Text

Amends 53 & 52 to Licenses DPR-80 & DPR-82,respectively, Revising Tech Specs to Allow Boric Acid Concentration in Boric Acid Tank to Be Reduced from 12 to 4 Weight Percent at Fourth Refueling Outage for Each Unit
	ML20042G587
Person / Time
Site:	Diablo Canyon
Issue date:	04/26/1990
From:	Larkins J; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20042G588	List: ML20042G587; ML20042G591;
References
	NUDOCS 9005150115
	Download: ML20042G587 (24)
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PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON NUCLEAR POWER PLANT, UNIT 1 DOCKET NO. 50-275 AMENDMENT TO FACILITY OPERATING L: CENSE Amendment No. 53 License No. DPR-80 1.

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

A.

The applica+, ion for amendment by Pacific Gas & Electric Company (the licensee), dated July 5,1989, as supplemented by letters dsted December 1,1989 and April 10, 1990, complies with the standards and requirements of the Atomic Energy Act of 1954, as amanded (the Act), and the Commission'c regulations set forth in 10 CFR Chapter I; r

B.

The facility will o>erate in conformity with the application

.the provisions of tie Act, and the regulations of the Commission; C.

Thereisreasonableassurance(i)thattheactivitiesauthorized 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 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.

9005150:15 900426 PDR ADoCK 05000273 F

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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. DPR-80 is hereby amended to read as follows:

(2) Technical Specifications The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 53, are hereby incorporated in the license.

Pacific Gr.s & Electric Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan, except where otherwise stated in specific license conditions.

3.

This license amendment becomes effective at the date of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION

/-./)s John T. Larkins Acting Director Project Directorate V l

Division of Reactor Projects - III.

IV, Y and Special Projr, cts Office of Nuclear Reactor Regulation

Attachment:

Chhnges to the Technical Specifications Date of Issuance:

April 26, 1990 Y

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PACIFIC GAS AND ELECTRIC COMPANY DIABLO CANYON NUCLEAR POWER PLANT, UNIT 2 DOCKET NO. 50-323 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 52 i

License No. DPR-82 i

1.

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

A.

The application for amendment by Pacific Gas & Electric Company (the. licensee), dated July 5,1989, as supplemented by letters dated December 1, 1989 and April 10, 1990, complies with the standards and requirements of the Atomic Energy Act of 1954, as i

amended (the Act), and the Commission's regulations set forth in 10 CFR Chapter I; B.

The facility will o)erate in conformity with the application, the provisions of tie Act, and the regulations of the Commission; 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 activities will be conducted in compliance with the Comission's regulations; D.

The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.-

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Cornission's regulations and all applicable requirements have been satisfied.

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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. DPR 82 is hereby amended to read as follows:

(2)

Technical Specifications i

The Technical Specifications contained in Appendix A and the Environmental Protection Plan contained in Appendix B, as revised through Amendment No. 52, are herely incorporated in the license.

Pacific Gas & Electric Company shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan, except where otherwise stated in specific license

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conditions.

3.

This license amendment becomes effective at the date of its issuance.

FOR THE NUCLEAR REGULATORY COMMISSION John T. Larkins, Acting Director Project Directorate V Division of Reactor Projects. III, IV, Y and Special Projects Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: April 26, 1990 l

l l.

ATTACHMENT TO LICENSE AMENDMENT NOS. 53 AND 52 EACILITY OPERATING LICENSE NOS. DPR-80 and DPR-82 DOCKET NOS. 50-275 AND 50-323 Replace the following ) ages of the Appendix 'A" Technical Specifications with the attached pages. T1e revised pages are identified b,y amendment number and contain vertical lines indicating the areas of change. Overleaf pages are also included, as appropriate.

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3/4 1-1 3/4 1-1 3/4 1-3 3/4 1-3 3/4 1-7 3/4 1-7 3/4 1-8 3/4 1-8 i

3/4 1-9 3/4 1-9 3/4 1-12 3/4 1-12 3/4 1-13 3/4 1-13 3/4 5-11 3/4 5-11 3/4 9-1 3/4 9-1 3/4 10-1 3/4 10-1 i

B 3/4 1-2 B 3/4 1-2 i

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.3/4.1 REACTIVITY CONTROL SYSTEMS 3/4.1.1 BORATION CONTROL SHUTDOWN MARGIN - T,y, GREATER THAN 200'F (IMITING CONDITION FOR OPERATION 3.1.1.1 The SHLITDOWN MARGIN shall be greater than or equal to 1.6% Ak/k.

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

ACTION:

1 For Unit 1 and 2, Cycle 4:

I With the SHUTDOWN MARGIN less than 1.6% Ak/k, immediately initiate and continue boration at greater than or equal to 10 ppm of a solution containing greater than or equal to 20,000 ppm boron or equivalent until the required SHUTDOWN MARGIN is restored.

For Unit I and 2, Cycle 5 and after:

With the SHUTDOWN MARGIN less than 1.6% Ak/k, 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 q uivalent until the required SHUTDOWN MARGIN is restored.

SURVEILLANCE REQUIREMENTS 4.1.1.1.1 The SHUTDOWN MARGIN shall be determined to be greater than or equal to 1.6% Ak/k:

Within I hour after detection of an inoperable control rod (s) and a.

at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter while the rod (s) is inoperable.

If the inoperable control rod is immovable or untrippable, the above l

required SHUTDOWN MARGIN shall be verified acceptable with an increased allowance for the withdrawn worth of the immovable or untrippable con-trol rod (s);

b.

When in MODES 1 or 2 with K,ff greater than or equal to 1, at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months by verifying that control bank withdrawal is within t

the limits of Specification 3.1.3.6; When in MODE 2 with K,7f less than 1, within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months prior to achiev-c.

l ing reactor criticality by verifying that the predicted critical control rod position is within the limits of Specification 3.1.3.6; l

l d.

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

See Specios Test Exceptions Specification 3.10.1.

AMENDMENT NOS. 53 AND 52 DIABLO CANYON - UNITS 1 & 2 3/4 1-1

i REACTIVITY CONTROL SYSTEMS

)

i SURVEILLANCE REQUIREMENTS (Continued)

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

the following factors:

i 1)

Reactor Conlant 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.

4.1.1.1.2 The overall core reactivity balance shall be compared to predicted

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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 correspond to the actual core conditions prior to exceeding a fuel burnup of 60 EFPD after each fuel

loading, t

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DIABLO CANYON - UNITS 1 & 2 3/4 1-2

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, REACTIVITY CONTROL SYSTEMS l

l SHUTDOWN MARGIN - T LESS THAN OR EQUAL TO 200'F ava l

LIMITING CONDITION FOR OPERATION i

3.1.1.2 The SHUTDOWN MARGIN shall be greater than or equal to 1% Ak/k.

APPLICABILITY: MODE 5.

' ACTION:

For Unit 1 and 2, Cycle 4:

J With the SHUTDOWN MARGIN less than 1% Ak/k, immediately initiate and continue i

boration at greater than or equal to 10 gpm of a solution containing greater than or equal to 20,000 ppm boron or equivalent until the required SHUTDOWN MARGIN is restored.

For Unit 1 and 2, Cycle 5 and after:

With the SHUTDOWN MARGIN less than 1% Ak/k, 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.

SURVEILLnNCE REQUIREMENTS 4.1.1.2 The SHUTDOWN MARGIN shall be determined to be greater than or equal

- to 1% Ak/k:

Within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months after detection of an inoperable control rod (s) and a.

at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months 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 f

withdrawn worth of the immovable or untrippable control rod (s); and b.

At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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.

DIABLO CANYON - UNITS 1 & 2 3/4 1-3 AMENDMENT NOS. 53 AND 52

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REACTIVITY CONTRDL SYSTEMS MODERATOR TEMPERATURE COEFFICIENT l

l LIMITING CONDITION FOR OPERATION 3.1.1. 3 The moderator temperature coefficient (MTC) shall be:

a.

Less positive than +5 x 10 8 Ak/k/*F for 05 to 70% RATED THERMAL POWER, and for > 70E to 100% RATED THERMAL POWER the MTC decreases linearly to 0 AK/R/*F for the all rods withdrawn condition, beginning of cycle life (80L); or b.

Less negative than -3.9 x 10'4 Ak/k/*F for all rods withdrawn, end of cycle life (EOL), RATED THERMAL POWER condition.

APPLICABILITY: Specification 3.1.1.3a. - MODES 1 and 2* onlyf.

Specification 3.1.1.3b. - MODES 1, 2, and 3 onlyf.

ACTION:

With the MTC more positive than the limit of Specification 3.1.1.3a.

a.

above, operation in MODES I and 2 may proceed provided:

1.

Control rod withdrawal limits are estabitsbed and maintained sufficient to restore the MTC to less positive than the limit of Specification 3.1.1.3a within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in HOT STANDBY i

within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . 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 verifles 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 posittee NTC to within its limit for the all rods withdrawn condition.

b.

With the MTC more negative than the limit of Specification 3.1.1.3b.

above, be in HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

The provisions of Specification 3.0.4 are not applicable.

c.

With K,ff greater than or equal to 1.

See Special Test Exceptions Specification 3.10.3.

I DIABLO CANYON - UNITS 1 & 2 3/4 1-4 Amendment Nos.10, 8

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. REACTIVITY CONTROL SYSTEMS F4.1.2 B0 RATION SYSTEMS FLOW PATH - SHUTOOWN LIMITING CONDITION FOR OPERATION l

3.1.2.1 As a minimum, one of the following boron injection flow paths shall be OPERABLE with motor-operated valves required to change position and pumps required to operate for boron in OPERABLE emergency power source:jection capable of being powered from an A flow path from the boric acid tanks via a boric acid transfer pump a.

and charging pump to the Reactor Coolant System if the boric acid storage tank in Specification 3.1.2.5a. is OPERABLE, or b.

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

APPLICABILITY:

MODES 5 and 6.

ACTION:

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

SURVEILLANCE REQUIREMENTS i

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

For Unit I and 2, Cycle 4:

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

heat traced portion of the flow path is greater than or equal to 145'F when a flow path from the boric acid 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 l

position, or For Unit 1 and 2, Cycle 5 and after:

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

a.

path is greater than or equal to 65'F when a flow path fres the boric acid 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

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or otherwise securied in position, is in its correct position.

DIABLO CANYON - UNITS 1 & 2 3/4 1-7 Amendment Nos. 53 and 52

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"_ REACTIVITY CONTROL SYSTEMS L

FLOW PATHS - OPEP.ATING.

LIMITING CONDITION FOR OPERATION 3.1.2.2 Each of the following boron injection flow paths shall be OPERABLE:

a.'

The flow path from the boric acid tanks via a boric acid transfer pump and a charging pump to the Reactor Coolant System (RCS), and-3 L

b..

The flow path from the refueling water storage tank via a charging pump to the RCS.

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

ACTION:

With the flow path from the boric acid tanks inoperable, restore the e

a.

1 inoperable tiow path to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be.in at least HOT STANDBY and borated to a SHUTDOWN MARGIN equivalent to at~

.least 1% Ak/k at 200*F-within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; restore the flow path to OPERABLE status within the next 7 days or be in COLD SHUTDOWN within the next 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months , b.

With the flow path from the refueling water storage tank inoperable,.

restore the' flow path to OPERABLE status within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or be in at least HOT STANDBY within the next 6_ hours and in. COLD SHUTDOWN 4

within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLAWCE REQUIREMENTS 4.1.2.2 Each of the above required flow paths shall be demonstrated OPERABLE:

For Unit I and 2, Cycle 4:

1

- At least once per 7 days by verifying that the temperature of the

'a.-

heat traced portion of the flow path from the boric acid tanks is greater than or equal to 145'F, b.

At least ~once per 31 days by verifying thst 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, At least once per 18 months by. verifying that each automatic valve c.

in the flow path actuates to its correct position on a safety injection test signal, and

0nly one boron injection flow path is required to be OPERABLE whenever the temperature of one or more of the RCS cold legs is less than or equal to 323*F.

1 - c LDIABLO' CANYON - UNITS 1 & 2-3/4 1-8 Amendment Nos. 53 and 52 f

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e REACTIVITY CONTROL SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) d.

At least once per 18 months' by verifying ti.it the flow path required by Specification 3.1.2.2a. delivers at least 10 gpm to. the RCS.

For Unit I and 2, Cycle'5 and after.:

a.

At least once per 7 days by verifying that the temperature of the flow path from the boric acid tanks is greater than or equal to 65'F.

b 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.

c.

At least once per 18 months by verifying that each automatic valve-in the flow path actuates to its correct posit $on on a safety injection test

-signal, and

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d..

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.

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.DIABLO' CANYON - UNITS 1 & 2 3/t. 1-9 Amendment Hos. 53 and 52

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9 REACTIVITY CONTROL SYSTEMS

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CHARGING PUMP - SHUTDOWN.

I LIMITING CONDITION FOR OPERATION i

3.1.2.3 At least or,o charging pump in the boron injection flow path required by Specifiestion 3.1.2.1 shall be O

- an'0PERABLE emergency power source.PERABLE and capable of being powered from y

APPLICABILITY:

MODES 5 and 6.

2 ACTION:

' With no charging' pump-OPERABLE or capable of being powered from an OPERABLE emergency power-source, suspend all operations involving CORE ALTERATIONS or

-positive reactivity changes, l

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I SURVEILLANCE-REQUIREMENTS 4.1.2.3.1.At-least the above required char.ging pump shall be demonstrated OPERABLE when tMted pursuant to Specification 4.0.5.-

In addition, when the above requireu u arging pump is a centrifugal charging pump, verify that,. on recircu'ation flow, the centrifuga'l charging pump develops a differential pressure of greater.than or equal to 2400 psid.

4.1.2.3.2 -All. centrifugal charging pumps, excluding the above required OPERABLE pump, shall be' demonstrated inoperable

at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , except when the reactor vessel. head is removed, by verifying that the motor breaker.D.C..

centrol power is de-ene'rgized.

An inoperable pump may be made OPERABLE for testing per Specification 4.0.5

-provided the discharge of the pump has been isolated from the Reactor Coolant i=

System by an isolation valve with power removed from the valve operator, or

.by a sealed closed manual isolation val e.

DIABLO CANYON - UNITS 1 & 2 2/4 ?.-10 8

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TREACTIVITY CONTROL SYSTEMS

,1 CHARGING PUMPS - OPERATING LIMITING CONDITION FOR OPERATION 3.1.2.4 At least two 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 hours or be in at least HOT STANDBY. and borated to a a

SHUTDOWN MARGIN equivalent to at least 1% Ak/k at 200*F within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ;_

restore at-least two charging pumps to OPERABLE status within the next 7 days or be in COLD SHUTDOWN within the next 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REQUIREMENTS 1

4.'1.2.4.1 At least two charging pumps shall be demonstrated OPERABLE when tested pursuant to Specification 4.0.5.-

In addition, when the above required charging pumps include a centrifugal charging pump (s), verify that, on recircu-lation flow, each required centrifuga1' charging pump (s)-develops a differential

_ pressure'of: greater than or equal' to 2400 psid.

4.1.2.4.2 All centrifugal charging pumps, except the above required OPERABLE i

pump, shall be demonstrated inoperable

at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months whenever the temperature of one or more of the Reactor Coolant System (RCS) cold legs is less than or equal to 323'F by verifying that the motor breaker D.C. control i

power is de-energized.

A maximum of one centrifugal charging pump shall be OPERABLE whenever the I

temperature of one or more of the RCS cold legs is less than or equal to 323'F.

An inoperable pump may be made OPERABLE for-testing per Specification 4.0.5 provided the discharge of the, pump has been isolated from the Reactor Coolant System by an isolation valve with power removed from the valve operator, or by a se& led closed manual isolation valve.

s DIABLO CANYON - UNITS l'& 2 3/4 1-11

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REACTIVITY CONTROL SYSTEMS BORATED WATER SOURCE - SHUT 00WN

' LIMITING CONDITION FOR OPERATION

, 3.1.2.5 As a minimum, one of the fol' lowing borated water sources shall be OPERABLE:

For Unit 1 and 2, Cycle 4:

'A Boric Acid Storage System and at least one associated heat tracing a.

channel with:

1)

A minimum contained borated water volume of 835 gallons, 2)

A boron concentration between 20,000 and 22,500 ppe, and 3)

A minimum-solution temperature of 145'F.

b.

The Refueling Water Storage Tank (RWST) with:-

1)

A minimum contained borated water volume of 50,000 gallons, 2)

A minimum baron concentration of 2300 ppm, and l

3)

A minimum solution temperature of 35'F, or For Unit 1 and 7., Cycle 5 and after:

a.

A Boric Acid Storage. System with:

1) A minimum contained borated water volume of 2,499 gallons, 2)- A boron concentration between 7,000 and 7,700 ppm, and

3) A minimum solution temperature of 65'F.

b.

The Refueling Water Storage Tank (RWST) with:

1) A minimum contained borated water volume of 50,000 gallons,

2) A minimum boron concentration of 2300 ppm, and

3) A minimum solution temperature of 35'F.

APPLICABILITY: -MODES 5 and 6.

ACTION:

With no borated water source OPERABLE, suspend all operatior.,, volving CORE ALTERATIONS or positive reactivity changes.

s SURVEILLANCE REQUIREMENTS 4.1.2.5 The above required borated water source shall be demonstrated OPERABLE:

a.

At least once per 7 days by:

1)

Verifying the boron concentration of the water, 2)

Verifying the contained borated water volume, and 3)

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

b.

At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by verifying the RWST temperature when it is the source of borated water and the outside ambient air temperature is less than 35'F.

DIABLO CANYON - UNITS 1 & 2 3/4 1-12 Amendment Nos.53 and 52

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' REACTIVITY CONTROL SYSTEMS BORATED WATER SOURCES - OPERATING l

LIMITING CONDITION FOR OPERATION t

3.1.2.6 Each of_the following borated water source (s) shall be OPERABLE:

For Unit l'and 2, Cycle 4:

A Boric Acid Storage System and at least one associated heat tracing a.

channel with:

J

-1)

A minimum contained borated water volume of 5106 gallons,

~ 2)

A boron concentration between 20,000 and 22,500 ppm, and 3)

A minimum solution temperature of 145'F.

b.

The Refueling Water Storage Tank (RWST) with:

i 1)

A contained borated water volume of greater than or equal to 400,000 gallons, 2)

A boron concentration between 2300 and 2500 ppm, and 3)'

A minimum solution temperature of 35'F, or

[

For Unit 1 and 2, Cycle 5 and af ter:

a.'

A Boric Acid Storage System with:

1) A minimum contained borated water volume of 14,042 gallons,

2) A boron concentration between 7,000 and 7,700 ppm, and

3) A minimum solution temperature of 65'F.

b.

The Refueling Water Storage Tank (RWST) with:

1) A minimum contained borated water _ volume of 50,000 gallons,.

2)- A boron concentration between 2300 and 2500 ppm, and

3) A minimum solution temperature of 35'F.

APPLICABILITY:

MODES 1, 2, 3 and 4.

3 ACTION:

With the Boric Acid Storage System inoperable, restore the system a.

to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 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 and borated to a SHUTDOWN MARGIN equivalent to at'least 1% Ak/k at 200*F; restore the Boric Acid Storage System to OPERABLE status within the next 7 days or be in COLD S4UTDOWN within the next 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

b.

With the RWST inoperable, restore the tank to OPERABLE status within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or he in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHU'00WH within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

!DIABLO CANYON - UNITS 1 & 2 3/4 1-13 Amendment Nos. 53 a d 52 n

,.._.7 p

p i

i

)

REACTIVITY CONTROL SYSTEMS-

$URVEILLANCE REQUIREMENTS 4.12.6 ~ Euch borated water source shall-be demonstrated OPERABLE:

a.

At least once per 7 days by:

1)

Verifying the boron concentration in the water, a

2)

Verifying the contained borated water voltsee of the water source, and r

3.)

Verifying the Boric Acid Storage System solution temperature, b.

At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by verifying the RWST temperature when the outside air temperature is less than 35'F.

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1 1

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DIABLO CANYON - UNITS 1 & 2 3/4 1-14

1,

'J, ;

EMERGENCY CORE COOLING SYSTEMS 3/4.5.5 REFUELING WATER STORAGE TANK LIMITING CONDITION FOR OPERATION 3.5.5 The Refueling Water. Storage Tank (RWST) shall be OPERABLE with:

a.

A minimum contained berated water volume of 400,000 gallons, b.

'A boron concentration of between 2300 ar.d 2500 ppa, and c.

A minimum solution temperature of 35'F.

APPLICABILITY: MODES 1-, 2, 3 and_4.

ACTION:

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 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the followir.g 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REQUIREMENTS 4.5.5 The RWST shall be demonstrated OPERABLE:

a.

At least once per 7 days by:

1)

Verifying the contained borated water volume in the tank, and

-2)

Verifying the boron concentration of the water.

b.

At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by verifying the RWST temperature when the outside ambient air temperature is less than 35'F.

DIABLO CANYON - UNITS 1 & 2 3/4 5-11 Amendmentr.. '53.and 52 e

mer

c ;

i 3/4.9: REFUELING' OPERATIONS

'3/4.9.1 BODNi ;0NCENTRATION LIMITING CONDITION FOR OPERATION-3.9.1' The boron concentration of all filled portions of the Reactor Coolant System and the refueling canal _ shall be maintained uniform and sufficient to ensure that the more restrictive of the following reactivity conditions is met

- either:

A K,ff of 0.95 or less, which includes a 1% Ak/k conservative a.

allowance for uncertainties, or b.

A boron concentration of greater than or equal to 2000 ppa, which includes a 50 ppm conservative allowance for uncertainties.

APPLICABILITY:

MODE 6*.-

ACTION:-

+

For' Unit 1 and 2, Cycle 4:

l With the-requirements of the above specification not satisfied, immediately suspent all operations involving CORE ALTERATIONS or positive reactivity changes'and initiate and continue boration at creater than or equal to 10 gpm of a solution containing greater than or equal to 20,000 ppm boron or its equivalent until K,ff is reduced to less than or equal to 0.95 or the boren concentration is restored to greater than or equal-to 2000 ppe, whichever is

'the more restrictive, or For Unit 1 and 2, Cycle 5 and after:

With the requirements of the above specification not satisfied,-immediately suspend all operations involving' CORE ALTERATIONS or positive reactivity changes and-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 its equivalent until K,ff-is reduced to less than or equal to 0.95 or the boron concentration is restored to greater than or equal to 2,000 ppm, whichever is the more. restrictive.

SURVEILLANCE REQUIREMENTS 4,9.1.1 The more restrictive of the above two reactivity conditions shall be determined prior to:

a.

Removing or unbolting the reactor vessel head, and b.

Withdrawal of any full-length control rod in excess of 3 feet from its fully inserted position within the reactor vessel.

4.9.1.2 The boron concentration of the Reactor Coolant System and the refueling canal shall be determined by chemical analysis at least once each 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

The reactor shall be maintained in MODE 6 whenever fuel is in the reactor 1

vessel with the vessel head closure bolts less than fully tensioned or with j

.the head removed..

.DIABLO CANYON - UNITS 1 & 2 3/4 9-1 Amendment Nos. 53 and 52

~

REFUELING OPERATIONS 3/4.9.2 INSTRUMENTATION

~

LIMI11NG CONDITION FOR OPERATION 3.9.2 As a minimus, two Source Ran each with continuous visual indica *.ge Neutron Flux Monitors shall be OPERABLE ion in the control room and one with audible indication in containment and the control roce.

APPLICABILITY: MODE 6.

ACTION:

a.

With one of the above required monitors inoperable or not operating, immediately suspend all operations involving CORE ALTERATIONS or positive reactivity changes except for latching the control rod drive mechanisa shaft to the rod cluster control assemblies and friction testing of individual control rods.

b.

With both of the above required monitors inoperable er not operating, determine the boron concentration of the Reactor Coolant System at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

SURVEILLANCE REQUIREMENTS 4.9.2 Each Source Range Neutron Flux Monitor shall be demonstrated OPERABLE by performance of:

a.

A CHANNEL CHECK at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months , b.

An ANALOG CHANNEL OPERATIONAL TEST within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months prior to the initial start of CORE ALTERATIONS, and c.

An ANALOG CHANNEL OPERATIONAL TEST at least once per 7 days.

4 9

OIABLO CANYON - UNITS 1 & 2 3/4 9-2 AMENDMENT N05.46 AND 45 DCT 3 01989

1 1

(

,9 3/4.10 SPECIAL TEST EXCEPTIONS.

3/4.10.,$HUTDOWN MARGIN LIMITING CONDITION FOR OPERATION 3.30.1 The SHUTDOWN MARGIN requirement of Specification 3.1.1.1 ma-a suspended for measurement of control rod worth and shutdown margin provided reactivity equivalent to at least the highest estimated control rod worth is available for' trip insertion from OPERABLE control rod (s).

APPL.ICABILITY:- MODE 2.

ACTION:

For Unit 1 and 2,: Cycle 4:

With any full-length. control rod not fully inserted and with less a.

than the above reactivity equivalent available for trip insertion immediately initiate and continue boration at greater than or equal to 10 gpm of a solution containing greater than or equal to 20,000 ppm boron or its e wivalent until the SHUTDOWN MARGIN required by Specification 3.1.:. 1 is restored.

b.

With all. full-length contro; rods; fully inserted and the reactor

.subcritical by less than the above reactivity equivalent, immediately initiate and continue boration at greater than or equal to 10 gpm of a solution containing greater than or equal to 20,000 ppe boron or its equivalent until the SHUTDOWN MARGIN required by Specification 3.1.1.1 is restored.

For Unit 1-and 2, Cycle 5 and after:

a.

With any full-length control-rod not fully inserted and with less than the above reactivity equivalent available for the trip insertion 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 its equivalent until the SHUTDOWN MARGIN required by Specification.3.1.1.1 is restored.

b...

With all full-length control rods fully inserted and the reactor subtritical by less than the above reactivity equivalent, 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 its equivalent until the SHUTDOWN MARGIN required by Specification 3.1.1.1 is restored.

SURVEILLANCE REQUIREMENTS 4.10.1.1. The position of each full-length control rod either partially or fully withdrawn shall be determined at least once per 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

4.10.1.2 Each full-length control rod not fully inserted shall ce demonstrated capable of full insertion when tripped from at least the 50% withdrawn position within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months prior to reducing the SHUTDOWN MARGIN to less than the-limits of

)

Specification 3.1.1.1.

DIABLO CANYON - UNITS 1 & 2 3/4 10-1 Amendment Nos. 53 and 52 l

N

~. -

.7 t

c ESPECIAL ~ TEST EXCEPTIONS:

L3/4.10.2 GROUP HEIGHT. INSERTION AND POWER DISTRIBUTION LIMITS LIMITING CONDITION FOR OPERATION L

3.10.2' The' croup height, insertion and power distribution limits of Specifice

.tions 3.1.3.1, 3.1.3.5, 3.1.3.6, 3.2.1, and 3.2.4 may be suspended during the H

performance of PHYSICS TESTS provided:

k b

a.

The THERMAL ^ POWER h, maintained ~1ess than or equal to 85% of RATED-4 THERMAL POWER, and-b.

The limits of Specifications 3.2.2.1 or 3.2.2.2 and 3.2.3 are maintained and determined at the frequencies specified in Specifica-tion 4.10.2.2 below.

p-o APPLICABILITY:

MODE 1.

ACTION:

)

With any of the limits of Specifications 3.2.2.1 or 3.2.2.2 or 3.2.3 being l

exceeded while the. requirements of Specifications 3.1.3.1.-3.1.3.5, 3.1.3.6, 3.2.1 and 3.2.4 are suspended, either:

l

[

Reduce TiiERMAL POWER ' sufficient to satisfy the ACTION require-a.

ments of Specifications 3.2.2.1 or-3.2.2.2 and 3.2.3, or l

b.

Be in HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

L SURVEILLANCE REQUIREMENTS-1 4.10.2.1 The THERMAL POWER.shalllbe. determined to be less than or equal to 8S%-

'ef RATED THERMAL POWER at least once per hour during PHYSICS TESTS.

o 4.10.2.2 The requirements of the below listed specifications shall be performed L

at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months during PHYSICS TESTS:

Specifications 4.2.2.1.2.or 4.2.2.2.2 and 4.2.2.1.3 or 4.2.2.2.3, and

~. -

a h

'b.

Specification 4.2.3.2.

i p

r DIABLO CANYON - UNITS 1 & 2 3/4 10-2 Amendment Nos. 37 and 36 Effective at end of Unit 1 Cycle 3 igm 10 W

_,r.m.

.... e.

=

4.

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3/4.1 REACTIVITY CONTROL SYSTEMS BASES 3/4.1.1 Q)RATIONCONTROL-3/4.1.1.1 and 3/4.1.1.2 SHUTDOW MARGIN

_A sufficient SHUT 00W MARGIN ensures that:

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

SHUTDOW MARGIN requirements vary throughout core 111fe as a function of fuel depletion,- RCS boron concentration, and RCS T,,9 The most restrictive condition occurs at E0L, with T,yg at no load operating temperature, and is associated with a postulated steam line break accident and resulting uncontrolled RCS coo 1 4wn.

In the analysis of this accident, a minimum SHUTDOW MARGIN of 1.6%

Ah/k is initially required to control the reactivity transient.

the SHUTDOW MARGIN requirement is based upon this limiting condition and isAccordingly consistent with FSAR safety analysis assumptions. With T,,,less than 200'F, the reactivity transients resulting from a postulated steam line break cooldown are minimal and a 1% Ak/k shutdown margin provides adequate protection.

3/4.1.1.3 MODERATOR TEMPERATURE COEFFICIENT

/

4k The limitations on ag.derator temperature coefficient (MTC) are provided to ensure that the value of this coefficient remains within the limiting conditions assumed in the FSAR accident and transient analysis.

The MC values of this specification are applicable to a specific set of plant conditions; eccordingly, 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 involved subtracting the incremental change in the MDC associated with a core condition of all rods inse.rted (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 MTC value -3.9 x 10 4 Ak/k/*F.

The MTC value of -3,0 x-10

Ak/k/*F represents a conservative value (with corrections for burnup and soluble boron) at a core condition of 300 ppa equilibrium boron concentration and is, obtained by making these corrections to the limiting MTC '

value of -3.9 x 10 4 Ak/k/*F.

The Surveillance Requirements for measurement of the MTC at the beginning and near the end of each fuel cycle are adequate to confirm that the MTC remains within its limits since this coefficient changes slowly due princi lly to the

, reduction in RCS boron concentration associated with fuel burnup. paIn addition, verification during startup usting at beginning of li#e hot zero power for each

(

cycle validates that the MTC parameters are within tir 11mits specified for all other pover levels.

DIABLO CANYON - UN'ITS 1 & 2 B 3/4 1-1 Amendment Nos.10, 8 l

a

,m v

.~

.R_EACTIVITY CONTROL SYSTEMS T

8ASES

'3/4.1.'1.4" MINIMUM TEMPERATURE FOR CRITICALITY l

This specification ensures'that the reactor will'not be made critical with the Reactor Coolant System average temperature less than 541*F.

This 111mitation is required to ensure:

(1) the moderator temperature coefficient is within its analyzed temperature ran

'within its normal operating range, (ge, (2) the protective instrumentation is

3) the pre!.suri..er is capable of being in

-an OPERABLE status with a steam bubble, and (4) the reactor vessel is above its minimum RT temperature.

s NDT

~3/4.1.2 'BORATION SYSTEMS The boron injection system ensures that negative reactivity control is available during each mode of facility operation.

The components required to

~

L perform this function include:

(1) borated water sources, (2) charging pumps, L

(3)' separate flow paths,-(4) boric acid transfer pumps, (5) associated heat tracing systems (only Unit 1 and~2, Cycle 4), end (6) an emergency. power supply from OPERABLE diesel generator;.

a With the RCS average temperature above 200'F, a minimum of two boron-

. injection flow paths are required to ensure single functional capability in o

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

The boration ~ capability of either flow path is sufficient to provide a SHUTDOWN g

H

-MARGIN from expected operating conditions of 1.6% Ak/k after xenon decay and

{

l.

cooldown to 200*F..The maximum expected boration capability requirement occurs at BOL when borating from hot zero power to COLD' SHUTDOWN and requires 5106 gallons 1

,H of 20,000 ppm (Unit I and 2, Cycle 4) or 14,042 gallons of 7,000 ppm (Unit 1 and 2, l

Cycle:S and after) borated water from the boric acid storage-tanks:or 65,784-gallons' of 2300 ppn borated water from the refueling water storage tank.

With the RCS tesperature below 200'F, one Boron Injection System is y

acceptable without single failure consideration on tho basis of-the stable l-reactivity condition of the reactor and'the additional restrictions prohibiting CORE ALTERATIONS'and positive reactivity change in the event the single injec-l tion system becomes inoperable.

l The boron capability required below 200'F is sufficient to provide a SHUTDOWN MARGIN of 1% Ak/k after xenon decay and cooldown from 200'F to 140'F.

This conciltion requires either 835 gallons of 20,000 ppm (Unit I and 2, Cycle 4) or_2,499 gallons of 7,000 ppm (Unit 1 and 2, Cycle 5 and after) borated water from

~ the boric acid storage tanks or 17,865 gallons of 2300 ppm borated water from the refueling water storage tank.

The limits-on contained water niome and boron concentration of the RWST also ensure a.pH value of between 8.0 and 9.5 for the solution recirculated

.within containment after a LOCA. This pH band minimizes the evolution of

.. iodine-and minimizes the effect of chloride and caustic stress corrosion on mechanical' systems and components.

'DIABLO CANYON'- UNITS 1 & 2 B 3/4 1-2 Amendment Nos. 53 and 52 i

_

ML20042G587

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