE 2.2-1 (Continued)'

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REACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTS

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FUNCTIONAL UNIT-ALLOWANCE (TA)

Z S

TRIP SETPOINT ALLOWABLE VALUE

13.

Steam Generator Water 11.5

~10.18 1.67

> 11.5% of narrow

>:10.7% of. narrow

[

Level-Low-Low-range instrument range instrument ?

l span-each. steam.

span each steam

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-a

. generator

. generator-m i

14.

DELETED.

-l 15.

Undervoltage - Reactor 27.7 1.39 0

>75% of BUS

>73% of BUS Yoltage Coolant Pumps Voltage-each bus-

- each bus 16.

Underfrequency-Reactor 10.0 0.20-0

>57.5 Hz-each bus

>57.4 Hz-each bus Coolant Pumps m

di 17.

Turbine Trip a.

Emergency Trip Header N.A.

N.A.

N.A.

>1000 psig

>958 psig Low Pressure b.

Turbine Stop Valve N.A.

N.A.

N.A.

>EE open

>1% open Closure 18.

Safety Injection Input N.A.

N.A.

N.A.

N.A

.N.A.

from ESF R

19.

Reactor Coolant Pump N.A.

N.A.

N.A.

N.A.

N. A.

R Breaker Position Trip 5

20.

Reactor Trip Breakers N.A.

N.A.

N.A.

N.A.

N.A.

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- TABLE 2.2-1 (Continued)

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,g JREACTOR TRIP SYSTEM INSTRUMENTATION TRIP SETPOINTSL E

NOTATION (Continuad)

<N 1

-= '

Lag compensator on measured.Tavg;.

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Time constant utilized in the measured T,yg lag compensator,.rg = 0.s; 1

=

6 z

Z K

=

0.0012/ F for T > T"Jand'K = 0 1or T.1 T";

6 6

ro T

=

Average Temperature,- F; T"

Indicated T,-

at RATED. THERMAL POWER (Calibration temperature for AT

=

yg instrumentation,.5576.2 F);

Laplace transform operator, s~1; and 5

=

to O

f (AI) 0 for all AI.

=

o 2

NOTE 4:

The channel's maximum Trip Setpoint shall not exceed.its computed Trip Setpoint by more than.

2.6% of AT span.

NOTE 5:

The sensor error for temperature is-L72% and 0.73% of span for pressure.

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LIMITING-SAFETC SYSTEM SETTINGS j

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Undervoltage and Underfrequency - Reactor Coolant Pump Busses

- The Undervoltage and _Underfrequency Reactor Coolant Pump bus trips provide o

reactor core protection'against DNB as a result of loss of voltage or under-F frequency to more than1one reactor coolant pump.

The'specified setpointsrassure

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a reactor trip signal is generated before the low flow-trip setpoint is: reached.

Time delays are ' incorporated -in: the underfrequency and_ undervoltage trips Lto prevent ' spurious reactor trips from momentary electrical power transients.

For undervoltage, the delay is set so that the time required for a' signal to reach

the reactor. trip breakers following the simultaneous trip of two or more reactor coolant' pump; bus circuit
breakers shall not exceed 1.2 seconds.

For underfre-1 quency, the-delay is set so that the time' required for a' signal.-to reach the,

-reactor trip-breakers after the-underfrequency trip setpoint is reached:shall.

not exceed 0.6 seconds.

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On decreasing power, the Undervoltage and Underfrequency Reactor Coolant

' Pump Bus trips are automatically blocked by' P-7 (a. power level of approximately 10 percent of RATED THERMAL POWER with a turbine impulse chamber pressure at 0

approximately 10 percent of full power equivalent); and on increasing power, reinstated automatically by P-7.

" Turbine Trip

.. A Turbine. Trip causes a direct reactor trip when operating above P-9.

Each of:the turbine-trips provide turbine protection and reduce.the severity of the ensuing' transient.

No credit was taken in the accident-analyses for operation of these trips.

Their functional capability at the specified trip settings is required to enhance the overall reliability of the Reactor Protection System.

, BEAVER VALLEY - UNIT 2 B 2-6 Amendment No. 27

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a TABLE-3.3-1 '(Continued)

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REACTOR TRIP SYSTEM INSTRUMENTATION ~

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3

- MINIMUM

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TOTAL NO.

. CHANNELS CHANNELS:

APPLICABLE FUNCTIONAL UNIT'

-0F CHANNELS.

TO TRIP-OPERABLE MODES-ACTION:

11. Pressurizer Water Level-High 3

2

.- 2 c-h (Above P-7)

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1, 2

,7

12. Loss of Flow - Single Loop 3/ loop

.2/ loop in 2/ loop'in l'

7

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(Above-P-8).

'any operating 'each operating-loop 1

- loop

13. Loss of Flow - Two Loop 3/ loop.

2/ loop in 2/ loop in.'

1 7

(Above P-7 and below P-8)-

two operating each operating loops loop s*

14. Steam Generator Water.

3/ loop 2/ loop 2/ loop 1, 2

'7

[

Level-Low-Low

15. DELETED.

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16. Undervoltage-Reactor Coolant 3-1/ bus 2

2 1

'7 Pumps (Above P-7)

17. Underfrequency-Reactor 3-1/ bus 2

2 1

17:

Coolant Pumps (Above P-7)

18. Turbine Trip-(Above P-9) a.

Emergency Trip Header 3

2 2

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E Low Pressure 2

b.

Turbine Stop Valve Closure 4

'4' 4

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S7 TABLE 3.3-2 REACTOR TRIP SYSTEM INSTRUMENTATION RESPONSE TIMES FUNCTIONAL UNIT RESPONSE TIME 1.

Manual Reactor Trip NOT APPLICABLE

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2.

Power Range, Neutron Flux 5 0.5 seconds *'

3.

Power Range, Neutron Flux, High_ Positive Rate NOT APPLICABLE-C l

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Power Range, Neutron Flux, High Negative Rate 5 0.5 seconds

  • 5.

Intermediate Range, Neutron Flux-NOT APPLICABLE 6.

Source Range,' Neutron Flux NOT APPLICABLE (Below P-10) 7.

Overtemperature AT

$ 5.5 seconds

  • 8.

.0verpower AT 5 5.5 seconds

  • l 9.

Pressurizer Pressure--Low

< 2.0 seconds I

(Above:P-7) r

10. Pressurizer Pressure--High 5 2.0 seconds-(
11. Pressurizer Water Level--High NOT APPLICABLE L

(Above P-7)

12. Loss of Flow - Single. Loop (Above P-8) 5 1.0 seconds L.

r

13. Loss of Flow - Two Loop

-< 1.0: seconds

-(Above P-7 and below P-8).

14. Steam Generator Water Level--Low-Low

-< 2.0 seconds (Loop Stop Valves Open)

15. DELETED.
16. Undervoltage-Reactor Coolant Pumps 5 1.5 seconds (Above P-7) l:

l-17.'Underfrequency-Reactor Coolant Pumps 5 0.9 seconds l -.

(Above.P-7) l 1

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  • Neutron detectors are exempt from response time testing.

Response

time shall be measured from detector output or input of first electronic component in channel.

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. BEAVER VALLEY - UNIT 2 3/4 3-8 Amendment No. %, 27 l

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TABLE'4.3-1 (Continued)-

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. REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS

-CHANNEL-

. MODES IN WHICH' iE.

CHANNEL-CHANNEL FUNCTIONAL SURVEILLANCE E

FUNCTIONAL UNIT CHECK CALIBRATION TEST REQUIRED-

11. Pressurizer Water Level-High 5

R M

1, 2 E

(Above P-7)

Z

12. Loss of' Flow - Single Loop S

R M

1

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m (Above P-8)'

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13. Loss of Flow - Two Loop S..

R See 12 above I_

(Above P-7 and below P-8)

14. Steam / Generator Water Level-S-

R M

1, 2 R

Low-Low a

Y

15. DELETED.

M I-

16. Undervoltage - Reactor Coolant M.A.

R M

1~

Pumps (Above P-7)

17. Underfrequency - Reactor Coolant N.A.

R M

1-Pumps (Above P-7) l J

l

18. Turbine Trip (Above P-9) l l

A.

Emergency Trip Header N.A.

R S/U(1) 1, 2 Low Pressure B.

Turbine Stop Valve Closure N.A.

R-5/U(1) 1,. 2 E

19. Safety Injection Input from ESF N. A.-

N.A.

R.

1, 2 8

i

20. Reactor Coolant Pump Breaker.

- N. A.-

N.A.

R N.A.

l Position Trip (Above.P-7) l N,

21. Reactor Trip Breaker N.A.

N.A.

M(5, 11) and S/U(1) 1, 2,l3*, 4*,'5*

22. Automatic Trip Logic N.A.

M.A.

M(5) 1, 2,'3*, 4*, 5*

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