Text

Amend 13 to License NPF-8 Assuring Identical Requirements & Editorial Improvements by Minimizing Potential for Confusion & Allowing for Consistency Re Operation,Maint & Surveillance Procedures
	ML20051G633
Person / Time
Site:	Farley
Issue date:	05/05/1982
From:	Varga S; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20051G659	List: ML20051G633; ML20051G688; ML20051G789;
References
	NUDOCS 8205170148
	Download: ML20051G633 (54)
	v • d • e

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'o, UNITED STATES NUCLEAR REGULATORY COMMISSION

$ d' @3 c / ',g

/E WASHINGTON, D. C. 20555 fe ALABAMA POWER COMPANY DOCKET NO. 50-364 JOSEPH M. FARLEY NUCLEAR PLANT, nit NO. 2 AMENDMENT TO FACILITY OPERATING L. ?QSE Amendment No. 13 License No. NPF-8 s

1.

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

A.

The applications for amendment by Alabama Power Company (the licensee) dated October 28 and November 16, 1981 and March 18, 1982, comply with the standards and requirements of the Atomic

}

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

The facility will operate in conformity with the applications, the provisions of the Act, and the rules and regulations of the Commission; There is reasonable assurance (1) that the activities authorized C.

by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will j

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.

)

I 1

820517O/Y3 5

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

2-2.

Accordingly, the license is amended b'y 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 3 is hereby amended to read as follows:

(2) Technical Scecifications o

The Techr.ical Specifications contained in Appendices A and B, as revised througn Amendment No.13, are hereby incorporated in the license. The licensee shall operate the facility in accordance with the Technical Specifications.

3.

This license amendment is effective as of the date of its issuance.

F0y THE NUCLE Jt,REGi;LATCRY COMMISSION

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[ Operating Reactors' B i

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Division of Licens ng i

Attachment:

1 Changes to the Technical Specifications Date of Issuance: May 5,1982 l

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ATTACHNENT TO LICENSE AMENDMENT AMENDMENT NO. 13 TO FACILITY OPERATING LICENSE NO. NPF-8 f

DOCKET NO. 50-364 Revise Appendix A as follows:

Remove Pages Insert Pages j

t 1-9 1-9 f

i 2-2 2-2 3/4 0-2

'3/4 0-2 3/4 2-4 3/4 2-4 i

3/4 3-2 3/4 3-2 3/4 3-3 3/4 3-3 3/4 3-6 3/4 3-6 l

3/4 3-12 3/4 3-12

{

3/4 3-19 3/4 3-19 4

i 3/4 3-20 3/4 3-20 3/4 3-23 3/4 3-23 3/4 3-24 3/4 3-24 3/4 3-36 3/4 3-36 3/4 3-37 3/4 3-37 3/4 3-39 3/4 3-39 3/4 3-40 3/4 3-40 f

4 3/4 3-41 3/4 3-41 i

3/4 3-57 3/4 3-57 3/4 3-58 3/4 3-58 3/4 3-59 3/4 3-59 3/4 4-4a 3/4 4-4a I

e 3/4 4-8 3/4 4-8 3/4 4-17 3/4 4-17 i

3/4 7-9 3/4 7-9 3/4 7-13 3/4 7-13 3/4 7-21 3/4 7-21 f

3/4 7-22 3/4 7-22 3/4 7-23 3/4 7-23 3/4 8-1 3/4 8-1 3/4 8-2 3/4 8-2 3/4 8-3 3/4 8-3 3/4 8-4 3/4 8-4 3/4 8-5 3/4 8-5 3/4 8-6 3/4 8-6 3/4 8-7 3/4 8-7 i

3/4 8-8 3/4 8-8 3/4 8-12 3/4 8-12 l

3/4 8-15 3/4 8-15 3/4 8-16 3/4 8-16 j

3/4 9-16 3/4 9-16 3/4 10-5 3/4 10-5 3/4 11-2 3/4 11-2 l

3/4 11-5 3/4 11-5 3/4 11-12 3/4 11-12 3/4 11-13 3/4 11-13 i

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.. Remove Pages Insert Pages B 3/4 2-1 B 3/4 2-1 B 3/4 4-2 B 3/4 4-2 B 3/4 7-5 B 3/4 7-5 6-15 6-15 6-24 6-24

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TABLE 1.2

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i FREQUENCY NOTATION NOTATION FREQUENCY

j m

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

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

b~

W At least once per 7 days.

At least once per 31 days

M Q

At least once per 92 days.

SA At least once per 184 days.

A At least once per 366 days.

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R At least once per 18 months.

S/U Prior to each reactor startup.

P Completed prior to each release.

N.A.

Not applicable.

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FARLEY-UNIT 2 1-9 Amendment No.13

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0.2 0.4 0.6 0.8 1.0 1.2 FRACTION OF RATED THERMAL POWER

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l Figure 2.11 Reactor Core Safety Limit Three Loops in Ope 1 tion l

APPLICABILITY: <5 % STEAM GENERATOR TUBE PLUGGING i

FARLEY-UNIT 2 2-2 Amendment No.13

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l APPLICABILITY SURVEILLANCE REQUIREMENTS v

1.

At least HOT STAND 3Y within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , 2.

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

'4 3.

At least COLD SHUTDOWN within the subsequent 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

-l I

This specification is not applicable in MODES 5 or 6.

4.0.1 Surveillance Requirements shall be applicable during the OPERATIONAL MODES or other conditions specified for individual Limiting Conditions for Operation unless otherwise stated in an individual Surveillance Requirement.

4.0.2 Each Surveillance Requirement shall be performed within the specified I

time interval with:

i A maximum allowable extension not to exceed 25% of the surveillance a.

I interval, and t

b.

The combined time interval for any 3 consecutive surveillance intervals not to exceed 3.25 times the specified surveillance interval.

I 4.0.3 Failure to perform a Surveillance Requirement

within the specified time l

interval shall constitute a failure to meet the OPERABILITY requirements for a Limiting Condition for Operation. Exceptions to these requirements are stated in the individual specifications. Surveillance Requirements do not have to be l

performed on inoperable equipment.

f Entry into an OPERATIONAL MODE or other specified condition shall not 4.0.4 be made unless the Surveillance Requirement (s) associated with the Limiting Condition for Operation have been performed within the stated surveillance interval or as otherwise specified.

4.0.5 Surveillance Requirements for inservice inspection and testing of ASME Code Class 1, 2 and 3 components shall be applicable as follows:

l Inservice inspection of ASME Code Class 1, 2 and 3 components and j

a.

inservice testing of ASME Code Class 1, 2 and 3 pumps and valves shall 1

be performed in accordance with Section XI of the ASME Boiler and Pres-i sure Vessel Code and applicable Addenda as required by 10 CFR 50, i

Section 50.55a(g), except where specific written relief has been

i granted by the Commission pursuant to 10 CFR 50, Section 50.55a(g)(6)(f).

ll Surveillance intervals specified in Section XI of the ASME Boiler b.

and Pressure Vessel Code and applicable Addenda for the inservice j

inspection and testing activities required by the ASME Boiler and j

Pressure Vessel Code and applicable Addenda shall be applicable as follows in these Technical Specifications:

l Upon determination that the surveillance had been inadvertantly emitted, the Y

. Surveillance Requirement shall be successfully performed within the Limiting I

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Condition of Operation (LCO) period which would begin upon discovery.

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FARLEY-UNIT 2 3/4 0-2 Amendment No. 13

POWER DISTRIBUTION LIMITS i

3/4.2.2 HEATFLUXHOTCHANNELFACTOR-Fg

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LIMITING CONDITION FOR OPERATION 3.2.2 F (Z) shall be limited by the following relationships:

q 2.31] [K(Z)] for P > 0.5 F(Z)1[T A

F (Z) 1 [(4.62)] [K(Z)] for P 1 0.5 q

where P THERMAL POWER RATED THERMAL POWER I

and K(Z) is the function obtained from Figure (3.2-2) for a i

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given core height location.

APPLICABILITY: H0DE 1 ACTION:

With F (Z) exceeding its limit:

q Reduce THERMAL POWER at least 1% for each 1% F (Z) exceeds the limit within 15 minutes and similiarly reduce the Po9er Range Neutron a.

Flux-High Trip Setpoints within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; POWER OPERATION i

may proceed for up to a total of 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ; subsequent POWER OPERATION ower delta T Trip Setpoints have been may proceed provided the Overp% fn(Z) exceeds the. limit.

The reduced at least 1% for each 1 Overpower delta T Trip Setpoint rVduction shall be performed with the reactor in at least HOT STANDBY.

l Identify and correct the cause of the out of limit condition prior t

b.

to increasing THERMAL POWER above the reduced limit required oy a, 1

Z) is above; THERMAL POWER may then be increased provided Fn(imit.

j demonstrated through incore mapping to be within its l a

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k 3/4 2-4 Amendment No.13 FARLEY-UNIT 2 i

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TABLE 3.3-1 i

5 REACTOR TRIP SYSTEM INSTRUMENTATION l2

'2 MINIMUM d-TOTAL NO.

CHANNELS CHANNELS APPLICABLE 55 OF CHANNELS

-TO TRIP _

OPERABLE MODES _

ACTION 4

FUNCTIONAL UNIT 2

1 2

1, 2, and

12 m

1.

Manual Reactor Trip 4

2 3

1, 2 2,,

2.

Power Range Neutron Flux 2

4 2

3 2

A.

High B.

Low 4

2 3

1, 2 2

3.

Power Range, Neutron Flux High Positive Rate 4-2 3

1, 2 2

4.

Power Range, Neutron Flux, High Negative Rate R

5.

Intermediate Range, Neutron. Flux 2

1 2

1, 2, and

3 2

1 2,,,

2,,, and

5 4

Y 6.

Source Range, Neutron Flux 2

0 1

3, 4 and 5 A.

Startup B.

Shutoovn 7,

J 7.

Overtemperature AT 3

2 2

1, 2 Three Loop Operation 1***

2 1, 2 9

3 Two Loop Operation p

7,

_h 8.

Overpower AT Three Loop Operation 3

2 2

1, 2 3

1**

2 1, 2 9

g Two Loop Operation 1

7, l

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=

3 2

2 f

9.

Pressurizer Pressure-Low

10. Pressurizer Pressure--High 3

2 2

1, 2 7

1 uns b

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TABLE 3.3-1 (Continued)

A REACTOR TRIP SYSTEM INSTRUMENTATION r-O MINIMUM E-TOTAL NO.

CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION

11. Pressurizer Water Level--High 3

2 2

1 7

l 12.

A.

Loss of Flow - Single Loop 3/ loop 2/ loop in 2/ loop in 1

7 (Abrve P-8) any oper-each oper-ating loop ating loop B.

Loss of Flow - Two Loops 3/ loop 2/ loop in 2/ loop 1

7 (Above P-7 and below P-8) two oper-each oper-ating loops ating loop

13. Steam Generator Water 3/ loop 2/ loop in 2/ loop in 1, 2 7

Level--Low-Low any oper-each oper-ating loops ating loop

,s

14. Steam /Feedwater Flow 2/ loop-level 1/ loop-level 1/ loop-level 1, 2 7

^

m Mismatch and Low Steam and coincident and Generator Water Level 2/ loop-flow with 2/ loop-flow mismatch in 1/ loop-flow mismatch in same loop mismatch in same loop or same loop 2/ loop-level and p

15 1/ loop-flow i

mismatch in same loop m

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15. Undervoltage-Reactor Coolant z-Pumps 3-2/ bus 2

2 1

7 U

16. Underfrequency-Reactor Coolant y

Pumps 3-2/ bus 2

2 1

7 i

TABLE 3.3-1 (Continued)

I TABLE NOTATION

'With the reactor trip system breakers in the closed position, the control rod drive system capable of rod withdrawal, and fuel in the reactor vessel.

RdtThe channel (s) associated with the protective functions derived from the out of service Reactor Coolant Loop shall be placed in the tripped condition.

The provisions of Specification 3.0.4 are not applicable.

" High voltage to detector may be de-energized above P-6.

~

ndication only.

I The provisions of Specification 3.0.3 are not applicable if THERMAL POWER level > 10% of RATED THERMAL POWER.

ACTION STATEMENTS ACTION 1 - With.the number of OPERABLE' channels one less than required by the Minimum Channels OPERABLE requirement, be in HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; however, one channel may be bypassed for up to i

2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing per Specification 4.3.1.1.

j

,I ACTION 2 - With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:

The inoperable channel is placed in the tripped condition a.

within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

l b.

The, Minimum Channels OPERABLE requirement is, met; however, the inoperable channel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing of the other channels per Specification 4.3.1.1.

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

to 75% of RATED THERMAL POWER and the Power Range, Neutron Flux trip setpoint is reduced to less than or equal to 85%

of RATED THEP. MAL POWER within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; or, the QUADRANT POWER TILT RATIO is rgonitored at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

l d.

The QUADRANT POWER TILT RATIO, as indicated by the remaining three detectors, is verified consistent with the quadrant power distribution obtained~by using the movable incore detectors in the four pairs,of symmetric thimble locations at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months when THERMAL POWER is greater than 75% of RATED THERMAL POWER.

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FARLEY-UNIT 2 3/4 3-6 Amendment tio. 13

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TABLE 4.3-1

'5 REACTOR TRIP SYSTEM INSTRUMENTATION SURVEILLANCE REQUIREMENTS _

NG CHANNEL MODES IN WHICH h

CHANNE(

CHANNEL FUNCTIONAL SURVEILLANCE TEST _

REQUIRED q

CHECK CALIBRATION FUNCTIONAL UNIT

~

i 1.

Manual Reactor T. ip N.A.

N.A.

S/U(1)

N.A.

2.

Power Range, Neutron Flux 5

D(2),M(3)

M 1, 2 A.

High and Q(6)

B.

Low S

D(2),M(3)

S/U(10) 2 and Q(6) 3.

Power Range, Neutron Flux, M.A.

R(6)

M 1, 2 l

High Positive Rate 4.

Power Range, Nectron Flux, N.A.

R(6)

M 1, 2 y

2 High Negative Rate 5.

Intermediate Range, S

R(6)

S/U(1) 1, 2, and

N Neutron Flux 6.

Source Range, Neutron Flux S(7)

R(6)

M and S/U(1) 2, 3, 4, l

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5, and

7.

Overtemperature AT S

R M

1, 2 p

k 8.

Overpower'AT S

R M

1, 2 N

A 9.

Pressurizer Pressure--Low 5

R M

1

?

10. Pressurizer Pressure--High 5

R M

1, 2 U

11. Pressurizer Water Level--High S

R M

i 12.

A.

Loss of Flow - Single Loop S

R M

1 B.

Loss of Flow - Two Loops S

R N.A.

1 o

9

~

f TABLE 3.3-3 (Continued) 5 ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION i

g "J

MINIMUM M

TOTAL NO.

CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERARLE MODES ACTION y

4.

STEAM LINE ISOLATION a.

Manual 1/ steam line 1/ steam line 1/ operating 1, 2**, 3**

22 steam line b.

Automatic 2

1 2

1, 2**, 3**

21 Actuation Logic a

c.

Contains.ent Pressure--

3 2

3 1, 2**, 3**

14 High-High d.

Steam Flow in Two 1,.2**, 3**

Steam Lines--High a

N Three Loops 2/ steam line 1/ steam line 1/ steam line 14 Operating any 2 steam lines e

1. 1. any 1/ operating 15

/

Two Loops 2/ operating 1

Operating steam line operating steam line steam line E

's COINCIDENT WITH 1, 2**, 3**

T,yg--Low-Low f

Three Loops 1 T,yg/ loop 1 T,yg any 1 T,yg any 14*

g Operad ng 2 loops 2 loops C;

Two loops 1 T,yg/oper-O T,yg 1 T,yg in any 15 l

Operating ating loop in any oper-operating loop ating loop L

' TABLE 3.3-3 (Continued)

E ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTR'JMENTATION

Q

.c MINIMUM 5

TOTAL NO.

CHANNELS CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES __

ACTION

I ma 1, 2n*,3 e.

Steam Line Pressure-low A

Three Loops 1 pressure /

1 pressure 1 pressure 14 Operating loop any 2 loops any 2 loops Two Loops 1 pressure /

1 pressure 1 pressure 15 Operating operating in any oper-any operating loop ating loop loop R

5.

TURBINE TRIP &

FEEDWATER ISOLATION a

Yy a.

Steam Generator 3/ loop 2/ loop in 2/ loop in 1, 2 14 Water Level--

any oper-each oper-High-High ating loop ating loop

a i

R On

~

i w

6 s

'i I

TABLE 3.3-3 (Continued)

TABLE NOTATION

rip function may be bypassed in this MODE below the P-11.

T

{

(Pressurizer Pressure Block of Safety Injection) setpoint.

" Trip function may be bypassed in this MODE below P-12.

(T,,, Block of Safety Injection) setpoint.

The channel (s) associated with the protective functions derived from the out of service Reactor Coolan,t Loop shall be placed in the tripped mode.

The provisions of Specification 3.0.4 are not applicable.

- Not applicable if main steam isolation valves are closed.

ACTION STATEMENTS ACTION 13 - With the number of OPERABLE channels one less than the Minimum ll Channels OPERABLE requirement, be in 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 ; however,

,i one channel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing per Specification 4.3.2.1 provided the other channel 1

l 1s OPERABLE.

I ACTION 14 - With the number of OPERABLE channels one less than the Total Number of Channels, operation may proceed until performance of the next required CHANNEL FUNCTIONAL TEST provided the i

l inoperable channel is placed in the tripped condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

I

'i ACTION 15 - With a channel associated with an operating loop inoperable.

restore the inoperable channel to OPERABLE status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months l

or b-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 at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; however, one channel associated with an operating loop may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing per Specification 4.3.2.1.

i 3

ACTION 16 - With the number of OPERABLE channels one less than the Total Number of Channels, operation may proceed provided the inoperable channel is placed in the bypassed condition and the Minimum Channels OPERABLE requirement is met; one additional channel l

may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing per Specification 4.3.2.1.

ACTION 17 - With less than the Minimum Channels OPERABLE, operation may continue provided the containment purge and exhaust valves are 4

maintained closed.

1 FARLEY-UNIT 2 3/4 3-23 Amendment No.13

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TABLE 3.3-3 (Continued)

)

ACTION 18 - With the number of OPERABLE Channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hou'rs or be in at least HOT STANDSY 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 .

ACTION 19 - With the number of OPERABLE Channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the following conditions are satisfied:

The inoperable channel is placed in the tripped condition

, a.

within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

b.

The Minimum Channels OPERABLE requirement is met; however, the inoperable channel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing of other channels per Specification 4.3.2.1.

ACTION 20 - With the interlock inoperable to the extent that a safeguards function which should not be blocked in the current MODE is blocked, declare the safeguard function (s) inoperable and follow the appropriate ACTION statement (s) of Table 3.3-3 for the affected function (s).

Interlock Affected Channels on Table 3.3-3 1

1. P-4 a.

Pressurizer Pressure - Low e

l

2. P-12 a.

Steam Line Pressure - Low b.

Steam Flow in Two Steam Lines High

!i Coincident With T,yg-Low-Low ACTION 21 - With the number of OPERABLE Channels one less than the Minimum Channels OPERABLE requirement, be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; however; one channel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing provided the other channel is OPERABLE.

ACTION 22 - With the number of OPERABLE Channels one less than the Total Number of Channels restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in at least HOT STANDBY within

'l 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 .

ACTION 23 - With the number of OPERABLE channels one less than the Minimum Number of Channels, operation may proceed until performance of the next required CHANNEL FUNCTIONAL TEST.

l 8

l, l'

Amendment No.13 FARLEY-UNIT 2 3/4 3-24 l

l

l -..' : ~

G ----

TABLE 4.3-2 (Continued) h ENGINEERED SAFETY FEATURE ACTUATION SYSTEM INSTRUMENTATION E

SURVEILLANCE _JEQUIREMENTS

?

E CHANNEL MODES IN WHICH Z

CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE t

FUNCTIONAL UNIT CHECK _

CALIBRATION TEST REQUIRED n

6.

AUXILIARY FEECkATER a.

Automatic Actuation Logic N.A.

N.A.

M(2)(6) 1,2,3 b.

Steam Generator Water S

R M

1,2,3 Level--Low-Low s

c.

Undervoltage - RCP N.A.

R M

1 I

d.

S.I.

See I above (all SI surveillance requirements) w e.

Trip of Main Feedwater N.A.

N.A.

S/U(5) 1 2

Pumps w

L, 7.

LOSS OF POWER rn a.

4.16 kv Emergency Bus N.A.

R(3)

M(4) 1, 2, 3, 4 Undervoltage (Loss of Voltage) p b.

4.16 kv Emergency Bus N.A.

R(3)

M(4) 1, 2, 3, 4 I

g Undervoltage (Degraded g

Voltage) 8.

ENGIhEERED SAFETY FEATURE N.A.

N.A.

R N.A.

l ACTUATION SYSTEM INTERLOCKS C

4 We W

W

,ie e.-

e-=*weeaummmwg mansw ww-w=

.m___.-

TABLE 4.3-2 (Continued)

TABLE NOTATION I

(1) Manual actuation switches shall be tested at least once per 18 months during shutdown. All other circuitry associated with manual safeguards

..i actuation shall receive a CHANNEL FUNCTIONAL TEST at least once per 31 days.

(2) Each train or logic channel shall be tested at least every 62 days on a STAGGERED TEST BASIS.

k (3) Channel calibration shall exclude actuation of the final trip actuation relay."

(4) Functional testing shall consist of verification of relay. operation upon removal of input voltage and operation of 2-out-of-3 logic excluding the final trip actuation relay.*

(5) If not performed in the previous 92 days.

(6) Excluding automatic actuation logic for trip of main feedwater pumps.

I I

ji l

)

l' l

i i

" Actuation of the final trip actuation relay shall be included in response ij time testing.

}

>l l

FARLEY-UNIT 2 3/4 3-37 Amendment No.13

- - - - - ~ -

TABLE 3.3-6 b

RADIATION MONITORING INSTRUMENTATION Qd MINIMUM CHANNELS APPLICABLE ALARM / TRIP MEASUREMENT

[

INSTRUMENT OPERABLE MODES SETPOINT RANGE ACTION 1.

AREA MONITORS a.

Fuel Storage Pool 1

(a) 1 15 mR/hr 10-1 4

-10 mR/hr 23 Area (R-5) 7 b.

Containment Area (R-27A&B) 2 1,2,3,4 N/A 1 - 10 R/hr 27a 2.

PROCESS MONITORS a.

Fuel Storage Pool Ana Gaseous Activity-Ventilation System 6

1 1

Isolation (R-25A&B) 1 (b)

$ 8.73 x 10-3'pCi/cc(c)10-10

l cpm 25 w

i a

b.

Containment i.

Gaseous Activity-a) Purge & Exhaust 6

Isolation (R-24A&B) 1 1,2,3 (d)

< 2.27 x 10 pCi/cc(c) 10-10 cpm 26 4,5,6 (d) 7 2.27 x 10 pCi/cc(c) 26 1,2,3,4,5,6 (e) 7 4.54 x 10 pCi/cc(c) 26 1,2,3,4,5,6 (f) 32.27x10 pCi/cc(c) 26 i

p 6

E.

b) RCS Leakage.

1 1,2,3 & 4 N/A 10-10 cpm 24

1 l

Detection (R-12) l 11.

Particulate Activity 6

F RCS Leakage 1

1,2,3 & 4 N/A 10-10 cpm 24 Detection (R-11)

I a

c.

Control Room 6

Isolation (R35A&B) 1 1,2,3,4 and S 800 cpm 10-10 cpm 27 during movement of irradiated fuel or movement of loads over irradiated fuel

i TABLE 3.3-6 (Continued)

I ACTION STATEMENTS ACTION 23 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, perform area surveys of the monitored area with portable monitoring instrumentation at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

ACTION 24 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.4.7.1.

ACTION 25 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.9.12 and 3.9.13.

ACTION 26 - With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, comply with the ACTION requirements of Specification 3.9.9.

ACTION 27 - With the number of channels OPERABLE less than required by the Minimum Chanaels OPERABLE requirement, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months initiate and maintain operation of the control room emergency ventilation system in the recirculation mode of operation.

ACTION 27a - With the number of OPERABLE Channels less than required by the Minimum Channels OPERABLE requirement, either restore the i

inoperable Channel (s) to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , or:

1)

Initiate the preplanned alternate method of monitoring the f4

, appropriate parameter (s), and Prepare and submit a Special Report to the Commission f ';

pursuant to Specification 6.9.2 within the next 14 days 2)

~

following the event outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status.

l l

a.

With fuel in storage pool.

b.

With irradiated fuel in the storage pool.

l c.

Above background with no flow.

l) d.

With mini purge in operation.

With slow speed main purge in operation.

'p e.

f.

With fast speed main purge in operation.

i I$

FARLEY-UNIT 2 3/4 3-40 Amendment No.13

-~

6

W

't

@&qgesI' Weh*h h1eMN-'

,M TABLE 4.3-3 3#

RADIATION MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS Q

CHANNEL MODES IN WHICH a5 CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE A

IDH UST RMUIMD

[

INSTRUMENT 1.

AREA MONITORS a.

Fuel Storage Pool Area S

R M

(R-S) b.

Containment Area (R-27A&B)

S R

N/A 1,2,3,4 2.

PROCESS MONITORS a.

Fuel Storage Pool Area Gaseous Activity -

Ventilation System R

Isolation (R-25 A&B)

S R

M Y

b.

Containment

=

i.

Gaseous Activity a) Purge & Exhaust M

All MODES Isolation (R-24 A&B)

S R

b) RCS Leakage Detection S

R M

1,2,3 & 4 (R-12) g 11.

Particulate Activity RCS Leakage Detection S

R M..

1,2,3 & 4 (R-11)

=

?

c.

Control Room Isolation S

R M

1,2,3,4 and during l

'd movement of irradiated fuel or movement of loads over irradiated fuel ith fuel in the storage pool or building.

With' irradiated fuel in the storage poo..

~-

i i

TABLE 3.3-11 i

i ACCIDENT MONITORING INSTRUMENTATION h

E REQUIRED MININUM

-f NUMBER CHANNELS E

OF CHANNELS OPERABLE q

INSTRUMENT

-W Range 2

1 1.

Reactor Coolant Outlet Temperature-THot

-Wide Range 2

1 2.

Reactor Coolant Inlet Temperature-T old 2

1 l

3.

Reactor Coolant Pressure-Wide Range 2/ steam generator 1/ steam generator Steam Generator Water Level-Wide Range or Narrow Range 4.

2 1

Refueling Water Storage Tank Water' L'evel 5.

2 1

6.

Containment Pressure 2

1 7.

Pressurizer Water Level 2/ steam generator 1/ steam generator 8.

Steam Line Pressure 1

2 9.

Auxiliary Feedwater Flow Rate

.2 1

j Reactor Coolant System Subcooling Margin' Monitor 1/ valve l!

10.

1/ valve

il.

PORV Position Indicator

~

1/ valve 1/ valve

[

- 12.

PORV Block Valve Position Indicator 2/ valve 1/ valve R

13. Safety Valve Position Indication (One channel E

is position indicator and one channel is l

[

discharge temperature) 2 1

14. Containment Water Level - Narrow Eange 2

1 C

15. Containment Water level - Wide Range 4/ core quadrant 2/ core quadrant 16.

Incore Thermocouples

'Not applicable if the associated block valve is in the closed position.**Not applica y

. ~. ~......

_ m - -- --

TABLE 4.3-7

.~

(

h

, ACCIDENT MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS E

CHANNEL CHANNEL 7

E INSTRUMENT CHECK CALIBRATION A

H R

1.

Reactor Coolant Outlet Tmperature-THot m

k7de Range 2.

-Wide Range M

R Reactor Coolant Temperature-TCold 3.

Reactor Coolant Pressure-Wide Range M

R 4.

Steam Generator Water Level-Wide Range or M

R Narrow Range 5.

Refueling Water Storage Tank Water Level M

R 6.

Containment Pressure M

R m2 7.

Pressurizer Water Level M

R m

v 8.

Steam Line Pressure M

R j

9.

Auxiliary Feedwater Flow Rate M

R i

10. Reactor Coolant System Subcooling Margin Moniter M

R h"

11.

PORV Position Indicator M

R

?i

- 12.

PORY Block Valve Position Indicator M

R l

13. Safety Valve Position Indication M

R E

14. Containment Pater Level - Narrow Range M

R w

15. Containment Water Level - Wide Range M

R 16.

Incore Thermocouples M

R "Not applicable if the associated block valve is in the closed position.

- Not applicable if the block valve is verified in the closed position and power removed.

~

l INSTRUMENTATION FIRE DETECTION INSTRUMENTATION LIMITING CONDITION FOR' OPERATION 3.3.3.9 As a minimum, the fire detection instrumentation for each fire detection zone shown in Table 3.3-12 shall be OPERABLE.

APPLICABILITY: Whenever equipment protected by the fire detection instrument is required to be OPERABLE.

ACTION:

With the number of OPERABLE fire detection instrument (s) less than the minimum number OPERABLE requirement of Table 3.3-12:

a.

Within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months establish a fire' watch patrol to inspect the zone (s) with the inoperable instrument (s) at least once per hour, unless the instrument (s) is located inside the containment, then monitor the containment air temperature at least once per hour at the locations listed in Specification 4.6.1.5.

Restore the inoperable instrument (s).to OPERABLE status within I

b.

j 14 days, or in lieu of any other report. required by Specifi-cation 6.9.1, prepare and submit a Special Report to the Ccmmission l

pursuant to Specification 6.9.2 within the next 30 days outlining i

l the action taken, the cause of the inoperability.and the. plans and schedule for restoring the instrument (s) to OPERABLE status, The provisions of Specifications 3.0.3 and 3.0.4 are'not applicable.

c.

SURVEILLANCE REQUIREMENTS 4.3.3.9.1 Each of the above required fire detection instruments which are l'

accessible during plant operation shall be demonstrated OPERABLE at least once per 6 months by performance of a functi.on test which includes subjecting the detector to test aerosol. Fire detectors which are not accessible during plant l

i

}

operation shall be demonstrated OPERABLE by the performance of this functional test during each COLD SHUTDOWN exceeding 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months unless performed in the 1

lll previous 6 months.

's

'r 4.3.3.9.2 The NFPA Standard 720 supervised circuits supervision associated with the detector alarms of each of the above required fire detection instruments shall be demonstrated OPERABLE at least once per 6 months.

I i !

l Amendment No.13 FARLEY-UNIT 2 3/4 3-59

~

i REACTOR COOLANT SYSTEM COLD SHUTDOWN LIMITING CONDITION FOR OPERATION Two# residual heat removal (RHR) loops shall be OPERABLE

and

'3.4.1.4 a.

at least one RHR loop shall be in operation.**

APPLICABILITY: MODE 5."

ACTION:

With less than the above required RHR/ Reactor Coolant loops a.

OPERABLE, immediately initiate corrective action to return the required RHR/ Reactor coolant loops to OPERABLE status as soon as possible.

b.

With no coolant loop in operation, suspend all operations involving a reduction in boron concentration of the Reactor Coolant System and immediately initiate corrective action to return the required coolant loop to operation.

j l'

SURVEILLANCE REQUIREMENTS 4.4.1.4 At least one RHR loop shall be determined to be in operation and circulating reactor coolant at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

f "The normal or emergency power source may be inoperable in MODE 5.

- The RHR loop may be removed from operation for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months provided (1) no operations are permitted that would cause dilution of the Reactor Coolant System boron concentration, and (2) core outlet temperature is m'aintained at least 10 F below saturation temperature.

Three filled Reactor Coolant loops and at least two steam generators having levels greater than or equal to 10% of wide range indication may be

'l substituted for one RHR loop.

Il A Reactor Coolant purnp shall not be started with one or more of the Reactor Coolant System cold leg temperatures less than or equal to 310 F unless (1) the pressurizer water volume is less than 770 cubic feet (24% of wide range, cold, pressurizer level indication) or (2) the secondary water tem-perature of each steam generator is less than 50*F above each of the Reactor i

Coolant System cold leg temperatures.

FARLEY-UNIT 2 3/4 4-4a Amendment No. 13

-).

REACTOR C001. ANT SYSTEM I

)

/ t

'3/4.4.5 RELIEF VALVES

't

}

LIMITING CONDITION FOR OPERATION 3.4.5 All power relief valves (PORVs) and their associated block valves shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3.

ACTION:

With one or more PORV(s) inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months either restore the PORV(s) to OPERABLE status or close the associated block valve (s) a.

and remove power from the block valve (s); otherwise, 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 .

With one or more block valve (s) inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months either b.*

restore the block valve (s) to OPERABLE s+.atus or. lose the block valve (s) and remove power from the block valve (s); otherwise, 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 SHUTOOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months , The provisions of Specification 3.0.4 are not applicable.

c.

I SURVEILLANCE REQUIREMENTS Each PORY shall be demonstrated OPERABLE at least once per 18 months f~

4.4.5.1 by performance of a CHANNEL CALIBRATION and operating the valve through one I

cycle of full travel.

Each block valve shall be demonstrated OPERABLE at least once per.

4.4.5.2 92 days by operating the valve through one complete cycle of full travel unless the block valve is closed with the power removed in order to meet l

the ACTION requirements of a. above.

i I

'i

'l

\\

l I

f

[

FARLEY-UNIT 2 3/4 4-8 Amendment No.13

--..,..-n,

--~:.

~~--'

_ 2: --. - -

~~

' REACTOR COOLANT SYSTEM OPERATIONAL LEAXAGE

{'

f LIMITING CONDITION FOR OPERATION n

3.4.7.2 Reactor Coolant System leakage shall be limited to:

a.

No PRESSURE BOUNDARY LEAKAGE, b.

'l GPM UNIDENTIFIED LEAKAGE, 1 GPM total primary-to-secoridary leakage through all steam generators c.

and 500 gallons per day through any one steam generator, d.

10 GPM IDENTIFIED LEAKAGE from the Reactor Coolant System, and e.

31 GPM CONTROLLED LEAKAGE at a Reactor Coolant System pressure of 2235 20 psig.

I f.

1 GEM leakage from any Reactor Coolant System Pressure Isolation Valve specified in Table 3.4-1 at a Reactor Coolant System pressure of 2235

20 psig.

APPLICABILIT(:

MODES 1, 2, 3 and 4 ACTIONi With any PRESSURE BOUNDARY LEAKAGE, be in at least HOT STANDBY n..

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 b.

With any Reactor Coolant System leakage greater than any one of the

~

above limits, excluding PRESSURE. BOUNDARY LEAKAGE, reduce the leakage rate to within' limits within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or be in at least HOT STANDBY within the next 6 ho'urs and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

With any Reactor Coolant System Pressure Isolation Valve leakage c.

greater that the 'above limit, isolate the high pressure portion of the affected system from the low pressure portion within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months by use of at least two closed manual or deactivated automatic valves, or be in at least HOT STANDBY within the next S hours and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .-

l ls S_URVEILLANCE REOUIREMENTS j - d -.-

?

4.4.7.2.1 Reactor Coolant System leakages shall be demonstrated to be within each of the above limits by; Monitoring the containment atmosphere particulate radioactivity a.

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

b.

Monitoring the containment air cooler condensate level system or containment atmosphere gaseous radioactivity monitor at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

Ann en N.13 FARLEY-UNIT 2 3/4 4-17

=

~

4 PLANT SYSTEMS MAIN STEAM LINE ISOLATION VALVES 1

1 ll LIMITING CONDITION FOR OPERATION 3.7.1.5 Each main steam line isolation valve shall be OPERABLE.

APPLICABILITY: MODES 1, 2 and 3.

ACTION:

MODES 1 - With one main steam line isolation valve inoperable, POWER OPERATIOR may continue provided the inoperable valve is restored to OPERABLE status within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; otherwise, reduce power to less than or equal to 5% of RATED THERMAL POWER within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

MODES 2 - With one main ; team line isolation valve inoperable, subsequent and 3 operation in H0 DES 2 or 3 may proceed provided the isolation valve is restored to OPERABLE status or closed within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months after entering MODE 2; otherwise, be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTOOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

The provisions of Specification 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS Each main steam line isolation valve shall be demonstrated OPERABLE 4.7.1.5 by verifying full closure within 5 seconds when tested pursuant to Specification 4.0.5.

i i

?

1 b

i FARLEY-UNIT 2 3/4 7-9 Amendment No. 13

- =e

.wm..,_..

1 k

PLANT SYSTEMS 3/4.7.5 RIVER WATER SYSTEM LIMITING CONDITION FOR OPERATION

3.7.5 At least two independent river water loops shall be OPERABLE with at least two river water pumps per loop.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

a With only one river water loop OPERABLE, restore at least two loops to OPERABLE status within 7 days 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 l

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

SURVEILLANCE REQUIREMENTS 4.7.5 Each river water loop shall be demonstrated OPERABLE:

l At least once per 31 days by verifying that each valve (manual, i

i a.

power operated or automatic), in the flow path, servicing safety l,

related equipment that is not locked, sealed, or otherwise secured in position, is in its correct position.

j

b. ' At least once per 18 months during shutdown, by:

j 1.

Verifying that each automatic valve servicing safety related equipment actuates to its correct position on a low pond level signal.

l-Verifying that the buried piping is leak tight by a visual 2.

l inspection of the ground area.

i

?

d; i

k i

FARLEY-UNIT 2 3/4 7-13 Amendment No. 13 l

-~

'I PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) b.

Visual Inspection Acceptance Criteria Visual inspcctions shall verify (1) that there are no visible indica-tions of damage or impaired OPERABILITY and (2) attachments to the Snubbers which foundation or supporting structure are secure.

appear inoperable as a result of visual inspections r.ay be determined OPERABLE for the purpose of establishing the next visual inspection interval, providing that (1) the cause of the rejection is clearly established and remedied for that particular snubber and for other snubbers that may be generically susceptible; and (2) the affected snubber is functionally tested in the as found condition and deter-mined OPERABLE per Specifications 4.7.9.d or 4.7.9.e.,as applicable.

However, when the fluid port of a hydraulic snubber is found to be uncovered, the snubber shall be declared inoperable and cannot be t

determined OPERABLE via functional testing unless the test is started

<l with the piston in the as found setting, extending the piston rod in f

All snubbers connected

'I the tension and compression mode directions.

to an inoperable common hydraulic fluid reservoir shall be counted as inoperable snubbers.

c.

Functional Tests At least once per 18 months during shutdown, a representative sample of 88 snubbers shall be functionally tested either in place or in a If more than 3 snubbers do not meet the functional test bench test.

acceptance criteria of Specification 4.7.9.d or 4.7.9.e, an additional sample selected according to the expression 22(a-3) shall be func-tionally tested, where a is the total number of snubbers found inoperable during the functional testing of the initial representative sample.

Functional testing shall continue according to the expression (22)b where b is the number of snubbers found inoperable in the previous

.l re-sample, until no additional inoperable snubbars are found within a sample or until all snubbers in Table 3.7-4a and 3.7-4b have been functionally tested.

Snubbers greater than 50,000 lb. capacity may not be excluded from I

{

functional testing requirements.*

l The representative sample selected for functional test

, f At : east 25% of the snubbers range of size and capat.ity of snubbers.in the initial representative l

a l

following three categories:

The first snubber away from each, reactor vessel nozzle I

1.

i second refueling "This portion of the specification is not effective until theout l

later.

FARLEY-UNIT 2 3/4 7-21 Amendment No. 13 i

~

-_ ~

i PtANT SYSTEMS i

i SURVEItLANCE REQUIREMENTS (Continued) 2.

Snubbers within five feet of heavy equipment (valve, pump, turbine, motor,etc.)

t l

3.

Snubbers within ten feet of the discharge from a safety relief valve Snubbers identified in Tables 3.7-4a and 3.7-4b as "Especially Difficult to Remove" or in "High Radiation Zones During Shutdown" shall also be included in the representative sample.* Tables 3.7-4a and 3.7-4b may be used jointly or separately as the basis for the l

sampling plan.

In addition to the regular sample, snubbers which failed the previous t

If a functional test shall be retested during the next test period.

spare snubber has been installed in place of a failed snubber, then both the failed snubber (if it is repaired and installed in another Test results of position) and the spare snubber shall be retested.

these snubbers raay not be included for the re-sampling.

If any snubber selected for functional testing either fails to lockup or falls to move, i.e., frozen in place, the cause will ba evaluated and if caused by manufacturer or design deficiency all i

snubbers of the same design subject to the same defect shall be functionally tested. This testing requirement shall be independent of the requirements stated above for snubbers not meeting the 4

functional test acceptance criteria.

i For the snubber (s) found inoperable, an engineering evaluation shall be performed on the components which are supported by the snubber (s).

The purpose of this engineering evaluation shall be to determine if the components supported by the snubber (s) were adversely affected by the inoperability of the snubber (s) in order to ensure that the attached component remains capable of meeting the designed service.

Hydraulic Snubbers Functional Test Acceptance Criteria d.

I The hydraulic snubber functional test shall verify that:

l Activation (restraining action) is achieved within the specified 1.

range of velocity or acceleration in both tension and compression.

j Permanent or other exemptions from functional testing for individual snubbers j

n-in these categories may be, granted by the Commission only if a justifiable basis for exemption is presented and/or snubber Iffe destructive testing was performed to qualify snubber operability for all design conditions at either i

l ;

the completion of their fabrication or at a subsequent date, ll

'i I

FARLEY-UNIT 2 3/4 7-22 Amendment flo.13 l

l PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 2.

Snubber bleed, or release rate, where required, is within the specified range in compression or tension. For snubbers specifically required to not displace under continuous load, the ability of the snubber to withstand load without displacement shall be verified.

Mechanical Snubbers Functional Test Acceptance Criteria

l e.

The mechanical snubber functional test shall verify that:

1.

The force that initiates free movement of the snubber rod in either tension or compression is less than the specified maximum drag force.-

2.

Activation (restraining action) is achieved within the specified range in both tension and compression.

l l

I 3.

Snubber release rate, where required, is within the specified range in compression or tension.

For snubbers specifically required not to displace under continuous' load, the ability of f

the snubber to withstand load without displacement shall be verified.

I, l'

i I

l l

l "This portion of the specification is effective prior to startup following the second refueling outage.

.t FARLEY-UNIT 2 3/4 7-23 Amendment No. 13 j

1

'*~

3/4.8 ELECTRICAL POWER SYSTEMS 3/4.8.1 A.C. SOURCES OPERATING LIMITING CONDITION FOR OPERATION 3.8.1.1 As a minimum, the following A.C. electrical powar sources shall be OPERABLE:

Two physically independent circuits from the offsite transmission a.

network to the switchyard and two physically independent circuits from the switchyard to the onsite Class 1E distribution system, and b.

Two separate and independent diesel generator sets (Set A: DG 1-2A and DG-IC, Set B: DG-2B and DG-2C) each with:

l 1.

Separate day tanks containing a minimum volume of 900 gallons of fuel for the 4075 kw diesel generators and 700 gallons of fuel for the 2850 kw diesel generators.

l 2.

A separate fuel transfer pump for each diesel.

A fuel storage system consisting of four, independent storage tanks c.

y each containing a minimum of 25,000 gallons of fuel."

APPLICABILITY: MODES 1, 2, 3 and 4.

}o:

f ACTION:

a.

With an offsite circuit inoperable, demonstrate the OPERABILITY of the remaining offsite A.C. source by performing Surveillance Require-ment 4.8.1.1.1.a within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months and at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months q

thereafter, and performing Surveillance Requirement 4.8.1.1.2.a, Items 1, 2, 3, 4, and 6 on diesel generators 1-2A and 2B within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months unless such surveillance has been performed within the pre-ii vious 7 days.

Restore at least two offsite circuits to OPERABLE status within,7 days or be in at least HOT STANDBY within the next i

6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUT 00WN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months . The l

provisions of Specification 3.0.4 are not applicable.

4 b.

With one diesel generator set inoperable for reasons other than the yearly scheduled maintenance ** demonstrate the operability of the remaining A.C. sources by performing Surveillance Requirement 4.8.1.1.1.a within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months and at least once per 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months thereaf ter, and per-i forming Surveillance Requirement 4.8.1.1.2.a, items 1, 2, 3, 4, and 3

One operable fuel storage tank must be available for each required l l diesel generator.

I 1

- If this scheduled maintenance exceeds 10 days, the diesel generator set must be declared inoperable.

FARLEY-UNIT 2 3/4 8-1 Amendment No.13 I.

t 1

. +. - -,.-.

~ <-

-.~.

l ELECTRICAL POWER SYSTEMS 4

ACTION (Continued) 6 on two* diesel generators within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . Restore the diesel generator ' set to OPERABLE status within 18 days or be in at least HOT SHUT 00hh 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 . The provisions of Specification 3.0.4 are not applicable if only one of the four diesel generator units is i

inoperable.

With one offsite circuit and one diesel generator set of the above c.

required A.C. electrical power sources inoperable for reasons other than the yearly scheduled maintenance,** demonstrate the OPERABILITY of the remaining offsite A.C. source by performing Surveillance Require-i J

ment 4.8.1.1.1.a within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and performing Surveillance 1

Requirement 4.8.1.1.2.a. items 1, 2, 3, 4, and 6 on two* diesel generators within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . Restore at least one of the inoperable j

sources to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the g

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

Restore the other AC power source (offsite circuit or diesel generator set) to OPERABLE status in accordance with the provisions of Section 3.8.1.1 Action Statements a or b, as 4

li appropriate, d.

With two of the above required offsite A.C. circuits inoperable, demonstrate the OPERABILITY of both diesel generator sets by per-forming Surveillance Requirement 4.8.1.1.2.a within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ; unless the diesel generators are already operating; restore at least one of j

the inoperable offsite sources to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or ll 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 . With only one offsite source restored, restore both offsite circuits to OPERABLE status within 7 days from time of initial loss 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 SHUT 00hN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

With both of the above required diesel generator sets inoperable, ll demonstrate the OPERABILITY of two offsite A.C. circuits by per-e.

forming Surveillance Requirement 4.8.1.1.1.a within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and performing Surveillance Requirement 4.8.1.1.2.a. items 1, '2, 3, 4, and 6 on one diesel generator in a diesel set on the other Unit i

within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months ; restore at least one of the inoperable diesel gen-

,l

'i erator sets to OPERABLE status:

Ii E4 "The two diesel generators chosen to be tested shall verify.that at

'ii least one train of LOCA/ shutdown loads is capable of being powered at each Unit.

- If this scheduled maintenance exceeds 10 days, the diesel generator set must be declared inoperable.

)

i 1

lf Amendment No. 13 FARLEY-UNIT 2 3/4 8-2

~.

--.m.

ELECTRICAL POWER SYSTEMS ACTION (Continued)

l 1.

Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months if (DG 1-2A and DG-2C) or(DG-2B and DG-IC) or (DG-1C and I

DG-2C) are inoperable; or 2.

Within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months if DG 1-2A and DG-2B are inoperable; or 3.

Within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-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 if three or more diesel generators are inoperable.

Restore both diesel generator sets to OPERABLE status within 18 days from time of initial loss 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

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

SURVEILLANCE REQUIREMENTS 4.8.1.1.1 Each of the above required independent circuits between the offsite transmission network and the onsite Class 1E distribution system shall be:

a., Determined OPERABLE at least once per 7 days by verifying correct breaker alignments, indicated power availability, and b.

Deomonstrated OPERABLE at least once per 18 months during shutdown by transferring unit power supply from the normal circuit to the 7

alternate circuit.

4.8.1.1.2 E'ach diesel generator shall be demonstrated OPERABLE:

In accordance with the frequency specified in Table 4.8-1 on a a.

STAGGERED TEST BASIS by:

1.

Verifying the fuel level in the day tank.

2.

Verifying the fuel level 1,n the fuel storage tanks.

I 3.

Verifying the fuel transfer pump can be started and transfers fuel from the storage system to the day tank.

4.

Verifying the diesel starts and accelerates to at least 900 rpm for the 2850 kw generator and 514 rpm for the 4075 kw generators in less than or equal to 12 seconds. The generator voltage and frequency shall be > 3952 volts and > 57 Hz within 12 seconds l

after the start sigiial and operates Tor 5 minutes.

5.

Verifying the generator is synchronized, loaded to 2700-2850 kw for the 2850 kw generator and 3875-4075 kw for the 4075 kw generator and operates for greater than or equal to 60 minutes.

i

}

i-FARLEY-UNIT 2 3/4 8-3 Amendment No.13 emee*

-"---t-m4-

e

.o_.~

')

i ELECTRICAL POWER SYSTEMS

)

SURVEILLANCE REQUIREMENTS (Continued) 6.

Verifying the diesel generator is aligned to provide standby power to the associated emergency busses.

At least once per 92 days by verifying that a sample of diesel fuel

- b.

from the fuel storage tank obtained in accordance with ASTM-D270-65 is within the acceptable limits specified in Table 1 of ASTM D975-74

,i when checked f.or viscosity, water and sediment, c.

At least once per 18 months by:.

1.

Subjecting the diesel to an inspection and maintenance in accordance with procedures prepared in conjunction with its manufacturer's recommendations, 2.

Simulating a loss of offsite power by itself, and:

4 1.

a)

Verifying de-energization of the emergency busses and load shedding from the emergency busses.

j Verifying the diesel starts on the auto-start signal, b) energizes the e*mergency busses with permanently connected l

loads within 12 seconds, energizes the auto-connected shutdown loads through the load sequencer and operates for I

greater than or equal to 5 minutes while its generator is J

loaded with the shutdown loads. After energization of all loads, the steady state voltage and frequency of the emergency busses shall be maintained at 4160 i 420 volts and 60 2 1.2 Hz during this test.

Verifying that on a Safety Injection test signal (without loss l

3.

of offsite power) the diesel generator starts on the auto-start signal and operates on standby for greater than or equal to 5 The generator voltage and frequency shall be > 3952 minutes.

volts and > 57 Hz within 12 seconds after the auto-start signal; l

the steady state generator voltage and frequency shall be maintained between 4160 i 420 volts and 60 1 1.2 Hz during this

I test.

Simulating a loss of offsite power in conjunction with a Safety l

4.

Injection test signal, and:

a)

Verifying de-energization of the emergency busses and load

?

shedding from the, emergency busses.

Verifying the diesel starts on the auto-start signal, b) energizes the energency busses with permanently connected loads within Iz' seconds, energizes the auto-connected l

3 emergency (accident) loads through the load sequencer and

)

Energization of the Unit 2 emergency bus for diesel generator 2C is achieved within 26 seconds.

FARLEY-UNIT 2 3/4 8-4 Amendment No.13 4

aan.,a.w s "

-,=eewn-=

e me s m wm ~ =

om em -

~ v,

m

l ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) operates for greater than or equal to 5 minutes while its generator is loaded with the emergency loads. After energization, the steady state voltage and frequency of the emergency busses shall be maintained at 4160 1 420 volts and 60 i 1.2 Hz during this test.

Verifying that all automatic diesel generator trips, c) except engine overspeed and generator differential and low lube oil pressure, are automatically bypassed upon loss of voltage on the emergency bus and/or a safety infection test signal.

5. ' Verify that the diesel generators operate for 24' hours while loaded to 4353 kw for the 4075 kw diesels and 3100 for the 2850 kw diesels (2000 hour0.0231 days 0.556 hours 0.00331 weeks 7.61e-4 months rating). After completing this 24-hour test, manually trip the diesel generator from the 2000-hour load and demonstrate hot restart capability by performing Surveillance Requirement 4.8.1.1.2.a.4 within 10 minutes.

6.

Verifying ttiat the auto-connected loads to each diesel genera-j tor do not exceed the 2000-hour rating of 4353 kw for the 4075 kw generator and 3100 kw for the 2850 kw generator.

g l

7.

Verifying the diesel generator's capability to:

l a)

Synchronize with the offsite power source while the genera-

}

tor is loaded with its emergency loads upon a simulated i

restoratiori of offsite power.

i>f b)

Transfer its loads to the offsite power source, and c)

Be restored to its standby status.

8.

Verifying that with the diesel generators operating in a test l

mode (connected to its bus), a simulated safety injection signal overrides the test mode by returning the diesel gen-

!l' erator to standby operation.

9.

Verifying that the automatic load sequence timer is OPERABLE l

with each load sequence time within i 10% of its required value 4

or 0.5 seconds whichever is greater.

10.

Verifying that the following diesel generator lockout features l

I J prevent diesel generator starting only when required:

'i l

a) 011 Temperature High (OTH) 1

>1 1

'FARLEY-UNIT 2 3/4 8-5 Amendment No. 13 i

I

--'-*t*

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q

,wew,-.

M-

-w e meel> - w

ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) i b)

Coolant Temperature High (CTH) c)

Coolant Pressure Low (CPL) d)

Crankcase Pressure High (CCPH) 11.

Verifying the capability to reject a load of greater than or equal to the largest single load associated with that diesel generator (approximately 1000 kw); while maintaining voltage between 3740 and 4580 volts and speed less than or pqual to 75%

of the difference between nominal speed and the overspeed trip

{

setpoint.

d.

At least once per 10 years or after any modifications which could affect diesel generator interdependence by starting the diesel generators simultaneously, and verifying that the diesel generators accelerate to at least 900 rpm, for the 2850 kw generator and 514 rpm for the 4075 kw generator, in less than or equal to 12 seconds.

l At least once per 5 years, on a staggered basis, by verifying that e.

the diesel generator can reject a load of 1200-2400 kw without tripping. The diesel generator output breaker (s) must remain closed i

such that the diesel generator is connected to at least one emergency 8

j bus. Verify that all fuses and breakers on the energized emergency l

bus (es) are not tripped. The generator voltage shall remain within 3330 and 4990 volts during and following the load rejection.

4.8.1.1.3 Reports - All diesel generator failures, valid or nonvalid, shall i

be reported to the Commission pursuant to Specification 6.9.1.

Reports of diesel generator failures shall include the information recommended in Regu-

'I latory Position C.3.b of Regulatory Guide 1.108, Revision 1, August 1977. If

. the number of failures in.the last 100 valid tests (on a per diesel basis) is l

greater than or equal to 7, the report shall be supplemented to include the additional information recommended in Regulatory Position C.3.b of Regulatory Guide 1.108, Revision 1, August 1977.

l 1

3/4 8-6 Amendment No.13 FARLEY-UNIT 2 i

-+,-

,ep.-_

.m

t 9

n TABLE 4.8-1 DIESEL GENERATOR TEST SCHEDULE (PER DIESEL)

Number of Failures In Test Frequency Last 100 Valid Tests

At least once per 14 days 42 At least once per 7 days 3,3 l

t 1

l-f1 i

}

WCriteria for determining r. umber of failures and number of valid tests shall

~

be in accordance with Regulatory Position C.2.e of Regulatory Guide 1.108, Revision 1. August 1977, where the last 100 tests are determined on a per j

I For the purposes of this test schedule, only valid tests diesel basis.

conducted after the OL issuance date shall be included in the computation l.

of the "last 100 valid tests."

l-3/48-7 Amendment No.13 FARLEY - UNIT 2 l

I i

ELECTRICAL POWER SYSTEMS

)

SHUTOOWN t

LIMITlHG CONDITION FOR OPERATION 1

I l

3.8.1.2 As a minimum, the following A.C. electrical power sources shall i

be OPERABLE:

l One circuit from the offsite transmission network to the switchyard and from the switchyard to the onsite Class 1E a.

distribution system, and f

b.

Diesel generator 1-2A,1C or 2B each with:

A day tank containing a minimum volume of 900 gallons of 1.

fuel for the 4075 kw diesel generator and 700 gallons of fuel for the 2850 kw diesel generator.

A fuel storage tank containing a minimum volume of 25,000 2.

I gallons of fuel, and 1

'l 3.

A fuel transfer pump.

l APPLICABILITY _: MODES 5 and 6.

j l

ACTION:,

l ~

With less than the above minimum required A.C. electrical power sources I

l OPEPABLE, suspend all operations involving CORE ALTERATIONS or positive reactivity changes until the minimum required A.C. electrical power i

j sources are r,estored to OPERABLE status..

l}

SURVEILLANCE REQUIREMENTS 4.8.1.2 The above required A.C. electrical power sources shall be l4

,derenstrated OPERABLE by the perfonnance of each of the S l

I

j 1

FARLEY-UNIT 2 3/4 B-8 Amendment No.13

~~

j ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

I The voltage of each connected cell is greater than or equal to l

2.

2.02 volts under float charge and has not decreased more than 0.1 volts from the value observed during the original acceptance l

test.

The specific gravity, corrected to 77'F and full electrolyte l

3.

1evel, of each connected cell is greater than or equal to 1.190 and has not decreased more than 0.08 from the value observed l

during the previous test, and The total battery terminal voltage is greater than or equal to f-4.

121.2 volts.

At least once per 18 months by verifying that:

c.

The cells, cell plates and battery racks show no visual i

1.

indication of physical damage or abnormal deterioration, The cell-to-cell and terminal connections are clean, tight, and

}:

2.

coated with anti-corrosion material, and The battery charger will supply at least 536 amperes at 3.

> 125 vt:lts for at least 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

~

At 1 east once per 18 months during shutdown, by verifying that the d.

battery capacity is adequate to supply and maintain in OPERABLE status all of the actual emergency loads for 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months when the

]

battery is subjected to a battery service test or the individual i

cell voltage does not decrease below 1.75 volts when the battery is subjected to the following equivalent load profile.

i l

f Order In Which Duration loads Are Current (ampsl (min.)

Applied 1

920 1

2 430 58 3

920 1

j 4

430 59 5

920 1

i i

3/4 8-12 Amendment No.13 FARLEY-UNIT 2

ELECTRICAL POWER SYSTEMS SERVICE WATER BUILDING D.C. DISTRIBUTION - OPERATING I

LIMITING CONDITION FOR OPERATION l7 3.8.2.5 The following D.C. distribution systems shall be energized and OPERABLE:

l TRAIN "A" consisting of 125-volt D.C. Distribution Cabinet 1M,125-volt battery bank No.1 and a full capacity charger.

TRAIN "B" consisting of 125-volt D.C. Distribution Cabinet 1N.,

125-volt battery bank No. 2, and a full capacity charger.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

With one 125-volt D.C. distribution train inoperable, restore the inoperable l

distribution system to OPERABLE and energized status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-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 i

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

SURVEILLANCE REQUIREMENTS i

, L.

4.8.2.5.1 Each D.C. train shall be determined OPERABLE and energized at l

1 east once per 7 days by verifying correct breaker alignment and indicated power availability.

4.8.2.5.2 Each 125-volt battery bank and charger shall be demonstrated OPERABLE:

a.

At least once per 7 days by verifying that:

1.

The electrolyte level of the pilot cell is between the minimum

~

and maximum level indication marks.

l4 2.

The pilot cell specific gravity, corrected to 77*F and full l

electrolyte level, is greater than or equal to 1.190, j

1 3.

The pilot cell voltage is greater than or equal to 2.C2 volts,'and l

t Il 4.

The total battery terminal voltage is greater than or equal to 121.2 volts.

b.

At least once per 92 days by verifying that:

il1 1.

The electrolyte level of each cell is between the minimum and maximum level indication marks, l

Amendment No.13 FARLEY-UNIT 2 3/4 8-15

-m.

l t

ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS (Continued) 2.

The voltage of each connected cell is greater than or equal to l

2.02 volts under float charge and has not decreased more than 0.1 volts from the value observed during the original acceptance test, and 3.

The specific gravity, corrected to 77'F and full electrolyte l

level, of each connected cell is greater than or equal to 1.190 and has not decreased more than 0.08 from the value observed during the previous test.

At least once per 18 months by verifying that:

c.

1.

The cells, cell plates and battery racks show no visual indication of physical damage or abnormal deterioration, i

2.

The cell-to-cell and terminal connections are clean, tight, and coated with anti-corrosion material, and 3.

The battery charger will supply at least 3 amperes at > 125 volts l

for at least 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

At least once per 18 months, during shutdown, by verifying that the l

di battery capacity is adequate to supply and maintain in OPERABLE status all of the actual emergency loads for 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months when the battery is subjected to a battery service test or the individual cell voltage does not decrease below 1.75 volts when the battery is subjected to-the following e'quivalent load profile:

(

Order in dhich Current Loads are Applied (amps)

Duration 1

25 0 - 0.1 sec 2

1-0.1 sec - 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months l

i.

4 i

m

)

FARLEY-UNIT 2 3/4 8-16 Amendment No. 13 4

_.--.e-s--.

t REFUELING OPERATIONS

)

3/4.9.14 CONTAINMENT PURGE EXHAUST FILTER t

~

LIMITING CONDITION FOR OPERATION The containment purge exhaust filter shall be OPERABLE and valve 3.9.14 N1P13V293 closed.

APPLICABILITY: During CORE ALTERATIONS and Fuel Movement inside containment l

bith any containment purge isolation valve open.

With the containment purge exhaust filter inoperable either:

ACTION:

Immediately close the 48 inch containment purge isolation valves 1.

(CBV-HV-3196, 3197, 3198A and 3198D) and the 18 inch containment mini-purge isolation valves (CBV-HV-2866A, 28668, 2867A and 28678),

j 5

or 4

2.

Cease all CORE ALTERATIONS and fuel movement.

l SURVEILLANCE REQUIREMENTS 4

l The above required containment purge exhaust filter shall be 4.9.14 demonstrated OPERABLE:

At least once per 18 months or (1) after any structural maintenance on the HEPA filter or charcoal adsorber housings, or (2) following 1

a.

painting, fire or chemical release that could have contaminated i

,{

the charcoal adsorbers or HEPA filter in any ventilation ' zone communicating with the system by:

J 1

J i

i i

1 3/4 9-16 Amendment No.13 FARLEY-UNIT 2

I SPECIAL TEST EXCEPTIONS 3/4.10.5 POSITION INDICATION SYSTEM - SHUTDOWN LIMITING CONDITION FOR OPERATION 3.10.5 The limitations of Specification 3.1.3.3 may be suspended during the performance of individual full length (shutdown and control) rod drop time measurements provided; Only one shutdown or control bank is withdrawn from the fully a.

inserted position at a time, and b.

The rod position indicator is OPERABLE during the withdrawal of the l

rods.

APPLICABILITY: MODES 3, 4 and 5 during performance of rod drop time measurements.

ACTION:

l With the position indication system inoperable or with more than one bank of i

l rods withdrawn, immediately open the reactor trip breakers.

t

)

SURVEILLANCE REQUIREMENTS I

j' 4.10.5 The above required rod position indication systems shall be determined to be OPERABLE within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months prior to the start of and at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter during rod drop time measurements by verifying the de.t.and position indication system and the rod position indication systems agree

Within 12 steps when the rods are stationary, and a.

i b.

Within 24 steps during rod motion.

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FARLEY-UNIT 2 3/4 10-5 Amendment No.13

TABLE 4.11-1 RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM i

Minimum Detectable Minimum Concentration Liquid Release Sampling Analysis Type of Activity (MDC)

Type Frequency Frequency Analysis (pCi/ml)a,g A. Batch Waste P

P

~7 Principa 5x10 Release Each Batch Each Batch Emitters} Gamma c

Tanks

-6 I-131 1x10

-5 P

M Dissolved and lx10 One Batch /M Entrained Gases' (Gamma e.nitters)

-5 P

M H-3 1x10 b

Each Batch Composite Gross Alpha 1x10

~8 P

Q Sr-89, Sr-90 5x10 b

l Each Batch Composite

-6 Fe-55 1x10 i

1

~7 Principa 5x10 B. Continuous 0

W Emitters} Gamma d"

b Releases '

Grab Sample Composite I-131 1x10

1. Steam

-5 l

Generator M

M Dissolved and 1x10 Blowdown Gmb Sample Entrained Gases (Gamma Emitters)

-5 D

M H-3 1x10 b

Grab Sample Composite

~7 Gross Alpha 1x10

-8 l

D Q

5:-89, Sr-90 5x10 b

I Grab Sample Composite

-6 Fe-55 1x10

~7 2.

Turbine P

W PrincipleGgmma 5x10 b

Builping Grab Sample Composite Emitters

-5 Sump H-3 1x10

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FARLEY-UNIT 2 3/4 11-2 Amendment No.13 s~

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i RADI0 ACTIVE EFFLUENTS DOSE LIMITING CONDITION FOR OPERATION 4

The dose or dose commitment to an individual from radioactive 3.11.1.2 materials in liquid effluents released, from each reactor unit, from the site L

(see Figure 5.1-4) shall be limited:

During any calendar quarter to less than or equal to 1.5 mrem to the a.

total bcdy and to less than or equal to 5 mrem to any organ, and-During any calendar year to less than or equal to 3 mrem to the b.

total body and to less than or equal to 10 mrem to any organ.,

APPLICABILITY: At all times.

ACTION:

With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, in lieu of a.

any other report required by Specification 6.9.1, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a i

Special Report which identifies the cause(s) for exceeding the l'

Ifmit(s) and defines the corrective actions to be taken to reduce the releases of radioactive materials in liquid effluents during the

. remainder of the current calendar quarter and during the remainder

(

of the current calendar year, so that the cumulative dose or dose commitment to an individual from these releases is within 3 mrem to the total body and 10 mrem to any organ.

l The provisions of specifications 3.0.3 and 3.0.4 are not applicable.

b.

l SURVEILLANCE REQUIREMENTS Cumul'ative dose contributions from liquid effluents 4.11.1.2 Dose Calculations.

shall be determined in accordance with the ODCM at least once per 31 days.

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3/4 11-5 Amendment No.13 FARLEY-UNIT 2

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i RADI0 ACTIVE EFFLUENTS i

DOSE - NOBLE GASES LIMITING CONDITION FOR OPERATION 3.11.2.2 The air dose due to noble gases released in gaseous effluents, from each reactor unit, from the site (see Figure 5.1-3) shall be limited to the following:

a.

During any calendar quarter: Less than or equal to 5 mrad for gamma radiation and less than or equal to 10 mrad for beta radiation and, 1

b.

During any calendar year:

Less than or equal to 10 mrad for gamma radiation and less than or equal to 20 mrad for beta radiation.

APPLICABILITY: At all times.

ACTION 4

With the calculated air dose from radioactive noble gases in gaseous a.

effluents exceeding any of the above limits, in lieu of any other report required by Specification 6.9.1, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report which identifies the cause(s) for exceeding the limit (s) and defines the corrective actions to be taken to reduce the releases of radioactive noble gases in gaseous effluents during the remainder of the current calendar quarter and during the remainder of the current calendar year, so that the cumulative dose.is within 10 mrad for l

l1 gamma radiation and 20 mrad for beta radiation.

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b.

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

1 SURVEILLANCE REQUIREMENTS a

4.11.2.2 Dose Calculations Cumulative dose contributions for the current calendar quarter and current calendar year shall be determined in accordance with the ODCM at least once per 31 days.

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FARLEY-UNIT 2 3/4 11-12 Amendment No. 13

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RADI0 ACTIVE EFFLUENTS DOSE - RADIOI0 DINES, RADI0 ACTIVE MATERIALS IN PARTICULATE FORM, AND RADIONUCLIDES OTHER THAN NOBLE GASES LIMITING CONDITION FOR OPERATION The dose to an individual from radiofodines and radioactive materials 3.11.2.3 in particulate form, and radionuclides (other than noble gases) with half-lives greater than 8 days in gaseous effluents released, from each reactor unit, froe the site (see Figure 5.1-3) shall be limited to the following:

a.

During any calendar quarter: Less than or equal to 7.5 arem to any organ and, b.

During any calendar year:

Less than or equal to 15 mrem to any organ.

APPLICABILITY: At all times.

ACTION:

With the calculated dose from the release of radiciodines, radioactive l

a.

materials in particulate form, or radionuclides (other than noble gases) with half lives greater than 8 days, in gaseous effluents exceeding any of the.above limits, in lieu of any other report required by Specification 6.9.1, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report which identifies the cause(s) for exceeding the limit and defines the corrective actions to be taken to reduce the releases of radio-iodines and radioactive materials in particulate form, and radio-nuclides (other than nobles gases) with half-lives greater than 8 days in gaseous effluents during the remainder of the current calendar quarter and during the remainder of the current calendar year, so that the cumulative dose or dose commitment to an individual i

from these releases is within 15 mrem to any organ, The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

b.

SURVEILLANCE REQUIREMENTS Dose Calculations Cumulative dose contributions for the current l

4.11.2.3 calendar quarter and current calendar year shall be determined in accordance l

with the 00CM at least once per 31 days.

I FARLEY-UNIT 2 3/4 11-13 Amendment No.13 l

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3/4.2 POWER DISTRIBUTION LIMITS BASES The specifications of this section provide assurance of fuel integrity during Condition I (Normal Operation) and II (Incidents of Moderate Frequency)

(a) maintaining the minimum DNBR in the core greater than or equal events by:

to 1.30 during normal operation and in short term transients, and (b) limiting the fission gas release, fuel pellet temperature and cladding mechanical i,

In addition, limiting the peak properties to within assumed design criteria.

linear power density during Condition I events provides assurance that the j ~,

initial conditions assumed for the LOCA analyses are met and the ECCS acceptance criteria limit of 2200"F is not exceeded.

The definitions of certain hot channel and peaking factors as used in these specifications are as follows:

Heat Flux Hot Channel Factor, is defined as the maximum local F (Z) 9 heat flux on the surface of a fuel rod at core elevation Z divided by the average fuel rod heat flux, allowing for manufacturing tolerances on fuel pellets and rods and measurement uncertainty.

Nuclear Enthalpy Rise Hot Channel Factor, is defined as the ratio of Fh the integral of linear power along the rod with the highest integrated power to the average rod power.

Radial Peaking Factor, is defined as the ratio of peak power density Fxy(Z) to average power density in the horizontal plane at core elevation Z.

y i

j 3/4.2.1 AXIAL FLUX DIFFERENCE The limits on AXIAL FLUX DIFFERENCE (AFD) assure that the F (Z) upper q

bound envelope of 2.31 times the normalized axial peaking factor is not l

exceeded during either normal operation or in the event of xenon redistribution following power changes.

l Target flux difference is determined at equilibrium xenon conditions.

The full length rods may be positioned within the core in accordance with 1

their respective insertion ifmits and should be inserted near their normal The value of the position for steady state operation at high power levels. target flu of RATED THERMAL POWER is the target flux difference at RATED THERMAL POWER for the associated core burnup conditions. Target flux differences for other THERMAL POWER levels are obtained by multiplying the RATED THERMAL POWER valu by the appropriate fractional THERMAL POWER level. The periodic updating of j

the target flux difference value is necessary to reflect core burnup considerations.

l FARLEY-UNIT 2 B 3/4 2-1 Amendmsnt No. 13

k REACTOR COOLANT SYSTEM

)

BASES

' l 3/4.4.2 and 3/4.4.3 SAFETY VALVES

' The pressurizer code safety valves operate to prevent the RCS from being Each safety valve is pressurized above its Safety Limit of 2735 psig.lbs per hour of saturated steam at the vu 345,000 designed to relieve The relief capacity of a single safety valve is adequate to relieve point.

In the event any overpressure condition which could occur during shutdown.

that no safety valves are OPERABLE, an operating RHR loop, connected to the RCS, provides overpressure relief capability and will prevent RCS overpres-In addition, the Overpressure Protection System provi, des a surization.

diverse means of protecticn against RCS overpressurization at low temperatures.

During operation, all pressurizer code safety valves must be OPERABLE to prevent the RCS from being pressurized above its safety limit of 2735 psig.

The combined relief capacity of all of these valves is greater than the maximum surge rate resulting from a complete loss of load assuming no reactor trip until the first Reactor Protective System trip set point is reached (i.e., no credit is taken for a direct reactor trip on the loss of load) and also assuming no operation of the power operated relief valves or steam dump valves.

l Demonstration of the safety valves' lift settings will occur only during shutdown and will be performed in accordance with the provisions of Section XI of the ASME Boiler and Pressure Code.

3/4.4.4 PRESSURIZER The limit on the maximum water volume in the pressurizer assures that the parameter is maintaineQ within the normal steady state envelope of operation The limit is consistent with the initial SAR assumptions.

assumed in the SAR.

The 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months periodic surveillance is sufficient to ensure that the parameter The is restored to within its limit following expected transient operation.

maximum water volume also ensures that a steam bubble is formed and thus the The requirement that a minimum RCS is not a hydraulically solid system.

l number of pressurizer heaters be OPERABLE enhances the capability of the plant to control Reactor Coolant Pressure and establish natural circulation.

I iI 3/4.4.5 RELIEF VALVES (PORV's)

'l The power operated reitef salves and steam bubble function to relieve RCS l) pressure during all design transients up to and including the design step load decrease with steam dump. Operation of the PORV's minimizes the undesirable Each PORV has a l

opening of tL' spring-loaded pressurizer code safety valves.

remotely oper* ted block valve to provide a positive shutoff capability should l

l a relief valv'. become inoperable.

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8 3/4 4-2 Amendment No.13 t

FARLEY-UNIT 2 l

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PLANT SYSTEMS BASES 3/4.7.9 SNUBBERS All snubbers are required OPERABLE to ensure that the structural integrity of the reactor coolant system and all other safety related systems is maintained during and following a seismic or other event initiating dynamic loads.

Snubbers excluded from this inspection program are those installed on nonsafety related systems and then only if their failure or failure of the system on l

which they are installed, would have no adverse effect on any safety related i

system.

The visual inspection frequency is based upon maintaining a constant level of snubber protection to systems. Therefore, the required inspection l

interval varies inversely with the obser,ed snubber failures and is determined i'

by the number of inoperable snubbers found during an inspection.

Inspections performed before that interval has elapsed may be used as a new reference l

point to determine the next inspection. However, the results of such early inspections performed before the original required time interval has elapsed (nominal time less 25%) may not be used to lengthen the required inspection interval. Any inspection whose results require a shorter inspection interval i

will override the previous schedule.

When the cause of the rejection of a inubber is clearly established and

'(

I ramedied fcr that snubber and for any other snubbers that may be generically l

susceptible, and verified by inservice functional testing, that snubber may be t

exempted from being counted as inoperable. Generically susceptible snubbers l

are those which are of a specific make or model and have the same design l

.I features directly related to rejection of the snubber by visual inspection, or j

are similarly located or exposed to the same environmental conditions such as temperature, radiation, and vibration.

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~

When a snubber is found inoperable, an engineering evaluation is performed.

b The engineering evaluation shall determine whether or not the snubber mode of

,l failure has imparted a significant effect or degradation on the attached l'

component.

To provide assurance of snubber functional reliability, a representative sample of the installed snubbers will be functionally tested during plant shutdowns at 18 month intervals. Selection of a representative sample according i

to the expression 35(1 + {} provides a confidence level of approximately 95%

that 90% to 100% of the snubbers in the plant will be OPERABLE within' acceptance l

limits, where c is the allowable numbe of snubbers not meetino the acceotance

't criteria. Observed failures of these sample snubbers shall require functional testing of additional units.

Hydraulic snubbers and mechanical snubbers may each be treated as a different entity for the above surv'eillance programs.

1 1

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FARLEY-UNIT 2 B 3/4 7-5 Amendment No.13 l

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I ADMINISTRATIVE CONTPOLS b.

In-Plant Radiation Monitoring A program which will ensure the capability to accurately determine i

4 the airborne iodine concentration in certain plant areas where personnel may be present under accident conditions. This program shall include the following:

(i) Training of personnel, (11) Procedures for monitoring, and (iii) Provisions for maintenance of sampling and analyses equipment.

c.

Secondary Water Chemistry A program for monitoring of secondary water chemistry to inhibit steam generator tube degradation. This program shall include:

j (i) Identification of a sampling schedule for the critical variables and the control points for these variables.

(

l (ii) Identification of the procedures used to measure the values of the critical variables, j

(iii) Identification of process sampling points, including monitoring the condenser hotwells for evidence of condenser in-leakage.

j (iv) Procedures for the recording and management of data, (v) Procedures defining corrective actions for off-control point-chemistry conditions, and (vi) A procedure identifying (a) the authority responsible for the interpretation of the data, and (b) the sequence and timing of j

administrative events required to initiate corrective action.

{

i d.

Post-accident Sampling A program which will ensure the capability to obtain and analyze

!j reactor coolant, radioactive fodines and particulates in plant gaseous effluents, and containment atmosphere samples under accident t

i j conditions. The program shall include the training of personnel, the procedures for sampling and analysis and the provisions for maintenance of sampling and analysis equipment.

knendment No.13 j

FARLEY-UNIT 2 6-15 l

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- - - - - ~-

- ~

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a ADMINISTRATIVE CONTROLS 6.12 HIGH RADIATION AREA 6.12.1 In lieu of the " control device" or " alarm signal" required by paragraph 20.203(c)(2) of 10 CFR 20, each high radiation area in which the intensity of radiation is greater than 100 mrem /hr but less than 1000 mres/hr shall be barricaded and conspicuously posted as a high radiation area and entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit." Any individual or group of individuals permitted to enter such areas i

shall be provided with or accompanied by one or more of the following:

a.

'A radiat. ion monitoring device which continuously indicates the y

radiation dose rate in the area.

2 b.

A radiation monitoring device which continuously integrates the radiation dose rate in the area and alarms when a preset integrated-dose is received.. Entry into such areas with this monitoring device may be made after the dose rate level in the area has been l

established and personnel have been made knowledgeable of them.

c.

A health physics qualified individual (i.e., qualified in radiation protection procedures) with a radiation dose rate monitoring device who is responsible for providing positive control over,the activi-ties within the area and shall. perform periodic radiation surveillance at the frequency specified by the facility Health l

Physics Supervisor.

6.12.2 In addition to the requirements of 6.12.1, areas accessible to personnel l

with radiation irvels such that a major portion of the body could receive in one l.

hour a dose greater than 1000 mrem shall be provided with locked doors to prevent j

unauthorized entry, and the keys shall be maintained under the administrative

i control of the Shift Foreman on duty and/or health physics supervision.

Doors I

shall remain locked except during periods of access by personnel under an approved Radiation Work Permit which shall specify the dose rate levels in the immediate work area and the maximum allowable stay time for individuals in 1

that area.

For individual areas accessible to personnel with radiation levels such that a major portion of the body could receive in one hour a dose in excess of 1000 mrem ** that are located within large areas, such as PWR containment, j

where no enclosure exists for purposes of locking, and no enclosure can be reasonably constructed around the individual areas, then that area shall be i

roped off, conspicuously posted and a flashing light shall be activated as a l

warning device.

In lieu of the stay time specification of the RWP, direct or remote (such as use of closed circuit TV cameras) continuous surveillance may s

be made by personnel qualified in radiation protection procedures to provide positive exposure control over the activities within the area.

1

Health Physics personnel or personnel escorted by Health Physics personnel shall be exempt from the RWP issuance requirement during the performance of their assigned radiation protection duties, provided they are following plant radiation protection procedures for entry into high radiation areas.

- Measurement made at 18" from source of radioactivity.

FARLEY-UNIT 2 6-24 Amendment No. 13 l

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ML20051G633

Text

Attachment:

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