Latest revision as of 08:53, 17 February 2020

Text

Revised Pages Re Surveillance Requirements for Tech Spec Upgrade
	ML20010H866
Person / Time
Site:	Farley
Issue date:	09/22/1981
From:	; ALABAMA POWER CO.
To:	;
Shared Package
ML20010H860	List: ML20010H859; ML20010H866;
References
	NUDOCS 8109290367
	Download: ML20010H866 (64)
	v • d • e

t ATTACHMENT I Proposed Technical Specification Changes 8109290367 810922 PDR ADOCK 05000348 P PDR

APPLICABILITY <

- SURVEILLANCE REOUIREMENTS l l

1. At least HOT STANDBY 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

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

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 perfomed within the specified time interval with:

a. A maximum allowable extension not to exceed 25% of the surveillance interval, and

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

4.0.3 Performance of a Surveillance Requirement within the specified time interval shall constitute compliance with OPERABILITY requirements for a Limiting Condition for' 0peration and associated ACTIO.1 statements unless otherwise required by the specification. Surveillance Require-m ments do not have to be performed on inoperable equipment.

4.0.4 Entry into an OPEIIATIONAL MODE or other specified condition shall not 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 follcw -

a. Inservice inspection of ASME Code Class 1, 2 and 3 components and inservice testing of ASME Code Class 1, 2 and 3 pumps and valves shall be perfomed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by 10 CFR 50, Section 50.55a(g), except where specific written relief has been granted by the Commission pursuant to 10 CFR 50, Section 50.55a(g)(6)(i).

b. Surveillance intervals specified in Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda for the inservice inspection and testing activities required by the ASME Boiler and Pressure Vessel Code and applicable Addenda shall be applicable as follows in these Technical Specifications:

FARLEY-!JNIT ki 3/4 0-2

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k[) e TABLE 3.3-l' REACIOR TRIP SYSTEH INSTRUMENTATIO!I in T HINIMUM E TOIAL ll0. CllANilELS CllANilELS APPLICAULE M FUNCTIONAL UillT Of CllAllllELS 10 TRIP OPERABLE H0 DES ACTION

,*d P 1. Hanual Reactor Trip 2 1 2 1, 2, and

12 3

2. Power Range,lleutron Flux A. liigli 4 2 3 1, 2 11 . Low 4 2 3 2 2l 2

3. Power Range, Neutron flux 4 2 3 1, 2 2

.lligli PoslLive Rate

4. Power Range, Neutron Flux, 4 2 3 1, 2 2 liigli Negative Rate

$ 5. Intermediate Range, fleutron Flux 2 1 2 1, 2, and

3 to 4 6. Source Range, Heutron Flux gg A. Startup 2 1 2 ggy 2 , and

4

8. Shutdown 2 0 1 3, 4 and 5 5

7. Overtemperature AT y llirce Loop Operation 3 2 2 1, 2 7 Two Loop Operation 3 1** 2 1, 2 9

8. Overpower AT y Three Loop Operation 3 2 2 1, 2 7 Two Loop Operation 3 1** 2 1, 2 9

9. Pressurizer Pressure-Low 3 2 2 184 7

10. Pressurizer Pressure--liigli 3 2 2 1, 2 7

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? TABLE 3.3-1 (Centinued)

E Q REACTOR TRIP SYSTEM INSTRUMENTATION i

(b MINIMUM TOTAL NO. CHANNF'_0 CHANNELS APPLICABLE FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION

17. Turbine Trip g

! A. Low Auto Stop Oil Pressure 3 2 2 1 7, B. Turbine Throttle Valve 4 4 4 1 7

Closure i

18. Safety Injection Input I from ESF 2 1 2 1, 2 1

19. Reactor Coolant Pump Breaker Position Trip A. Above P-8 1/ breaker 1 1/ breaker 1 10,

B. Above P-7 1/ breaker 2 1/ breaker 1 11 R per oper-

ating loop Y

20. Reactor Trip System Interlocks A. Intermediate Range

Neutron Flux, P-6 2 1 2 2, and* 8

8. Low Power Reactor j Trips Block, P-7 P-10 Input 4 2 3 1 8 4 P-13 Input 2 1 2 1 8

)

C. Power Range Neutron

Flux, P-8 4 2 3 1 8 i

, i D. Power Range Neutron

f Flux, P-10 (Input to P-7) 4 2 3 1, 2 8 E. Turbine Impulse Chamber i Pressure, P-13 2 1 2 1 8 F. Power Range Neutron 4 2 3 1 8 Flux, P-9

9 -

I I Allt E ..,-1 (Continued)

E IIEACI0ll ll!!P SYST[H IllSTittlHEllTATlatl 6

<L . MINIMUlf

2 101 AL !!0. CilAllNELS CilAllNELS APPLICADLE Q FilflCTI0llAL Uilli of CllAliNEM 10 TillP OPEllAULE H0 DES ACTION w

p 21. Ileactor Trip Breakers 2 1 2 1, 2, and ^ l .

22. Automatic Trip Logic 2 1 2 1, 2, and

1 i

R b

'f' u,

s

TABLE 3.3-1 (Continued)

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

The channel (s) associated with the protective functions derived from the g

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.

1. 1. I ndication only.

The provisions of Soecification 3.0.3 are not applicable if THERMAL POWER level > 10% of RATO THERMAL POWER.

ACTION STATEMENTS ACTION 1 - With the number of OPERABLE channels one less than recuired 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 cp to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing per Specification 4.3.1.1.

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:

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~({L a.' The inoper~blea 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 .

b. The Minimum Channels OPERABLE recuirement is :st; however, dditi:::: channel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months 44% I eff#"bkL for ::: surveillance testin per Specification e.3.1.1.

/r ke. etkee cLanMis

c. Either, THERMAL POWER is restricted to less than or ecual to 75% of RATED THERMAL POWER and the Power Range, Neutron

, Flux trip setcoint is reduced to less than or ecual to SE%

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

d. The QUADRANT POWER TILT RATIO, as indicated by the remaining three datectors, is verified consistent with the quadrant power distribution obtained by using the movable incore detec: cts 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.

l i

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l5 FARLEY-UNIT 14, 3/4 3-6 l

k

TABLE 3.3-1 (Continued)

ACTION 3 - With the number of channels OPERABLE one less than required by the Minimum Channels OPERABLE requirement and with the THERMAL POWER level:

a. Below the P-6 (Block of Source Range Reactor Trip) setpoint, restore the inoperable channel to OPERABLE status prior to increasing THERMAL POWER above the P-6 Setpoint.

b. Above the P-6 (Block of Source Range Reactor Trip) setpoint, but below E% of RATED THERMAL POWER, restore the inoperable channel to OPERABLE status prior to increasing THERMAL PCWER above 5% of RATED THERMAL POWER.

c. Above 5% of RATED THERMAL POWER, POWER OPERATION say continue.

ACTION 4 - With the number of OPERABLE channels one less than required by the Minimum Channels OPERABLE requirement and with the THERMAL POWER level:

.a. Below'the P-6 (Block of Source Range Reactor Trip) setpoint, restore the inoperable channel to OPERABLE status prior to increasing THERMAL POWER above the P-6 Setpoint.

b. Above the P-6 (Block of Source Range Reactor Trip) setpoint,

-r- operation may continue.

o

\.C ACTION 5 - With the number of OPERABLE channels one less than recuired by the Minimum Channels OPERABLE requirement, verify co=cliance with the SHUTDOWN MARGIN requirements of Specification 3.1.1.1 or 3.1.1.2, as applicable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months thereafter.

ACTION 6 - With the number of OPERABLE channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the fo. ..1ng concitions are satisfied:

l

a. The 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 .

b. The Minimum Channels OPERABLE requirement is met; j -

however, one additional channel may be bypassed for

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

Specification 4.3.1.1.

ACTION 7 - With the number of OPERABLE channels one less '.han the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed until performance :f the next required CHANNEL FUNCTIONAL TEST provided the 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 .

1 1

i _

l PARLEY-UNITgb i, 3/4 3-7 I

\ _ . _ . . - - - . . - . . .

r- TABLE 3.3-1 (Continued) .

ACTION 8 - With the interlock inoperable to the extent that a reactor trip wnich should not be blocked in the current MODE is blocked, declare the trip function incperable and follow the ACTION statements of Table 3.3-1 for the affected channel (s).

Interlock Affected Channels on Table 3.3-1

1. P-6 a. Source Range, Neutron Flux Startup Shutdown *

2. P-7 a. Low Reactor Coolant Loop Flew (2 loops)

b. Undervoltage - Reactor Coolant Pumps

c. Underfrequency - Reactor Coolant Pu=ps

d. Pressurizer Low Pressure

e. Pressurizer High Level

3. P-8 a. Lcw Reactor Coolant Loop Flcw (1 loep)

4. P-9 a. Turbine Trip ,

5. P-10 c. Inter =ediate Range, Neutron Flux

b. Power Range, Neutron Flux - Low Setpoint

c. . Source Range, Neutron Flux L, Startup*

V Shutdown

d. P-7 (Itam 2 above) u-r -

6. P-13 a. P-7 (Itam 2 abcve)

ACTION 9 - With a channel associated with an cperating icep incperable, 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 or be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; hcwever, one channel asscciated with an cperating loco may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing per Specification 4.3.1.1.

ACTION 10 - With one channel incperacle, restere the incperable channel to CPERABLE status within 2 hcurs or recuce THERMAL PCWER to telew the P-S (Lew Reacter Ccclant Pu=p Flew and Reacter C0olant ? cap

. Breaker Position) setpoint within the next 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months . Operation belcw the P-8 (Lew Reacter Coolant Pu=p Flew and Reactor C olant Pu=o Breaker Position) setpoint may continue pursuant to l ACTION 11. ,

f

(

FARLEY-UNIT [ 3/4 3-8 w r

TABLE 3.3-1 (Concinuedl

f-ACTION 11 - With less than the Minimum Number of Channels OPERABLE, ooeration may continue provided the 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 .

t

)

ACTION 12 - With the nuecer of OPERABLE channels one less than required by the Minimum Channels OPERABLE requirement, restore the inoperable

, channel to CPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , or be in HOT '

STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

l l

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i FARLEy-UNIT g-{ 3/4 3-9 N- g

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.,, ..mtE 4.3-1 El p, !!! ACI0lt IRIP SYS1Lil INSilluMENTATION SilRVEILLANCE REQUIRTHElliS

. f .

., E q CilANNEL H0 DES IN WillCll CllAllllEL CllAHilEL FUNCTI0llAL SURVEILLANCE

{ $ FUNCTIONAL UNIT Cill:CK CALIBRATION TEST REQUIRED

1. Manual Reactor Trip fl. A. li. A. S/U(1) H.A.

2. Power Range,-Neutron Flux A. liluli S D(2),H(3) H 1, 2

' and Q(6) 11 . Low . 5 D(2),H(3) S/U(10) 2 and Q(G)

3. Power Range, Heutron Flux, ll'. A. R(6) H 1, 2

! liigh Positive Rate M 4. Power Range, Neutron Flux, ll. A. R(6) H. 1, 2

~

[ liigli Negative Rate

, % 5. Intermediate Range, S R(6) S/U(1) 1, 2, and *

Neutron Flux

6. Source Range,lieutron Flux S(7) R(6) H and S/U(1) 2,3,4

5, and g i

j 7. Overtemperature AT S R H 1, 2

8. Overpower AT S R H 1, 2 2

9. Pressurizer Pressure--Low S R H Ig p

10. Pressurizer Pressure--liigli S R H '1, 2

11. Pressurizer Water Level--llioli S R H Ig d.

I. A. Loss of Flow - Single Loop S, R H 1

D. Loss of Flow - Two Loops S R N.A. 1

] - -

N, lil!!! E . .-1 (Continued)

REACIOR 1111P SYSifil lilSTRUMENTATI0li SURVEILLANCE REQUIREllEllTS f5 CilANilEL H0 DES IN WillCil

~'

CilAllllEL CilANNEL FUNCTIONAL SURVEILLANCE fullCTIONAL UNil CilECK CALIBRATION lEST REQUIRED

13. Steam Generator llater Level-- S R H 1, 2 low-l.oW

14. Steam /Feedwater Flow llismatcli and S R H 1, 2 g

Low Steam Generator Wter Level

15. Undervolta0e - Reactor Coolant ll. A. R H 1 Pumps

16. Underfrequency - Reactor Coolant II. A. -

R H I Pumps

17. Turbine Trip ,

y A. Low Auto Stop 011 Pressure H.A. H.A. S/U(9)(1) H.A.

D. Turbine liirottle Valve Closure ti. A. H.A. S/U(9)(1) H.A.

18. Safety Injection input from ESF H.A. H.A. M(4) 1, 2

19. Reactor Coolant Pump ilreaker li. A. H.A. R 1 Position Irlp

20. Reactor Trip System Interlocks ll. A. R S/U(8) 1

21. Reactor Trip Breaker ll. A. N.A. M(5) and S/U(1) 1, 2, and

1

22. Automatic Trip Loulc H.A. N.A. M(5) 1, 2, and

I

TABLE 4.3-1 (Continued) b

(_ TABLE NOTATION With the reactor trip system breakers closed and the control rod drive system capable of rod withdrawal. .

(1) -

If not perfor=ed in previous 7 days.

- 4 (2) -

Heatr balance only,1bove 1E% of RATED THERMAL POWER. Adjust channel

. if absolute difference greater than 2 pe cent.

(3) -

Comoare incere to excore axial flux difference above 15% of RATED THERMAL POWER..

Recalibrate if the absolute difference greater than or equal to 3 percent.

(4).- Manual E5F functional inpt'. check every 18 months.

(5) -

Each train or logic channel shall be tested at least every 52 days on a STAGGERED TEST BASIS.

(6) -

Neutron detectors m'y abe excluded from CHANNEL CALIBRATION.

. (7) -

Below the P-6 (Block of Source Range Reactor Trip) setpoint.

(B) -

Logic only, if not perfor=ed in previous 92 days.

/- ,

_q- (9) -

CHANNEL FUNCTIONAL TEST will consist of verifying that each channel t

indicates a turbina trip prior to latching the turbine and indicates no turbine trip after latching the turbine.

(10) - If not perfor=ed i. the previous 31 days.

~

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Jb FARLEY-UNIT ,2' 3/4 3- 14

- I

I y TABLE 3.3-3 ,

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'y EllGillEERED SAFE 1Y TEATURE ACTUATI0ll SYSTEH INSiliUMENTATION E '

3

" 11IllIHUH N ft1NCTI0llAL Uti!T 10TAL 110.

OF CilAll!!El.S CilAllNELS 10 TRIP CllAllNELS OPERA!1LE APPLICABLE 1100ES ACTION

1. SAFE 1Y INJECTION, IURBINE TRIP AND FEEDWATER 150! ATION

, a. Manual Initiation 2 1 2 1, 2, 3, 4 18

' (

b. Autcmatic Actuation 2 1 2 ~1, 2, 3, 4 i 13 logic

c. Containment 3 2 2 1, 2, 3 A

14 w Pressure-fil0h N

, d. Pressurizer 3 2 2 1, 2i 3# 14" i

a, Pressure - Low

e. Differential 1, 2, 3##

Pressure Between Steam Lines - liigh A

Three Loops 3/ steam line 2/ steam line 2/ steam line 14 Operating twice and 1/3 steam lines Two Leops 3/ operating 2 ###/stea::: 2/operatin3 15

, Operating steam line line twice steam line in either-operatine i steam line s ~

- I l

2 TAlllE 3.3-3 (Continued)

EllGIllEERED SAFELY IEAlllRE ACTUATION SYSTEH INSTRUMENTATION

'a a '

5

~' HINIHUH y tuNCTIONAL UNIT 10TAL 110.

OF CilAN!!El.S CilANNEL'S TO 1 RIP CilANNELS OPERA 31E APPLICABLE H0 DES ACTION

f. Steam Lina Pressure-Low 1, 2, 3 Tlirce Loops 1 pressure / 1 pressure 1 pressure A

14 Operating ,

loop any 2 loops any 2 loops -

1 Two Loops 1 pressure / l### pressure 1 pressure Operating 15 loop in any oper- any operating sting loop loop

2. CONTAINHENT SPRAY -

i io a. Hanual 2 1 2 1, 2, 3, 4 I P, h , '

b. Automatic Actuation, 2 1 2 1, 2, 3, 4 13 ca Logic

c. Containment Prc.ssure-- 4 . 2 3 1, 2, 3 16 liigli-liigli-liigli e

-- ~ -

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lAlllE 3,3-3 (Centinucci)

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[NGINEERED SAFE 1Y ffATURE ACTUATION SYSTEH INSTRUMENTATION 5 .

b M HINIHUM '

TOTAL NO. CllANNELS CllANNELS APPLICABLE u FUNCil0NAl. UNIT OF CllAllllELS TO TRIP OPERABLE H0 DES ACTION

3. CONIAlllHENT ISOLATION

a. Phase "A" Isolation

1) Hanual 2 1 2 1, 2, 3, 4 18 t 2) From Safety Inject.lon 2 1 2 1, 2, 3, 4 13

' Automatic Actuation Logic

b. Phase "II" Isolation y 1) Hanual 2 1 2 1, 2, 3, 4 18

2) Automatic 2 1 2 1, 2, 1, 4 y . Actuation Logic 13

3) Containnent Pressure 4 2 3 1, 2, 3 16 liigh-liigli-liigh 2

c. PurDe anal Exhaust Isolation

1) Hanual 2 1 2 1,2,3,4 17

2) Actomatic 2 1 2 1, 2, 3, 4 17

Actuallon Logic s

9

s, . ."

l I Alll E . 3-3 (Continue:1) h I'llGillEEllED SAFEIY IEAIURE AClUATION SYS1[H lil5TRUMENTAlloti E HINIMUH M 10iAL 110. CilANilELS CliANNELS APPLICABLE

< FullCTI0llAL UlllT Of CilAllllELS 10 TRIP OPEllAllLE H0 DES ACTION P

4. 51EAM LlHE ISot ATI0li j a. Manual I/ steam line 1/ steam line 1/ operating 1, [3# 22 -

steam line

b. Automatic 2 1 2 1, 2hN 21 Actuallon Logic

. c. Containment Pressure-- 3 2 3 1, MN 14 1

liigh-liigli to d. Steam Flow in Iwo 1, MN ~

h Steam Lines--Iligli to A g"!. Ihree loops 2/ steam line 1/ steam Ilpe 1/ steam line 14 Operating any 2 steam lines lwo Loops 2/ operating l ###/any 1/ operating 15 Operating steam line operating steam line steam line ColNCIDENI Willt -

l avg --L w-Low 1, 2N9 Three loops 1T avy I op 1 T,yg any 1T avg any 14* ,

Operating 2 loops 2 loops two loops 1Tavg/oper- 1 T,yg i T3,g in any 15 Opciating ating loop in'any oper- operal.ing loop l ating loup I -

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=

W i.A. m l C I C.

i a-= 0 C O m3 O 6 o= a= =

i = 3 a === c r W m .J Q4==.J m

O C .J C !

G U% % 2 O k %U C U C =a 8 C. 4 C. 3 C. = 4 f

-e so - u-

. a < ao

.e -J e>

- e ova ,

t J

.a m eJ-l W

s m

=

na a i. =.

me:

! = .2 W os a

=a o We a m =

l mW =< m :m =

l a -2 e me t

=W C e OW

- a nw a

>==

U

.- =

3 .

W e .

l i

FARLEY-UNIT K 1 3/4 3-20 1

I I . I IAlli E .. -3 (Continued)

[NGillEERED SAFELY FEATURE ACTUATION SYSTEH INSTRUMENTATION

-4 .

HINIMUM Te TOTAL N0. CilANNELS CllANNE'LS APPL! CABLE p FUNCTiullAL UNIT OF CllANilELS TO TRIP OPERABLE H0 DES ACTION i

6. AUXILIARY FEEDWAlER

a. Automatic Actuation ,

, Logic 2 1 2 1, 2, 3 21

b. Sim. Gen. Water Level-Low-Low '

l. Start Hotor R

a Driven Pumps 3/stm. gen. 2/sta. gen. 2/stm. gen. 1, 2, 3 14 .

[ any sta gen.

b '

11. Start Turbine- a Driven Pumps 3/stm. gen. 2/stm. gen. 2/stm. gen 1, 2, 3 14

any 2 sim. Gen.

c. Undervoltage-RCP Start Turbine-Driven Pump 3-2/ bus 2 2 1 14

d. S. I.

Start Hotor-Driven Pumps See I above (all S.I. Initiating functions and requirements) ,

i e. Trip of Hain Feedwater Pumps '

Start Hotor- a Driven Pumps 2/ pump 1/pune 1/ pump 1 23 4 *

( , ! ,-

TABIE a.2-3 (Continued)

n

$ ENGillEERED SAFETY FEAluRE ACTUATION SYSTEH INSTRUMENTATION I

Q, E . HINIHt#1 U TOTAL NO. CllANNELS CllANNELS APPLIrAHlf FUNCTIONAL UNIT OF CllANNELS TO TRIP OPERABLE H0 DES ACTION

7. LOSS OF POWER -

a. 4 kv Bus 3/Ilus 2/Dus 2/ Bus 1, 2, 3, 4 19" Loss of Voltage ,,

i

b. Grid Degraded Voltage 3/Dus 2/Dus 2/ Bus 1, 2, 3, 4 19"

8. ENGINEERED SAFETY FEATURE

, ACTUATION SYSTEH INTERLOCKS s

[ a. Pressurizer Pressure, 3 2 2 1, 2, 3 20 g, ,

P-ll

. . m

b. Low-Low T,yg, P-12 3 2 2 1, 2, 3 20

c. Steam Generator (See 5.a above)

Level, P-14

d. Reactor Trip, P-4 2 1 2 1, 2, 3 13 l

1

TABLE 3.3-3 (Continued)

TABLE NOTATION s

Trip function may be Lypa: sed in this MODE below the P-11.

(Pressurizer Pressure Block of Safety Injection) setpoint.

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

(Tavg B1 ck of Safety Injection) setpoint. -

The channel (s) associated with the protective functions derived fr m the cut of service Reactor Coolant Loop shall be placed in the tripped code.

"The provisions of Specification 3.0.4 are not applicable.

N lj ihmd* Sht&m bd:h Valb40KL M. ,

' ACTION STATEMENTS ACTION 13 - Wi(tn Ine numCf&TA6LE re we,= eat OPERABLE channels one less th.O the Jeee4 %n,* mum Nummes e( Channel be in HOT STAND 8Y 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, ene 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 is OPERABLE.

ACTION 14 - With the number of OPERABi.' , V inels one less than the Total Number of Channels, opera cien may proceed until performance

[. of the next required CHANhEL FUNCTIONAL TEST provided the 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 .

ACTION 15 - With a channel asscciated with an coerating locp incperable, 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 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 at least HOT SHUTDCWN within the fo11cwing 5 hcurs; hcwever, one channel associated with an cperating loep 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 16 - With the number of OPEFABLE channels one less than the Tocal Nu ber of Channels, cperation may preceed previded the incperable channel is Channels placea inrequirement OPERABLE the bypassed condition is h ..m. . .. c.and f the

' i Minimu

gp; cne additional 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.

ACTION 17 - With less than the Minimum Channels OPERABLE, cperation may continue provided the containment purge and exhaust valves are maintained closed.

MsgA6tE rep'rsweuf ACTION 18 - With the number ofi OPERABLE Channels one less than the 7eee+ Minim.w h Channelslf restore the inoperable channel to GPERABLE status within t.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 and in COLD SHUTDCWN within the folicwing 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

FARLEY-UNITl'1, 3/4 3-23

! l 1

( , ,

TABLE 3.3-3 (Continued)

ACTION 19 - With the nu=ber of OPERAELE Channels one less than the Total Number of Channels, STARTUP and/or POWER OPERATION may proceed l provided the following conditions are satisfied: ,

a. The insperable 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 .

b. The Mininum Channels OPERABLE requirements is cet; however,

-t%e. inp6/c emeeddo44ene4 channel cay be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing3per Specification 4.3.2.1.

- erksther chauels ACTION 20 - With the interlock incperable to the extent that a safeguards function which should act be blocked in the cur ent MODE is blocked, declare the safeguard function (s) inoperable and folicw,

th'e' appropriate ACTION state =ent(s) of Table 3.3-3 for the :

af-fected " unction (s).

Interlock Affected Channels on Table 3.3-3

1. P-4 a. Pressurizer Pressure - Lew

2. P-12 a. Steam Line Pressure - Low

b. Steam Flow in Two Steam Lines High

!, Coincident With 7 '9-Lew-Lcw (OPE %46l2 re6vWeweori d ACTION 21 '- With the nh. - -- dO t

N Channelsk, PERABLE be in at Channels one less within least HOT STANDEY than the hed Ml,,;%

S hours and in at least HOT SHUTDCWN within the follcwing S hours; however; ene channal may be bypassed ter up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing previ o.d the etner channel is CPERAELE.

ACTION 22 - With the number of OPERAELE Channels one less than the Total Number of Channels restore the inoperable channel to OPERAELE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in at least HOT STANO3Y within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDCVN within the folicwing S hours.

ACTION 23 - With the number of'0PERAELE channels one less than the Mini =um Number of Channels, cperation may proceed uncil performance of the next required CHANNEL FUNCTICNAL TEST.

FARLEY-UNITI'L 3/4 3-24

(

tE4.3-h b EllGIllEERED 5AFE1Y FEATURE ACTUATION SYSTEH INSTRUMENTATION SUltVEIIIAHUE RE00THmEHTS

- E CllANNEL 4 H0 DES IN WillCil .

CllAllllEL CllANNEL FUNCTIONAL SllilVEI' LANCE

4 FUNCTIONAL UNIT CllECK CALIBRATION TEST IIEQUIRED 1 SAFE 1Y INJECTION, luRilINE TRIP AND FEEDWATER ISOLATION

a. Manual Initiation N.A. H.A. N(1) '1,'2, 3, 4 ,

I

b. Automatic Actuation Logic , H.A. N.A. H(2) 1, 2, 3, 4

c. Containment Pressure-liigli 5 R H 1, 2, 3 4 d. Pressurizer Pressure--Low S - R H 1, 2, 3 w

h e. Differential Pressure S R H 1, 2, 3 '

w fictween Steam Lines--liigli '

f. Steata Line Pressure--Lov 5 11 H 1, 2, 3

2. CONTAINMENT SPRAY '

a. Manual Initiation " A. N.A. H(1) I, 2, 3, 4

b. Automatic Actuation Logic H.A.

N.A. H(2) 1, 2,'3, 4

. c. Containment Pressure-- S . R H 1, 2, 3 liigh-liigh-lligli '

6 l -

i .

l

7 'D( ,7

TAllLE ,.3-2 (Continuell}

E EllGIllEEREil SAFETY FEATURE AClUATION SYSTEM INSlflUMENTATI0li

[n sillWFl[l'ANCE Il@llillFilEH1S i E CilANNEL H0 DES IN WillCll

U CilAllNLL CilANNEL FUNCTIONAL SURVEILLANCE x IUNCTIONAl UNIT CllECK CALIBRATION lEST REQUIRED

3. CONTAINMENT ISOLATION

a. Phase "A" Isolation f

1) Hanual N.A. N.A. H(1) 1, 2, 3, 4

2) From Safety injection N.A. H.A. M(2) 1, 2, 3, 4 Automatic Actuation logic Isolation

b. Phase "B" D _ 1) Hanual N.A. H.A. H(1) 1, 2, 3, 4

. w i J.

2) Automatic Actuallon N.A. N.A. H(2) 1, 2, 3, 4 Logic

3) Containment Pressure-- S R H 1, 2, 3 liigh-liigh-liigh 9

c. Purge anit Exhaust Isolation

1) Hanual N.A. N.A. H(1)~ 1, 2, 3, 4

2) Automatic Actuation Logic N.A. N.A. H(2) 1, 2, 3, 4 i

I 1 Alli.E ..J-2 (Continued)

A EllGINEERED SAFETY FEA10RE ACTUATION SYSlEH INSTRUMENTATION

SillNEIEEANCE REQUTHDIENT5 E CllANNEL H0 DES IN Wil!Cil -

To CllANNEL CllANNEL , FUNCTIONAL SURVEILLANCE p FUNCTIONAL. UNIT CllECK CALIBRA110N TEST REQUIRED i 4. SIEAM LINE ISOLATION

! a. Manual ll. A. N.A. H(1) 1,. 2, 3 1 .

I b. Automatic Actuation Logic N.A. N.A. M(2) 1, 2, '

c. Containment Pressure-- S R H 1, 2, 3 liigh-liigli ,

d. Steam Flow in Two Steam 5 - R H 1,2,3 w Lines--liigli Colucident with .

3 T av0 w .

h e. Steam Line Pressiere--Low S P. H 1, 2, 3

5. 1HRBINE TRIP AND FEEDWAIER ISOLATION

a. Steam Generator Water 5 R H 1, 2, 3 Level--liigh-liigli -

e

I I

y .

IABIE ..J-2 (Continued) .

EllGIllEERED SAFETY fEAIUllE ACTUATION SYSTEll IliSTRUMENTATION Q IURVEILTAIRE REQUIREIEHIS

-8 CllANNEL MODES IN WillCil CllANNEL CilANNEL FUNCTIONAL SURVEllLANCE 7 FUNCTIONAL UNIT CllECK CALIBRATION TEST REQUIRED f 6.

AUXILIARY FEEDWATER j a. Automatic Actuation Logic H.A.

1 ,

N.A. H(2)(6) 1, 2, 3

b. Steam Generator Water S R 14 1, 2, 3 Level--Low-Low

c. Undervoltage - RCP XNJ. R H

, 1

d. S.I. See 1 above (all Si surveillance requirements) 4' Trip of Hain Feedwater

~

, [ e. H. A. N.A. S/U(5) I a

Pumps,

7. LOSS OF POWER I

a. 4.16 kv Emergency Ilus N.A. R(3) H(4) 1, 2, 3, 4 i Undervoltage (Loss of Voltage) ,

b. 4.16 kv Emergency Bus N.A. . R(3) M(4), 1, 2, 3, 4 Undervoltage (Degraded Voltage)

8. ENGINEERED SAFETY FEA1URE li. A. N.A. R H.A.

ACTUAI10N SYSlEH IlllEllLOCKS to d

I

TABLE 4.3-2 (Continued)

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

(3) Channel calibration shall exclude actuation of the final trip actuatica relcy."

(4) Functio'nal 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.

(h EX pumps. GUY 00"% l0 CEC.har L +'IP cf m'I" M

( '

, ,\ .

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

FARLEY-UNIT 1 1. 3/4 3-37

, - - - . .,n- - - - --, .v. - - - - - - ,

INSTRUMENTATION R_ EMOTE SHUTDOWN INSTRUMENTATION LIMITING CONDITION FOR OPERATION

's. 3. 3. 5 The remote shutdown monitoring instrumentat:en channels shown in Table 3.3-9 shall be OPERABLE with readouts displayed external to the control roon. ,

APPLICABILITY: MODES 1, 2 and 3.

ACTION:

a. With the number of OPERABLE remote shutdown monitoring channels less than required by Table 3.3-9, restore the inoperable channel to OPERABLEstatuswithin/daysorbeinHOTSHUTDOWNwithinthenext 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . 3l

b. The provisions of Specification 3.0.4 are not applicable. l l

SURVEILLANCE REOUIREMENTS 4.3.3.5 Each remote shutdown monitoring instrumentation channel shall be '

demonstrated OPERABLE by performance of the CHANNEL CHECX and CHANNEL

_ CALIBRATION cperations at the frequencies shewn in Table 4.3-6.

I l

FARLEY-UNIT 1 1 3/4 3-49

- -+ ,- -,-v c.,,w.,-.w, ,,- ,.v-,,. - ,- . = , wg ---,--.,,--c. .--, - - - ,c ---w -r ----,--- --- - w + - - - .e---.

O '

TABLE 3.3 f _

Q 5

g ACCIDENT MONITORING INSTRUMENTATION Q,

E REQUIRED MINIMUM Z NUMBER CHANNELS S( INSTRUMENT OF CHANNELS OPERABLE w

1. Reactor Coolant Outlet Temperature-THot-Wide Range 2 1 l 2. Reactor Coolant Inlet Temperature-T Cold -Wide Range 2 1 i

3. Reactor Coolant Pressure-Wide Range 2 1

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

5. Hefueling Water Storage Tank Water Level 2 1

6. Containment Pressure 2 1

$ 7. Pressurizer Water Level 2 1

8. Steam Line Pressure 2/ steam generator 1/ steam generator

9. Auxiliary Feedwater Flow Rate 2 1

10. Reactor Coolant System Subcooling Margin Monitor 2 1

11. PORV Position Indicator 1/ valve 1/ valve

- 12. PORV Block Valve Position Indicator 1/ valve 1/ valve

13. Safe Valve Position Indicatofovi(One c6mel is pos$on / valve 1/ valve id % and one clonwnel s's o6'se A n e '

l 'i. . . . . .-. . . . _ : ; - L1;c '. " ~m E p _f e. f4mpniw'e ) _l

- -1

f .- '? "__. .. ... Z.e . m.. ' .1 "_ m 1

lk)df. Incore Thermocouples 4/ core quadrant 2/ core quadrant

^Not applicable if the asso#,ated block valve is in the closed position.

! **Not applicable if the block valve is verified in the closed position and power removed, b

REACTOR COOLANT SYSTEM i

3/4.4.5 RELIEF VALVES 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:

a. 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 OPFrJ3LE <tatus or close the associated block valve (s) and remove power *:cm 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 .

b. With one or more block valve (s) inoperable, within : hour either restore the block valve (s) to OPERABLE status or close 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 .

c- c. The provisions of Specification 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.4.5.1 Each PORV shall be demonstrated OPERABLE at least once per 18 months by performance of a CHANNEL CALIBRATION and operating the valve through one

~

cycle of full travel.

durin eneu ca.o suwn l 4.4.5.2 Each block valve shall be demonstrated OPERABLEp .._ _

f* '-- ^ ?

92 days by operating the valve through one complete cycle of full travel /

vhle.ss %e. %\cek valve. is closU evi% 'ffe (bwer Vfn10Ved in er$2r

% meekk ACYIvA) reguvemen+s of a, above.

FARLEY-UNIT /I 3/4 4-8 e - --&-w eas y r. 9 y %

97.., .v.s.m ..

9ygy- .- y, y p a ,-g.9 4 y ,m m. g.,+.- e.- ye ,.9 - y.-a p - , w y

( CONTAINMENT SYSTEMS CONTAINMENT STRUCTURAL INTEGRiT_Y_

LIMITING CONDITIONS FOR OPERATION 3.6.1.6 The structural integrity of ne containment shall be maintained at a level consistent with the acceptwice criteria in Specification 4.6.1.6.

APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

dith the ;tructural integrity of the containment not conforming to the above requiremests, restore the structural integrity to within the limits 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 mt 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and j

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

r SURVEILLANCE REQUIREMENTS _

i '

4.6.1.6.1 Containment Tendons. The containment tendons' structural

?(

u_

integrity shall be oemonstrated at the end of one, three and five years following the initial containment structural integrity test end at five year intervals thereafter. The tendons' structural integrity shall be i

demonstrated Sy:

a. Determining that a representative sample of at least 21 tendons (6 dome, 5 vertical, and 10 hoop) each have a lift off force within the acceptance limits, defined as not less than the allowable lower bound force nor greater than the allowable I upper bound force per wire at the time of the test as shown in Figuce 4.6-1. This test shall include an unloading cycle in which coch of these tendons is detensioned to determine if any l wires or strands are broken or damaged. If the lift off force of any one tendon in the total sample population is out of the allowable bounds (less that, minimum or greater than maximum),

an adjacent terdon on each side of the defective tendon shall also be checked for lif t off force. If both of these tendons are found acceptable, the surveillance prograt my proceed considering the single deficiency as unique and acceptable.

More than one defecti*.c tendon out of the original sample population is evidtnce of abnormal degradation of the contain-ment struc ture. Unless there is evidence of abnormal degrada-tion of the containment sts M tire during the first three tests of the tendons, the number of tendons checked for lift off force du-ing subsequent tests may be reduced to a representative

{- sample of at least 9 tendons (3 dome, 3 vertical and 3 hoop).

FARLEY - UNIT 1 3/4 6f

==_ = - --- .- - - - -

-l

. . . _ _ _ _ . . . ~ . _ _ _ _ _ . _ ._ _ _ , _ . . .__ _ _.

(7

[CO.'iTAI.'i"E'iT SYSTEtiS SURVEILLMCE P.EQUIREMENTS (Continued)

b. Removing one wire from each of a dome, vertical and hoop tendon checked for lift off force and determining that:

1. The corrosion level over the entire length of the tendon

~

wires has not progressed since the original installation or the previous surveillance.

2. There are no changes in physical appearance of the sheathing filler material.

g 3. A ninimum tensile strength of 240,000 pounds for at least three wire sampics (one from each end and one at i(

h mid-length) cut from each removed wire. Failure of any

// one of the wire samples to meet the minimum tensile bt strength test is evidence of abnormal degradation of the <

containment structure. ,

4.6.1.6.2 End Anchorages and Adjacent Concrete Surfaces The structural integrity of the end anchorages and adjacent concrete surfaces shall be deacr.strated by determining through inspection that no adverse changes have occurred in the visual appearance of the end anchorage concrete cxterior surfaces or the concrete crack patterns adjacent to the end anchcrages. Inspections of the concrete shall be performed during the first Type A containment leakage rate tests only (reference Specification 1.6.1.2) while the containment is at its maximum test pressure.

4.6.1.6.3 ~ Liner Plate The structural integrity of the containment liner piete shall be determined during the shutdown for the first Type A contain. ment leakage rate test only (reference Specification 4.6.1.2) by a visual inspection of the plate and verifying no adve.we. changes in appearance or other abnormal degradation.

?.6.1.6.4 Re: orts _ An initial report of any abnormal degradation of the contain ent structure detected during the above required tests and inspecticns shall be made within 10 days after completion of the sur-veillance recuirements of this specification and the detailed report shall be subnitted pursuant to Specification 6.9.1 within 90 days after completion.

IEE' EV - l";IT_1 'UA - -

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*^

.*"~' % -. MC

'" w li:= *

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$ g *:!* '- W :.1. :-l: 1.,9 $ Ty1l g ,.

w m -

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p g .- - ) p. t g qf g,

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~.nH1 I E:i;2 uimpsprmmruww -* 21. ----- .,

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$M 01 OS n- - - - - + - : , ,

o . Wp~- ~ [ T T.ipTT 1 S 10 20 40 TIME AFTER INITIAL TENSION # 4G (YEARS)

HOOP AND DOME TENDONS

~

( "

(- ( ( (ii yt u m i:tt

re. -

.=

-...._..._i

= t.::: : .c n -:

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.. =_ctra-= ;r.:-1 f sj:.i'.;^ : _..

b

, -. ... := ~ t "~'* - ~. 4

A 1 ,. -,. &[.= - L # 44kh-kwe y

_- 9 j.wu - . ..a..

.--+-*--

x.

$ W u.T '

~-~~t s & ! s. _.

w ::IT O un ";;i.iM#t MGWr3 t L .di E

3:

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%cN:% nn:n_

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.4 _. ----as &L _. -~.in 3

tn -......__ ___c=-_ ._i ,

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r, . mar.t::, c. _ . - n= , j in ::h ; ,1- ,

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M :c---- tn .tstofiTn--@4EE t.ittr: . __.._...

.!: =...,... t i nn.

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o un -~-

..i m . . . .=.=tnr. .i 2.t" 01 OS 1 S 10 20 40 TIME FTER INITIAL TENSIONING (YEARS)

VERTICAL TENDONS FIGURE 4.6-1 ACCEPTANCE LIMITS TENDON WIRE LIFT-OFF FORCE VERSUS TIME JOSEPH M. FARLEY NUCLEAR PLAhT TECHNICAL SPECIFICATION UNIT NO. 1 SHEET 1 FARLEY - UNIT 1 3/4 6-9a,

BASES OF LOAD VERSUS TIME CURVES .,

{

INITIAL LOCK-OFF FOR TENDO;d STRESSES CAN RANGE FROM .70 to .73 fs

(*a* IN THE FORMULA BELOW),OR s.25 KIPS I WIRE TO 8.60 KIPS / WIRE, CAllBRATION OF THE STRESSING DEVICE IS 82% TRACEABLE TO A NATIONAL STANDARD. ACTUAL WIRE FORCES ARE ACCURATE TO 22%, HOWEVER,lF DiFFERENT DEVICES OR THE SAME DEVICE CAllBRATED BETWEEN TWO SURVEILLANCE PERIODS ARE USED ON THE SAME TENDON IN TWO SURVEIL-LANCES.THERE WOULD BE A POSSIBLE 4% SPRE AD BETWEEN READtNGS

- OF THE SAME TENFCN LOAD. THUS.THE BAND FOR LOAD READINGS IS INCREASED T0 84% ("K 'IN THE FORMULA BELOW ).

AN AVERAGE ELASTIC SHORTENING LOSS (*e*lN THE FORMULA BELOW)MUST BE DEDUCTED FROM THE INITIAL FORCE PER WIRE DUE TO SEQUENTIAL STRESSING OF THE TENDONS.

THE COMBINATION OF LOSSES DUE TO CREEP AND SHRINKAGE OF THE CON.

CRETE, AND STEEL RELAXATION VARIES DUE TO THE RANGES OF THE VARIA-BLES SHOWNIN THE TABLE BELOW.

THUS.THE GENERAL EXPRESSION FOR THE FORCE PER WIRE CAN BE GIVEN AS.

AT INITI AL INSTALL ATION, fw, = (a fs' x K* e) Aw CONCRETE SP.RINKAGE CONCRETE CREEP 1 eSTEEL RELAX ATION AT FORTY YEARS, fwg e twi. Aw [(Itex Esx#c/sg) + (Es m Es) * (rx fs)]

WHERE fs a TENSILE CAPACITY OF TENDON WIRE = 240 ksi eq e CONCRETE STRAIN DUE TO CREEP

c,vc = MAXIMUM CONCRETE STRESS FOR THAT GENERAL AREA iMAXI.

MUM ALLOWABLE CONCRETE STRESS Es a CONCRETE STRAIN DUE TO SHRINKAGE r

PERCENT OFINITIAL PRESTRESS (fs) LOST AT A CONSTANT SUSTAINED STRAIN Awe WIRE AREA. 04909 SO IN Ese MODULUS OF ELASTICITY OF THE WIRE xio! ksi tu ** * ~

di u tr fm i LPPER LO GPPERI.fWEN PPERD/KRLEYERLDER enlFPER DW%

FOUPOEO.ROEOutO EOUPO BOI.tO3JuroEctt0EOUPO BOutoBCV Q

.73 .70 1 04 .96 4 97 317 410 28 9 29 0 100 17 0 80 8.5 14 65 N

.73 .70 104 .96 2 68 317 410 28 9 29 0 54 170 &O 85 14 64

, FEN 5 NOTE . THE 40 YEAR DESIGN PRESTRESS REQUIREMENTS FOR THE HOOP, DOME,

- AND VERTICAL TENDONS ARE 6 01.635 AND 6.81 keps PER WIRE RESPEC-TiVELY. THE PREDICTED LOWER LIMIT ON THE GRAPH AT OR NEAR A TIME OF 40 YEARS FALLS BELOW THE DESIGN REQUIREMENT FOR THE DON'E AND VERTICAL TENDONS THIS IS ACCEPTABLE SINCE THE DEVIATION IS WITHIN THE 8 4% LOAD READING ACCURACY.

4 FIGURE 4.6-1 ACCEPTANCE LIMITS TENDON k' IRE LIFT-OFF FORCE VERSUS TIME JOSEPH M. FARLEY NL' CLEAR PLANT TECHNICAL SPECIFICATION qg UNIT NO. 1 SHEET 2

-FARLEY - UNIT 1 3/4 6-Mf

( CONTAINMENTST!TEff CONTAINMENT VENTIL\ TION SYSTEM LIMITING CONDITION FOR OPERATION 3.6.1.7 The 48-inch containment purge supply and exhaust isolation valves (CSV-HV-3198A,3198D,3196,3197) shall be closed. The 18-inch containment purge supply and exhaust isolation val'ves may be open.

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

ACTION:

With one 48-inch containment purge supply and/or one exhaus', isolation valve o;5en, close the open valve (s) within one hour or be in at ', east 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 .

'j SURVEILLANCE REOUIREMENTS

\_

4. 6.1. 7.1 The .tE-inch ccntainment purge sucaly and exhaust isclation valves snail te cetermined closed at least cnce per Il days.

4. 6.1. 7. '2 The valve seals of the 48-inch and the 18-inch purge supply and exhaust isolation valves shall be replaced at least once per 5 years.

FARLEY-UNITk1_ 3/4 6-10

CONTAINMENT SYSTEMS f

(

SURVEILLANCE REOUIREMENTS (Continued) 4.6.3.2 Each isolation valve specified in Table 3.6-1 shall be demonstrated OPERABLE during the COLD SHUTDCWN or REFUELING MODE at least once per 18 months by:

a. Verifying that on a Phase A containment isolation test signal, each Phase A isolation valve actuates to its isolation position.

. b. Verifying that on a Phase B containment isolation test signal, each Phase B isolation valve actuates to its isolation position.

4.'6.3.3 The isolation time of each power operated or automatic valve of Table 3.6-1 shall be determined to be within its limit when tested pursuant to Specification 4.0.5.

4.6.3.4 The containment purge isolation valves shall be demonstrated OPERABLE i prior to startup after each COLD SHUTDOWN if not performed in the previous 3 months by verifying that when the measured leakage rate is added to the leakage rates determined pursuant to Specification 4.6.1.2.d for all other Type 3 and C penetrations, the combined leakage rate is less than or equal to 0.60L .

In addition, the leakage rate for the containment purge isolation valvesashall

be co= pared to the previously measured leakage rate (for the containment purge

, . .{ isolation valves) to detect excess valve degradation.

An engineering evaluation shall be performed to determine what corrective sc:icn, if any, is necessary.

l 1 -

t FARLEY-UNIThTL 3/4 6-15

~

s.

\ PLANT SYSTEMS MAIN STEAM LINE ISOLATION VALVES LIMITING CONDITION FOR OPERATION

3. 7.1. 5 Each main steam line isolation valve shall be OPERABLE.

APPLICABILITY: MODES 1, 2 and 3.

ACTION:

MODE 1 - With one main steam line isola?.fon valve inoperable, POWER OPERATION may continue provided the inoperable valve is seeker restored to OPERABLE status ammtened within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; otherwise, emmesmeAr reduce, W';i'- -

RATED 7%5ietspfl. power u>l%'n to less +kan or egas/ +o 5% of PowCK & hweL ,

MODES 2 - With one main steam line isolation valve inoperable, subsequent and 3 operation in MODES 4 2 or 3 raay proceed provided the isolation

{ valve ist:f-t:' :f :':::d; 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.

C_ redoed -h o@?ABLE siafus or closel wiK* nA koves a4+ct edering MbOE '2.

SURVEILLANCE REQUIREMENTS

4. 7.1. 5 Each main steam line isolation valve shall be demonstrated OPERABLE by verifying full closure within 5 seconds when tested pursuant to Specification

_ 4.0.5.

FARLEY-UNIT / 3/4 7-9

~

PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

b. Vist.1 Inspection Acceptance Criteria Visual inspections shall verify (1) that there are no visible indica-tions of damage or impaired OPERABILITY, (2) attachments to the foundation or supporting structure are secure, and (3) in those locations where snobber movement can be manually induced without disconnecting the snubber, that the snubber has freedom of movement and is not frozen up. Snubbers which appear inoperable as a result of visual inspections may 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 determined 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 determined OPERABLE via functional testing for the purpose of establishing the next visual inspection internal. All snubbers connected to an inoperable common hydraulic fluid reservoir shall be counted as inoperable snubbers.

c. Functional Tests At e .,t onc er 18p ont'is dy in h ow . repr tati ample of of et a'A f ea 4ype of ubber use he p t s 11 unctio ly tes eithe i 1 o i b c es.

yngCfp ac ance ' eriasno M pecifi ea pe ' Wc d s not M Ge un d o 1W 1on 4 . d or . 9.e a ad av

' W 1*o that/. e of iu er al e nct). ly t _d un ' r no o e ailure de fo d r unt 1 all sn ers hav een f tiona' y tested.

The representative sample selected for functional testing shall l include the various configurations, operating environments and the i rance of size and capacity of snubbers. At least 25% of the snubbers 63.id{ Mn thefrepresentative sample shall include snubbers from the following l thre2 categories:

1. The first snubber away from each react.or vessel nozzle

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

l

3. Snubbers within ten feet of the discharge from a safety relief valve

/

FARLEY-UNITg 3/4 7-21 ,

Insert to 4.7.9.c At least once per 18 months during shutdown, a representative sarple of 88 snubbers shall be functionally tested either in place or in a bench test. If more than 3 snubbers do not meet the functional 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 functionally 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 re-sample, until no additional inoperable snubbers are found within a sample or until all snubbers in Tables 3.7-4a and 3.7-4b have been functionally tested.

Snubbers greater than 50,000 lb. capacity may be excluded from functional testing requirements, t

/

___ , _ _ . _ _ . , . .. ._ . ~ **f C. _ _ j_ _

PLANT SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

e. Mechanical Snubbers Functional Test Acceptance Criteria #

o e The mechanical snubber 3functional test shalfnahber verify that:-

1. The force that initiates free movement of the snubber rod in either tension or compression is lest t.han the specified maximum drag force. Drag force shall not have increased more than 50%

since the last functional test.

2. Activation (restraining action) is achieved within the specified range of velocity or acceleration in both tension and compression.

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 the snubber to withstand load without displacement shall be verified. .

- Tke. mechancat snvloher Gune&nal 'fest +ce snubbers rafe}

> less %. 35o peuwds skall verify tid :

1. T*ke snubher will sfroke over Hs -fullronfe. of

-haveI In loe % + e asts n and cosepression, L The. snuhber does ne+ egl,; fit irregular fravel orerhev ind:ca+ ions of iniernal meelanicoI in+erfereace.

M- tT U $ ()er 5'0" O %e speclGca+ Ion is eSSeel;ye pe;ar 4a S}qrhys rollow.,H3 'he rovttk rebel.'u9 ouinge or wisen a commert-laf in-place 3/4 7 23 FARLEY-UNIT /+Iis available., w teksvet es Ider.

(+es ,n y device.

1 1

PLANT SYSTEMS SPRAY AND/0R SPP.INKLER SYSTEiti LIMITING CONDITION FOR OPERATION

~

\

l i

3.7.11.2 The spray and/or aprinkler systems listed in table 3.7-5 shall be OPERABLE. ;

APPLICABILITY: Whenever equipment in the spray / sprinkler protected areas is required to be OPERABLE.

ACTION:

a. With one or more of the above required spray and/or sprinkler systems inoperable, within one hour establish a continuous fire watch with backup fire suppression equipment for those areas in which redundant

. systems or components could be damaged; for other areas, establish a hourly fire watch patrol. Restore the system to OPERABLE status ,

within 14 days or, in lieu of any other report required by Specifi-cation 6.9.1, prepare and submit a Special Report to the Commission pursuant to Spacification 6.9.2 within the next 30 days outlining the action taken, the cause of the inoperability and the plans and schedule for restoring the system to OPERABLE status.

__ b. The provisions of Specification 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4

l 4.7.11.2 Each of the above required spray and/ a sprinkler. systems shal be demonstrated OPERABLE: ,

~

a. At least once per 31 days by verifying that each valve (manual, l power operated or automatic).in the flow path in in its correct !

I position. >

l

b. At least once per 12 months by cycling each testable valve in the flow path through at least one complete cycle of full travel.

i i

i t

t a FARLEY-UNIT / 3/47-pi l

PLANT SYSTEMS CO SYSTEMS ;

2 _

7 LIMITING CONDITION FOR OPERATION 3.7.11.3 The following high pressure and low pressure2CO systems shall.be f A Amig OPERABLE.

. ~ . '.

.. '1/e:; if&$

Service Water Intake Structure (each 4160 volt bus.andfea

^

E . . m ~ -i w ;, m :c::

, 'a. h vi load center - HP. < c f .W ,

.n ; };p/ 'r* NV&YL; M' M

. . .l:.x

b. Turbine Building 13 ton unit and distrib'uiion system'in the'Auxilia'ry N [ '? U Building - L.P. . .jfs.c: N

. . . .'- _ ggy n

c. Diesel Building 5 ton unit hnd distribution system. ~ %. ( - N APPLICABILITY: Whenever equipment protected by the CO2 ystems s in required to Le OPERABLE.

ACTION: .

a.

WithoneormoreoftheaboverequiredC0@esystemsinoperable, within one hour establish a continuous f.i. watch with backup fir.e- _

suppression equipment for those areas in which redundant systems or components could be damaged; for other areas, establish an hourly fire watch patrol. Restore the system to OPERABLE status within 14 days or, lieu of any other report required by Specification 6.9.1, ,

prepare and submit a Special Report to the Commission pursuant to /

)_ Specification 6.9.2 within the next 30 : fays outlining the action (

taken, the cause of the inoperability aad the plans and schedule for restoring the system to OPERABLE status.

b. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 1@'

4.7.11.3.1 Each of the above required C0 systems 7 sila11 be demonstrated OPERADLE at least once per 31 days by verTfying that each man':41 valve in the flow path is in its correct position.

l 4.7.11.3.2 Each of the above required low pressure CO2 :,y:,cems shall be demonstrated OPERABLE:

a. At least once per 7 days by verifying the C09 storage tank level to be greater than 50% and pressure to be greater than 250 psig, and j b. At least once per 18 months by verifying:

1. The system valves and associated ventilation dampers and fire door release mechanisms actuate manually and autcmatically, upon receipt of a simulated actuation signal, and

2. Flow from each nozzle during a " Puff Test."

28 FARLEY-UNIT g b 3/4 7 ,W t

~ ~

l ._ . . . _ . _. _. _ , -- . . . . - -

l J ~ . - -

FLANT SYSTEMS 3/4.7.12 FIRE BARRIER PENETRATIONS j

LIMITING CONDITION FOR OPERATION .

~

h: .&

3.7.12 All fire barrier penetrations (including cable penetration barrier's, 0-I .M: J'y ' '

firedoors and fire dampers) in fire zone boundaries prctecting safety related' jdsy ;gT

d areas shall be functional.

.y.a;i.: 3;R.* f W',St

~ >%;:W L'-: .

, i APPLICABILITY: At all times. W: '

7 7 "; r.

ACTION: ? . I;.

T )'y'q

'~ '

.?

a. With one or more of the above required fire barrist: penetrations _',

non-functional, within one hour either, establish a coitinuous fire watch on at least one side of the affected penetration, or verify the OPERABILITY of fire detectors on at least one side of the non-functional fire barrier and establish a hourly fire watch patrol.

Restore the non-functional fire barrier penetration (s) to functional status within 7 days or, in lieu of any other report required by , -

Specification 6.9.1, prepare and submit a Special Report to the -'

Commission pursuant to Specification 6.9.2 within the next 30 days outlining the action taken, the cause of the non-functional penetration and plans and schedule for restoring the fire barrier penetration (s) to functional status. '

The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

b.

SURVEILLANCE REQUIREENTS 4.7.12 Each of the above required fire barrier penetrations snall be verified to be functional:

a. At least once per 18 months by a visual inspection.

b. Prior to returning a penetration fire barrier to functional status following repairs or maintenance by performance of a visual inspection of the affected penetration fire barrier (s).

1 r+

FARLEY-UNIT / 3/47-g

-+ - e e ,e ummyu -en y p g '- w m- e cp w y y v - , , -

l ,

3/4.8 ELECTRICAL POWER SYSTEMS .j 3/4.8.1 A.C. SOURCES .

OPERATING -

LIMITING CONDITION FOR OPERATION 3.8.1.1 As a minimum, the following A.C. electrical power sources shall be OPERABLE:

a. Two physically independent circuits between the offsite transmission network to the switchyard and two physically independent circuits from the switchyard to the onsite Class lE distribution system, and

b. Two separate and indep dent diesel generator sets (Set A: DG l-2A and DG-1C, Set B: DG and DG-2C) each with:

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 generator.

2. A separate fuel transfer pump for each diesel.

c. A fuel storage system consisting of four, independent storage tanks each containing a minimum of 25,000 gallons of fuel.*

g'

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

ACTION:

a. With an offsite circuit inoperable, demonstrate the OPERABILITY of the remaining A.C. sources by performing Surveillance Requirements 4.8.1.1.1.a and 4.8.1.1.2.a.4 within one hout and at least once per 8

- hours thereafter; restore at least two offsite circuits to OPERABLE l -status within 72 hoars or be in at least HOT STANDBY within the next -

l 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 .

! b. With one diesel generator set inoperable, demonstrate the operability of the remaining A.C. sources by performing Surveillance Requirements 4.8.1.1.1.a and 4.8.1.1.2.a.4 within one hour and at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter. Restore both diesel generator sets to OPERABLE -

status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or comply with the following:

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

l l

l l *0ne inoperable fuel storage tank is equivalent to one inoperable diesel i generator set.

J ..

1 .

FARLEY-UNITg 3/4 8-1

I .

i ELECTRICAL POWER SYSTEhd ACTION (Continued)

's.

2) One diesel generator set may be made inoperabie for up to 14 days to perform scheduled maintenance and testing on diesel generators IC (or 2C) provided all the following are satisfied:

a) Unit 1 is in MODE 5 or 6 and apprnpriate technical specifica-tions covering the diesel generator sets are satisfied.

b) The remaining Unit 2 diesel generators 1-2A, , 1C (or 2C) are OPERABLE.

c) The service water system is recirculated to the pond and surveillance requirement 4.7.6.2.1 is verified prior to removing 1C (or 2C) from service and once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter.

d) Diesel Generator 1C (or 2C) is returned to OPERABLE status as soon as maintenance is completed.

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 .

~

) c. With one offsite circuit and one diesel generator set of the above required A.C.' electrical power sources inoperable, demonstrate the (

OPERABILITY of the remaining A.C. sources by performing Surveillance '

Requirements 4.8.1.1.1.a and 4.8.1.1.2.a.4 within one hour and at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter; restore at least one of the inoperable sources tc OPERABLE status within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months or be in at least HOT STANDBY within the next 6 hcurs and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months . Restore at least two offsite

_ circuits and both diesel generator sets to OPERABLE status within ,

72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months from the 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 SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

d. With two of the above required offsite A.C. circuits inoperable, demonstrate the OPERABILITY of both diesel generator. sets by l performing Surveillance Requirement 4.8.1.1.2.a.4 within one hour I

and at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter, unless the diesel generators are already operating; restore at least one of 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 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 i

l offsite source restored, restore both offsite circuits to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months from time of initial loss or be in at least liOT 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 .

j-t l

FARLEY-UNIT / 3/4 8-2 l

ELECTRICAL POWER SYSTEMS

-d ACTION: (Continued)

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

~

performing Surveillance Requirement 4.8.1.1.1.a within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months thereafter; restore at least one of the ,

inoperable diesel generator sets to OPERABLE 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 ST7.NDBY 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 . Restore both diesel ,

generator sets to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months from time of initial loss or be in 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 .

SURVEILLANCE REQUIREMENTS 4.3.1.1.1 Each of the above inde, c endent circuits cetween the effsite transmission network and the onsite Class IE distribution system shall be:

a. Determined CPERASLE at least once per 7 days by verifying correct breaker alignments, indicated pcwer availability, anc

- b. Demcnstrated 0?E?a3LE at least once per 18 m:nths dcr'n; shut-down by transferring unit power supply frca the narril circuit to the alternate circuit.

4.8.1.1.2 Each diesel generator set shall be demonstrated C?E?.AELE:

a. At least once per 31 days, on a STAGGERED TE3T BASIS, by: i l

1. Verifying the fuel levei in the day tank, i

2. Verifying the fuel level in the fuel storage tanks, FARLEy UNJTL I!'r S'~ 2 A

___ _ ~ . _ . _ . _ - - _- -

ELECTRICAL POWER SYSTEMS 3/4.8.2 ONSITE POWER DISTRIBUTION SYSTEMS A.C. DISTRIBUTION - OPERATING LIMITING CONDITION FOR OPERATION 3.8.2.1 The following A.C. electrical busses shall be OPERABLE, energized

,and aligned to an OPERABLE diesel generator:

4160 volt Emergency Bus F, H and K 4160 volt Emergency Bus G, J and L 600 volt Load Centers D, H, K and R 60J volt Load Centers E, J, L and S

('

sqe 120 volt A.C. Vital Bus A 120 volt A.C. Vital Bus B 120 volt A.C. Vital Bus C 120 volt A.C. Vital Bus D APPLICABILITY: MODES 1, 2, 3 and 4.

ACTION:

With less than the above complement of A.C. busses OPERABLE, restore .the inoperable bus to OPERABLE status 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 and in COLD SHUTDOWN within the folicw-ing 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

~

SURVEILLANCE REQUIREMENTS 4

4.8.2.1 The specified A.C. busses shall be determined OPERABLE and energized at least once per 7 days by verifying correct breaker alignment and indicated power availability.

b FARLEY-UNIT 1 3/48-gf

7:

' ELECTRICAL POWER SYSTEMS ,

A.C. DISTRIBUTION - SHUTDOWN .

-- LIMITING CONDITION FOR OPERATION 3.8.2.2 As a minimum, the following train oriented A.C. electrical busses shall be OPERABLE and aligned to an OPERABLE diesel generator.

3 - 4160 volt Emergency Bus

~

4 - 600 volt Load Centers 2 - 120 volt' A.C. Vital Busses APPLICABILITY: MODES 5 and 6.

ACTION:

With less than the above complement of A.C. busses OPERABLE and energized, establish CONTAINMENT INTEGRITY within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

(

SURVEILLANCE REOUIREMENTS 4.8.2.2 The specified A.C. busses shall be determined OPERABLE and

- energized at least once per 7 days by verifying t.rrect breaker alignment and indicated power availability. _

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ELECTRICAL POWER SYSTEMS i l

AUXILIARY BUILDING D.C. DISTRIBUTION - OPERATING LIMITING CONDITION FOR OPERATION 3.8.2.3 The following D.C. distribution systems shall be OPERABLE ~and energized:

1 TRAIN "A" consisting of 125-volt 0.C. bus No. JA,125-volt battet/ bank No. 2'A and a full capacity charger.

. 1 1 TRAIN "B" consisting of 125-volt D.C. bus No. 23,125-volt battery bank No. 23 and a full capacity charger.

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

ACTION:

'With one 125-volt D.C. train inoperable or not energized, restore the inoperable train 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 following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

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( SURVEILLANCE REOUfREMENTS 1.3.2.3.1 Each D.C. train shall be cetermined OPERAELE anc energizec at least once per 7. days by verifying correct breaker alignment and incicated voltage on the bus.

4.3.2.3.2 Each 125-volt battr.ry bank and charger shall be demonstrated OPERABLE:

a. At least once per 7 days by verifying that:

1. The electrolyte level of eaca pilo: cell is between the minimum and =aximum level indication marks,

2. The pilot cell specific gravity, corrected to 77 F and full electrolyte level, is greater than or equal to 1.190, and ,

3. The pilot cell. voltage is greater than or equal to 2.02 volts.

b. At least once per 92 days by verifying that:

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

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1 ELECTRICAL POWER SYSTEMS i

SURVEILLANCE REQUIREMENTS (Continued) ,

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M The voltage of each connected cell is greater than or equal to 2.02 volts under float charge and has not decreased more than y,) gvolts from the value observed during the original accept-ance test.

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3/. The specific gravity, corrected to 77 F and full electrolyte 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,

//[- The total battery teminal voltage is greatar_than or equal to 121.2 volts, and 4 % < -

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c. At least once per 1.1 months by verifying that:

., 1. The cells, cell plates and battery racks show no visual

( indication of physical damage or abnomal deterioration,

2. The call-tc-cell and terminal connections are clean, tight, and

cted sitn anti-corrosien material, 9:- 5: - d :: = s cf M x -:: n M--m s-;arr.f n' n. n :ticc i; -

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The battery cr.arger will supply at least 535 a :eres at

> 125 volts for at least 1. nours.

c. At least once per 18 months, during shutcown, by verifying that the battery ca:acity is acecuate to suptly and maintain in OPERAELE status all of tne actual emergency loads for 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months wnen the battary is subjected to a battery service test or the individual cell voltage does not cecrease below 1.75 volts wnen the battery is subjected to the following equivalent load profile.

Order In Which '

Loads Are Current Duration Acolied (ames) (min.)

1 920 1 2 430 58 3 920 1 4 430 59 5 920 1 9

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ELECTRICAL POWER SYSTEMS, k

SUP'IEILLANCE REOUIREMENTS (Continued)

e. At least once per 60 months, during shutdown, by verifying that the battery capacity is at least 80% of the manufacturer's rating when

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subjected to a perfor=ance discharge test. This performance discharge test shall be performed subsequent to the satisfactory co=pletion of the required battery service test.

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ELECTRICAL POWER SYSTEMS , . ~~ ~ ; ;,; _ ,

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AUXILIARYBUILDINGD.C.DISTRIBUTTUN-SHUTDOWN LIMITING CONDITION FOR OPERATION )

1 3.8.2.4 As a minimei, one D.C. distribution system consisting of the following shall be OPERABLE'and energized:

1 - 125-volt D.C. bus, and

. 1 - 125-volt battery bank ind full capacity charger associated with the above D.C. bus.

APPLICABILITY: MODES 5 and 6.

ACTION:

With less than the above complement of D.C. equipment and bus OPERABLE and energized, establish CCNTAINMENT INTEGRITY within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

SURVEILLANCE REOUIREMENTS 4.S.2.4.1 The above recuired 125-volt D.C. bus shall be determined OPERASLE and energi:ed at least once per 7 days by verifying correct breaker alignment and indicated voltage on the bus with an overall voltage of greater than or ecual to 121.2 volts.

4.3.2.4.2 The above recuirec 125-volt battery bank and charger shall be cemonstrated OPERABLE per Surveillance Requirement 4.3.2.3.2.

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ELECTRICAL POWER SYSTEMS SERVICE WATER BUILDING D.C. DISTRIBUTION - CPFRATING LIMITING CONDITION FOR OPERATION 3.8.2.5 The following D.C. distribution systems shall be energized and OPERABLE:

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

TRAIN "B" consisting of 125-volt D.C. Distribution Cabinet N, 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 system inoperable, restore the inoperable 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 30 following STANDBY hours. within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDCNN within the I

SURVEILLANCE REOUIREMENTS 4.E.2.E.1 Each D.C. bus train shall be cetermined OPERAELE and energized at least once. per 7 cays by verifying correct breaker alignment and indicated pcwer availability with an overall voltage of greater than or equal to 121.2 volts.

a. 8. 2. 5. 2 Each 125-volt battery bank and charger shall be demonstrated 0?ERABLE:

a. At least once per 7 days by verifying that:

1. The electrolyte level of each pilot cell is between the minimum and maximum level indication marks,

2. The pilot cell specific gravity, corrected to 77"F and full ,

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

3. The pilot cell voltage is greater than or equal to 2.02 volts.

b. At least once per 92 days by verifying that:

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

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ELECTRICAL POWER SYSTEMS SURVEILLANCE REQUIREMENTS (Continued)

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L,7f The voltage of each connected cell is greater than or equal to 2.02 volts under float charge and has not decreased more than o,/ G-M volts from the value observed during the original acceptance test, 3/ The specific gravity, corrected to 77*F and full electrolyte 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, -

Y)l. The total battery terminal voltage is greater than or equal to 121.2 volts, and Wir "h: i;t ... ; :... (;..;r;;7 ;...;..t' _ith th; bett= ; - '1 t e'- e, ,oce +' s- ,__g 7e ;;;,

, c. At least once per 18 months by verifying that:

r 1. The cells, cell plates and battery racks show no visual indication af. physical. damage or abnor=al deterioration,

2. The call-to-cell and terminal connections are clean, tight, and coatad with anti-corrosion atarial,

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t. ..:'. ... ;s:4c..: ::^rectic, r J cc : ---: h a n : g. . '. . ' O , :- - c hav'.ni j3,/f. The battery charger will supply at least 3 amperes at > 125 volts for at least 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

d. At least cnce per 13 onths, during shutdown, by verifying that the battery ccpccity is adecuate to supply and maintain in C.:E?.ASLE 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 equivalent load profile: ,

l Order in Which Currrent Loads are Acolied (amos) Duration l 1 25 0 - 0.1 sec 2 1 0.1 - 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ; p..

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/ 53 FARLEY-UNITN 3/48-}8 i

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ELECTRICAL POWER SYSTEMS SURVEILLANCE REOUIREMENTS (Continued)

e. At least once per 60 months, during shutdown, by verifying that the

_ battery capacity is at least 80% of the manufacturer's r'ating when subjected to a perfo mance discharge test. This performance discharge test shall be performed subsequent to the satisfactory co=pletion of the required battery service test.

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CONTAINMENT SYSTEMS BASES The maximum peak pressure expected to be obtained from a LOCA event is 45 psig. The limit of 3 psig for initial positive containment pressure will limit the total pressure to 48 psig which is less than design pressure and is consistent with the accident analyses.

3/4.6.1.5 AIR TEMPERATURE The limitations on containment average air temperature ensure that the overall containment average air temperature does not exceed the initial temperature condition assumed in the accident analysis for a LOCA or steam line break accident.

3/4.6.1.6 CONTAINMENT STRUCTURAL INTEGRITY This limitation ensures that the structural integrity of the containment will be maintained comparable to the original design standards for the life of the facility. Structural integrity is required to ensure that the containment ,

will withstand the maximum pressure of 48 psig in the event of a LOCA. 3e visual examination of tendons, anchorages and exposed interior and exterior surfaces of the containment, and the Type A leakage test, : h ; ithin d.a P :' :d ~ _

't '_ L . c :2 v:r;., is sufficient to demonstrate this CEU Y' 6easurement ef 4he cmfMtment VM eM forf e 3 The surveillance recuirements for demonstrating the containment's structural integrity are in comoliance with the reccamencations of paragrapn C.1.3 of Regulatory Guide 1.35 " Inservice Surveillance of Ungrouted Tencons in Prestressed Concrete Containment Structures," January 1976.

3/4.5.1.7 CONTAINMENT VENTILATION SYSTEM The 48-inch containment purge su::1y and exhaust isolation valves are recuired to be clcsed curing plant oceration since these valves have not ceen cemonstratec capable of closing during a LOCA or steam line break accident.

Maintaining these valves closed during plant coerations ensures that excessive cuantities of radioactive materials will not ba released via the containment purge system.

The use of the containment purge lines is restricted to the 18-inch purge supply and exhaust isolation valves to ensure that the site boundary dose guide-lines of 10 CFR Part 100 would not be exceeded in tae event of a loss-of-coolant accident during purging operations.

l FARLEY-UNIT %"j. B 3/4 6-2

PLANT SYSTEMS BASES The surveillance requirements provide assurance that the minimum OPERABILITY requirements of the fire suppression systems are met.

~

In the event the fire suppression water system becomes inoperable, immediate corrective measures must be taken since this system provides the major fire suppression capability of the plant. The requirement for a twenty-four hour report to the Commission provides for prompt evaluation of the acceptability of the corrective measures to provide adequate fire suppression capability for the continued protection of the nuclear plant.

3/4.7.12 FIRE BARRIER PENETRATIONS The functional integrity of the fire barrier penetrations ensures that fires will be confined or adequately retarded frum spreading to adjacent portions of the facility. This design feature minimizes the possibility of a single fire rapidly involving several areas of the facility prior to detection and extinguishment. The fire barrier penetrations are a passive elerant in the facility fire protection program and are subject to periodic inspections.

Fire barrier penetrations are considered functional when the visually

~

observed condition is the same as the as-designed condition. For those fire barrier penetrations that are not in the as-designed condition, an evaluation shall be performed to show that the modification has not degraded the fire rating of the fire barrier penetration.

During periods of time when a barrier is not functional, either, 1) a continuous fire watch is required to be maintained in the vicinity of the affected barrier, or 2) the fire detectors on at least one side of the affected barrier must be verified OPERABLE and an hourly fire watch patrol established, until the barrier is restored to functional status.

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ATTACHMENT II (Revision 1) TECHNICAL SPECIFICATIONS Page 1 of'5 PROBLEMS ASSOCIATES WITH UNIT 1 IF UPDATED IDENTICAll.V TO UNIT 2 PAGE SPECIFICATION DESCRIPTION

1. 3/4 0-1 3.0.3 Issue: APC's preference is for action requirements to start at time of initial (Motherhood) discovery of failure rather than time of failure. No NRC generic require-ment to incorporate in operating plants.

Resolution: APC wishes to withdraw this request from further consideration. However, APC will interpret action requirements to start at time of initial discovery of

, failure as discussed with NRC staff on 9/18/81.

2. 3/4 0-2 4.0.3 Issue: Allows APC to perform surveillance prior to declaring equipment inoperable, (Motherhood) i.e., if surveillance test was not performed on time, then surveillance can be performed rather than declaring equipment inoperable. No NRC generic requirement to incorporate in operating plants.

Resolution: See Attachment III.

3. 3/4 3-4 Table 3.3-1 Issue: APC proposes to make 3.0.4 not cpplicable to ACTION STATEMENT 8 which is for-Item 20 the Reactor Trip System Interlocks. No safety analysis invalidated by change.

(Reactor Trip Only by making 3.0.4 not applicable to reactor trips would invalidate safety System Interlocks) analyses.

Resolution: APC wishes to withdraw this request from further consideration.

4. 3/4 3-19 Table 3.3-3 Issue: APC prefers to make Steam Line Isolation not applicable in modes 2 ano 3 if 3-20 Item 4 MSIVs are closed. This is a common sense approach. The current Spec" cation 3-23 (Steam Line would require a change to a lower mode to perform instrumentation mainte1ance Isolation Actuation) in some situations even if the MSIVs are shut.

Resolution: NRC agreed with APC provided Spec. 3.7.1.5 is modified to preclude operation in Mode 1 with one MSIV inoperable. These tech. spec, changes are proposed in Attachment 1.

(Revision 3 Attachment II (cont'd) Pa'ge 2 of 5 PAGE- SPECIFICATION DESCRIPTION

5. 3/4 3-19 Table 3.3-3 Item-4.d Issue: APC prefers.to add bypass below P-12 far Tavg. Low-Low. Same argument (Steam Line as Item No. 4.

Isolation. Actuation)

Resolution: APC wishes to withdraw this request from further consideration.

6. 3/4 3-22 Table 3.3-3 Item 8 Issue: APC prefers to add 3.0.4 not applicable to ACTION STATEMENTS 20 and 13 (ESF Interlocks) which are for the ESF System Interlocks. Same argument as Item 3.

Resolution: APC wishes to withdraw this request from further consideration.

7. 3/4 3-36 Table 4.3-2 Item 6.a Issue: APC wants to exclude automatic actuation logic for trip of main feedwater .

(Aux. Feed Actuation) pumps for auto start of AFW. Accident analysis does not take credit for- )

this start signal. FNP design does not allow testing via solid state protection system. Cannot be tested at power.

Resolution: NRC agreed with APC provided this portion of automatic actuation logic is tested as part of Item 6.e which it is. See Tech. Spec. changes proposed in Attachment 1.

8. 3/4 3-49 3.3.3.5 HSP Instruments Issue: NRC Proposes to reduce LC0 ACTION STATEMENT from 31 days to 7 days.

No NRC generic requirement to incorporate into operating plant.

Resolution: See Attachment III.

9. 3/4 3-57 Table 3.3-11 Issue: APC prefers to utilize pressurizer SV discharge temperature if limit (Accident Monitoring switch fails to extend LC0 to 7 days since only one limit switch is available. Logical approach.to allow operation until weekend to repair since backup' indication exists and only one limit switch installed.

Resolution: NRC agreed with APC. See Tech. Spec. changes proposed in Attachment I.

10. 3/4 3-72 3.3.4 Issue: No NRC generic requirement to incorporate into operating plant.

3-73 (Turbine-Overspeed (Unit 2 only) Protection)

Resolution: NRC agreed not to. incorporate this_ Tech. Spec. as part of Unit 1 upgrade.

^1 I

- --- - - a

(Revision 1)

Attachment II (cont'd) Page 3 of 5 PAGE SPECIFICATION DESCRIPTION

11. 3/4 4-8 3.4.5 Issue: APC prefers to perform surveillance test in CSD, if not perfc i (PORV Block Valves) the previous 92 days, to preclude blowing valve packing while operating.

Resolution: See Attachment III.

12. 3/4 6-8 3.6.1.6 Issue: APC prefers the following for tendons:

(Containment Tendon Surveillance) 1. Acceptance criteria to be above 40-year limit rather than predict limit because 40-year limit is the design limit for the tendons.

2. Only detension one in each group (dome, vertical, hoop).

Detensioning tends to be counter-productive and enhances the probability

., of damaging individual wires without gaining any significant information from the process.

Resolution: APC wishes to withdraw this request from further consideration at this time. However, APC considers this as an important issue and will file

a separate license amendment request on this issue in the near future.

13, 3/4 7-13 3.7.5 Issue: APC prefers seven days to three days for the ACTION STATEMENT because (River Water System) FNP has closed service water system and pond for ultimate heat sink.

- This is consistent with action times for other similar safety related systems.

Resolution: NRC agreed with APC.

14, 3/4 7-21 3.7.9 Issue: APC prefers the following for snubbers:

7-22 (Snubbers) 7-23 1. NRC 120-day letter response.

7-24 2. Acceptance criteria for mechanical snubbers to allow manual testing.

(No test equipment is available.)

3. APC prefers to limit engineering evaluation to those snubbers that are locked up. Also to limit evaluation to component rather than system.

Resolution: See Attachment III.

2

(Revision 1 )

Attachment II (cont'd) Page 4 of 5 PAGE SPECIFICATION DESCRIPTION

15. 3/4 7-85 3.7.11 Issue: APC prefers to utilize a fire patrol vs. a continuous fire watch.

4 7-88 (Fire Protection) x 7-94 B3/4 7-7 Resolution: APC wishes to withdraw this request from further consideration at this time. However, APC considers this as an important issue and will file a separate license amendment request on this #ssue in the near future. Proposed Tech. Specs, consistent with the Unit 2 version are provided in Attachment I.

16. 3/4 7-65 3.7.13 Issue: No NRC generic requirement to incorporate into operating plant.

7-66 (Area Temperature (Unit 2 only) Monitoring) Resolution: NRC agreed not to incorporate this Tech. Spec. as part of Unit 1 upgrade.

, 17. 3/4 8-1 3.8.1.1 Issue: No NRC generic requirement to incorporate into operating plant.

thru 3.8.1.2 I 3/4 8-8 (Diesel Generators)

B3/4 8-1 Resolution: NRC agreed not to incorporate this Tech. Spec. as part of Unit 1 (Unit 2 only) upgrade.

18. 3/4 8-9 3.8.2.1 Issue: No NRC generic requirement to incorporate into operating plant.

8-10 3.8.2.2 (Unit 2 only) (Inverters) Resolution: NRC agreed not to incorporate this Tech. Spec. as part of Unit i upgrade. APC will address upon receipt of generic NRC letter.

19. 3/4 8-12 4.8.2.3.2 Issue: No NRC generic requirement to incorporate into operating plant.

8-16 4.8.2.5.2 B3/4 8-1 (Batteries) Resolution: NRC agreed not to' incorporate this Tech. Spec. as part of Unit 1 1 (Unit 2 only) upgrade. APC will address upon receipt of generic NRC letter.

20. '3/4 8-18 3.8.3.1 Issue: No NRC generic requirement to incorporate into operating plant.

thru (Containment Pene-3/4 8-28 tration Overcurrent Resolution: NRC agreed not to incorporate this Tech. Spec. as part of Unit 1 (Unit 2 only) Protection Devices) upgrade.

21. 3/4 8-29 3.8.3.2 Issue: No NRC generic requirement to incorporate into operating plant.

thru (MOV Thermal Over-3/4 8-32 load Protection Resolution: NRC agreed not to inccrporate this Tech. Spec. as part of Unit 1 (Unit 2 only) Devices) upgrade.

a

_ _ . . . - _ . _ . _ . . - _ . ._.. __. _ ,- _ .. . . _ _ _ . , . . . - . _ . _ _ . _ . . _ _ _ . _ _ . . . _ _ . . _ . - - . _ _ . _ . ~

i

'(Revision.1)' ;

}

Attachment II (cont'd) Page 5 of 5 PAGE- -SPECIFICATION DESCRIPTION i 22. 3/4 11-15 3.11.2.5 Issue: APC prefers to change 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months to immediately. It may take more than l' 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .to reduce. Oxygen content. Logical change that reduction of l- 02 should-start immediately; however, may be impossible to meet specification within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

! . Resolution: APC withes to withJraw this request from further consideration.

i 4

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-- . = - . . - -

l ATTACHMENT III FNP-1 TECHNICAL SPECIFICATION UPGRADE OUTSTANDING ITEMS Item Page Specification Issue / Proposed Solution 2 3/4 0-2 4.0.3 Issue: The proposed NRC versico of this technical specification requires that if (Motherhood) surveillance is not performed in the allotted time interval then equipment should be declared inoperable. If the_ utility gets into a problem then an emergency technical specification should be approved by the NRC. A potential problem created by this proposed technical specification is that inadequate time may exist to perform the surveillance requirements before the ACTION STATEMENT requires a shutdown. For example, if_the boron injection tank surveillance is not performed on time (Section 4.5.4.1.b), the tank would be declared inoperable and the ACTION STATEMENT would require completion of the surveillance within one hour or be in H0T STANDBY.

Previous operating experience indicates that the surveillance requirement of verifying boron concentration in less than one hour caa not be assured. Therefore, any time the surveillance test is missed on certain pieces of equipment (e.g.,

boron injection tank, refueling water storage tank, ECCS accumulators, etc.), the proposed technical specification would likely require a shutdown due to the impracticality of obtaining an emergency change to the technical specifications in this timeframe. In practive, the equipment has simply not been tested and would likely be found satisfactory if the surveillance tests were performed.

Proposed Solution: APC proposes to use the current Unit 1 version of Spec. 4.0.3 that allows the surveillance test to be performed prior to declaring the equipment inoperable. This would eliminate unnecessary shutdown of the Unit. There is no generic requirement to incorporate the NRC proposed technical specification into l operating plant requirements.

8 3/4 3-49 3.3.3.5 Issue: The proposed technical specification would reduce the LC0 ACTION STATEMENT (Instruments HSP) from 31 days to 7 days. This would not allow much_ time to correct instrument problems before the plant would have to be shutdown. There is no generic require-

ment to incorporate this change into operating plant requirements.

Proposed Solution: APC proposes to maintain the UNIT l LCO ACTION time of 31 days on the basis that other operating plants are allowed 31 days. Also, the probability of an instrument failure.in the Hot Shutdown Panel (HSP) coincident with control room evacuation during a 31-day period is extremely small. Therefore, the 7-day l restriction does not appear to be justified.

i l

L _ _ _ _

Attachm:nt III (cont'd) Page 2 Item Page Specification Issue / Proposed Solution 11 3/4 4-8 3.4.5 Iv ua: The proposed technical specification requires stroke testing of the PORV (p0RV Block Valve) block valve every 92 days. This could cause problems since the valve is not normally cycled that often and the testing could result in blowing the valve packing while the plant is operating. NRC indicates that this surveillance requirement should be part of the inservice testing program (Section 4.0.5) and therefore any exemption to the surveillance schedule must be submitted per 10 CFR 50, Section 50.55 a(g)(6)(i).

Proposed Solution: The presently NRC-approved inservice testing program does not include the PORV block valve and therefore 10 CFR 50, Section 50.55 a(g)(6)(i) does not apply. In lieu of the NRC schedule, APC proposes that the block valve be surveillance tested only during cold shutdown (CSD).

14 3/4 7-21 3.7.9 Issue: Alabama Power Company requests the use of a qualitative rather than 7-23 quantitative acceptance criteria for the functional testing of mechanical snubbers rated less than 350 pounds since the equipment required to do the quantitative type of testing is not commercially available. In addition, Alabama Power Company estimates that this type of testing would add approximately three weeks to each refueling outage. Alabama Power Conpany also requests that snubbers with rated capacities greater than 5G,000 pounds be excluded from functional testing due to the impracticality of testing large, difficult-to-remove snubbers.

Proposed Solution: Alabama Power Company proposes to use a qualitative type of acceptance criteria for snubbers rated less than 350 pounds as specified in the Technical Specifications proposed in Attachment 1. Secondly, an exclusion statement for snubbers with a rating greater than 50,000 pounds has been proposed in Attachment 1. In addition, Alabama Power Company proposes to delay the implementation of Specification 4.7.9.e until startup following the first refueling outage or when a commercial in-place testing device is available, whichever is later.

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