Text

Amends 20 & 6 to Licenses NPF-87 & NPF-89,respectively, Removing Refs to Source Range Boron Dilution Flux Doubling Instrumentation & Associated Action Statement,Surveillance & Implementation Footnotes
	ML20059J295
Person / Time
Site:	Comanche Peak
Issue date:	11/03/1993
From:	Black S; Office of Nuclear Reactor Regulation
To:	;
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ML20059J300	List: ML20059J295; ML20059J302;
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	NUDOCS 9311120156
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' W I,E UNITED STATES Y

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NUCLEAR REGULATORY COMMISSION

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WASHINGTON, D.C. 2055f4001 1

TEXAS UTILITIES ELECTRIC COMPANY COMANCHE PEAK STEAM ELECTRIC STATION. UNIT 1 DOCKET NO. 50-445 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 20 i

License No. NPF-87 1.

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

A.

The application for amendment by Texas Utilities Electric Company (TV Electric, the licensee) dated April 30, 1993, as supplemented by letter dated July 30, 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, 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 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.

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 Ucense No. NPF-87 is hereby amended to read as follows:

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9311120156 931103 E

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2.

Technical Specifications and Environmental Protection Plan The Technical Specifications-contained in Appendix A, as revised through Amendment No.

20, 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 15 days of its date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION pc%L Suzanne C. 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:

November 3, 1993 b

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f-tndlTED STATES i'

NUCLEAR REGULATORY COMMISSION gv,/

WASHINGTON, D.C. 20555 4 001 TEXAS UTILITIES ELECTRIC COMPANY COMANCHE PEAK STEAM ELECTRIC STATION. UNIT 2 DOCKET NO. 50-446 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 6 License No. NPF-89 1.

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

A.

The application for amendment by Texas Utilities Electric Company (TU Electric, the licensee) dated April 30, 1993, as supplemented by letter dated July 30, 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, 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 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.

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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 j

and Paragraph 2.C.(2) of Facility Operating License No. NPF-89 is hereby amended to read as follows:

1 (2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A,- as revised through Amendment No.

6, and the Environmental Protection Plan contained in Appendix B, are hereby incorporated into this license.

TV 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 i

implemented within 15 days of its date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION I

+0$clL Suzanne C. 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:

November 3, 1993 i

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'l ATTACHMENT TO LICENSE AMENDMENT NOS. 20AND 6 FACILITY OPERATING LICENSE NOS. NPF-87 AND NPF-89 DOCKET NOS. 50-445 AND 50-446 j

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.

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

REMOVE 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 I

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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.

SURVEILLANCE REOUIREMENTS 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 Table 3.3-1.

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

t-g TABLE 3.3-1 3g REACTOR TRIP SYSTEM INSTRUMENTATION E

HINIMUM

,g TOTAL NO.

CHANNELS CHANNELS APPLICABLE

^

FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION g

1.

Manual Reactor Trip 2

1 2

1, 2 1

2 1

2 3*, 4*, 5' 9.

~

g 2.

Power Range, Neutron Flux o

a.

High Setpoint 4

2 3

1, 2 2

N 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

N 5.

Intermediate Range, Neutron Flux 2

1 2

1*,

2 3

6.

Source Range, Neutron Flux EE gg a.

Reactor Trip and Indication 6

1)

Startup 2

1 2

2 4

m-2)

Shutdown 2'

1 2

3,4,5 5

k k 7.

Overtemperature N-16 4

2 3

1, 2 12

,S 8.

Overpower N-16 4

2-3 1, 2 12 AA d

9.

Pressurizer Pressure--Low 4

2 3

1 6

22PP 10.

Pressurizer Pressure--High=

4 2

3' 1, 2 6

.m.

o

,9 4

e a

9

TABLE 3.3-1 (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 the P-6 (Intermediate Range Neutron Flux Interlock) Setpoint.

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

dAbove the P-7 (At Power) Setpoint

' Deleted.

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

8Above the P-7 and below the P-8 Setpoints.

hgg)gg

'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:

i

?

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 , 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

=

Either, THERMAL POWER is restricted to less than or equal to c.

)

75% of RATED THERMAL POWER and the Power Range Neutron Flux Trip Setpoint is reduced to less than or equal to 85% of j

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.

l COMANCHE PEAK - UNITS 1 AND 2 3/4 3-5 Unit 1 - Amendment No. M,M,M,20 I

Unit 2 - Amendment No. E,6 I

TABLE 3.3-1 (Continued)

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ACTION STATEMENTS (Continued) 1 ACTION 3

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

Channels OPERABLE requirement and with the THERMAL POWER level:

)

i a.

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

Setpoint, restore the inoperable channel to OPERABLE status prior to increasing THERMAL POWER above the P Setpoint, j

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 i

Channels OPERABLE requirement, suspend all operations involving positive reactivity changes.

ACTION 5

- With the number of OPERAB*E channels one less than the Minimum l

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 .

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ACTION 6

- With the number of OPERABLE channels one less than the Total Number of Channelt, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied, a.

The inoperable channel is placed in the tripped condition b

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. hour determine by observation of the associated permissive i

annunciator window (s) that the interlock is in its required state for the existing plant condition, or apply Specification 3.0.3.

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COMANCHE PEAK - UNITS 1 AND 2 3/4 3-6 Unit 1 - Amendment No. M,44,%,20

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Unit 2 - Amendment No. E,6 m -

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TABLE 3,3-1 (Continued)

ACTION STATEMENTS (Continued) r ACTION 8 - 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 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 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 open the reactor trip breakers within the next hour.

ACTION 10 - With the number of OPERABLE channels less than the Total hu=ber 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 iL 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 ACTIDH 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 Minimus Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 6 hourt 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 byonssed 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.

l C0KANCHE PEAK - UNITS 1 AND 2 3/4 3-7 Unit 1 - Amendment No. 13

8 TABLE 4.3-1

,5 REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE RE0VIREMENTS 9

TRIP m

g ANALOG ACTUATING MODES FOR CHANNEL DEVICE WHICH CHANNEL CHANNEL OPERATIONAL OPERATIONAL ACTUATION SURVEILLANCE

[

FUNCTIONAL UNIT CHECK CALIBRATION TEST TEST LOGIC TES_T IS REOUIRED-z 3

1.

Manual Reactor Trip' N.A.

N.A.

R(14)

N.A.

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

[

2.

Power Range, Neutron Flux x

[

a.

High Setpoint S

D(2, 4),

Q N.A.

N.A.

1, 2 M(3, 4),

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 m1 4.

Power Range, Neutron Flux, N.A.

R(4)

Q N.A.

N.A.

1, 2 High Negative Rate w

m 5.

Intermediate Range, S

R(4, 5)

S/U(1)

N.A.

- l*,

2 Neutron Flux 6.

Source Range, Neutron Flux S

R(4, 13)

S/U(1), Q(9)

N.A.

2, 3, 4, 5 l

6 w

7.

Overtemperature N-16 S

D(2,4),

Q N.A.

N.A.

1, 2 M(3,4),

i e pp Q(4, 6),

jg R(4, 5) aa MS 8.

Overpower N-16 S

D(2, 4),

Q

- N.A.

N.A.

1, 2 A%

R(4,5)

' ff 9.

Pressurizer Pressure--Low S

R Q(8)-

N.A.

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10. Pressurizer Pressure--High S

R Q

N.A.

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TABLE 4.3-1 (Continued)

TABLE NOTATIONS a

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

l 4elow P-6 (Intermediate Range Neutron Flux Interlock) Setpoint..

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

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

l

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

t (1)

If not performed in previous 31 days.

1 i

(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 i

respective channel is greater than 25. The provisions of-'

-l Specification 4.0.4 are not applicable for entry.into MODE 1.or 2.

q (3)

Single point comparison of incore to excore AXIAL FLUX DIFFERENCE above l

)

15% of RATED THERMAL POWER. Recalibrate if the absolute difference is greater than or equal to 35.

For the purpose of these surveillance 1

requirements, 'N' is defined as at least once per 31 EFPD. The provisions of Specification 4.0.4 are not applicable for entry into NDDE 1 or 2.

l (4) Neutron 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 N-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 THERNAL-POWER.- For the purpose of these surveillance requirements 'Q' is. defined as at least once-l 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.

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

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TABLE 4.3-1 (Continued)

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.

_l-(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) Deleted.

(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.

COMANCHE PEAK - UNITS I AND 2 3/4 3-12 Unit t - Amendment No. M,M,M,20 Unit c - Amendment No. 2,6

ML20059J295

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