Text

Amend 10 to License NPF-87,temporarily Removing Operability Requirements for Boron Dilution Mitigation Sys for 6 Months Following Second Refueling Outage
	ML20097H421
Person / Time
Site:	Comanche Peak
Issue date:	06/08/1992
From:	Black S; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20097H424	List: ML20097H421; ML20097H426;
References
	NUDOCS 9206260317
	Download: ML20097H421 (11)
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'n UNITED STATES 3,

i NUCLEAR REGULATORY COMMISSION p

WASHINGTON. o C,,WA TEXAS UTIllTIES ELE 11RIC COMPANY J T AL.*

[QMANCHE PEAK STEAM ELLCTRIC STATION. QNIT 1 QQCKET NO. 50-445 AMENDMENT TO FAC,[llTY OPERATING LICENSE Amendment No. 10 License No. NPF-87 1.

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

A.

The application for amendment by Icxas Utilities Electric Company (TV Electric) acting for itself and as agent for Texas Municipal Power Agency (licensees) dated February 28, 1992, as supplemented by letters dated April 6, 1992, and May 26, 1992, 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, as amended, 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 license amendment will not be inimical to the common defense and security c.r 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 Commission's regulations and all applicable requirements have been satisfied.

'The currcnt owners of the Comanche Peak Steam Electric Station are:

Texas Utilities Electric Company and Texas Municipal Power Agency.

Transfer of ownership from Texas Municipal Power Agency to Texas Utilities Electric Company was previously authorized by Amendment No. 9 to Construction Permit CPPR-126 on August 25, 1988 to take place in 10 installments as set forth in the Agreement attached to the application for Amendment dated March 4, 1988.

At the completion thereof, Texas Municipal Power Agency will no longer retain any ownership interest.

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-2 2.

Accordingly, the license is amended by changes to the Technical Specift-cations as indicated in the attachment to this license amendment and Paragraph 2.C.(2) of Facility Operating License No. NPF-87 is hereby amended to read as follows:

2.-

Technical _1ggeifications The Technical Specifications contained in Appendix A, as revised through Amendment No.

10, and the Environmental Protection Plan contained in Appendix B, both of which are uttached hereto, are hereby incorporated in the license.

The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.- The license amendment is effective as of its date of issuance to be implemented within thirty days of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION h ' I-y t.4 i., t Suzanne C. Black, Ofrector Project Directorate IV-2 Division of Reactor Projects lil/IV/V Office of Nuclear Reactor Regulation

Attachment:

Charges to the Technical Specifications Date of issuance:

June B, 1992 t

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ATTACHMENT TO LICENSE AMEFDMENT NO.

10 s

FACILITY OPERATING LICENSE NO. NPf-87 DOCKET NO. 50-446 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages.

The revised pages are identified by

-- amendment number and contain marginal lines indicating the area of change.

The corresponding overleaf pages are also provided to maintain document completeness, i

EEH0VE INSERT 3/4 3-2 3/4 3-2 l

3/4 3-5 3/4 3-5 L

3/4 3 6 3/4 3-6 3/4 3-8 3/4 3-8 i

3/4 3-11 3/4 3-11 3/4 3-12 3/4 3-12 7

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3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.1 As a minimum, the Reactor Trip System instrumentation channels and interlocks of Table 3.3-1 shall be OPERABLE.

APPLICABILITY:

As shown in Table 3.3-1.

ACTION:

As shown in Table 3.3-1.

t SURVEILLANCE REQUIREMENTS 4.3.1.1 Each Reactor Trip System instrumentation channel and interlock and the automatic trip logic shall be demonstrated OPERABLE by the performance of the Reactor Trip System Instrumentation Surveillance Requirements specified in Table 4.3-1.

4.3.1.2 The REACTOR TRIP 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 train such that both trains are tested at least once per 36 months and 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 channels in a specific Reactor trip function as shown in the

" Total No. of Channels" column of Ttble-3.3-1.

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TABLE 3.3-1 (Continued)

TABLE NOTATIONS i

aOnly if the reactor trip breakers happen to be in the closed position and the l

Control Rod Drive System is capable of rod withdrawal.

l b8elow the P-6 (Intermediate Range Neutron Flux-Interlock) Setpoint.

c i

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

j dAbove the P-7 (At Power) Setpoint

'The applicable MODES and ACTION statecients for these channels noted in Table 3.3-2 are more restrictive and therefore, applicable.

I Above the P-8 (3-loop flow permissive) Setpoint.

9Above the P-7 and below the P-8 Setpoints, hThe boron dilution flux doubling signals may be blocked during reactor startup.*

l I

1 Above the P-9.(Reactor trip on Turbine trip Interlock) Setpoint.

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 .

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

Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:

The inoperable channel is placed in the tripped condition a.

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, 3

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-hours per Specification 4.2.4.2.

T[iiiron Dilution Flux Doubling iequirements become effective for Unit 1 six months after criticality for Cycle 3.

COMANCHE PEAK - UNIT I 3/4 3-5 Amendment No.

10 l

_. _. _ _. _ _,. _. _ _. _.. _... -. _ _ -. ~.. _, _ _ _

- - - - - -. ~ - _ -

TABLE 3.3-1'(Continued)

ACTION.51 ATEMENTS (Continued)

ACTION 3 -

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

Below the P-6 (Intermediate Range Neutron flux Interlock) a.

Setpoint, restore the inoperable channel to OPEPABLE status prior to increasing 1HERMAL POWER above the P-6 Setpoint, j

b.

Above the P-6 (Intermediate Range Neutron flux Interlock) l Setpoint but below 10% of RATED THERMAL POWER, restore the inoperable channel to OPERABLE status prior to increasing 1HERMAL POWER above 104 of RATED THERMAL POWER.

ACTION 4 -

With the number of OPERABLE channels one less than the Minimum I

Channels OPERABLE requirement, suspend all operations involving j

positive reactivity changes.

ACTION 5.1 -

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 within the next hour open the reactor trip breakers and suspend all operations involving post-tive reactivity changes.

With no channels OPERABLE complete the above actions within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

ACTION 5.2*-

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 within the next hour verify either valve 105-8455 or valves 1C5-8560, FCV-IllB. 105-8439, ICS-8441, and 1C5-8453 are closed and secured in position, and verify this position at least once per 14 da.vs thereafter.

With no channels OPERABLE, complete the above actions within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months and verify the positions of the above valves at least once per 14 days thereafter.

ACTION 6 -

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 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.

ACTION 7 -

With less than the Minimum Number of Channels OPERABLE, within 1 r

hoec Ntermine by observation of the associated permissive annun-cihter window (s) that the interlock is in its required state for the existing plant condition, or apply Specification 3.0.3.

Boron Dilution Flux Doubling requirements become effective for Unit I six months after criticality for Cycle 3

. COMANCHE PFAf - OA> 1 3/4 3-6 Amendment No.

10

TABLE 3.3-1 (Continued)

ACTION STATEMENTS (Continued) 4 ACTION 8 - With the number of OPERABLE channels one less than the Minimum I

Channels OPERABLE requirement, be in at least 1107 STANDBY l

witnin 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; however, one cha3nel may be bypassed for up to

/ hours for surveillance testing per Specification 4.3.1.1 or maintenance, provided the other channel is OPERABLE.

ACTION 9 - With the number of OPERABLE channels one less than the Minimum i

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 r

breakers within the next hour, ACTION 10 - With the number of OPERABLE channels less th6n 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 .

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 l

diverse trip features is inoperable except for the time required

- l

'or performing maintenance to restore the breaker to OPERABLE status, during which time ACTION B applies.

I ACTION 12 - With the number of OPERABLE channels one less than the Tota)

Humber of Channels, STAR 10P and/or POWER OPERATION may proceed provided the following conditions are satisfied:

The inoperable channel is placed in the tripped condition a.

within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , and b.

The Minimum Channels OPERABLE requirement is met; however, the inoperable channsi 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 Specifications 4.3.1.1 or 4.2.5.4.

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REACTOR TRIP SYSItM INSTRUMENTATION SURVEILLANCE' REQUIREMENTS A

TRIP j;

ANALOG ACTUATING MGDES FOR 7

CHANNEL DEVICE WICH CHANNEL. ' CHANNEL OPERAT10NAL.

' OPERAT!0NAL ACTUATION SURVEILLANCE c.

2.i FUNCTIONAL' UNIT' CHECK CAi.IBRATION TEST

. TEST LOGIC TEST M QUIRED a

a a

1.

Manual Reactor Trip N.A.

N.A.

R(14)

N.A.

1,2,3,4,S

~

2.

Power Range, Neutron Flux a.

High Setpoint 5

D(2,'4),

Q N.A.

N.A.

1, 2 g

M(3, 4),

Q(4, 6),

R(4. 5)

C b.

Low Setpoint 5

R(4)-

5/U(1)

N. A.

N.A.

I,2 3.

Power Range Neutron Flux, N.A.

R(4)

Q N.A.

N. A.

1, 2 4

y High Positive Rate c>

4.

Power Range, Neutron Flux, N.A.

R(4)

Q N.A.

N.A.

' 1, 2

.High Negative Rate C

5.

Intermediate. Range, 5

R(4, 5) 5/U(1)

N. A.

N.A.

I,2 Neutron Flux

=

Source Range, Neutron Flu d,e-R(4, 13)

5/U(1),Q(9)

R(12)*

N.A.

2, 3, 4, 5 l

y 6.

a s 7.

Oveyt,emperaEure N-15 5

D(2, 4)

Q N.A.

N. A.

1, 2 M(3, 4) 4"

.Q(4,L6)

~

R(4,'5)

~.

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Y R(4, 5).

Q N.A.

N.A.

1, 2 8.

Overpower N-16 5

D(2,4) m d

s

=

~ 5-R Q(8)

N.A.

l, P

9.

Pressurizer Pressure--Low En 10.

Pressurizer Pressure--High 5 R

Q N.A.

N.A.

1, 2 a

.4

Boron DilutT65 Flux Doubling requirements become effective for Un'it 1 six months after criticality for Cycle 3.

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~____.__._.-. _._.._ _._ _ _ ______-_._.._._ _

1 TABLE 4.3,_1_(Continued)

TABLE NO.TATIONS i

h t

"Only if the reactor trip breakers happen to be in the close.1 position and the Control Rod Drive $ystem is capable of rod withdrawal.

i bBelow P-6 (Intermediate Range Neutron Flux Interlock) Setpoint.

\\

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

\\

dAbove the P-7 (At Power) Setpoint.

l "Above the P-9 (Reactor trip on Turbine trip Interlock) Setpoint.

(

(1)

If not performed in previous 31 days.

(2) Comparison of calorimetric to excore power and N-16 power indication tbove 15% of RATED THERMAL POWER.

Adjust excore channel and/or b l6 channel gains consistent with cainrimetric power if absolute difierence of the respective channel is greater inan 2%.

The. provisions of Specification 4.0.4 are not applicable for entry into MODE 1 or 2.

(3) Single point comparison of~incore to excore AXIAL FLUX DIFFERENCE above 15% of "ED THERMAL DOWER.

Recalibrate if the absolute dif ference is greater than or equal to 3%.

For the purpose of these surveillance requirements, "M" is defined as at least once per 31 EFPO.

The provisions of Specification 4.0.4 are not applicable f or entry into H0DE-1 or 2.

(4)' Nutron and N-16 detectors may be excluded from CHANNEL CALIBRATION.

(5) Detector plateau curves shall be obtained and evaluated.

For the Intermediate Range Neutron Flux, Power Range Neutron Flux and H-16 channels the provisions of Specification 4.0.4 are not applicable for entry into MODE 1 or 2.

(6)

Incore - Excore Calibration, above 75% of RATED THERMAL POWER.

For the purpose of these surveillance requirements

'.'Q" is defined as at least

.once per 92 EfPD.

The provisions of Specification 4.0.4 are not applic-able for entry into MODE 1 or 2.

(7) Each train shall be tested at least every 62 days on a STAGGERED TEST BASIS.

(8)' The MODES specified for these channels in Table 4.3-2 are more restrictive and therefore applicable.

(9)- Quarterly surveillance in MODES 3", 4", and 5 shall also include verifica+

8 tion that permissives P-6 end-P-10 are in their required state for exist-ing plant conditions by observation of the permissive annunciator window.

Quarterly surveillance shall include verification of the Boron Ollution i

Alarm Setpoint of less than or equal to an increare of twice the count rate within a 10-minute period.

l

BorUrTDilutiTin Flui Doubling requirements become effective for Unit I six months i

after criticality for Cycle 3.

l COMANCHE PEAX - UNIT-1 3/4 3 Amendment No. 10

. ~.

l.

TAB,LE 4 3-1 (Contin,ued) t TA@tE,NOTATJONi_(Continued]

[

-(10) Setpoint verifiention is not applicable.

(11) The TRIP ACTUATING DEVICE OPERATIONAL TEST snail independently verify the OPERABil,lTY of the undervoltage and strJnt, trip attachments of the reactor trip breakers.

s (12) At least once per 18 months during shutdown, verify that on a simulated Boron Dilution Flux Dot.bling test $ignal the normal CVCS discharge valves close and the centrifugal charging pumps suction valves froui the RW5T t

open;*

l I

(1?) With the high voltage setting varied as recommended by the manufacturer, an initial discriminator bias curve thall be measured for each detector, Subsequent discrimina',or tnas curves shall be obtained, evaluated and compared to the initial curves.

(14) The TRIP ACTUATING DEVICE OPERATIONAL TEST shall independently verify the

~

OPERABILITY of the undervoltage and shant trip circuits for l'ie Manual Reactor Trip function.

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

i (15) local tranual-shunt trip prior tn placing breaker in service.

I (15) Automatic.unddrvoltage trip.

r i

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Boron DITutlen riux~0otibTing requirements become effective for unit I six months after criticality for Cycle 3.

COMANCHE PEAK - UNIT 1 3/4 3-12 Amendment No.

10

-. -

ML20097H421

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