Text

Amends 16 & 2 to Licenses NPF-87 & NPF-89,respectively, Revising TS to Extend Period for Removal of Operability Requirements of Boron Dilution Mitigation Sys
	ML20045H102
Person / Time
Site:	Comanche Peak
Issue date:	06/28/1993
From:	Black S; Office of Nuclear Reactor Regulation
To:	;
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UNITED STATES

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NUCLEAR REGULATORY COMMISSION g

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TEXAS UTILITIES ELECTRIC COMPANY. ET AL.*

COMANCHE PEAK STEAM ELECTRIC STATION. UNIT 1 00CKET NO. 50-445 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.16 License No. NPF-87 1.

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

A.

The application for amendment by Texas Utilities Electric Company (TU Electric) acting for itself and as agent for Texas Municipal Power Agency (licensees) dated May 14, 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 license 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 Commission's regulations and all applicable requirements have been satisfied.

The current owners of the Comanche Peak Steam Electric Station aret 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 4,11988.

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

9307190062 930628 PDR ADDCK 05000445' P

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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. NPF-87 is hereby amended to read as follows:

2.

Technical Specifications and Environmental Protection plan The Technical Specifications contained in Appendix A, as revised through Amendment No.16, and the Environmental Protection Plan contained in Appendix B, both of which are attached 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 Ck Suzanne

. Black, Director Project Directorate IV-2 Division of Reactor Projects ill/IV/V Office of Nuclear Reactor Reguiation

Attachment:

Changes to the Technical Specifications Date of Issuance: June 28, 1993 e

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[o UNITED STATES g

NUCLEAR REGULATORY COMMISSION n

WASHINGTON. D. C. 20555 E

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'$9.....,o TEXAS UTILITIES ELECTRIC COMPANY. ET AL.*

COMANCHE PEAK STEAM ELECTRIC STATION. UNIT 2 DOCKET NO. 50-446 AMENDMENT TO FACillTY OPERATING LICENSE Amendment No. 2 License No. NPF-89 1.

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

A.

The application for amendment by Texas Utilities Electric Company (TV Electric) acting for itself and as agent for Texas Municipal Power Agency (licensees) dated May 14, 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 license 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 Commission's regulations and all applicable requirements have been satisfied.

The current 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. 8 to Construction Permit CPPR-127 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.

, 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-89 is hereby amended to read as follows:

(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 2, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated into this license.

TU Electric shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

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

FOR THE NUCLEAR REGULATORY COMMISSION WM Suzanne

. Black, Director Project Directorate IV-2 Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: June 28, 1993 8

..-... _. _..m ATTACHMENT TO LICENSE AMENDMENT NOS. 16 AND 2 FACILITY OPERATING l! CENSE NOS. NPF-87 AND NPF-89 DOCKET NOS. 50-445 AND 50-44k 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.

REMQEE INSERT 3/4 3-2 3/4 3-2 3/4 3-5 3/4 3-5 3/4 3-6 3/4 3-6 3/4 3-8 3/4 3-8 3/4 3-12 3/4 3-12 s

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3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION LIMITING CONDITION FOP 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.

SURVEILLANCE RE0VIREMENTS 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 i

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

i i

I a

CDMANCHE PEAK - UNITS 1 AND 2 3/4 3-1

TABLE 3.3-1 g

h REACTOR TRIP SYSTEM INSTRUMENTATION E

m MINIMUM A

TOTAL NO.

CHANNELS CHANNELS APPLICABLE M'

FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION 1.

Manual Reactor Trip 2

1 2

1, 2 1

d 2

1 2

3*, 4*,

5" 9

2.

Power Range, Neutron Flux o

m a.

High Setpoint 4

2 3

1, 2 2

b.

Low Setpoint 4

2 3

1*,

2 2

3.

Power Range, Neutron Flux, 4

2 3

1, 2 2

High Positive Rate R

4.

Power Range, Neutron Flux, 4

2 3

1, 2 2

High Negative Rate Y

5.

Intermediate Range, Neutron Flux 2

1 2

1*,

2 3

6.

Source Range, Neutron Flux a.

Reactor Trip and Indication EE 1)

Startup 2

1 2

2 4

b

E 2)

Shutdown 2

1 2

3,4,5 5.1 m-h b.

Boron Dilution Flux Doubling

2 1

2 3,4, 5

5.1,5.2 EE 7.

Overtemperature N-16 4

2 3

1, 2 12 gg aa yl 8.

Overpower N-16 4

2 3

1, 2 12 d

9.

Pressurizer Pressure--Low 4

2 3

I 6

10.

Pressurizer Pressure--High 4

2 3

1, 2 6

mg f

Boron Dilution Flux Doubling requirements become effective for Unit I and Unit 2 after criticality for Unit 1, Cycle 4.

a,

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TABLE 3.3-1 (Continuedl TABLE NOTATIONS

'Only if the reactor trip breakers happen to be in the closed position and the Control Rod Drive System is capable of rod withdrawal.

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

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

dAbove the P-7 (At Power) Setpoint

' Deleted.

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

i SAbove the P-7 and below the P-8 Setpoints.

hThe boron dilution flux doubling signals may be blocked during reactor startup.*

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

q 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 , i

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, and c.

Either, THERMAL POWER is restricted to less than or equal Eto 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 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months per Specification 4.2.4.2.

4

Bcron Dilution Flux Doubling requiremerits become effective for Unit 1 and Unit 2 after criticality for Unit 1, Cycle 4.

COMANCHE PEAK - UNITS 1 AND 2 3/4 3-5 Unit 1 - Amendment No. 40,13,44,16 Unit 2 - Amendment No. 2 P

TABLE 3.3-1 (Continued)

ACTION STATEMENTS (Continued)

ACTION 3

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

a.

Below the P-6 (Intermediate Range Neutron Flux Interlock)

Setpoint, restore the inoperable channel to OPERABLE status prior to increasirg THERMAL POWER above the P-6

Setpoint, b.

Above the P-6 (Intermediate Range Neutron Flux Interlock)

Setpoint but below 10% of RATED THERMAL POWER, restore the inoperable channel to OPERABLE status prior to increasing THERMAL POWER above 10% of RATED THERMAL POWER.

ACTION 4

- With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, suspend all operations involving--

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 positive 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 CS-8455 or valves CS-8560, FCV-IllB, CS-8439, CS-8441, and CS-8453 are closed and secured in position, and verify this position at least once per 14 days 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 I hour determine by observation of the associated permissive-annunciator window (s) that the interlock is in its required

Boron Dilution Flux Doubling requirements become effective for Unit I and Unit 2 after criticality for Unit 1, Cycle 4.

COMANCHE PEAK - UNITS 1 AND 2 3/4 3-6 Unit 1 - Amendment No. 10,14, 1 6 Unit 2 - Amendment No. 2 L

?

TABLE 3.3-1 (Continued)

ACTION STATEMENTS (Continued)

ACTION 8 - With the number of. 0PERABLE channels one less than the Minimum Channels OPERABLE requirement, be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; however, one channel 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 Specification 4.3.1.1 or. maintenance, provided the other channel is OPERABLE.

ACTION 9 - With the number of OPERABLE channels one less than u e 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 open the reactor trip breakers within the next hour.

ACTION 10 - With the number of OPERABLE channels less than 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 diverse trip fea-tures is inoperable except for the time required for performing maintenance to restore the breaker to OPERABLE status, during which time ACTION 8 applies.

ACTION 12 - 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 per Specifications 4.3.1.1 or 4.2.5.4.

ACTION 13 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; however, one 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 per Specification 4.3.1.1, provided the other channel is OPERABLE.

COMANCHE PEAK - UNITS 1 AND 2 3/4 3-7 Unit 1 - Amendment No. 13

n TABLE 4.3-1 REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS 2

TRIP ANALOG ACTUATING MODES FOR A

CHANNEL DEVICE WHICH M

CHANNEL.

CHANNEL OPERATIONAL OPERATIONAL ACTUATION SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST TEST LOGIC TEST IS REOUIRED i

1.

Manual Reactor Trip N.A.

N.A.

R(14)

N.A.

1, 2, 3', 4',5*

2.

Power Range, Neutron Flux a.

High Setpoint S

D(2,4),

Q N.A.

N.A.

1, 2 M(3, 4),

m Q(4,6),

R(4, 5) b.

Low Setpoint S

R(4)

S/U(1)

N.A.

1*,

2 3.

Power Range, Neutron Flux, N.A.

R(4)

Q N.A.

N.A.

1, 2

{

High Positive Rate w

4.

Power Range, Neutron Flux, N.A.

R(4)

Q N.A.

N.A.

1, 2 c'o High Negative Rate 5.

Intermediate Range, S

R(4, 5)

S/U(1)

N.A.

1*,

2 Neutron Flux CC 6

3. 3.

6.

Source Range, Neutron Flux S

R(4, 13)

S/U(1), Q(9) R(12)*

N. A.'

2, 3, 4, 5 7.

Overtemperature N-16 S

D(2, 4),

Q N.A.

N.A.

1, 2 -

M(3, 4),

'RR Q(4, 6),

((

R(4, 5) as 8.

Overpower N-16 S

D(2, 4),

Q N.A.

N.A.

1, 2 R(4, 5) zz d

PP 9.

Pressurizer Pressure--Low S

R Q(8)

'N.A.

N.A.

I "h

10. Pressurizer Pressure--High S

R Q

N.A.

1, 2 L

Boron Dilution Flux Doubling requirements become effective for Unit I and Unit 2 after criticality for Unit 1, Cycle 4.

e

E i

k TABLE 4.3-1 (Continued)

TABLE NOTATIONS

0nly if the reactor trip breakers happen to be in the closed position and the Control Rod Drive System is capable of rod withdrawal.

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

6

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

i dAbove the P-7 (At Power) Setpoint.

'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 above 15% of RATED THERMAL POWER. Adjust excore channel and/or N-16 channel gains consistent with calorimetric power if absolute difference of the j

respective channel is greater than 2%. The provisions of Specification 4.0.4 are not applicable for entry into MODE 1 or 2.

i (3) Single point comparison of incore to excore AXIAL FLUX DIFFERENCE above 15% of RATED THERMAL POWER.

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

For the purpose of these surveillance requirements, "M" is defined as at least once per 31 EFPD. The provisions of Specification 4.0.4 are not applicable for entry into MODE 1 or 2.

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

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

For the 1

Intermediate Range Neutron Flux, Power Range Neutron Flur and N-16 channels i

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 applicable 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.

COMANCHE PEAK - UNITS 1 AND 2 3/4 3-11

I k-TABLE 4.3-1 (Continuedl TABLE NOTATIONS (Continued)

(9) Quarterly surveillance in MODES 3', 4', and 5' shall also include verifica-tion that permissives P-6 and P-10 are in their required state for existing plant conditions by observation of the permissive annunciator window.

Quarterly surveillance shall include verification of the Boron Dilution -

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

(10) Setpoint verification is not applicable.

(11) The TRIP ACTUATING DEVICE OPERATIONAL TEST shall independently verify the OPERABILITY of the undervoltage and shunt trip attachments of the reactor trip breakers.

(12) At least once per 18 months during shutdown, verify that on a simulated Boron Dilution Flux Doubling test signal the normal CVCS discharge valves close and the centrifugal charging pumps suction valves from the RWST open.*

(13) With the high voltage setting varied as recommended by the manufacturer, an initial discriminator bias curve shall be measured for each detector.

Subsequent discriminator bias 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 shunt trip circuits for' the Manual Reactor Trip Function. The test shall also' verify the OPERABILITY of.the Bypass Breaker trip circuit (s).

(15) local manual shunt trip prior to placing breaker in service.

(16) Automatic undervoltage trip.

Baron Dilution Flux Doubling requirements become effective for Unit I and Unit 2 after criticality for Unit 1, Cycle 4.

COMANCHE PEAK - UNITS 1 AND 2 3/4 3-12 Unit 1 - Amendment No. 10,44, 16 Unit 2 - Amendment No. 2

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ML20045H102

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