ML20095G893

Amends 44 & 30 to Licenses NPF-87 & NPF-89,respectively, Moving Shutdown Margin Limits from TS to COLR

ML20095G893
Person / Time
Site:	Comanche Peak
Issue date:	12/15/1995
From:	Polich T NRC (Affiliation Not Assigned)
To:
Shared Package
ML20095G899	List: ML20095G893 ML20095G900
References
NUDOCS 9512220007
Download: ML20095G893 (23)

Text

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UNITED STATES p

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NUCLEAR REGULATORY COMMISSION f

WASHINGTON, D.C. 20066 4001

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TEXAS UTILITJ S ELECTRIC COMPANY COMANCHE PEAK STEAM ELECTRIC STATION. UNIT 1 DOCKET NO. 50-445 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 44 License No. NPF-87 1.

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

A.

The application for amendment by Texas Utilities Electric Company (TU Electric, the licensee) dated August 15, 1995 (TXX-95215),

complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission'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 Comission; 1

C.

There is reasonable assurance:

(1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activitier will be conducted in compliance with the Comission's regulaties; D.

The issuance of this license 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 Commission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by ch4nges 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:

9512220007 951215 DR ADOCK 0500 5

' 2.

Technical Soecifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 44, 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 30 days.

FOR THE NUCLEAR REGULATORY COMMISSION

&lfD Timothy J. Volich, Project Manager Project Directorate IV-1 3

Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: December 15, 1995 l

. _ _. _.. _ _ _... ~ _ _ _ _ _ _ _ _ _ _ _ _.. _ _.

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UNITED STATES g

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NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20066-4001 o

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TEXAS UTILITIES ELECTRIC COMPANY COMANCHE PEAK STEAM ELECTRIC STATION. UNIT 2 DOCKET NO. 50-446 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 30 License No. NPF-89 1.

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

A.

The application for amendment by Texas Utilities Electric Company (TU Electric, the licensee) dated August 15, 1995 (TXX-95215),

complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission'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 Comission; C.

There is reasonable assurance:

(i) that the activities authorized by this amendment can be conducted without endangering the health a;,d safety of the public, and (ii) that such activities will be-conducted in compliance with the Comission's regulations; D.

The issuance of this license imendment 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 amer.dment is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in tha attachment to this license amendment and Paragraph ?.C.(2) of Facility Operating License No. NPF-89 is hereby amended to read.as follows:

?

i (2) Technical Soecifications and Environmental Protection Plan i

The Technical Specifications contained in Appendix A, as revised 1

through Amendment No. 30, 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.

f l

3.

This license amendment is effective as of its date of issuance to be implemented within 30 days.

FOR THE NUCLEAR REGULATORY COMMISSION i

& fO Timothy J.

olich, Project Manager Project Directorate IV-1 Division of Reactor Projects III/IV Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: December 15, 1995 l

l

ATTACHMENT TO LICENSE AMENDMENT NOS. 44 AND 30 FACILITY OPERATING LICENSE NOS. NPF-87 AND NPF-89 DOCKET NOS. 50 445 AND 50-446 Replace the following pages of the Appendix A Technical Specifications with the attached pages. The revised pages are identified by Amendment number and contain marginal lines indicating the areas of change. The corresponding overleaf pages are also provided to maintain document completeness.

REMOVE INSERT 3/4 1-1 3/4 1-1 3/4 1-3 3/4 1-3 3/4 1-8 3/4 1-8 3/4 1-10 3/4 1-10 3/4 1-13 3/4 1-13 B 3/4 1-1 B 3/4 1-1 i

B 3/4 1-2 B 3/4 1-2 B 3/4 1-3 B 3/4 1-3 6-20 6-20 6-21 6-21 6-21a 6-21a

1/4.1." REACTIVITY CONTROL SYSTEMS 3/4.1.1 BORATION CONTROL SHUTDOWN MARGIN - T, GREATER THAN 200*F LIMITING CONDITION FOR OPERATION l

3.1.1.1 The SHUTDOWN MARGIN shall be greater than or equal to the value specified in the Core Operating Limits Report (COLR).

APPLICABILITY: MODES 1, 2*, 3, and 4.

ACTION:

With the SHUTDOWN MARGIN less than the value specified in the COLR, l

immediately initiate and continue boration at greater than or equal to 30 gpm of a solution containing greater than or equal to 7,000 ppm boron or equivalent until the required SHUTDOWN MARGIN is restored.

SURVEILLANCE RE0VIREMENTS t

4.1.1.1.1 The SHUTDOWN MARGIN shall be determined to be greater than or equal to the value specified in the COLR:

l a.

Within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after detection of an inoperable control rod (s) and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter while the rod (s) is inoperable.

If the inoperable control rod is immovable or untrippable, the above required SHUTDOWN MARGIN shall be verified acceptable with an increased allowance for the withdrawn worth of the immovable or untrippable control rod (s);

b.

When in MODE 1 or MODE 2 with K.,, greater than or equal to 1 at least once per 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />'s by verifying that control bank withdrawal is within the limits of Specification 3.1.3.6; c.

When in MODE 2 with K.,, less than 1, within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> prior to achieving reactor criticality by verifying that the predicted critical control rod position is within the limits of Specification 3.1.3.6; d.

Prior to initial operation above 5% RATED THERMAL POWER after each fuel loading, by consideration of the factors of Specifica-tion 4.1.1.1.le. below, with the control banks at the maximum inser-tion limit of Specification 3.1.3.6; and 1

• See Special Test Exceptions Specification 3.10.1.

' Unit 2 - Amendment No.30,44 Unit 1 - Amendment No. 44 COMANCHE PEAK - UNITS 1 AND 2 3/4 1-1

REACTIVITY CONTROL SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

When in MODE 3 or 4, at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by consideration of e.

the following factors:

1)

Reactor Coolant System boron concentration, 2)

Control rod position, 3)

Reactor Coolant System average temperature, 4)

Fuel burnup based on gross thermal energy generation,

/

5)

Xenon concentration, and 6)

Samarium concentration, y

4.1.1.1.2 The overall core reactivity balance shall be compared to predicted values to demonstrate agreement within i 1% ak/k at least once per 31 Effective Full Power Days (EFPD). This comparison shall consider at least those factors stated in Specification 4.1.1.1.le., above. The predicted reactivity values shall be adjusted (normalized) to dorrespond to the actual core conditions prior to exceeding a fuel burnup of 60 EFPD after each fuel loading.

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

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' REACTIVITY CONTROL SYSTEMS SHUTDOWN MARGIN - T_; LESS THAN OR E0 VAL TO 200*F LIMITING CONDITION FOR OPERATION 3.1.1.2 The SHUTDOWN MARGIN shall be greater than or equal to the value specified in the Core Operating Limits Report (COLR).

APPLICABILITY: MODE 5.

ACTION:

With the SHUTDOWN MARGIN less than the value specified in the COLR, l

immediately initiate and continue boration at greater than or equal to 30 gpm of a solution containing greater than or equal to 7,000 ppm boron or equivalent until the required SHUTDOWN MARGIN is restored.

SURVEILLANCE RE0VIREMENTS 4.1.1.2 The SHUTDOWN MARGIN shall be determined to be greater than or equal to the value specified in the COLR:

l a.

Within I hour after detection of an inoperable control rod (s) and at least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> thereafter while the rod (s) is inoperable.

If the inoperable control rod is immovable or untrippable, the SHUTDOWN MARGIN shall be verified acceptable with an increased allowance for the withdrawn worth of the immovable or untrippable control rod (s); and b.

At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by consideration of the following factors:

1)

Reactor Coolant System boron concentration, 2)

Control rod position, 3)

Reactor Coolant System average temperature, 4)

Fuel burnup based on gross thermal energy generation, 5)

Xenon concentration, and 6)

Samarium concentration.

1 i

COMANCHE PEAK - UNITS 1 AND 2 3/4 1-3 Unit 1 - Amendment No. 5,44 Unit 2 - Amendment No. 30

REACTIVITY CONTROL SYSTEMS MODERATOR TEMPERATURE COEFFICIENT LIMITING CONDITION FOR OPERATION 3.1.1.3 The moderator temperature coefficient (MTC) shall be within the limits specified in the CORE OPERATING LIMITS RE, PORT (COLR). The maximum upper limit shall be less than or equal to +0.5 x 10' Ak/k/*F for power levels up to 70% RATED THERMAL POWER with a linear ramp to 0 Ak/k/*F at 100% RATED THERMAL POWER.

APPLICABILITY:

Beginning of Cycle Life (BOL) limit - MODES 1 and 2* only**.

End of Cycle Life (EOL) limit - MODES 1, 2, and 3 only**.

ACTION:'

j a.

With the MTC more positive than the BOL limit specified in the COLR, operation in MODES I and 2 may proceed provided:

i 1.

Control rod withdrawal limits are established and maintained sufficient to restore the MTC to less positive than the BOL limit specified in the COLR within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in HOT STANOBY within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />. These withdrawal limits shall be in addition to the insertion limits of Specification 3.1.3.6; 2.

The control rods are maintained within the withdrawal limits established above until a subsequent calculation verifies that the MTC has been restored to within its limit for the all rods withdrawn condition; and 3.

A Special Report is prepared and submitted to the Commission, pursuant to Specification 6.9.2, within 10 days, describing the value of the measured MTC, the interim control rod withdrawal limits, and the predicted average core burnup necessary for restoring the positive MTC to within its limit for the all rods withdrawn condition.

b.

With the MTC more negative than the E0L limit specified in the COLR, be in HOT SHUTDOWN within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

• With K,,, greater than or equal to 1.

• • See Special Test Exceptions Specification 3.10.3.

COMANCHE PEAK - UNITS 1 AND 2 3/4 1-4 Unit 1 - Amendment No. 6

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REACTIVITY CONTROL SYSTEMS FLOW PATHS - OPERATING LIMITING CONDITION FOR OPERATION 3.1.2.2 At least two of the following three boron injection flow paths shall be OPERABLE:

a.

The flow path from the boric acid storage tanks via either a boric acid transfer pump or a gravity feed connection and a charging pump to the Reactor Coolant System (RCS), and b.

Two flow paths from the refueling water storage tank via., centrifugal charging pumps to the RCS.

APPLICABILITY: MODES 1, 2, 3, and 4.*

ACTION:

With only one of the above required boron injection flow paths to the RCS OPERABLE, restore at least two boron injection flow paths to the RCS to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY and borated to a SHUTDOWN MARGIN equivalent to at least the value specified in the COLR at l 200*F within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; restore at least two flow paths to OPERABLE status within the next 7 days or be in COLD SHUTDOWN within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

SURVEILLANCE RE0VIREMENTS 4.1.2.2 At least two of the above required flow paths shall be demonstrated OPERABLE:

a.

At least once per 7 days by verifying that the temperature of the flow path from the boric acid storage tanks is greater than or equal to.65*F when it is a required water source; b.

At least once per 31 days by verifying that each valve (manual, power-operated, or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position; and c.

At least once per 18 months by verifying that the flow path required by Specification 3.1.2.2a. delivers at least 30 gpm to the RCS.

• A maximum of two charging pumps shall be OPERABLE whenever the temperature of one or more of the RCS cold legs is less than or equal to 350*F except when Specification 3.4.8.3 is not applicable. An inoperable pump may be energized for testing provided the discharge of the pump has been isolated from the RCS by a closed isolation valve (s) with power removed from the valve operator (s) or by a manual isolation valve (s) secured in the closed position.

COMANCHE PEAK - UNITS 1 AND 2 3/4 1-8 Unit 1 - Amendment No. 6,44 Unit 2 - Amendment No. 30

REACTIVITY CONTROL SYSTEMS 3/4.1.2 B0 RATION SYSTEMS

' FLOW PATH - SHUTDOWN LIMITING CONDITION FOR OPERATION 3.1.2.1 As a minimum, one of the following boron injection flow paths shall be OPERABLE and capable of being powered from an OPERABLE emergency power source:

A flow path from the boric acid storage tanks via either a boric acid a.

transfer pump or a gravity feed connection and a charging pump to the Reactor Coolant System if the boric acid storage tank in Specification 3.1.2.Sa. is OPERABLE, or b.

The flow path from the refueling water storage tank via a centrifugal charging pump to the Reactor Coolant System if the refueling water storage tank in Specification 3.1.2.5b. is OPERABLE.

APPLICA8ILITY:

MODES 5 and 6.

ACTION:

With none of the above flow paths OPERABLE or capable of being powered from an OPERA 8LE emergency power source, suspend all operations involving CORE ALTERATIONS or positive reactivity changes.

SURVEILLANCE REQUIREMENTS U

I 4.1.2.1 At least one of the above required flow paths shall be demonstrated OPERABLE:

At least once per 7 days by verifying that the temperature of the flow a.

path is greater than or equal to 65'F when a flow path from the boric acid storage tanks is used, and b.

At least once per 31 days by verifying that each valve (manual, power-operated, or automatic) in the flow path that is not locked, sealed, or otherwise secured in position, is in its correct position.

COMANCHE PEAK - UNITS 1 AND 2 3/4 1-7

4

\\

'REACTIVITYCONTROLSYSTEMS i

CHARGING PUMPS - OPERATING I

LIMITING CONDITION FOR OPERATION 3.1.2.4 At least two centrifugal charging pumps shall be OPERABLE.

APPLICABILITY: MODES 1, 2, 3*, and 4* **.

ACTION:

With only one charging pump OPERABLE, restore at least two charging pumps to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT STANDBY and borated to a 200*F within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />; restore at least two charging pumps to OPERABLE SHUTDOWN MARGIN equivalent to at least the value specified in the COLR at status within the next 7 days or be in COLD SHUTDOWN within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

SURVEILLANCE REQUIREMENTS 4.1.2.4.1 The required untrifugal charging pump (s) shall be demonstrated OPERABLE by testing pursuant to Specification 4.0.5.

4.1.2.4.2 The required positive displacement charging pump shall be demonstrated OPERABLE by testing pursuant to Specification 4.1.2.2.c.

4.1.2.4.3 -Whenever the temperature of one or more of the Reactor Coolant System (RCS) cold legs is less than or equal to 350*F, a maximum of two charging pumps shall be OPERABLE, except when Specification 3.4.8.3 is not applicable.

When required, one charging pump shall be demonstrated inoperable # at least once per 31 days by verifying that the motor circuit breakers are secured in the open position.

• The provisions of Specifications 3.0.4 and 4.0.4 are not applicable for entry into MODES 3 and 4 for the charging pump declared inoperable pursuant to Specification 3.1.2.4 provided the charging pump is restored to OPERABLE status within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> after entering MODE 3 or prior to the temperature of one or more of the RCS cold legs exceeding 375*F, whichever comes first.

3

• • In MODE 4 the positive displacement pump may be used in lieu of one of the required centrifugal charging pumps.

1. n inoperable pump may be energized for testing provided the discharge of A

the pump has been isolated from the RCS by a closed isolation valve (s) with power removed from the valve operator (s) or by a manual isolation valve (s) secured in the closed position.

COMANCHE PEAK - UNITS 1 AND 2 3/4 1-10 Unit 1 - Amendment No. 6,44 Unit 2 - Amendment No. 30

. -. ~ _ _

^

l REACTIVITY CONTROL SYSTEMS CHARGING PUMP - SHUTDOWN j

l LIMITING CONDITION FOR OPERATION l

3.1.2.3 At least one charging pump in the boron injection flow path required by l

Specification 3.1.2.1 shall be OPERABLE and capable of being powered from an OPERABLE emergency power source.

APPLICABILITY: MODES 5 and 6.

ACTION:

With no charging pump OPERABLE or capable of being powered from an'0PERABLE emergency power source, suspend all operations involving CORE ALTERATIONS or 31sitive reactivity changes.

i i

l SURVEILLANCE REQUIREMENTS i

4.1.2.3.1 At least once per 92 days the above required positive displacement charging pump shall be demonstrated OPERAELE by verifying that the flow path

)

required by Specification 3.1.2.la. is capable of delivering at least 30 gpm to the RCS; or l

4.1.2.3.2 The above required centrifugal charging pump shall be demonstrated i

OPERABLE by verifying, on recirculation flow, that a differential pressure across the pump of greater than or equal to 2370 psid is developed when tested pursuant to Specification 4.0.5.

4.1.2.3.3 A maximum of two charging pumps shall be OPERABLE, one charging pump shall be demonstrated inoperable

• at least once per 31 days, except when the reactor vessel head is removed, by verifying that the motor circuit breakers are secured in the open position.

• An inoperable pump may be energized for testing provided the discharge of the pump has been isolated from the RCS by a closed isolation valve (s) with power removed from the valve operator (s) or by a manual isolation valve (s) secured in the closed position.

COMANCHE PEAK - UNITS 1 AND 2 3/41-9

. REACTIVITY CONTROL SYSTEMS BORATED WATER SOURCES - OPERATING LIMITING CONDITION FOR OPERATION 3.1.2.6 As a minimum, the following borated water source (s) shall be OPERABLE as required by Specification 3.1.2.2:

a.

A boric acid storage tank with:

1)

A minimum indicated borated water level of 50%,

2)

A minimum baron concentration of 7000 ppm, and 3)

A minimum solution temperature of 65*F.

b.

The refueling water storage tank (RWST) with:

1)

A minimum indicated borated water level of 95%,

j 2)

A boron concentration between 2400 ppm and 2600 ppm, 3)

A minimum solution temperature of 40*F, and 4)

A maximum solution temperature of 120*F.

APPLICABILITY: MODES 1, 2, 3, and 4.

ACTION:

a.

With the boric acid storage tank inoperable and being used as one of the above required borated water sources, restore the tank to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least 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 borated to a SHUTDOWN MARGIN equivalent to at least the value specified in the COLR at 200*F; restore the boric acidstoragetanktoOPERABLEstatuswithinthenext7daysorbeinl COLD SHUTDOWN within the next 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />, b.

With the RWST inoperable, restore the tank to OPERABLE status within I hour or be in at least 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 in COLD SHUTDOWN within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />.

COMANCHE PEAK - UNITS 1 AND 2 3/4 1-13 Unit 1 - Amendment No. 5, M,25, 44 Unit 2 - Amendment No. 5r14, 30

REACTIVITY CONTROL SYSTEMS SURVEILLANCE RE0VIREMENTS 4.1.2.6 Each borated water source shall be demonstrated OPERABLE:

At least once per 7' days by:

a.

1)

Verifying the baron concentration in the water, 2)

Verifying the indica'ted borated water level of the water l

source, and 3)

Verifying the boric acid storage tank solution temperature when it is the source of borated water.

l l

b.

At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by verifying the RWST temperature when the outside air temperature is either less than 40*F or greater than 120*F.

l l

l l

l CDMANCHE PEAK - UNITS 1 AND 2 3/4 1-14 Unit 1 - Amendment No.26 Unit 2 - Amendment No.12

j

' 3/4.f REACTIVITY CONTROL SYSTEMS BASES 3/4.1.1 B0 RATION CONTROL 3/4.1.1.1 and 3/4.1.1.2 SHUTDOWN MARGIN A sufficient SHUTDOWN MARGIN ensures that:

(1) the reactor can be made subcritical from all operating conditions, (2) the reactivity transients asso-ciated with postulated accident conditions are controllable within acceptable limits, and (3) the reactor will be maintained sufficiently subcritical to preclude inadvertent criticality in the shutdown condition.

SHUTDOWN MARGIN requirements vary throughout core life as a function of fuel depletion, RCS boron concentration, and RCS T The most restrictive conditionoccursatEOL,withT.,atnoloadoperaUn.g temperature, and is associated with a postulated steam line break accident and resulting uncon-trolled RCS cooldown.

In the analysis of this accident, a minimum SHUTDOWN MARGIN (as specified in the COLR) is required to control the reactivity transient when T.,is above 200*F. Accordingly, the SHUTDOWN MARGIN i

requirement is based upon this liuiting condition and is consistent with FSAR safety analysis assumptions. With T. less than 200*F, the required SHUTDOWN MARGIN is based on the results of the, boron dilution accident analysis.

Since the actual overall core reactivity balance comparison required by 4.1.1.1.2 cannot be performed until after criticality is attained, this comparison.is not required (and the provisions of Specification 4.0.4 are not applicable) for entry into any Operational Mode within the first 31 EFPD following initial fuel load or refueling.

3/4.1.1.3 MODERATOR TEMPERATURE COEFFICIENT The limitations on moderator temperature coefficient (MTC) are provided to ensure that the value of this coefficient remains within the limiting condition assumed in the FSAR accident and transient analyses.

The MTC values of this specification are applicable to a specific set of plant conditions; accordingly, verification of MTC values at conditions other than those explicitly stated will require extrapolation to those conditions in order to permit an accurate comparison.

The most negative MTC value equivalent to the most positive moderator density coefficient (MDC) was obtained by incrementally correcting the MDC used in the FSAR analyses to nominal operating conditions. These corrections COMANCHE PEAK - UNITS 1 AND 2 8 3/4 1-1 Unit 1 - Amendment No. h44,44 Unit 2 - Amemdment No. 30

l REACTIVITY CONTROL SYSTEMS BASES MODERATOR TEMPERATURE COEFFICIENT (Continued) involved subtracting the incremental change in the MDC associated with a core condition of all rods inserted (most positive MDC) to an all rods withdrawn condition and, a conversion for the rate of change of moderator density with temperature at RATED THERMAL POWER conditions.

This value of the MDC was then transformed into the limiting End of Cycle Life (EOL) MTC value. The 300 ppa surveillance limit MTC value represents a conservative value (with corrections for burnup and soluble boron) at a core condition of 300 ppe equilibrium boron concentration and is obtained by making these corrections to the limiting EOL MTC value.

i The Surveillance Requirements for measurement of the MTC at the beginning and near the end of the fuel cycle are adequate to confirm that the MTC remains within its limits since this coefficient changes slowly due principally to the reduction in RCS boron concentration associated with fuel burnup.

3/4.1.1.4 MINIMUM TEMPERATURE FOR CRITICALITY This specification ensures that the reactor will not be made critical with the Reactor Coolant System average temperature less than 551*F. This limitation is required to ensure:

(1) the moderator temperature coefficient l

is within its analyzed temperature range, (2) the trip instrumentation is within its normal operating range, (3) the pressurizer is capable of being in an OPERABLE status with a steam bubble, and (4) the reactor vessel is above its minimum RTm temperature.

3/4.1.2 B0 RATION SYSTEMS The Boron Injection System ensures that negative reactivity control is available during each mode of facility operation. The components required to perform this function include:

(1) borated water sources, (2) charging pumps, (3) separate flow paths, (4) boric acid transfer pumps, and (5) an emergency power supply from OPERABLE diesel generators.

With the RCS average temperature above 200'F, a minimum of two boron injection flow paths are required to ensure single functional capability in i

the event an assumed failure renders one of the flow paths inoperable. The l

boration capability of either flow path is sufficient to provide the required SHUTDOWN MARGIN from expected operating conditions after xenon decay and cooldown to 200*F.

The maximum expected boration capability requirement occurs at E0L from full power equilibrium xenon conditions and requires 15,700 gallons of 7000 ppm borated water from the boric acid storage tanks or 70,702 gallons of 2400 ppm borated water from the refueling water storage tank l

(RWST).

l COMANCHE PEAK - UNITS 1 AND 2 B 3/4 1-2 Unit 1 - Amendment No. 5, M, M,25,44 Unit ? - Amendment No. h44,30

• REACTiVITYCONTROLSYSTEMS BASES B0 RATION SYSTEMS (Continued)

With the RCS temperature below 200*F, one Boron Injection System is acceptable without single failure consideration on the basis of the stable reactivity condition of the reactor and the additional restrictions prohibiting CORE ALTERATIONS and positive reactivity changes in the event the single Baron Injection System becomes inoperable.

The limitation for a maximum of two charging pumps to be OPERABLE and the requirement to verify one charging pump to be inoperable below 350*F provides assurance that a mass addition pressure transient can be relieved by the operation of a single PORV.

The limitation for minimum solution temperature of the borated water sources are sufficient to prevent boric acid crystallization with the highest allowable boron concentration.

The boron capability required below 200*F is sufficient to provide the required SHUTDOWN MARGIN after xenon decay and cooldown from 200*F to 140*F.

This condition requires either 1,100 gallons of 7000 ppm borated water from the boric acid storage tanks or 7,113 gallons of 2400 ppm borated water from the RWST.

As listed below, the required indicated levels for the boric acid storage tanks and the RWST include allowances for required / analytical volume, unusable volume, measurement uncertainties (which include instrument error and tank tolerances, as applicable), margin, and other required volume.

Ind.

Unusable Required Measurement Tank MODES Level Volume Volume Uncertainty Margin Other (gal)

(gal)

(gal)

(gal)

RWST 5,6 24%

98,900 7,113 4% of span 10,293 N/A 1,2,3,4 95%

45,494 70,702 4% of span N/A 357,535*

Boric 5,6 10%

3,221 1,100 6% of span N/A N/A Acid 5,6 20%

3,221 1,100 6% of span 3,679 N/A Storage (gravity feed)

Tank 1,2,3,4 50%

3,221 15,700 6% of span N/A N/A The OPERABILITY of one Baron Injection System during REFUELING ensures that this system is available for reactivity control while in MODE 6.

• Additional volume required to meet Specification 3.5.4.

COMANCHE PEAK - UNITS 1 AND 2 B 3/4 1-3 Unit 1 - Amendment No. 5,1",25,44 Unit 2 - Amendment No. 5de,30

RUCTIVITY CONTROL SYSTEMS BASES 314.1.3 M0VARLE CONTROL ASSEMBLIES The specifications of this section ensure that:

(1) acceptable power distribution limits are maintained (1) the minimum SHUTDOWN MARGIN is main-tained, and (3) the potential effects of rod misalignment on associated accident analyses are limited. OPERA 8ILITY of the control rod position indicators is required to determine control rod positions and thereby ensure comp 11ence with the control ved alignment and insertion limits. Verification that the Digital Rod Position Indicator agrees with the demanded position within i 12 steps at 24, 48,120 and 228 steps withdrawn for the Control Banks and 18, 210, and 228 steps withdrawn for the Shutdown Banks provides assurances that the Digital Rod Position Indicator is operating correctly over the full range of indication.

Since the Digital Rod Position Indication System does not indicate the actual shutdown rod position between 18 steps and 210 steps, only points in the indi-cated rangas are picked for verification of agreement with demanded position.

The ACTION statements which permit limited variations from the basic requirements are accompanied by additional restrictions which ensure that the original design criteria are met. Misalignment of a rod requires measurement of peaking facters and a restriction in THERMAL POWER. These restrictions provide assurance of fuel rod integrity during continued operation.

In addition, those safety analyses affected by a sisaligned rod are reevaluated to confirm that the results remain valid during future operation.

For Specification 3.1.3.1 ACTIONS b and c it is incumbent upon the plant to verify the trippability of the inoperable control rod (s). This may be by verification of a control system failure, usually electrical in natur6, or that the failure is associated with the control rod stepping mechanism.

In the event the plant is enable to verify the rM(s) trippability, it must be assumed to be untrippable and thus fall under the requirements of ACTION a.

Assuming a con-trolled shutdown from 2005 RATED THERMAL POWER, this allows approximately four hours for this verification.

The maximum rod drop time restriction is consistent with the assumed rod drop time used in the safety analyses. Measurement with T greater than or equal to 551T and with all reactor coolant pumps operating" ensures that the measured drop times will be representative of insertion times experienced during a Reactor trip at operating conditions.

Control r'od positions and OPERABILITY of the rod pos) Mon indicators are required to be verified on a nominal basis of once per 12 hwrs with more fre-quant verifications required if an automatic monitoring channel is inoperable.

'l These verification frequencies are adequate for assuring that the applicable LCOs are satisfied.

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

I _. _ _._ _ _ _.. _ __ ___ _ _ _ _ _

ADMINISTRATIVE CONTROLS MONTHLY OPERATING REPORTS (Continued) shall' be submitted on a monthly basis to t'ie U.S. Nuclear Regulatory Commission, Document Control Desk, Wash.i, ton, D.C. 20555, with a copy to the Regional Administrator of the Regional 0.fice of the NRC, no later than the l

15th of each month following the calendt e month covered by the report.

CORE OPERATING LIMITS REPORT j

6.9.1.6a Core operating limits shall i u established and documented in the CORE OPERATING LIMITS REPORT (COLR) be ;re each reload cycle or any remaining part of a reload cycle for the followi.!;:

1). Moderator temperature coefficM nt BOL and E0L limits and 300 ppm sur-3 i

veillance limit for Specifica. ion 3/4.1.1.3, i

2).

Shutdown Rod Insertion Limit ior Specification 3/4.1.3.5,.

f 3). Control Rod Insertion Limits t ir Specification 3/4.1.3.6, 4). AXIAL FLUX DIFFERENCE Limits aid target band for Specification j

3/4.2.1.,

j 5).

Heat Flux Hot Channel Factor, ((Z), W(Z), Fa", and the Fa (Z) c allowances for Specification 3/4.2.2, 6).

Nuclear Enthalpy Rise Hot Channel Factor Limit and the Power Factor l

i Multiplier for Specification 3/4.2.3.

)

7).

Shutdown Margin for Specifications 3/4.1.1.1,3/4.1.1.2,3/4.1.2.2, 1

3/4.1.2.4, and 3/4.1.2.6.

f 6.9.1.6b The following analytical methods used to determine the core 1

operating limits are for Units 1 and 2, unless otherwise stated, and shall be those previously approved by the NRC in:

1). WCAP-9272-P-A, " WESTINGHOUSE RELOAD SAFETY EVALUATION METHODOLOGY,"

July 1985 (W Proprietary).

(Methodology for Specifications 3.1.1.3 -

Moderator Temperature Coefficient, 3.1.3.5 - Shutdown Bank Insertion Limit, 3.1.3.6 - Control Bank Insertion Limits, 3.2.1 - Axial Flux Difference, 3.2.2 - Heat Flux Hot Channel Factor, 3.2.3 - Nuclear Enthalpy Rise Hot Channel Factor, 3/4.1.1.1,3/4.1.1.2,3/4.1.2.2, 3/4.1.2.4, and 3/4.1.2.6 - Shutdown Margin.)

2). WCAP-8385, " POWER DISTRIBUTION CONTROL AND LOAD FOLLOWING PROCEDURES -

TOPICAL REPORT," September 1974 (W Proprietary).

(Methodology for Specification 3.2.1 - Axial Flux Difference [ Constant Axial Offset Control).)

3).

T. M. Anderson to K. Kniel (Chief of Core Performance Branch, NRC) l January 31, 1980--

Attachment:

Operation and Safety Analysis Aspects of an Improved Load Follow Package.

(Methodology for Specification 3.2.1 - Axial Flux Difference (Constant Axial Offset Control).)

4). NUREG-0800, Standard Review Plan, U.S. Nuclear Regulatory Commission, Section 4.3, Nuclear Design, July 1981.

Branch Technical Position CPB 4.3-1, Westinghouse Constant Axial Offset Control (CAOC), Rev. 2, July 1981. (Methodology for Specification 3.2.1 - Axial Flux Difference (Constant Axial Offset Control].)

COMANCHE PEAK - UNITS 1 AND 2 6-20 Unit 1 - Amendment No. 5,14,34,44 Unit 2 - Amendment No. 40,30

ADMINISTRATIVE CONTROLS ANNUAL REPORTS (Continued) b.

The results of specific activity analyses in which the primary coolant exceeded the limits of Specification 3.4.7.

The following information shall be included:

(1) Reactor power history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded (in graphic and tabular format); (2) Results of the last isotopic analysis for radiciodine performed prior to exceeding the limit, results of analysis while limit was exceeded and results of one analysis after the radiciodine activity was reduced to less than limit.

Each result should include date and time of sampling and the radiciodine concentrations; (3) Clean-up flow history starting 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> prior to the first sample in which the limit was exceeded; (4) Graph of the I-131 concentration (pC1/gn) and one other radioidine isotope concentration (pCi/ge) as a function of time for the duration of the specific activity above the steady-state level; and (5) The time duration when the specific activity of the primary coolant exceeded the radiciodine limit.

ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT

• 6.9.1.3 The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted before May 1 of each year. The report shall include summaries, interpretations, and analysis of trends of the results of the Radiological Environmental Monitoring Program for the reporting period. The material provided shall be consistent with the objectives outlined in (1) the OOCH, and 1

(2) Sections IV.B.2, IV.B.3, and IV.C of Appendix I to 10 CFR 50.

M T & RADIOACTIVE EFFLUENT RELEASE REPORT **

l 6.9.J.4 The Annual Radioactive Effluent Release Report covering the operation l

of the unit during the previous year shall be submitted prior to May 1 of each year. The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit. The material provided shall be (1) consistent with the objectives outlined in the 00CM and PCP and (2) in conformance with 10 CFR 50.36a and Section IV.B.1 of Appendix ! to 10 CFR 50.

HD. HIE.Y 0flB811ML_BIEDRIIt 6.9.1.5 Routine reports of operating statistics and shutdown experience, including documentation of all challenges to the PORVs or safety valves, i

• A single submittal may be made for a multiple unit station.

• • A single submittal may be made for a multi-unit station. The submittal j

should combine those sections that are common to all units at the station; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit.

COMANCHE PEAK - UNITS 1 AND 2 6-19 Unit 1 - Amendment No. 25 Unit 2 - Amendment No.11

ADMINISTRATIVE CONTROLS CORE OPERATING LIMITS REPORT (Continued) 5). WCAP-10216-P-A, Revision lA, " RELAXATION OF CONSTANT AXIAL OFFSET CONTROL Fa SURVEILLANCE TECHNICAL SPECIFICATION," February 1994 (M Proprietary). (Methodology for Specification 3.2.2 - Heat Flux Hot Channel Factor (W(z) surveillance requirements for Fa Methodology).)

6). WCAP-10079-P-A, "NOTRUMP, A N00AL TRANSIENT SMALL BREAK AND GENERAL NETWORK CODE," August 1985, (W Proprietary).

7). WCAP-10054-P-A, " WESTINGHOUSE SMALL BREAK ECCS EVALUATION MODEL USING THE NOTRUMP CODE", August 1985, (W Proprietary).

l 8). WCAP-11145-P-A, " WESTINGHOUSE SMALL BREAK LOCA ECCS EVALUATION MODEL GENERIC STUDY WITH THE NOTRUMP CODE", October 1986, (M Proprietary).

l 9). RXE-90-006-P, " Power Distribution Control Analysis and Overtemperature N-16 and Overpower N-16 Trip Setpoint Methodology," February 1991.

(Methodology for Specification 3.2.1 - Axial Flux Difference, 3.2.2 -

Heat Flux Hot Channel Factor.)

10). RXE-88-102-P, "TVE-1 Departure from Nucleate Boiling Correlation",

January 1989.

11). RXE-88-102-P, Sup. 1, "TUE-1 DNB Correlation - Supplement 1",

December 1990.

12). RXE-89-002, "VIPRE-01 Core Thermal-Hydraulic Analysis Methods for Comanche Peak Steam Electric Station Licensing Applications", June 1989.

13). RXE-91-001, " Transient Analysis Methods for Comanche Peak Steam Electric Station Licensing Applir tions", February 1991.

14). RXE-91-002, " Reactivity Anomaly Events Methodology", May 1991.

(Methodology for Specification 3.1.1.3 - Moderator Temperature Coefficient, 3.1.3.5 - Shutdown Bank Insertion Limit, 3.1.3.6 -

Control Bank Insertion Limits, 3.2.1 - Axial Flux Difference, 3.2.2 -

Heat Flux Hot Channel Factor, 3.2.3 - Nuclear Enthalpy Rise Hot Channel Factor.)

15). RXE-90-007, "Large Break Loss of Coolant Accident Analysis Methodology", December 1990.

i 16). TXX-88306, " Steam Generator Tube Rupture Analysis", March 15, 1988.

17). RXE-91-005, " Methodology for Reactor Core Response to Steamline Break Events," May, 1991.

(Methodolooy fcr Specifications 3/4.1.1.1, 3/4.1.1.2, 3/4.1.2.2, 3/4.1.2./., and 3/4.1.2.6 - Shutdown Margin.)

COMANCHE PEAK - UNITS 1 AND 2 6-21 Unit 1 - Amendment No. 1,0,10,10, "',20,20,44 L

Unit 2 - Amendment No. t,7,14,20,30

ADMINISTRATIVE CONTROLS CORE OPERATING LIMITS REPORT (Continued) l Reference 18) is for Unit 2 only:

18). WCAP-9220-P-A, Rev. 1, " WESTINGHOUSE ECCS EVALUATION MODEL-1981 Version", February 1982 (H Proprietary).

19). RXE-94-001-A, " Safety Analysis of Postulated Inadvertent Boron Dilution Event in Modes 3, 4, and 5," February 1994.

(Methodology for Specifications 3/4.1.1.1,3/4.1.1.2,3/4.1.2.2,3/4.1.2.4,and 3/4.1.2.6 - Shutdown Margin.)

6.9.1.6c The core operating limits shall be determined so that all applicable limits (e.g., fuel thermal-mechanical limits, core thermal-hydraulic limits, ECCS limits, nuclear limits such as SHUTDOWN MARGIN, and transient and accident analysis limits) of the safety analysis are met.

6.9.1.6d The CORE OPERATING LIMITS REPORT, including any mid-cycle revisions or supplements thereto, shall be provided upon issuance, for each reload cycle, to the NRC Document Control Desk with copies to the Regional Administrator and Resident Inspector.

l COMANCHE PEAK - UNITS 1 AND 2 6-21a Unit 1 - Amendment No. G+,44 Unit 2 - Amendment No. 7, 30

.