ML20210T289

Amend 107 to License DPR-66,changing Tech Specs to Add Requirements for Independent Testing of Reactor Trip Breaker,Undervoltage & Shunt Trip Attachments & Bypass Breakers

ML20210T289
Person / Time
Site:	Beaver Valley
Issue date:	02/04/1987
From:	Rubenstein L Office of Nuclear Reactor Regulation
To:
Shared Package
ML20210T296	List: ML20210T289 ML20210T309
References
NUDOCS 8702180143
Download: ML20210T289 (13)

Text

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UNITED STATES

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NUCLEAR REGULATORY COMMISSION b-l WASHINGTON. D. C. 20555 o

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PUOVESNE LIGHT COMDAP;Y 0410 EDISON COMPANY-PENNSYLVAffiA POWER C0t/DANY n0CKET NO. 50-334 PEAVER VALLEY onWER STATION, I.it!TT NO. 1 AMFND*FP:T TO FACTLITY OPERATING LICENSE 4

Amendment No.107.

I' License No. DPR-66' i

1.

The Nuclear Reculatory Comission (the Commissioni has found that:

A.

The application for amendment by Du'quesne Light Comoany, Ohio Edison Company, and Pennsylvania Power Company (the licensees) dated October 9,1986, 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 reculations of the Commission; C.

There is reasonable assurance (ii that the activities authorized hv this amendment can be conducted without endancering the health and safety of the public, and (111 that such activities will be conducted in compliance with.the Commission's regulations; O.

The issuance of this amendment will not be inimical to the. common 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 reouirements have been satisfied.

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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. OPR-66 is hereby amended to read as follows:

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ADOCK 05000334 PDR

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? '(?) Technical Speci'ications The Technical Soeci#ications contained in Apnendix A, as revised throuch Arendment Nn 107, are herehy

-incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This amendment is effective on issuance, to be implemented no later than 30 davs after issuance.

FOR T5iE NilCLEaR DE4tlLATODY COMMTSS'ON

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. w, Lester S. Dub'e stein, Director PWR Proiect nirectorate #'

nivision of DVR Licensino-A Office of Nuclear Reactor Reculation

Attachment:

Chances to the Technical-a Specifications Date of issuance: February 4, 1987 4

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ATTACHPFNT TO LICENSE AMEN 0 MENT AMENDMENT NO.107 TO FACILITY ODERATING LICENSF NO. OPR-66 DOCKET NO. 50-334 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 area of change. The corresponding overleaf pages are also provided, where appropriate, to maintain document completeness.

Remove Paces Insert Paoes 3/4 3-4 3/4 3-4 3/4 3-5 3/4 3-5 3/4 3-7 3/4 3-7 3/4 3-11 3/4 3-11 3/4 3-12 3/4 3-12 3/4 3-13 3/4 3-13 B3/4 3-1 B3/4 3-1 B3/4 3-la R3/4 3-la l

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TABLE 3.3-1 (Continued)

REACTOR TRIP SYSTEM INS'TRUMENTATION W

9 MINIMUM TOTAL NO.

CHANNELS CHANNELS APPLICABLE N

FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION N

E

18. Turbine Trip (Above P-9)

N A.

Auto Stop Oil Pressure 3

2 2

1 7

B.

Turbine Stop Valve Closure 4

4 4

1 8

i

19. Safety Injection Input y

from ESF 2

1 2

1,2 1

' 20. Reactor Coolant Pump Breaker Position Trip (Above P-7) 1/ breaker 2

1/ breaker 1

11 per oper-ating loop

21. Reactor Trip Breakers 2

1 2

1,2.

1,40 2

1 2

3*,4*,5*

39,40 s

22. Automatic Trip Logic 2

1 2

1,2 1

w 1

2 1

2 3*,4*,5*

39

23. Reactor Trip System Interlocks i

A.

Intermediate Range.

2 1

1 2

3

.g Neutron Flux, P-6 3

g-B.

Power Range 4

2 3

1 12.

g Neutron Flux, P-8 e

g C.

Power Range 4

2 3

1 12:

Neutron Flux, P-9 E2

'l D.

Power Range 4

2 3

1 12

.)

Neutron Flux, P-10 E.

Turbine Impulse 2

1 1

1 12 Chaniber Pressure, P-13

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.q m,s TABLE ~3.3-1 (Continued)

TABLE NOTATION With. - the reactor-trip system breakers in the closed position and the control rod drive system capable of rod withdrawal.

The channel (s)- associated with the protective functions derived from the out of service Reactor Coolant Loop shall be placed in the tripped condition.

(1) Trip function may be manually bypassed in this Mode above P-10.

(2) Trip function may be manually bypassed in this Mode above P-6.

ACTION STATEMENTS ACTION 1 -

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 2 -

With the number of OPERABLE channels one less than the Total Number of Channels and with the THERMAL POWER level:

a.

Less than or equal to 5% of RATED THERMAL POWER, place the inoperable channel. 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 /> and restore the inoperable channel to OPERABLE status within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> after increasing THERMAL POWER above 5% of RATED THERMAL POWER; otherwise, reduce thermal power to less than 5% RATED THERMAL POWER within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

b.

Above 5%

of RATED THERMAL POWER, operation u.ay continue provided all of the following conditions are satisfied:

1.

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 />.

2.

The Minimum Channels OPERABLE requirement is met;

however, 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.

3.

Either, THERMAL POWER is restricted to 1 75%

of RATED THERMAL and the Power Range, Neutron Flux Trip setpoint is reduced to 1 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 QUANDRANT POWER ~ TILT RATIO 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 /> per Specification l

4.2.4.c.

ACTION 3 -

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

Amendment No. 83,101 BEAVER VALLEY - UNIT 1 3/4 3-5

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-TABLE 3.3-1 (CONTINUED)

ACTION 9 With a

channel associated with an operating loop-inoperable, restore.the inoperable channel to OPERABLE

. status within 2

hours or be in HOT STANDBY within the next 6

hours; however, one channel associated with an operating loop '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.

ACTION 10 Not applicable.

ACTION 11 With.less th'an the Minimum Number of Channels OPERABLE, operation may. continue provided.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 />.

ACTION 12 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 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 reactor trip breakers.

ACTION 39 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 within the next hour.

ACTION 40 With one of the diverse trip features (Undervoltage or shunt trip attachment) inoperable,_ restore it 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 declare the breaker inoperable and apply.

ACTION 1

or-ACTION 39 as applicable.

Neither breaker shall be bypassed while one of the diverse trip features is inoperable except for the time required for performing maintenance to restore

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the breaker to OPERABLE status.

l BEAVER VALLEY - UNIT 1 3/4 3-7 (next.page-is 3/4 3-9) l l'

Amendment flo. S3.107

TABLE 4.3-1 REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS m

Channel Modes in which

{

channel channel Functional Surveillance nW Functional Unit check calibration Test Required E

1.

Manual Reactor Trip N.A.

N.A.

S/U(1), R(10)

N.A.

n N

2.

Power Range, Neutron Flux a.

High Setpoint S

D(2), M(3)

M 1, 2 and Q(6) z U

b.

Low Setpoint S

N.A.

S/U(1) 2 w

3.

Power Range, Neutron Flux, N.A.

R M

1, 2 High Positive Rate 4.

Power Range, Neutron Flux, N.A.

R M

1, 2 High Negative Rate 5.

Intermediate Range, S

N.A.

S/U(1),

1,.2, 3*

u,

}

Neutron Flux M(7) 4*,

5*

y 6.

Source Range, Neutron Flux N.A..

N.A.

S/U(1),

2, 3*,

4*

p (Below P-10)

M(8) and 5*

7.

Overtemperature AT S

R M

1, 2 8.

Overpower AT S

R M

1, 2 N

9.

Pressurizer Pressure-Low S

R M

1,- 2 S

"l 10.

Pressurizer Pressure-High S

R M

1, 2 af 11.

Pressurizer Water Level-High S R

M 1, 2

=

12.

Loss of Flow-Single Loop S

R M

1 4

13.

Loss of Flow - Two Loops S

R N.A.

1-14.

Steam / Generator Water S

R M

1, 2

Level-Low-Low I

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TABLE 4.3-1, (CONTINUED).

REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS Channel Modes in Which 9

Channel Channel Functional Surveillance Functional Unit Check Calibration Test Required W

< 15.

Steam Feedwater Flow Mis-S R

M 1,

2 j%

match and Low Steam Gen-y erator Water Level i

K l

16.

Undervoltage-Reactor N.A.

R M

1 a

l Coolant Pumps c

z.

Underfrequency-Reactor N.A R

M 1.

y 17.

j Coolant Pumps g

4 18.

Turbine Trip a.

Auto Stop Oil Pressure N.A.

N.A.

S/U(1) 1, 2 b.

Turbine Stop Valve N.A N.A.

S/U(1) 1, 2 Closure i

x 19.

Safety Injection Input from N.A N.A.

M(4) 1, 2 y

ESF-w 20.

Reactor Coolant Pump li. A N.A.

R N.A".

Breaker Position Trip i

i 21.

Reactor Trip Breaker N.A.

N.A.

M(5, 11)-

.1, 2,

3*,

and S/U(1).

4*, 5*

22.

Automatic Trip, Logic N.A.

N. A. -

M(5)-

1, 2,13*,-

4*, 5*

y' e-E 23.

Reactor Trip System Interlocks 2

r S-A.

P-6 N.A.

N.A..

M(9) 1, 2

B.

P-8 N.A.

N.A.

,M(9) 1 n

l.

C.

P-9 N.A.

N.A.

M(9) 1 D.

P-10 N.A.

N.A.

M(9) 1 lF E.

P-13 N.A.

R M(9):

l'.

.g~124. ' Reactor Trip Bypass N.A.

N.A.

M(12), R(13),

1,.2, 3*

- r Breakers S/U(1)~

4*,

5*

i.

TABLE 4.3-1 (CONTINUED)

NOTATION

-With. the reactor trip ' system breakers closed and the control rod drive system capable of rod withdrawal.

If not performed in previous 7 days.

(1)

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

(2) incore to excore axial imbalance above 15% of RATED Compare (3)

THERMAL POWER.

Recalibrate if absolute difference ?_ 3 percent.

Manual ESF functional input check every 18 months.

(4)

Each train tested every other month.

(5)

Neutron detectors may be excluded from CHANNEL CALIBRATION.

(6)

Below P-10.

(7)

Below P-6.

(8)

Required only when below Interlock Trip Setpoint.

(9)

The CHANNEL FUNCTIONAL TEST shall independently verify the (10)

OPERABILITY of the undervoltage and shunt trip circuits for the Manual Reactor Trip Function.

The test shall also verify the OPERABILITY of the Bypass Breaker. trip circuit (s).

The CHANNEL FUNCTIONAL TEST shall independently verify the (11)

OPERABILITY of the undervoltage and shunt trip attachments of the Reactor Trip Breakers.

( 12 ) -

Local manual shunt trip prior to placing breaker in service.

Automatic undervoltage trip.

(13)

' Amendment No. 83,107 BEAVER VALLEY - UNIT 1 3/4 3-13

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INSTRUMENTATION ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INS 3/4.3.2 LIMITING CONDITION FOR OPERATION The engineered safety feature actuation system instrumentation channels and interlocks shown in Table 3.3-3 shall be O 3.3.2.1 trip setpoints set consistent with the values shown in the Trip Setpoin column of Table 3.3-4 and with RESPONSE TIMES as sh APPLICABILITY _: As shown in Table 3.3-3.

ACTION _:

With an engineered safety feature actuation system instrumentation channel trip setpoint less conservative than the value shown in a.

the Allowable Values column of Table 3.3-4, declare the channel inoperable and apply the applicable ACTION requirement of Table 3.3-3 until the channel is restored to OPERABLE status with the trip setpoint adjusted consistent with the Trip Setpoint Value, With an engineered safety feature actuation system instrumentation channel inoperable, take the action shown in Table 3.3-3.

b.

SURVEILLANCE REQUIREMENTS Each engineered safety feature actuation system instrumentation channel shall be demonstrated OPERABLE by t 4.3.2.1.1 the modes and at the frequencies shown in Table 4.3-2.

The logic for the interlocks shall be demonstrated OPERABLE

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during the at power CHANNEL FUNCTIONAL TEST of ch 4.3.2.1.2 OPERABLE at least once per 18 months during CHANNEL CALIBRAT interlock operation.

of each channel affected by interlock operation.

The ENGINEERED SAFETY FEATURES RESPONSE T function shall be demonstrated to be within the limit at least once per 4.3.2.1.3 Each test shall include at least one logic train such that both logic trains are tested at least once per 36 months and one c 18 months.

per function such that all channels are tested at least once per N 18 months where N is the total number of redu BEAVER VALLEY - UNIT 1 3/4 3-14

3/4.3 INSTRUMENTATION BASES 3/4.3.1 AND 3/4.3.2 PROTECTIVE AND ENGINEERED SAFETY FEATURES (ESP)

INSTRUMENTATION OPERABILITY of the. protective and ESF instrumentation systems The ensure that 1) the associated ESF action and/or and interlockswill be inititated when the parameter monitored by each trip or combination thereof exceeds its setpoint, 2) the specified reactor channel coincidence logic is maintained, 3) sufficient redundancy is channel to be out of service for testing or maintained to permit a

and 4) sufficient system functional capability is maintenance, available for protective and ESF purposes from diverse parameters.

The OPERABILITY of these systems is required to provide the reliability, redundancy and diversity assumed available in overall and facility design for the protection and mitigation of accident the transient conditions.

The integrated operation of each of these systems is consistent with the assumptions used in the accident analyses.

The surveillance requirements specified for these systems ensure

.that the overall system functional capability is maintained comparable to the original design standards.

The periodic surveillance tests performed at the minimum frequencies are sufficient to demonstrate this capability.

for the Manual Trip

Function, requirements The surveillance and Reactor Trip Bypass Breakers are provided Breakers Reactor Trip possibility of an Anticipated Transient Without. Scram to reduce the (ATWS) event by ensuring OPERABILITY of the diverse trip features

(

Reference:

Generic Letter 85-09),

The measurement of response time at the specified frequencies provides assurance that the protective and ESF action function associated with each channel is completed within the time limit assumed in the accident analyses.

No credit was taken in the analyses for those channels with response times indicated as not applicable.

1

Response

time may be demonstrated by any series of sequential, measurements provided that such or total channel test overlapping Sensor demonstrate the total channel response time as defined.

time verification may be demonstrated by either 1) in place, tests response onsite or offsite test measurements or 2) utilizing replacement sensors with certified response times.

Engineered Safety Feature Actuation System interlocks perform The the following functions:

Actuates turbine

trip, closes main P-4 Reactor tripped valves on T below

setpoint, prevents the feedwaterofthemainfeekStervalveswhichwereclosedbya opening safety injection or high steam generator water level

signal, allows safety injection block so that components can be reset or tripped.

Reactor not tripped - prevents manual block of safety injection.

BEAVER VALLEY - UNIT 1 B 3/4 3-1 Amendment tio. U,107 i

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O 3/4.3 ' INSTRUMENTATION BASES (ESF)

PROTECTIVE AND ENGINEERED SAFETY FEATURES 3/4.3.1 AND 3/4.3.2 j-INSTRUMENTATION P-11 Above the setpoint P-11 automatically reinstates safety-injection actuation on Low pressurizer

pressure, automatically blocks. steamline isolation: on high. steam pressure rate,. enables safety injection and steamline isolation on (Loop Stop -Valve Open) with low steamline

pressure, and enables. auto actuation of the. pressurizer PORVs.

P-11 allows.the manual block of safety Below the setpoint actuation on low. pressurizer pressure, allows injectionblock of safety injection and steamline isolation on (Loop Stop Valve Open) with Low. steamline pressure and manual j

enabling steamline isolation on high steam pressure rate, auto actuation lof the pressurizer automatically disables Reactor Vessel Over Pressure Protection PORV's unless the-System is in service.

setpoint P-12 automatically reinstates an arming P-12 Above the Below the setpoint P-12 signal to the steam dump system.

steam dump and allows manual bypass of the steam blocks dump block to cooldown condenser dump valves.

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..g BEAVER VALLEY - UNIT 1 B 3/4 3-la Amendment No.107

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