Text

Amends 112 & 106 to Licenses NPF-35 & NPF-52,respectively, Revising TS to Reduce Slope Axial Power Imbalance Penalty & Increasing B Concentration Limits in Clas,Rwst,Rcs & Refueling Canal During Mode 6 Conditions
	ML20062L343
Person / Time
Site:	Catawba ; (NPF-35-A-112, NPF-52-A-106)
Issue date:	12/17/1993
From:	Plisco L; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20062L347	List: ML20062L343; ML20062L348;
References
	NUDOCS 9312300004
	Download: ML20062L343 (27)
	v • d • e

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E UNITED STATES l'

NUCLEAR REGULATORY COMMISSION (w

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wasmucTon. o c..-os, sum DUKE POWER COMPANY NORTH CAROLINA ELECTRIC MEMBERSHIP CORPORATION SALUDA RIVER ELECTRIC COOPERATIVE. INC.

DOCKET NO. 50-413 CATAWBA NUCLEAR STATION. UNIT 1 AMENDMENT TO FACIllTY OPERATING LICENSE 1

Amendment No.112 License No. NPF-35 1.

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

A.

The application for amer.dment to the Catawba Nuclear Station, Unit 1 (the facility) Facility Operating License No. NPF-35 filed by the Duke Power Company, acting for itself, North Carolina Electric Membership Corporation and Saluda River Electric Cooperative, Inc. (licensees), dated September 7, 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 as set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapter I; D.

The issuance of this amendment will nat 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.

9312300004 931217 PDR ADOCK 05000413 P

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2.

Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license amendment, and Paragraph 2.C.(2) of Facility Operating License No. NPF-35 is hereby amended to read as follows:

Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.112, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license.

Duke Power Company 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.

FOR THE NUCLEAR REGULATORY COMMISSION P

oren R. Plisco, Acting Director Project Directorate II-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Technical Specification Changes Date of Issuance:

December 17, 1993 9

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pa arc <,

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E UNITED STATES l

i!

NUCLEAR REGULATORY COMMISSION t

,/

WASHINGTON, D.C. 20555-0001 y

DUKE POWER COMPANY i

NORTH CAROLINA MUNICIPAL POWER AGENCY NO. 1 PIEDMONT MUNICIPAL POWER AGENCY DOCKET NO. 50-414 CATAWBA NUCLEAR STATION. UNIT 2 Af1ENDMENT TO FACILITY OPERATING LICENSE Amendment No. 106 License No. NPF-52 1.

The Nuclear Regulatory Commission (the Commission) has found that; j

A.

The application for amendment to the Catawba Nuclear Station, Unit 2 (the facility) Facility Operating License No. NPF-52 filed by the Duke Power Company, acting for itself, North Carolina Municipal Power Agency No. I and Piedmont Municipal Power Agency (licensees), dated September 7, 1993, complies with the standards l

and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations as set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; l

C.

There is reasonable assurance (i) that the activities authorized l

by this amendment can be conducted without endangering the health I

and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations set forth in 10 CFR Chapte.' I; 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.

l

r l

I 2.

Accordir, gly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachment to this license amendment, and Paragraph 2.C.(2) of Facility Operating License No. NPF-52 is hereby amended to read as follows:

l Technical Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No.106, and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license. Duke Power Company shall operate the facility in accordance with the Technical Specification?, and the Environmental Protection Plan.

3.

This license emendment is effective as of its date of issuance.

FOR TH NUCLEAR REGULATORY COMMISSION AA'*1 V

oren R. Plisco, Acting Director Project Directorate 11-3 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Attachment:

Technical Specification Changes

)

Date of Issuance:

December 17, 1993 1

i

-l i

4 ATTACHMENT TO LICENSE AMENDMENT NO.112 FACILITY OPERATING LICENSE NO. NPF-35 DOCKET NO. 50-413 AND TO LICENSE AMENDMENT NO. 106 FACILITY OPERATING LICENSE NO. NPF-52 DOCKET NO. 50-414 l

Replace the following pages of the Appendix "A" Technical Specifications with the enclosed pages.

The revised pages are identified by Amendment number and contain vertical lines indicating the areas of change.

Remove Paaes Insert Paces 2-8 A2-8 B2-8 3/4 1-11 3/4 Al-11 3/4 B1-11 3/4 1-12 3/4 Al-12 3/4 BI-12 3/4 5-1 3/4 A5 3/4 B5-1 1

3/4 5-2 3/4 A5-2 i

i 3/4 B5-2 3/4 5-11 3/4 45-11 3/4 65-11 3/4 9-1 3/4 A9-1

)

3/4 89-1 B 3/4 1-3 B 3/4 1-3 B 3/4 1-3a B 3/4 1-3a B 3/4 5-1 B 3/4 5-1 B 3/4-9-1 B 3/4 9-1 IV IV Va Va j

VIII VIII X

X

n TABLE 2.2-1 (Continued)

E

$2 TABLE NOTATIONS (Continued) i NOTE 1:

(Continued) e:5

[

T' s 590.8'F (Nominal T,y allowed by Safety Analysis);

K 0.001414; 3

Pressurizer pressure, psig; P

=

P' = 2235 psig (Nominal RCS operating pressure);

Laplace transform operator, s";

S

=

and f,(AI) is a function of the indicated difference between top and bottom detectors of the power-range neutron ion chambers; with gains to be selected based on measured instrument response during plant STARTUP tests such that:

6 (1)

For q, - q, between -39.9% and +3.0%,

and q,re percent RATED THERMAL POWER in the top and bottom halve the. core respectively,nd q f,(AI) = 0, where q a a

+

(ii)

For each percent AI that the magnitude of q - q is more negative than -39.9%, the oT Trip Setpoint shall be automatically reduced by $.910% of AT,; and (iii)

For each percent AI that the magnitude of q - q is more positive than +3.0%, the oJ Trip Setpoint shall be automatically reduced by l.52 (Unit 1) of oT.

o a

S NOTE 2:

The channel's maximum Trip Setpoint shall not exceed its computed Trip Setpoint by more 5

than 3.0%.

5 ro N

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TABl.E 2.2-1 (Continued) c,

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- g; TABLE NOTATIONS (Continued) eo NOTE 1:

(Continued) f5 T' s 590.8"F (Nominal T,,, allowed by Safety Analysis);

0.001414; e

no K

=

3 Pressurizer pressure, psig; P

=

7 P' = 2235 psig (Nominal RCS operating pressure);

Laplace transform operator, s ';

5

=

and f (AI) is a function of the indicated difference between top and bottom detectors of the power-i range neutron ion chambers; with gains to be selected based on measured instrument response during 4

plant STARTUP tests such that:

eu 2l-(i)

For qt - q,between -39.9% and +3.0%,

f (AI) = 0, where qt and gn are percent RATED THERMAL POWER in the top and bottom halves of ithe core respectively, ~ and gr + go, is total THERMAL POWER in percent of RATED THERMAL POWER; (ii)

For each percent AI that the magnitude of q, - gn is more negative than -39.9%, the AT Trip Setpoint shall be automatically reduced by 3.910% of AT ; and o

(iii)

For each percent AI that the magnitude of q1 - gn is more ' positive than +3.0%, the AT Trip

. Setpoint shall be automatically reduced by 2.316% (Unit 2) of AT,,.

l So jf NOTE 2:

.The channel?s maximum Trip'Setpoint shall not exceed its computed Trip Setpoint by more i

g than 3.0%.

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I i

REACTIVITY CONTROL SYSTEMS BORATED WATER SOURCE - SHUTDOWN LIMITING CONDITION FOR OPERATION

)

3.1.2.5 As a minimum, one of the following borated water sources shall be OPERABLE:

a.

A Boric Acid Storage System with:

l 1)

A minimum contained barated water volume of 12,000 gallons, 2)

A minimum boron concentration of 7000 ppm, and 3)

A minimum solution temperature of 65 F.

b.

The refueling water storage tank with:

j 1)

A minimum contained borated water volume of 45,000 gallons, 2)

A minimum boron concentration of 2175 ppm, and l

3)

A minimum solution temperature of 70 F.

APPLICABILITY: MODES 5 and 6. (Unit 1) l ACTION:

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

SURVEllLANCE 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. hours by verifying the refueling water storage tank temperature when it is the source of borated water and the outside air temperature is less than 70 F.

CATAWBA - UNIT.1 3/4 Al-ll Amendment No.112 -

1

RtACTIVITY CONTROLSYSTEMS BORATID WATER SOURCE - SHUTDOWN LIMITING CONDITION FOR OPERATION 3.1.2.5 As a minimum, one of the following borated water sources shall be OPERABLE:

a.

A Boric Acid Storage System with:

1)

A minimum contained borated water volume of 12,000 gallons, 2)

A minimum boron concentration of 7000 ppm, and 3)

A minimum solution temperature of 65'F.

b.

The refueling water storage tank with:

1)

A minimum contained borated water volume of 45,000 gallons, 2)

A minimum boron concentration of 2000 ppm, and 3)

A minimum solution temperature of 70"F.

APPLICABILITY: MODES 5 and 6. (Unit 2) l ACTION:

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

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 refueling water storage tank temperature when it is the source of borated water and the outside air temperature is less than 70*F.

CATAWBA - UNIT 2 3/4 B1-Il Amendment No.106 l

.~

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 System with:

l 1)

A minimum contained borated water volume of 22,000 gallons, l

i 2)

A minimum boron concentration of 7000 ppm, and 3)

A minimum solution temperature of 65 F.

b.

The refueling water. storage tank with:

1)

A contained borated water volume of at least 363,513 gallons, I

2)

A minimum boron concentration of 2175 ppm,

)

3)

A minimum solution temperature of 70 F, and 4)

A maximum solution temperature of 100 F.

APPLICABIllTY:

MODES 1, 2, 3, and 4. (Unit 1)

ACTION:

l a.

With the Boric Acid Storage System inoperable and being used as one of the above required borated water sources, restore the system 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 I

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

b.

With the refueling water storage tank 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 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 following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

o j

CATAWBA - UNIT 1 3/4 Al-12 Amendment No.112 l

-j

l i

REACTIVITY CONTROL SYSTEMS B0 RATED WATER SOURCES - OPERATING l

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 System with 1)

A minimum contained borated water volume of 22,000 gallons, 2)

A minimum boron concentration of 7000 ppm, and 3)

A minimum solution temperature of 65*F.

b.

The refueling water storage tank with:

1)

A contained borated water volume of at least 363,513 gallons, 2)

A minimum boron concentration of 2000 ppm, 3)

A minimum solution temperature of 70*F, and 4)

A maximum solution temperature of 100*f.

APPLICABILITY: MODES 1, 2, 3, and 4. (Unit 2) l ACTION:

a.

With the Boric Acid Storage System inoperable and being used as one i

of the above required borated water sources, restore the system 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 i

least 1% ok/k at 200*F; restore the Boric Acid Storage System 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 refueling water storage tank inoperable, restore the tank to

-0PERABLE 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 following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

1 i

~l CATAWBA - UNIT 2 3/4 B1-12 Amendment No.106 l

l

l 3/4.5 EMERGENCY CORE COOLING SYSTEMS 3 /4. 5.'1 ACCUMULATORS COLD LEG INJECTION LIMITING CONDITION FOR OPERATION 3.5.1 Each cold leg injection accumulator shall be OPERABLE with:

a.

The discharge isolation valve open, b.

A contained borated water volume of between 7630 and 8079 gallons, c.

A boron concentration of between 2000 and 2275 ppm, l

d.

A nitrogen cover-pressure of between 585 and 678 psig, and e.

A water level and pressure channel OPERABLE.

i APPLICABILITY: MODES 1, 2, and 3*. (Unit 1) l ACTION-a.

With one cold leg injection accumulator inoperable, except as a result of a closed isolation valve or boron concentration less than 2000 ppm, restore the inoperable accumulator to OPERABLE status l

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 i

and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

i i

b.

With one cold leg injection accumulator inoperable due to the isolation valve being closed, either immediately open the isolation valve or be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and-in HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

c.

With one accumulator inoperable due to boron concentration less than 2000 ppm and:

l 1)

The volume weighted average boron concentration of the accumula-tors 2000 ppm or greater, restore the inoperable accumulator to l

OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of the low boron determination 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 reduce Reactor Coolant System pressure to less than 1000 psig within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

2)

The volume weighted average boron concentration of the accu-mulators less than 2000 ppm but greater than 1900 ppm, restore l

the inoperable accumulator to OPERABLE status or return the volume weighted average boron concentration of the accumulators ~

to greater than 2000 ppm and l

6

Reactor Coolant System pressure above 1000 psig.

1 CATAWBA - UNIT 1 3/4 AS-1 Amendment No. 112 l

1 b

3/4.5 EMERGENCY CORE COOLING SYSTEMS E

3/4.5.1 ACCUMULATORS COLD LEG INJECTION i

LIMITING CONDITION FOR OPERATION 3.5.1 Each cold leg injection accumulator shall be OPERABLE with:

a.

The discharge isolation valve open, b.

A contained borated water volume of between 7630 and 8079 gallons, c.

A boron concentration of between 1900 and 2100 ppm, d.

A nitrogen cover-pressure of between 585 and 678 psig, and e.

A water level and pressure channel OPERABLE.

APPLICABILITY: MODES 1, 2, and 3*. (Unit 2) l ACTION:

a.

With one cold leg injection accumulator inoperable, except as a result of a closed isolation valve or baron concentration less than 1900 ppm, restore the inoperable accumulator 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 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months 3

and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b.

With one cold leg injection accumulator inoperable due to the isolation valve being closed, either immediately open the isolation valve or be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

c.

With one accumulator inoperable due to boron concentration less than i

1900 ppm and:

1)

The volume weighted average boron concentration of the accumula-tors 1900 ppm or greater, restore the inoperable accumulator to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of the low boron determination 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 reduce i

Reactor Coolant System pressure to less than 1000 psig within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

2)

The volume weighted average boron concentration of the accu-mulators less than 1900 ppm but greater than 1800 ppm, restore the inoperable accumulator to OPERABLE status or return the volume weighted average boron concentration of the accumulators to greater than 1900 ppm and

Reactor Coolant System pressure above 1000 psig.

CATAWBA - UNIT 2 3/4 B5-1 Amendment No.106 l

j

l'

}

EMERGENCY CORE COOLING SYSTEMS

- LIMITING CONDITION FOR OPERATION ACTION: (Continued) enter ACTION c.1 within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months of the low baron determination or be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and reduce Reactor Coolant System pressure to less than.1000 psig within the fol-lowing 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

3)

The volume weighted average boron concentration of the accumula-tors 1900 ppm or less, return the volume weighted average boron concentration of the accumulators to greater than 1900 ppm-and-enter ACTION c.2 within I hour of the low baron determination or--

be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and reduce Reactor-i' Coolant System pressure to less than.1000 psig within the following-6 hours.

SURVEILLANCE REQUIREMENTS 4.5.1 Each cold leg injection accumulator shall be demonstrated OPERABLE:

a.

At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months by:

1)

Verifying, by the absence of alarms, the contained borated water' I

volume and nitrogen cover-pressure in the tanks, and j

t 2)

Verifying that each cold leg injection accumulator isolation.

.l valve is open.

l b.

At least once per 31 days and within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months after each solution volume increase of greater than or equal to 75 gallons by verifying j

the boron concentration of the accumulator-solution; l

L c.

At least once per 31 days when the Reactor Coolant System pressure is l

above 2000 psig by verifying that power is removed from the isolation valve operators on Valves.N154A, NI65B,' NI76A, and NI888 and that the 1

respective circuit breakers are padlocked; and l

l d.

At least once per 18 months by verifying that each cold leg ' injection accumulator isolation valve opens automatically under each-of'the i

following conditions:**

1)

When an actual or a simulated Reactor Coolant System pressure signal exceeds the P-11 ~ (Pressurizer Pressure Block-of Safety.

Injection) Setpoint, and j

l 2)

Upon receipt of a Safety Injection test signal.

j r

i

- This surveillance need not be performed until prior to entering HOT STANDBY-t l

following the Unit I refueling.

i CATAWBA - UNIT 1 3/4 A5-2 Amendment No.112 l-i

!~

EfiERGENCY CORE COOLING SYSTEMS

- LIMITING CONDITION FOR OPERATION ACTION: (Continued)

F enter ACTION c.1 within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months of the low boron determination or be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and reduce Reactor Coolant System pressure to less than 1000 psig within the fol-3 lowing 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

3)

The volume weighted average boron ' concentration of the accumula-tors 1800 ppm or less, return the volume weighted average baron concentration of the accumulators to greater than 1800 ppm and enter ACTION c.2 within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months of the low boron determination or be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and reduce Reactor Coolant System pressure to less than 1000 psig within the i

following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

F SURVEILLANCE REQUIREMENTS 4.5.1 Each cold leg injection accumulator shall be demonstrated OPERABLE:

j a.

At least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months by:

i 1)

Verifying, by the absence of alarms, the contained barated water'

+

volume and nitrogen cover-pressure in the tanks, and 2)

Verifying that each cold leg injection accumulator isolation valve is open.

b.

At least once per 31 days and within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months after each solution volume increase of greater than or' equal to 75 gallons by verifying the boron concentration of the accumulator solution; c.

At least once per 31 days when the Reactor Coolant System pressure is' l

above ?000 psig by verifying that power is removed from the isolation valve operators on Valves NI54A, NI65B, NI76A, and NI88B and that the respective circuit breakers are padlocked; and d.

At least once per 18 months by verifying that each cold leg injection accumulator isolation valve opens automatically under each of the following conditions:**

t 1)

When an actual or a simulated React or Coolant System pressure j

signal exceeds the P-ll (Pressurir c Pressure Block of Safety Injection) Setpoint, and

'l 2)

Upon receipt of a Safety-Injection test signal.

l

)

- This surveillance need not be performed until prior to entering H0T STANDBY-

-following the Unit I refueling.

CATAWBA - UNIT 2 3/4 B5-2 Amendment No.106 i

i

i i

EMERGENCY CORE COOLING SYSTEMS 3 / 4. 5 ~. 4 REFUELING WATER STORAGE TANK LIMITING CONDITION FOR OPERATION i

3.5.4 The refueling water storage tank shall 'txa OPERABLE with:

i a.

A minimum contained borated water volume of 363,513 gallons, b.

A boron concentration of between 2175 and 2275 ppm of boron, l

f c.

A minimum solution temperature of 70 F, and d.

A maximum solution temperature of 100 F.

l APPLICABILITY: MODES 1, 2, 3, and 4. (Unit 1)

ACTION:

+

With the refueling water storage tank inoperable, restore the tank to OPERABLE status within I hour or be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

i i

SURVEILLANCE RE0VIREMENTS 4.5.4 The refueling water storage tank shall be demonstrated OPERABLE:

i a.

At least once per 7 days by:

1)

Verifying the contained borated water level in the tank, and 2)

Verifying the boron concentration of the water.

l b.

At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by verifying the refueling water storage tank temperature when the outside air temperature is less than 70 F or greater than 100 F CATAWBA - UNIT 1 3/4 A5-11 Amendment No.112

E'MERGENCY CORE COOLING SYSTEMS 3/4.5.4 REFUELING WATER STORAGE TANK LIMITING CONDITION FOR OPERATION 3.5.4 The refueling water storage tank shall be OPERABLE with:

a.

A minimum contained borated water volume of 363,513 gallons, b.

A boron concentration of between 2000 and 2100 ppm of boron, c.

A minimum solution temperature of 70 F, and d.

A maximum solution temperature of 100 F.

APPLICABILITY:

MODES 1, 2, 3, and 4. (Unit 2)

{

i ACTION:

With the refueling water storage tank 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 be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

SURVEILLANCE REQUIREMENTS 4.5.4 The refueling water storage tank shall be demonstrated OPERABLE:

a.

At least once per 7 days by:

1)

Verifying the contained borated water level 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 refueling water storage tank temperature when the outside air temperature is less than 70 F or greater than 100 F.

CATAWBA - UNIT 2 3/4 B5-11 Amendment No. 106

3'/4. 9 REFUELING OPERATIONS 3/4.9.L BORON CONCENTRATION 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.

A K, of 0.95 or less, or g

b.

A boroi concentration of greater than or equal to 2175 ppm.

l APPLICABILITY:

MODE 6.* (Unit 1) g ACTION:

i 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 i

of a solution containing greater than or equal to 7000 ppm boron or its equi.

valent until K is reduced to less than or equal to 0.95 or the boron con-ar centration is restored to greater than or equal to 2000 ppm, whichever is the

)

more restrictive.

q S!JRVEILLANCE 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 i

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 per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

i

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

vessel with the vessel head closure bolts less than fully tensioned or with the head removed.

i CATAWBA - UNIT 1

3/4 A9-1 Amendment No.

112

I 3/4.9 REFUELING OPERATIONS l

f 3/4.9.1 BORON CONCENTRATION j

LIMITING CONDITION FOR OPERATION I

3.9.1 The baron concentration of all filled portions of the Reactor Coolant System and the refueling canal shall be maintained uniform and sufficient to 1

ensure that the more restrictive of the following reactivity conditions is met either:

a.

A K, of 0.95 or less, or g

b.

A baron concentration of greater than or equal to 2000 ppm.

APPLICABILITY: MODE 6.* (Unit 2) l ACTION:

With the requirements of the above specification not satisfied, immediately suspend all operations involving CORE ALTERATIONS or positive reactivity i

changes and initiate and continue boration'at greater than or equal to 30 gpm of a solution containing greater than or equal to 7000 ppm boron or its equi-l valent until K r is reduced to less than or equal to 0.95 or the baron con-l a

centration is restored to greater than or equal to 2000 ppm, whichever is the more restrictive.

i SURVEILLANCE RE0VIREMENTS l

4.9.1.1 The more restrictive of the above two reactivity conditions shall be i

determined prior to:

i a.

Removing or unbolting the reactor vessel head, and i

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 per 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 vessel-with the vessel head closure bolts less than fully tensioned or with the head removed.

CATAWBA - UNIT 2 3/4 89-1 Amendment _ No.106

REACTIVITY CONTROL SYSTEMS BASES-BORATION SYSTEMS (Continued)

MARGIN from expected operating conditions of 1.3% Ak/k after xenon decay and cooldown to 200 F.

The maximum expected boration capability requirement occurs at EOL from full power equilibrium xenon conditions and requires 9,851 gallons of 7000 ppm borated water from the boric acid storage tanks or 57,107 gallons of 2175 ppm borated water for Unit 1 and 2000 ppm borated water for Unit 2 from the refueling water storage tank.

The Technical Specification requires 22,000 gallons of 7000 ppm borated water from the boric acid tanks to be available in Modes 1-4.

This volume is based on the required volume for maintaining shutdown margin, unusable volume (to allow for a full suction pipe), instrument error, and additional margin to account for different cores and conservatism as follows:

Modes 1-4 Boric Acid Tank Required volume for maintaining SDM 9,851 gallons 5% Additional Margin 496 gallons Unusable Volume (to maintain full suction pipe) 7,230 gallons l

l 14" of water equivalent Vortexing (4" of water above top of suction pipe 2,066 gallons Instrumentation Error (Based on Total loop Acc.

1,550 gallons for 1&2 NV5740 loops) - 2" of water equivalent 21,193 gallons This value is increased to 22,000 gallons for additional margin.

A similar approach is taken for calculating the required Refueling Water Storage Tank volume:

i When the temperature of one or more cold legs drops below 285 F in Mode 4, the potential for low temperature overpressurization of the reactor vessel makes it necessary to render one charging pump IN0PERABLE and at least one safety injection pump INOPERABLE. The limitation for a maximum of one cen-trifugal charging pump to be OPERABLE and the Surveillance Requirement to verify all charging pumps except the required OPERABLE pump to be inoperable below 285 F provides assurance that a mass addition pressure transient can be relieved by the operation of a single PORV.

Refuelina Water Storace Tank Reouirements For Maintainina SDM - Modes 1-4 Required Volume for Maintaining SDM 57,107 gallons Unusable Volume (below nozzle) 13,442 gallons Instrument Inaccuracy 11,307 gallons Vortexing 13.247 callons 95,103 gallons The Technical Specification Volume 363,513 gallons was determined by correcting the tank's low level setpoint (level at which makeup is added to i

CATAWBA - UNITS 1&2 B 3/4 1-3 Amendment No.112(Unit 1)

Amendment No.106(Unit 2) l

REACTIVITY CONTROL SYl ITEMS BASES BORAT10N SYSTEMS (Continued) tank) for instrument inaccuracy.

This level provides the maximum available volume to account for shutdown margin, worst case single failure, adequate containment sump volume for transfer to recirculation, and sufficient volume above the switchover initiation level such that no operator action is required prior to ten minutes after the initiation of the accident..

With the coolant temperature below 200 F, one Baron Injection flow path is acceptable without single failure consideration on the basis of the stable reactivity condition of the reactor and the additional restrictions prohibit-ing CORE ALTERATIONS and positive reactivity changes in the event the single Boron Injection flow path becomes inoperable.

The baron - ' ability required below 200 F is sufficient to provide a SHUTDOWN MAR' ' 1 1.% Ak/k after xenon decay and cooldown from 200 F to 140 F.

This conditiv.,.,,..res either 585 gallons of 7000 ppm borated water from the boric acid storage tanks or 3500 gallons of 2175 ppm borated water for-Unit 1 and 2000. ppm borated water for Unit 2 from the refueling water storage tank.

The Boric Acid Tank and Refueling Water Storage Tank volumes required in Modes 5-6 to provide necessary SDM are based on the following inputs as discussed previously:

Boric Acid Tank Required Volume for maintaining SDM 585 gallons Unusable Volume, Vortexing, Inst. Error 10,846 gallons 5% additional margin 33 aallo_0s 11,464 gallons This value is increased to tne Technical Specification value of 12,000 gallons for additional margin.

Refuelina Water Storaae Tank Required Volume for Maintaining SDM 3,500 gallons Water Below the Nozzle 13,442 gallons

, Instrument Inaccuracy 11,307 gallons Vortexing

13. 247 ' aallons 41,496 gallons l

This value is increased to the Technical Specification value of 45,000-i gallons for additional margin.

The contained water volume limits include allowance for water not avail-able because of discharge line location and other physical characteristics.

CATAWBA - UNITS 1&2 B 3/4 1-3a Amendment No.112 (Unit 1)

Amendment No.106 (Unit 2)

. r f

3 /4. 5' EMERGENCY CORE COOLING SYSTEMS BASES

. 3/4.5.1 ACCUMULATORS The OPERABILITY of each Reactor Coolant System accumulator ensures that a sufficient volume of borated water will be immediately forced into the' reactor i

core through each of the cold legs from the cold leg injection accumulators

(

and directly into the reactor vessel from the upper head injection accumula-tors in the event the Reactor Coolant System pressure falls below the pressure l

of the accumulators.

This initial surge of water into the core provides'the initial cooling mechanism during large pipe ruptures.

The limits on accumulator volume, boron concentration and pressure ensure that the assumptions used for accumulator injection in the safety analysis are l

met.

t The allowed down time for the accumulators are variable based upon boron i

concentration to ensure that the reactor is shutdown following a LOCA and that any problems are corrected in a timely manner.

Subcriticality is assured when l

boron concentration is above 1900 ppm for Unit I and 1800 ppm for Unit 2, so j

additional down time is allowed when concentration is above this value. A concentration of less than 2000 ppe for Unit 1 and 1900 ppm for Unit 2 in any:

single accumulator or as a volume weighted average may be indicative of a pro; blem, such as valve leakage, but since reactor shutdown is assured, additional time is allowed to restore boron concentration in' the accumulators.

l The accumulator power operated isolation valves are considered to be.

l

" operating bypasses" in the context of IEEE Std. 279-1971, which requires that bypasses of a protective function be removed automatically whenever permissive conditions are not met.

In addition, as these accumulator isolation valves i

fail to meet single failure criteria, removal of power to the valves is 1

required.

The limits for operation with an accumulator inoperable for any reason except an isolation valve closed minimizes the time exposure of the plant to a l

LOCA event occurring concurrent with f ailure of an additional accumulator which may result in unacceptable peak cladding temperatures.

If a closed isolation valve cannot be immediately opened, the full capability of one q

accumulator is not available and prompt action is required to place the' reactor in a mode where this capability is not required.

1

)

f l

CATAWBA - UNITS 1 &-2 B 3/4 5-1 Amendment No. 112 (Unit 1)

Amendment No. 106 (Unit 2)

3/4.9 REFUELING OPERATIONS

~

BASES 3/4.9.1 BORON CONCENTRATION l

The limitations on reactivity conditions during REFUELING ensure that-t (1) the reactor will remain subtritical during CORE ALTERATIONS, and (2) a uniform boron concentration is maintained for reactivity control in the water volume having direct access to the reactor vessel. These limitations are consistent with the initial conditions assumed for the boron dilution incident in the safety analyses.

The value of 0.95 or less for K, includes a 1% Ak/k j

g conservative allowance for uncertainties.

Similarly, the boron concentration value of 2175 ppm for Unit 1 and 2000 ppm for Unit 2 or greater includes a l

I conservative uncertainty allowance of 50 ppm boron.

3/4.9.2 ISSTRUMENTATION t

The OPERABILITY of the Boron Dilution Mitigation System ensures that monitoring capability is available to detect changes in the reactivity condition of the core.

l

)

3/4.9.3 DECAY TIME The minimum requirement for reactor subcriticality prior to movement of irradiated fuel assemblies in the reactor vessel ensures that sofficient time has elapsed to allow the radioactive decay of the short-lived fission products. This decay time is consistent with the assumptions used in the safety analyses.

3/4.9.4 CONTAINMENT BUILDING PENETRATIONS r

The requirements on containment building penetration closure and OPERABILITY of the Reactor Building Containment Purge System ensure that a i

release of radioactive material within containment will be restricted from leakage to the environment or filtered through the HEPA filters and activated carbon adsorbers prior to release to the atmosphere. The OPERABILITY and closure restrictions are sufficient to restrict radioactive material release 1

from a fuel element rupture based upon the lack of containment pressurization potential while in the REFUELING MODE. Operation of the Reactor Building Con-tainment Purge System and the resulting iodine removal capacity are consistent with the assumption of the safety analysis. Operation of the system with the heaters operating to maintain low humidity using automatic control for at i

least 10 continuous hours in a 31-day period is sufficient to reduce the i

buildup of moisture on the adsorbers and HEPA filters. ANSI N510-1980 will be used as a procedural guide for surveillance testing.

i

'l i

l CATAWBA - UNITS 1 & 2 B 3/4 9-1 Amendment No.112 (Unit'l)

Amendment No.106 (Unit 2)

1

^l LIMITING CONDITIONS FOR OPERATION AND SVRVEILLANCE REQUIREMENTS

1 SEC1 ION EA_GE 3/4.0 APPLICABILITY 3/4 0-1 i

3/4.1 REACTIY!TY CONTROL SYSTEMS 3/4.1.1 B0 RATION CONTROL Shutdown Margin - T,,, > 200

F 3/4 1-l'

]

Shutdown Margin - T,,, s 200'F

................ 3/4 1-3 j

Moderator Temperature Coefficient 3/4 1-4 l

Minimum Temperature for Criticality 3/4:1-6 l

3/4.1.2 BORATION SYSTEMS Flow Path - Shutdown...................

3/4 1-7 l

Flow Paths - Operating..................

3/4 1-8 Charging Pump - Shutdown.................

3/4 1 - 9_ '

Charging Pumps - Operating.................

3/4 1-10 Borated Water Source - Shutdown (Unit 1)........

3/4 Al-11

]

Borated Water Source - Shutdown (Unit 2)........

3/4 B1-11 j

Borated Water Sources - Operating (Unit 1).......

3/4 Al-12' Borated Water Sources - Operating (Unit 2).......

3/4 B1-12 1

3/4.1.3 MOVABLE CONTROL ASSEMBLIES Group Height.......................

3/4 1-14 TABLE 3.1-1 ACCIDENT ANALYSES REQUIRING REEVALUATION IN THE EVENT OF AN INOPERABLE FULL-LENGTH R0D..........

3/4 1-16 Position Indication Systems - Operating 3/4 1-17 Position Indication System - Shutdown 3/4 1-1B Ror' Orop Time 3/4 1-19 Shutdown Rod Insertion Limit...............

3/4 1-20 Control Bank Insertion Limits 3/4 1-21 1

3/4.2 POWER DISTRif0 TION LIMITS l

3/4 2-1 l

3/4.2.1 AXIAL FLUX DIFFERENCE 3/4.2.2 HEAT FLUX HOT CHANNEL FACTOR - FQ(X,Y,Z).......... 3/4 2-3 l

1 CATAWBA - UNITS 1 & 2 IV Amendment No. 112 (Unit 1)

Amendment No. 106 (Unit 2)

J

l'IMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS' i

SECTION PAGE 3/4.2.3 NUCLEAR ENTHALPY RISE HOT CHANNEL FACTOR 3/4 2-7 3/4.2.4 QUADRANT POWER TILT RATIO..............

3/4 2-10 i

3/4.2.5 DNB PARAMETERS 3/4 2-13

.}

TABLE 3.2-1 DNB PARAMETERS 3/4 2-15

'l FIGURE 3.2-1 REACTOR COOLANT SYSTEM TOTAL FLOW RATE VERSUS RATED

.l THERMAL POWER-FOUR LOOPS IN OPERATION........

3/4'2-16

{

i 3/4.3 INSTRUMENTATION

'l 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION.........

3/4 3-1 r

TABLE 3.3-1 REACTOR TRIP SYSTEM INSTRUMENTATION.........

3/4 3-2' TABLE 3.3-2 REACTOR TRIP SYSTEM INSTRUMENTATION RESPONSE TIMES..

3/4 3-7 l

TABLE 4.3-1 REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS

..................... 3/4 3-9

)

l 3/4.3.2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION,..................

3/4 3-13 TABLE 3.3-3 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION...................

3/4 3-15 TABLE 3.3-4 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION TRIP SETPOINTS 3/4 3-27 TAB'LE 3.3-5 ENGINEERED SAFETY FEATURES RESPONSE TIMES 3/4 3-37

.]

TABLE 4.3-2 ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS......

3/4 3-42 CATAWBA - UNITS 1 &-2 Va Amendment No.112 (Unit 1)

Amendment No.106 (Unit 2) 1

w CIMITING CONDITIONS FOR OPERATION AND-SURVEILLANCE RE0VIREMENTS

~

SECTION PAGE 3/4.5 EMERGENCY CORE COOLING SYSTEMS 3/4.5.1 ACCUMULATORS 2

Cold Leg Injection (Unit 1) 3/4 A5 1.

Cold Leg Injection (Unit 2) 3/4 B5-1 3/4.5.2 ECCS SUBSYSTEMS - T,y 2 350*F 3/4 5-5.

3/4.5.3 ECCS SUBSYSTEMS - T,y < 350*F 3/4 5-9 3/4.5.4 REFUELING WATER STORAGE TANK (Unit 1) 3/4 A5-ll 3/4.5.4 REFUELING WATER STORAGE TANK (Unit 2) 3/4 B5-11 3/4.6 CONTAINMENT SYSTEMS 3/4.6.1 PRIMARY. CONTAINMENT.

i Containment Integrity 3/4 6-1 Containment Leakage 3/4 6-2 TABLE 3.6-1 SECONDARY CONTAINMENT BYPASS LEAKAGE PATHS.......

3/4 6-5 l

Containment Air Locks 3/4 6-8 Internal Pressure 3/4 6-10 Air Temperature 3/4 6-11 l

Containment Vessel Structural Integrity 3/4 6-12 t

Reactor Bui' ding Structural Integrity 3/4'6-13 l

Annulus Ventilation System................

3/4 6-14 Containment Purge Systems 3/4 6-16 3/4.6.2 DEPRESSURIZATION AND COOLING SYSTEMS i

l Containment Spray System.................

3/4.6-18' 3/4.6.3 CONTAINMENT ISOLATION VALVES...............

3/4 6 j TABLE 3.6-2 CONTAINMENT ISOLATION VALVES.............

3/4 6-22

{

3/4.6.4 COMBUSTIBLE GAS CONTROL Hydrogen Monitors 3/4 6-38 Electric Hydrogen Recombiners 3/4 6-39 Hydrogen Mitigation System................

3/4 6-40

.i 3/4.6.5 ICE CONDENSER Ice Bed 3/4 6-41 Ice Bed Temperature Monitoring System 3/4 6-43 Ice Condenser Doors 3/4 6-43 Inlet Door Position Monitoring System 3/4 6 46

[

l l

I CATAWBA - UNITS 1 & 2 Vill Amendment No. 112 (Unit 1) i Amendment No. 106 (Unit 2) i

~

=

l l

+

i t

LIMITING CONDITIONS FOR OPERATION AND SURVE'LLANCE REQUIREMENTS SECTION PAGE

.i 3/4.7.11 (DELETED)

I 3/4.7.12 GROUNDWATER LE'.'EL 3/4 7-38 l

3/4.7.13 STANDBY SHUTDOWN 575lEM 3/4 7-40 1

3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A.C. SOURCES Operating 3/4 8-1 TABLE 4.81 DIESEL GENERATOR TEST SCHEDULE 3/4 8-9 TABLE 4.82 LOAD SEQUENCING TIMES.................

3/4 8-10 Shutdown..

3/4 8-11 l

. 3/4.8.2 D.C. SOURCES Operating 3/4 8-12 l

TABLE 4.83 BATTERY SURVEILLANCE REQUIREMENTS...........

3/8 8-15, Shutdown.........................

3/4 8-16

)

3/4.8.3 ONSITE POWER DISTRIBUTION Operating 3/4 8-17

(

Shutdown.........................

3/4 8-18

.i 3/4.8.4 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES Containment Penetration Conductor Overcurrent 7

Protective Devices...................

3/4 8-19 TABLE 3.81A UNIT 1 CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES....................

3/4 8-21 Table 3.8-1B UNIT 2 CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES....................

3/4 8-44 3/4.9 REFUELING OPERATIONS f

i 3/4.9.1 BORON CONCENTRATION (Unit 1)...............

3/4 A9-1 1

3/4.9.1 BORON CONCENTRATION (Unit 2) 3/4 B9-1 l

l 3/4.9.2 INSTRUMENTATION 3/4 9-2 i

3/4.9.3 DECAY TIME......................... 3/4 9-3 1

3/4.9.4 CONTAINMENT BUILDING PENETRATIONS 3/4 9-4 j

3/4.9.5 COMMUNICATIONS.......................

3/4 9-7 i

3/4.9.6 MANIPULATOR CRANE 3/4'9-8 J

3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE P0OL BUILDING 3/4 9-9 l

CATAWBA - UNITS 1 & 2 X

Amendment No.112 (Unit 1)

Amendment No.106 (Unit 2) 4 y

n

- --

Person / Time
ML20062L343
Site:	Catawba (NPF-35-A-112, NPF-52-A-106)
Issue date:	12/17/1993
From:	Plisco L Office of Nuclear Reactor Regulation
To:
Shared Package
ML20062L347	List: ML20062L343 ML20062L348
References
NUDOCS 9312300004
Download: ML20062L343 (27)
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