Text

Proposed TS Sections 3.0 & 4.0 Re Operational Mode Changes, Per Generic Ltr 87-09
	ML20101B243
Person / Time
Site:	Vogtle
Issue date:	05/27/1992
From:	; GEORGIA POWER CO.
To:	;
Shared Package
ML20101B240	List: ELV-03024, Application for Amends to Licenses NPF-68 & NPF-81,changing TS Sections 3.0 & 4.0 Re LCO & Surveillance Requirements to Eliminate Unnecessary Restrictions on Mode Changes,Per Generic Ltr 87-09; ML20101B243;
References
	GL-87-09, GL-87-9, NUDOCS 9206010057
	Download: ML20101B243 (82)
	v • d • e

_ _ - _ - _ _ _

ENCLOSURE: 3 VOGTLE ELECTRIC CENERATING PLANT PROPOSED CHANGES TO TECHNICAL SPECIFICATIONS AS A RESULT OFfGENERIC 87-09 INSTRUCTIONS - FOR INCORPORATION--

The proposed changes to the Vogtle Unit l'and Unit 2. Technical ~ Specifications would be-incorporated as follows:

Remos9 Pace Insert Pace 3/4 0-1 and 3/4 0-2 3/4;0-1 and 3/4 0-2 3/4 1-17 and 3/4 1-18* 3/4-1-17-and 3/4 1-18*

3/4 2-11* and 3/4 2-12. 13/4 2-11* and 3/4 2-12 3/4 3-1* and 3/4 3-2 3/4 3-1*-and 3/4 3-2 3/4 3-3 and 3/4z 3 _3/4-_3-3'and 3/4-3-4 3/4-3-5* and 3/4 3-6 3/4 3-5*'and 3/4 3-6 3/4 3-17 and-3/4 3-18* 3/4-3-17 and 3/4 3-18*

3/4.3-19* and 3/4 3-20 -3/4 3-19*-and 3/4 3-20 3/4 3-21 and 3/4 3-22 3/4 3-21 and'3/4'3-22 3/4 3-23 and 3/4 3-24 3/4 3-23 and 3/4.3-24 3/4 3-27 3/4_3 3/4 3-27a-and 3/4 3-28* 3/4 3-27a_and 3/4 3-28*1 3/413-45 and_3/4 3-46* 3/4 3-45 and 3/4_3-46* i 3/4 3-49 and 3/4.3-50 13/4(3-49 and=3/4 3-50 3/4 3-53 and 3/4 3-54* 3/4 3-53 sand 3/4 3-34*

3/4 3-61 and 3/4 3-62* 3/4 3-61 and 3/4L3-62*

3/4 3-65 and 3/4 3-66* 3/4 3-65 and 3/4 3-66* 1 3/4 3-71 and 3/4 3-72* '3/4.3-71 and 3/4 3-72*-

3/4.3-79 and 3/4 3-80* - 3/4'3-79 and 3/4 3-80*

3/4 4-37 and 3/4 4-38* 3/4 4-37 and 3/4 4-38*

3/4 6-15* and 3/4 6-16 3/4-6-15* a:M/3/4 6-16

, 3/4 7-3* and 3/4-7-4 3/4.7-3*'and 3/4-7-4 3/4 7-9 and 3/4 7-10* 3/417-9-and 3/4 7-10*:

3/4.7-25:and 3/4-7-26* - 3/4-7-25 and:3/4 7-26*.

.3/4 7-27 and 3/4 7-28*- ;3/4 7-271and-13/4.7-28*

3/4 8-19 and 3/4 8-20* 3/4 8-19 'and 3/4 8-20*:

3/4 9-7.cnd 3/4L9-8* 3/4 9-7 and 3/4 9-8*-

3/4 9-9* and 3/4 9-10 3/4 9-9* and 3/4 9-10 1

-3/4 9-13 and 3/4 9-14 3/419-13 and~3/4L9-14 3/4 11-1 and 3/4 11-2* 3/4 11-1 and_3/4 11-2*

3/4-.11-5 and'3/4 11-6 3/4 11-5 and:3/4:11'6.-

Overleaf pace contalnino no-chance.

E3-1 r

1 a

lT 9206010057 920527-PDR ADOCK-05000424

>P- PDR

. _ . . _ .. _ . _ . . . _ . .m. . _ _ _ . . . . . - . . , . - . . . . . . - _ , _ . . _ _ _ _ . . _ . . . _ _ _ . . . _ . . _ .

t .

'NCLOSURE 3 (CONTZNUED).

PROPOSED CHANGES TO TECHNICAL SPECIFICATIONS AS'A RESULT OF GINERIC 87-09 INSTRUCTIONE_FOR INCORPORATION l

Femove Pace Jasert Paoefs) 3/4 11-7 and 3/4 11-8 3/4 11-7 and 3/4 11-8 3/4 11-11* and 3/4 11-12 3/4 11-11* and 3/4 11-12 3/4 11-13 and 3/4 11-14 3/4 11-13 and 3/4 11-14.

3/4 11-15 and 3/4 11-16 3/4-11-15 and 3/4 11-16 l 3/4 11-17 and 3/4 11-18 3/4 11-17 and 3/4 11-18 l 3/4 12-la and 3/4 12-2 3/4 12-1* and 3/4'12-2 3/4 12-13 and 3/4 12-14 3/4 12-13 and 3/4 12-14 B 3/4 0-1 -B.3/4 0-1, B 3/4 0-2, and B 3/4 0 B 3/4 0-1a and B 3/4 0-2 B 3/4 0-4 and B 3/4 0-5 B 3/4 0-3 B 3/4 0-6

Overleaf oaae containina no chanae, E3-2

i .

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVE!LLANCE REQUIREMENTS

3/4.0 APPLICABILITY LIMITING CONDITION FOR OPERATION 3.0.1 Compliance with the Limiting Conditions for Operation contained in the l succeeding specifications is required during the OPERATIONAL MODES or other d '

conditions specified-therein; except that upon failure to meet the Limiting Conditions for Operation, the associated ACTION requirements shall be met.

3.0.2 Noncompliance with a specification shall exist when the requirements of the Limiting Condition for Operation and associated ACTION requirements are not met within the specified time intervals. If the Limiting Condition for Operation is restored prior to expiration of the specified time intervals, completion of the ACTION requirements is not required.

3.0.3 When a Limiting Condition for Operation is not met, except as provided in the associated ACTION requirements, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months action shall be initiated to place the unit in a MODE in which the specification does not apply by placing it, as applicable, in: ,

a. At least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ,

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

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

Where corrective measures are completed that permit operation under the ACTION requirements, the action may be taken in accordance with the specified time ;

limits as measured from the time of failure to meet the Limiting Condition for Operation. Exceptions to these requirements are stated in the individual specifications.

This specification is not applicable in MODE 5 or 6.

W e.n 3.0.4 Entry into an OPERATIONAL MODE or other specified condition shs11 not g be made en4ew.the conditions for the Limiting Condition for Operation aretmet

- w4thout relian: er prev!: tent cent:ined " +he a.CTIO" :quir:::nts- This provision shall not prevent passage through or to OPERATIONAL M0 DES as required to comply with ACTION requirements. Exceptions.to these requirements are stated-in the individual specifications.

i

Where specific instrument numbers are provided in parentheses they-are for information only, and apply to each unit unless specifically noted (to assist t identifying associated instrument channels or loops) and are not intended to limit the requirements to the specific instruments associated with the number. -

(and 4he asw:ia+. ed Ac. nod requires ct e>hu+ dexa l# 4 Lev o.re, nd md

%po&\n ct specdNed pe.cWied condHiers+ime m inHarVa.l. En% fn+o on oPERATkSJAL MobE. or~frem ushen c.edrocynance dern % q be made in occor-daneF_ M& Ac.md re n tq

%e. an uniimited pened e4 Mdectn(+5 corxMnueol opemkien og.4e VDGTLE UNITS - 1 & 2 3/4 0-1 9

4 N .

l

4 .

i APPLICABILITY j

_ LIMITING CONDITION FOR OPERATION (Continued) 3.0.5 Unless specifically noted, all the information provided in the Limiting )

Condition for Operation including the associated ACTION requirements. shall apply to each unit individually. In those cases where a specification makes reference to systems or components which are shared by both units, the affected systems or components will be clearly identified in parentheses or footnotes declaring the reference to be " common". Whenever the Limiting Condition for Operation refers to systems or components which are common, the ACTION requirements will apply to both units simultaneously. (This.will be indicated in the ACTION section.) Whenever certain portions of a specification refer to systems, components, operating parameters, setpoints, etc., which are different for each unit, this will be identified in parentheses or footnotes or in the APPLICABILITY section es appropriate, w

SURVEILLANCE REQUIREMENTS 4.0.1 Surveillance Requirements shall be met 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 perfor1ned within the specified time interval with a maximua allowable extension not to exceed 25% of the surveillance interval. necompNance wA deRned by sr .eci#io:h 4.0.g g ,;ggg 4.0.3 Failure to perform a Surveillance Requirement within the :p:: .__

44*e-intervabtshall constitute : f:iler:" t: :::t the OPERABILITY requirements for a Limiting Condition for Operation. -Ex::pti:n: t; th::: 7:wir:: r,t-e-

--.-**e-nated 'n the individual :p::ific:ti:n:. Surveillance Requirements-do not have to be performed on inoperable equipment.

4.0.4 Entry into an OPERATIONAL MODE or other specified condition shall not b'e made unless the Surveillance Requirement (s) associated with the Limiting Condition for Operation has been performed within the stated surveillance interval or as otherwise specified.TWe providion skcdl not preverd po.ss e '

4ksu h og- % OPE @A rtok14L Mt>ES h myired +o compty o'e AC.n r-ep ements, h

The,-Hme, limih5 of 4e, AcIloAl been pe& d-ch MMe H is idenHCled 4ho+ o csurveibNieb ce trement has a.rt., no+- opelico.bb

- e, Ac. nod . trernerrhs ma.y be. del ed -9er up 4o 2A ha.u-s fe pit 4e. c.ompteH op ee. stArveillcLnce, tchen ee.oJtounbte odo.je. Smc ,3 (limi4s oC 4e. ACTIM.J repimmenh ose. (ese Hvan 24 kours V0GTLE UNITS - 1 & 2 3/4 0-2 Amendment Amendment No.13 No. Unit33

2) ((Unit 1)

- -___m_.

REACTIVITY C0 nROL SYSTEMS

( 005ITION INDICATION SYSTEMS - OPERATING LIMITING CONDITION FOR OPERATION 3.1.3.2 The Digital Rod Position Indication System and the Demand Position Indication System shall be OPERABLE and capable of determining the control and shutdown rod positions within i 12 steps.

APPLICABILITY: MODES 1 and 2.

ACTION:

a. With a maximum of one digital rod position indicator per bank inoperable either: l

1. Determine the position of the nonindicating rod (s) indirectly by the movable incore detectors at l'ast e once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months and immediately after any motion of th sonindicating rod which exceeds 24 steps in one direction 5;nce the last determination I of the rod's position, or

2. Reduce THERMAL POWER to less than 50% of RATED THERMAL POWER within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

i

b. With a maximum of one demand position indicator per bank inoperable either:

1. Verify that all digital rod position indicators for the affected bank are OPERABLE and that the most withdrawn rod and the least withdrawn rod of the bank are within a maximum of 12 steps of l

each other at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , or

2. Reduce THERMAL POWER to less than 50% of RATED THERMAL POWER within'.8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

c. The--prov4s40ns--of-Spec 4&iceien 3.0.4 are not applicable--when

-ve rify 4 ng-system-operab 4Mty-foH owi ng -repair .

[

i .

SURVEILLANCE REQUIREMENTS l

l _( 4.1.3.2 Each digital rod position indicator shall be dete u ss to be OPERABLE by verifying that the Demand Position Indication System and the Digital Rod Position Indication System agree within 12 steps at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months except during time intervals when the rod position deviation monitor is l inoperable, then compare the Demand Position Indication System and the Digital Rod Position Indication System at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

V0G1LE UNITS - 1 & 2 3/4 1-17

POWER DISTRIBUTION LIMITS l LIMITING CONDITION FOR OPERATION 1

ACTION (Continued)

2. Reduce THERMAL POWER to less than 50% of RATED THERMAL POWER within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and reduce the Power Range Neutron flux-High )

Trip 5etpoints to less than or equal to 55% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; and

3. Ider,tify and correct the cause of the out-of-limit condition prior to increasing THERMAL POWER; subsequent POWER OPERATION above 50% of RATED THERMAL POWER may proceed provided that the QUADRANT POWER TILT RATIO is verified within its limit at least once per hour for 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months or until verified at 95% or greater '

RATED THERMAL POWER.

-d. The'-pre As4ons-of-Spec 4f4+at4on-34)r4-are-not--appWebler---

l SURVEILLANCE REQUIREMENTS l 4.2.4.1 The QUADRANT POWER TILT RATIO shall be determined to be within the limit above 50% of RATED THERMAL POWER by:

a. Calculating the ratio at least once per 7 days when the alarm is OPERABLE, and

b. Calculatir.g the ratio at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months during steady-state operation when the alarm is inoperable.

4.2.4.2 The QUADRANT POWER TILT RATIO shell be determined to be within the limit when above 75% of RATED THERMAL POWER with one Power Range channel _

inoperable by using the movable incore detectors to confirm that the normalized symmetric power distribution, obtained from two sets of four symmetrk thimble locations or full-core flux map, is consistent with the indicated QUADRANT POWER TILT RATIO at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

' 1

)

l V0GTLE UNITS - 1 & 2 3/4 2-12

j

< TABLE 3.3-1 8

. ~ ._ ;d . REACTOR TRIP SYSTEM IMS,TRUMENTATION

'" i

~~

g.- MINIMUM . ;

APPLICABLE' :l p TOTAL NO. CHANNELS CHANNELS

FUNCTIONAL UNIT' 0F CHANNELS TO TRIP l OPERABLE MODES . ACTION j

1. . Manual Reactor Trip 2 1 2 1, 2 l' . t N 2 1 2 3 , 4 , 5*

8 8 11'

2. .- -Power Range, Neutron Flux '!

.(NI-C0418&C,NI-00428&C, ,

. NI-00438&C,NI-00448&C) i

_ a. High.Setpoint 4 2 3 1, ~ 2 d

3.

b. -Low Setpoint Powr:r Range, Neutron Flux,_

4 4'

2 2

3 3

1, . 2 1, 2 -

/ 1 j

y High Positive Rate

_ y ' (NI-00418&C,NI-00428&C, .;

m- -NI-00438&C,NI-00448&C)

4. _(Deleted)

]j

e -

4: ~

5. .Interniediate Range, Neutron Flux ,

1. FF (Ni-oo3s.,0 E .

Q.

EE NI-00368,D&G)-

a. PEwerOperation 2 1 .2 I d

3

b. -

Startup..' ' '2 1- 2 2 3 i'

((

OO i

j 6. Source Range, Neutron Flux ,

j {" (NI-00318,0&E ,NI-00328,0&G) ;

~

C l' EE :a. Startup- -2 1 2 2 4 i- M - b. Shutoown' 2 1 2- 3 5 , 4, 5 5 _i a

2 J _ i

~

.. . 'd w .. --

, t

._ - . _- 1._ _.

l .

e e

TABLE 3.3-1 (Continued) 8

" REACTOR TRIP SYSTEM INSTRbHENTATION ,,

MINIMUM gE APPLICABLE TOTAL NO. CIIANNELS CHANNELS

% 10 (RIP OPERABLE MotiES ACTION

FUNCTIONAL UNIT OF Cl!ANNELS

GLU 4 2 3 1, 2 (F

" 7. Overtemperature AT

[ (101-0411C, IDI-0421C.

TDI-0431C, 101-0441C) 4 2 3 1, 2 6

8. Overpower AT (TDI-04118, TDI-04218, 101-0431B,T01-044)8) ,

d 4 2 3 1

9. Pressurizer Pressure--Low j i (PI-0455A,B&C, PI-0456 & PI-0456A.

PI-0457 & PI-0457A, PI-0458 &

l w l

4 PI-045aA) 2 3 1, 2

10. Pressurizer Pressure--High 4 (PI-0455A,B&C, Pi-0456 & FI-0456A',

PI-0457 & PI-045?A, PI-0458 & .

g/

PI-0458A)

I Pressurizer Water level--High* 3 2 2 I 11.

(LI-0459A, LI-0460A, LI-0461A)

12. Reactor Coolant Flow--Low h Single loop (Above P-8) 3/ loop 2/ loop in F2/ loop in 1 1

a. each oper-any oper-ating loop ating loop LOOP 2 LOOP 3 LOOP 4 (LOCP 1 FI-0414 FI-0424 FI-0434 FI-0444 F1-04I5 FI-0425 FI-0435 FI-0445 FI-0416 FI-0426 FI-0436 FI-0446)

"See Specification 3.3.3.6 N n_ 'N ar'

.~.

TABLE 3.3-1 (Contineed) 6 -

REACTOR TRIP SYSTEM INSTRUMENTATION , ,

O E MINIMUM TOTAL MO. CHANNELS CHANNELS APPLICABLE TO T'tIP OPERABLE M ACTION Of CliANNELS _ _ ODES _

d FUNCTIONAL UNIT 2/ loop 1 6

b. Two Loops (Above P-7 and 3/ loop 2/ loop in l two oper- each oper-

c. below P-8) ating loops ating loop m

LOOP 2 LOOP 3 LOOP 4 (LOOP 1 C1-0414 FI-0424 FI-0434 FI-0444 FI-0415 FI-0425 FI-0435 FI-0445 FI-0416 FI-0426 FI-0436 FI-0446) 1, 2 9 4/stm. gen. 2/stm. gen. 3/stm. gen.

13. Steam Generator Water in any oper- each oper-w Level--Low-Low

ating sim. ating stm.

2 gen. gen.

LOOP 2 ' LOOP 3 LOOP 4 (LOOP 1 LI-0517 LI-0527 LI-0537 LI-0547 LI-0518' LI-0528 LI-0538 LI-0548

- LI-0519 LI-0529 LI-0539 LI-0549 LI-0551 LI-0552 LI-0553 LI-0554)

14. Undervoltage--Reactor Coolant 2

I 3 I I [

eP' 4-2/ bus Pumps !

15. Underfrequency--Reactor Coolant I f g

2 3 I 6P' Pumps 4-2/ bus ,

i

16. Turbine Trip 2 2 l' l 3

a. Low Fluid 011 Pressure (PT-6161, PT-6162, PT-6163) 4 1 1'

[.

12C/

I Turbine Stop Valve Closure 4 b.

17. Safety Injection Input 1 2 1, 2 10 2

~

from ESF

e-- Specifier **on 3.3.3.r - -

W v _

W

TABLE 3.3-1 (Continued)

TABLE NOTATIONS a When the Reactor Trip System breakers are in the closed position and the Control = Rod Drive System is capable of rod withdrawal.

b The prov454ent-of-Specif4 cat 4cn-1A4-are et applicable M

)-

c Below the P-6 (Intermediate Range Neutron Flux Interlock) Setpoint.

d Below the P-10 (Low Setpoint Power Range Neutron Flux Interlock) Setpoint.

e Above the P-9 (Reactor Trip en Turbine Trip Interlock) Setpoint.

)

f 'Above the P-7'(Low Power Reactor Trip Block) Setpoint.'

g The applicable Modes and Action Statement fo'r these channels noted in Tatie 3.3-3 are more restrictive and, therefore, applicable.

h' Above the P-8 (Single Leop Loss of Flow) Setpoint.

i Trip logic consists of undervoltage/underfrequency for Reactor Coolant Pumps 1. or 2 and 3 or 4.

j The Source Range High Flux at Shutdown' Alarm may be blocked during-reactor startup in accordance with approved procedures.

ACTION STATEMENTS ACTION 1 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restors the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in HOT-STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

ACTION 2 -'With the number of OPERABLE channels one~1ess-than t'he Total Number of Channels, STARTUP and/cr POWER 0PERATION may proceed' provided the following-conditions are-satisfied:

a. The inoperable channel is placed in the tripped condition within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , ,

~ ~

b. lThe Minimum Channels OPERABLE requirement is met; however, the inoperable channel may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing of other channels per Specification 4.3.1.1, and

c. Either, THERMAL POWER.is restricted to less than or equ'a1.. I to 75% of RATED. THERMAL POWER and the Power Range Neutron Flux-Trip Setpoint-is reduced to. less than or equal to

,85% of RATED THERMAL POWER within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; or, the

-QUADRANT POWER TILT RATIO is monitored at least once per

, 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months per Specification'4.2;4.2.

V0GTLE UNITS - 1 & 2 3/4 3-6

, , . , , ..*", , -.w.-- , . , , , ,,a

.: R '^ r D R D _

TABLE 3.3-2 g

8 y ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION c MINIMUM TDTAL NO. CHANNELS CHANNELS APPLICABLE h

m OF CHANNELS TO TRIP OPERABLE MODES ACTION FUNCTIONAL UNlT e

9 1. Safety Injection (Roctor e- Trip, Feedwater Isolation, ro Component Cooling Water, Control Room Emergency Filtration Systern Actuation, Start Diesel Generators, Containment Cooling Fans, Nuclear Service Cooling Water, Containment Isolation, Con-tainment Ventilation Isolation, and Auxiliary Feedwater Motor-0 riven Pumps).

1 2 1,2,3,4 19

a. Manual Initiation 2 9 1, 2; 3, 4 14 U b. Automatic Actuation 2 1 2 Logic and Actuaticn Relays Containment Pressure--High-1* 3 2 2 1,2,3,4 15 c.

(PI-0934, PI-0935, PI-0936) 8 4 '2 3 1,2,3 20

d. Pressurizer Pressur-e--Low (PI-0455A,8&C, PI-0456 &

PI-0456A, PI-0457 & PI-0457A, PI-0458 & PI-045BA) 8 d

e. Steam Line Pressure--Lcw* 3/ steam line 2/ steam line 2/stean line 1, 2, 3 15 any steam fine LOOP 2 LOOP 3 LOOP 4 (LOOP 1 PI-0514A,B&C PI-0524A&B PI-0534A&B PI-0544A,B&C PI-0515A PI-0525A PI-0535A PI-0545A PI-0516A PI-0526A PI-0536A PI-0546A).

See Specification 3.3.3.6

l l 4 TABLE 3.3-2 (Continued)

S ENGINEERED SAFETY FEA7URES ACTUATION SYSTEM INSTRUMENTATION l,

k MINIMUM

p. TOTAL NO. CilANNELS CHANNELS APPLICABLE

, FUNCTIONAL UNIT OF CHANNELS 10 TRIP OPERABLE MODES ACTION

[ 4. Steam Line Isolation (Continued)

I I d ,

c. Containment Pressure--High-2* 3 2 2 1, 2 , 3 15 (PI-0934, PI-0935, PI-093,6)

d. Steam Line Pressure--Low

3/ steam 2/ steam 2/ steam 1, 2I , 3a ,f 15 d

line line any line steam line

- (LOOP 1 LOOP 2 LOOP 3 LOOP 4 w PI-0514A,B&C PI-0524A&B ~PI-0534A&B PI-0544A,B&C,

} PI-0515A PI-0525A PI-0535A PI-0545A, w PI-0516A PI-0526A PI-0536A PI-0546A) 5 e. Steam Line Pressure - 3/ steam 2/ steam 2/ steam 3b ,f 15 d

Negative Rate--High* line line any line steam line

, (LOOP 1 LOOP 2 LOOP 3 LOOP 4 PI-0514A,B&C PI-0524A&B PI-0534A&B PI-0544A,B&C PI-0515A PI-0525A P!-0535A PI-0545A PI-0516A. PI-0526A PI-0536A PI-0546A) c Turbine Trip and Feedwater Isolation

a. Automatic Actuation Logic 2 1 2 1, 2 25 .

and Actuation Relays

b. Low RCS Tavg Coincident with Reactor Trip ** , a g

1. Low RCS T,yg 4 2 3 1, 2 2tf/

2. Reactor Trip, P-4 See Functional Unit 9.b. for P-4 requirements.

See Specification 3.3.3.6

- Feedwater isolation only. Turbine trip occurs on reactor trip.

" ~

., w __. ..

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _~

r .

TABLE 3.3-2 (Continued) 6 ,,

1 ENGINEERLD SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION MINIMUM e CHANNELS CHANNELS APPLICABLE.

TOTAt NO. ' ACTION

-5 'TO TRIP OPERA 8LE MODES FUNCTIONAL *J';' Of CHANNELS

.d b 5. Turbine Trip and Feedwater e

ro Isolation-(Continued)-

c. Steam Generator Water' 4/stm. gen. 2/sts. gen. 3/sta. gen. 1, 2 '20 f in any oper- - in each Level--High-High:(P-14)* ating stm. - operating gen. stm. gen.

LOOP 2 LOOP 3 LOOP 4 (LOOP 1 LI-0517 LI-0527' LI-0537 LI-0547 R LI-0518 LI-0528- LI-0538 LI-0548 l

L1-0519 LI-0529 LI-0539 LI-0549 T LI-0551 LI-0552- LI-0553 LI-0554) ,

l3 . .

See~ Functional Unit 1. above for all Safety

d. Safety Injection Injection initiating functions and requirements. .

6. Auxiliary Feedwater

.1 2 1, 2, 3 . 22 a.' Automatic Actuation Logic 2 and Actuation Relays

'See Specification 3.3.3.6- c e

a e

m

.c.... ..,. . . . . . . . . . , . , , , ,,

____wr--- -

-1 .c.-w. .-... . .

TABLE 3.3-2 (Continued) ,

ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION .,

MINIMUM e APPLICABLE CHANNELS

.5 TOTAL NO. CHANNELS OPERABLE MODES ACTION TO TRIP d FUNCTIONAL UNIT OF CilANNELS

6. Auxiliary Feedwater (Continued) e eo b. Stm. Gen. Water Level--

Low-low

LOOP 2. LOOP 3 LOOP 4 (LOOP 1 LI-0517 LI-0527 LI-0537 LI-0547 LI-0518- LI-0528 LI-0538 LI-0548 LI-0519 LI-0529 LI-0539 LI-0549 LI-0551 LI-0552 LI-0553 LI-0554) 4/stm. can. 2/stm. gen. 3/sta. gen. 1, 2, 3

$ 1) Start Motor-Driven Pumps.

in any oper- in each w operating ating sim. gen e'o

" stm. gen. g

2) Start Turbine-Driven Pump 4/sta. gen. 2/stm. gen. 3/sta. gen. 1, 2, 3 20 h l in any in each l 2 operating operating- i sim. gen. stm. gen.

( c. Safety Injection Start See Functional Unit 1. above for all Safety Injection Motor-Driven

umps initiating functions and requirements.

d. Loss of or Degraded 4.16 kV ESF Bus Voltage-l 4/ train 2/ train 3/ train 1, 2, 3 23 1 . Start Motor-Driven Pumps 23 11 Start Turbine-Driven Pump 4/ train 2 from 3/ train 1, 2, 3 either train

~See Specification 3.3.3.6

- s .

W t- _

m g m

-W m '

.6 .

TABLE 3.3-2 (Continued)

[ ~8 0 '

. -ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION !

res MINIMUM

!E CHANNELS CHANNELS APPLICABLE.

TOTAL NO. ACTION 0 OF CHANNELS TO TRIP _ OPERABLE MODES _

'>' FUNCTIONAL UNIT

[ e. Trip of All Main Feedwater 2 1, 2 23 ,

Pumps, LStart Motor-Driven Pumps 2 2 h 1/ pump 1,2,3 23 to . .-

3 1/ pump

f. Manual initirrion t L

7. Semi-Automat . is# chover to

' Containment E:2rgency Sump ,

2 1, 2,'3, 4 14-Automatic Actuation-Logic 2 1

- a.

' and Actuation Relays 4 2 3 ,

1,23,4 17 RWST Level--Low-Low Coincident

. -b. See Functional Unit 1. above for all Safety Injection' initiating

) with Safety Injection *

-(LI-0990A&B,LI-0991A&B, functions and requirements. .

LI-0992A, LI-0993A) '

[

_4 W 7 l

8. Loss of Power.to 4.16 kV.ESF Bus 1, 2,.3, 4 20

.4/ bus 2/ bus 3/ bus *

a. -4.16 kV ESF Bus - -

Undervoltage-Loss of Voltage: '

~

b. '4.16 kV ESF Bus

Undervoltage-Degraded 3/ bus 1, 2, 3, 4-

~

^

4/ bus' 2/ bus Voltage

] 9. Engineered Safety Features- ,

Actuation System Interlocks- 21

{ 2

~

2 1,2,3 .

3 i a. Pressurizer Pressure, P i (PI-0455A,8(? , PI-0456 a

j. PI-0456A.. PI-0457 & PI-0457A) 1, 2, 3 ' 23 2 1. 2'

! b. Reactor Trip..P-4 '

4 2-

"See Specification 3.3.3.6 :

/

W ~ b %f a. --,:.- '

--__----_--.-______.__.-__-_---__.-_-_----a - - - . _ - - - - . _ _ _ - - _ _ - - _ . , - -

r -

s 1

y TABLE 3.3-2 (Continued) i 8

ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATIO_N MINIMUM MINIMUM 5 CHANNELS CHANNELS APPLICABLE TOTAL NO.

3 e OF CHANNELS TO TRIP OPERABLE MODES ACTION FUNCTIONAL UNIT

- 10. Control Room Emergency Fi!' ration

- . System Actuation m

a. Manual Initir' %n 2 1 1 in either Either Unit in Unit 1, 2 3, 4, 5', 6' 2

~

Automatic Actuation logic Either Unit in

b. '2 2 1,2,3,4, and Acteation Relays 2 1 5', 6' 2

c. Safety Injection See Functional Unit L above for all Safety injection R

initiating functions and requirements. ,,

Intake'Radiogas Monitor 2 1 2 Either Unit in

"_ , d. 1, 2, 3, 4, 8

(RE-12116. RE-12117) 5', 6' e

11. Fuel Handling Building Post Accident Ventilation Actuation

' (Common System)~

Manual-Initic> ion 2 1 1 ! j

a. '

Fuel Handling Building 4 1 1 i j b.

Exhaust Duct Radiation Sipal (ARE-2532 A&8 ARE-2533 A&B) 1 i i c.. Automatic Actuation logic 4 1 and Actuation Relays I WW

i

. . l TABLE 3.3 2 (Continued)

ACTION STATEMEllTS (Continued) i ACTION 24 - With Number the number of Channels, restoreof the3PERABLE inoperable channel channels one less than "l to OPERABLE th status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or declare the associated valve inoperable and take the ACTION requirsd by Specification 3.7.1.5. l l

k ACTION 25 - With the number of OPERABLE channels one le 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; however, one channel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ,

for surveillance testing per Specification 4.3.2.1 provided the i other channel is OPERABLE.

( ACTION 26 - With Channels the number OPERABLE of OPERABLE requiremant, channels restore at least one channel one less than to OPERABLE status within 7 days or within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months initiate and maintain operation of the Filtration System in the Emergency mcde$' trol Room .

l E ACTION 27 - a)

With one channel inoperable in a unit, restore the inoperable channel to OPERABLE status within 7 days OR within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months initiate and maintain operation of one Control Room Emergency Filtration System in the unaffected unit in the4 (CREFS) #. V i

emergency mode b)

With one channel inoperable in each unit, restore each inoperable channel to OPERABLE status within 7 days.0R peration of j within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months initiate and maintai l one CREFS in each unit in the emergency mode . {

c) With two channels inoperable in a unit, within I hour either 1) initiate an saintain operation of the two CREFS i

l in the unaffected uni operation of one CREFS nReach 2) initiate unitand in maintain the emergency W. modeI d)

With three channels inonerable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months initiate and maintain operation of t".e two CREFS in the em rgency mode l in the unit with only one channel (noperabl l e)

With four channels-inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months initiate >nd maintain operation of two CREFS in the emergency mode F l

' ACTION 28 - a)

With one channel inoperable in a unit, restore the inoperable channel to OPERABtE status within 7 days OR within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months either 1) lock closed Qep ffected- .I and lock open the uncffected OSA intake dampersW OR 2) initiate and mgistain operation of one CREFS in' the -l emergency mode W iThe initiated CREFS shall be Train B unless Train B isl inoperable. [ t

= -= w =tw.C.m umm e= m .

3/4 3-27 AMENDMENTNO.26(UNIT 1)

V0GTLE UNITS - 1 & 2 AMENDMENT NO.7 (UNIT 2)

_ . _ ~

., .s_, - - - -

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

TABLE 3.3-2 (Continued) l ACTION STATEMENTS (Continuedj

}

b) With one channel inoperable in each unit, restore .ach e inoperable channel to OPERAB'.E status within 7 days OP within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months initiatpnd nintain operation of l, one CREFS in the emergency mode F

( c) With two channels inoperable in a unit, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months either 1) lock closed the aff3qt_e4 and lock open the i

unaffected OSA intake damper W OR 2) initiate and maintain l' operatJ rode %go of one CREFS in each unit in the emergency l, With three channels inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months either 1)

( d) lock closed the OSA intake dampers of the unit with two inoperable channels-and lock open the other OSA intake dampers and either restore the renining affected channel to OPERABLE status within 7-days OR initiate a aintain operation'of one CREFS in the emergency mode in the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months OR 2) initiate and maintai o eration of ,

one CREFS in each unit in the emergency mode ^.'

e) With four channels inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months initiate and-maintain opera,t f one CREFS in each unit in the emergency mocia t

I I

I L L

The initiated CREFS shall be Train B unless Train 8 is inoperable.

l h "The pivvi5ivns of Specification 3.0.4 cre net-applicable-to-either-w4-t.

3/4 3-27a'

~

V0GTLE UNITS - 1 & 2 AMENDMENT NO. 26 (UNIT i)

AMENOMENT NO 'I-(UNIT-2) en- -:<m , .,, , ,. , . _ _ , . . , _ , _ _ _

s INSTRLHENTATION 3/4.3.3 MONITORINGINSTRUMENTATf0h RADIATION MONITORING FOR PLANT OPERATIONS LIMITING CONDITION FOR OPERATION 3.3.3.1 The radiation monitoring instrumentation channels for plant operations shown in Table 3.3-4 shall be ope.RABLE with their Alare/ Trip Setpoints within the specified limits.

APPLICABILITY: As shown 'i Table 3.3-4.

ACTION:

a. With a radiation monitoring channel Alars/ Trip Setpoint for plant operations exceeding the value shown in Table 3.3-4, adjust the Setpoint to within the limit within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or declare the channel inoperable.

b. With one or more radiation mon,itoring channels for plant operations inaperable, take the ACTION shown in Table 3.3-4.

c. The provisions of Specificatio 0.3 and4,0r4lare not' applicable.

SURVEILLANCE REQUIREMENTS 4.3.3.1 Each radiation monitoring instrumentation channel for plant operations shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL

, CALIBRATION and ANALOG CHANNEL OPERATIONAL TEST for the MODES and at.the

( frequencies shown in Table 4.3-3.

.. rs V0GTLE UNITS - 1 & 2 3/4 3-45 -

g

w 1NSTRUMENTAT10N

'5 MOVABLE INCORE DETECTORS p =

LIMITING CONDIY10N FOR OPERATION 3.3.3.2 The Hovable Incore Detection System shall be OPERABLE with:

a. At least 75% of the detector thimbles,

b. A minimum of two detector thimbles per core quadrant, and

c. Sufficient movable detectors, drive, and readout equipment to map these thimbles.

APPLICABILITY: When the Movable incore Detection System is used for-

a. Recalibration of the Excore Neutron Flux Detection System, or

b. Monitoring the QUADRANT POWER TILT RATIO, or .,

N '

c. Measurement of F 3q, F (Z) and Fxy, 9

ACTION:

With the Hovable Incore Detection System inoperaole, do not use the system for the above appilcable monitoring et calibration functions. The provisions of Specificatioq.0.3:nd2.0.'genotapplicable.

SURVEILLANCE RFOUIREMENTS 4.3.3.2 The Movable Incore Detection System shall be demonstrated OPERABLE within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months prior to ust by irradiating e:ch detector used and determining the acceptability of its voltage curve when required for:

a. Recalibration of the Excore Neutron Flux Detection.5ystem, or

b. Monitoru.g the QUADRANT POWER TILT RATIO, or H

c. Measurement of F aH, Fq(2) and Fxy, 6

V0GTLE UNITS - 1 & 2 3/4 3-49

.,$T tVME NT ATI ON ,

SEISMIC INSTRUMENT ATION (Common System) j LIMITING CONDITION FOR OPERATION 3.3.3.3 The seismic monitoring instrumentation shown in Table 3.3-5 shall be )

OPERABLE.

AFPLICABIllVY: At all times. .

AC110N:

a. With one or more of the aboy? required seismic monitoring hstruments inoperable for more than 'a0 days, prepare and submit a ipecial Report to the Commission pursuant to Specification 6.8.2 within the next 10 days outlining the cause ef the malfunction and the plans -

forrestoringtheinstrument(s)toOPERABLEstatus.

b. The provisions of Specificatio 3.0.3 e d 3.0. dare not applicule.

SURVEILLANCE REQUIREMENTS 4.3.3.3.1 Each of the above required seismic monitoring instrurents shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALI-BRAT 10N, and ANALOG CHANNEL OPERATIONAL TEST at the frequencies shown in Table 4.3-4, 4.3.3.3.2 Each of the above required seismic monitoring instruments which is '

accessible during power operations and which is actuated during a seismic event greater than or equal to 0.01 g shall be restored to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and a CHANNEL CALIBRATION performed within 15 days following the seismic event. Data shall be retrieved from actuated instruments and analyzed to determine the magnitude of the vibratory ground motion. A Special Report shall be prepared and submitted to the Commission pursuant to Specifica-tion 6.8.2 within 14 days describing the magnitude, frequency spectrum, and resultant effect upon facility features important to safety.

Each of the above seismic monitoring instruments which is actuated durino a seismic event greater than ur equal to 0.01 g but is not accessible during power g operation shall be restored to OPERABLE status and a CHANNEL CALIBRATION per- '

fortned the next time Unit 1 enters MODE 5 or below. A supplemental report shall then be prepared and submitted to the Commission with 14 days pursuant to

Specification 6.8.2 describing the additional data from these instruments.

l .

1 V0GTLE UNITS - 1 & 2 3/4 3-50

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

INSTRUMENTATION

( METEOR 0 LOGICAL INSTRUMENTATION (Common System)

MMITINGCONDITIONFOROPERATION 3.3.3.4 The meteorological monitoring instrumentation channels shown in Table 3.3-6 shall be OPERABLE.

APPLICABILITY: At all times.

ACTION:

a. With or.e or more required meteorological monitoring channels inoperable for more than 7 days, prepare and submit a Special Report to the Commission pursuant to Specification 6.8.2 within the next 10 days outlining t5e cause of the malfunct'on and the plans for restoring the channel (s) to OPERABLE status.

b. The provisions of Specificatio 0.3 and-3,0 e not applicable.

(

SURVEILLANCE REQUIREMENTS 4.3.3.4 Each of the meteorological monitoring instre.nentation channels shown in Table 3.3-6 shall be demonstrated OPERABLE by the performance of:

a. A Daily CHANNEL CHECK, and

b. A Semiannual CHANNEL CALIBRATION,

(,

V0GTLE UNITS - 1 & 2 3/4 3-53~

~

--e-..A ,r , - . -e-,- ,

w- , ,~---r,,-an ,qn,-, gn ~ g .nn. -- e ,------- ,---- ,

TABLE 3.3-8 (Continued)

ACTION STATEMENTS ACTION 30 - a. With the number of OPERABLE channels one less than the Total Number of Channels requirement, restore the inoperable channel to OPERABLE status within 31 days, or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

b. With the number of OPERABLE channels two less than the Total restore at least one inoperable Number channel teof Channelsstatus OPERABLE requirement,in with 7 days, or be in at least HDT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

c. With the number of OPERABLE channels less than the Minimum

(- Channels OPERABLE requirement, restore at least one inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or '

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

d. The provisions of Specification 3.0.4 are not applicable.

ACTION 31a - a. With the number of OPERABLE channels one less than the Total l i Number of Channels requirement, restore one inoperable channel to OPERABLE status within 7 days, or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . ,

b. With the number of OPERABLE channels less than the Minimum ;

Channels OPERABLE requirement, restore at least one inoperable 1 channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , or be in HOT SHUTDOWN

( within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

c. The provisions of Specification 3.0.4 are not applicable.

ACTION 31b - a. With the number of OPERABLE channels less than the Total Number of Channels requirement, comply with tan provisions of Specification 3.6.4.1.

b. The provisions of Specification 3.0.4 are not applicable.

ACTION 32 -

With'the number of OPERABLE channels less than the Minimum Chan-nels OPERABLE' requirement, restore at least one inoperable chen-nel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months , or be in HOT SHUTDOWN *

. within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months . The provisions of Specification 3.0.4 are not applicable.

-(

ACTION 33 -

With the number of OPERABLE channels less than the Minimum Channels OPERABLE requirement, initiate the alternate method of monitoring the parameter within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months and either restore the inoperable channel (s) to OPERABLE tatus within 7 days or prepare and submit a Special Report to the Commission, pursuant to Speci-C., fication 6.8.2, within 14 days that provides actions taken, cause of the inoperability, and the plans and schedule for restoring l

the channals to OPERABLE status. -TAs-prov4s4 ens-of Specifice- /

l -t4en-34A-are-not-app 34cabla,_ F V0GTLE UNITS - 1 & 2 3/4 3-61 AMENDMENT NO.27 (UNIT 1)

AMENDMENT NO.8 (UNIT'2)

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

INSTRUMENTATION

( RADI0 ACTIVE LIQUID EFFLUENT M0tlITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION r 3.3.3.9 The radioactive liquid effluent inonitoring instrumentation channels

( shown in Table 3.3-9 shall be OPERABLE with their Alarm / Trip Setpoints set to ensure that the limits of Specification 3.11.1.1 are not exceeded. The Alarm /

Trip Setpoints of these channels shall be determined and adjusted in accordance with the methodology and parameters in the CFFSITE DOSE CALCULATION MANUAL (ODCM).

( APPLICABILITJ: At all times.

ACTION:

3. With a radioactive liquid effluent monitoring instrumentation channel Alarm / Trip Setpoint less conservative than required by the above specification immediately suspend the release of radioactive liquid effluentsmonItoredbytheaffectedchannel,ordeclarethechannel inoperable,

b. With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3-9. Restore the inoperable instrumentation to OPERABLE status within 30 days and, if unsuccessful, explain in the next

( Semiannual Radioactive Effluent Release Report pursuant to Specificati e 6.8.1.4 why this inoperability was not corrected in a time?. -nner.

c. The provisions of Specificatioq 0.3 and-3 A 4 re not applicable.

SURVEILLANCE REQUIREMENTS 4.3.3.9 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE

{,

CPECK, CHANNEL CALIBRATION, and ANALOG CHANNEL OPERATI0tML TEST at the frequencies shown in Table 4.3-5.

V0GTLE UNITS - 1 & 2 3/4 3-65

INSTRUMENTATION I.

( RADIOACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION

}.IMI_TINGCONDITIONFOR_0PERATION 3.3.3.10 1he rabioactive gaseous effluent monitoring instrumentation channels

(' shown in Tabit 3.3-10 shall be OPERABLE with their Alarm / Trip Setpoirts sc to L

ensure that the limits of Specifications 3.11.2.la and 3.11.2.5 are not exceeded.

The Alarm / Trip Setpoints of these channels meeting Specification 3.11.2.la shall be determined and adjusted in accordance with the methodology and parameters in the ODCM. '

APPLICABILITY: As shown in Table 3.3-10 ACTION:

a. With a radioactive gaseous effluent monitoring instrumentation channel Alarm / Trip Setpoint less conservative than required by the above specification, immediately suspend the release of radioactive gaseous effluents monitored by the af fected channel, or d?clare the channel inoperable.

b. With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE, take the ACTION shorn in Table 3.3-10. Restore the inoperable in::trumentation to OPERABLE status within 30 days and, if unsuccessful, explain in the next' Semiannual Radioactive Effluent Release Report pursuant to Specifi-cation 6.8.1.4 why this inoperability was not corrected in a timely manner.

c. The provisions of Specificatio 0.3 and-3.A e not applicable.

f SURVEILLANCE REQUIREMENTS

( 4.3.3.10 Each radioactive gaseous effluent monitoring instrumantation channel l l shall be demonstiated OPERABLE by performance of the CHANNEL CHECK, SOURCE l CHECK, CHANNEL CALIBRATION and ANALOG CHANNEL OPERAT10NAL TEST at the frequencies shown in Table 4.3 6. .

V0GTLE UNITS - 1 & 2 3/4 3-71

INSTRUMENTA.

- TION HIGH-ENERGY LINE BREAK ISOLATION SENSORS LIMI11NG CONDITION FOR OPERATION

- 3.3.3.11 The high energy line break instrumentation listed in Table 3.3-11 shall be OPERARLE.

APPLICABILITY: As noted in Table 3.3-11.

{ AJTION:

a. With the number of OPERABLE electric steam boiler isolation instruments ;

less than the Minimum Channels OPERABLE as required by Table 3.3-11, re- i store the inoperable instruments to OPERABLE status within 7 days or sus-pend operation of the electric steam boiler until the inoperable sensors are restored to OPERABLE status. The-provisions-of-Specif4 cat 4on4ror4 g are-not-applicable #

b. With the number of OPERABLE steam generator blowdown line isolation instru- l ments or letdown line isolation instruments less than the Minimum Channels !

OPERABLE as required by Table 3.3.11, restore the inoperable instruments to OPERABLE status within 7 days o. be in HOT STANDBY vithin the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the folloving 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months . l

(

SURVEILLANCE REQUIREMENTS , 4.3.3.11 Each of the above high energy line break isolation instruments shall

, be demonstrated OPERABLE by the performance of an ANALOG CHANNEL OPERATIONAL TEST at least once per 18 months, f

l C

V0GTLE UNITS - 1 &'2 3/4 3-79

-# y

REACTOR COOLANT SYSTEM

( 3/4.4.10 STRUCTURAL INTEGRITY LIMITING CONDITION FOR OPERATION 3.4.10 The structural integrity of ASME Code Class 1, 2, and 3 components ,

shall be maintained in accordance with Specification 4.4.10. l t-APPLICABILITY: All MODES.

ACTION: ,

a. With the structural utegrity of any ASME Code Class 1 component (s) not conforming to the above requirements, restore the structural integrity of the affected component (s) to within its limit or isolate the affected component (s) prior to increasing the Reaccor Coolant System temperature more than 50'F above the minimum temperature required by NDT considerations.-

b. With the structural integrity of any ASME Code Class 2 component (s) not conforming to the above requirements, restore the structural integrity of the affected component (s) to within its limit or isolate the affected component (s) prior to increasing the Reactor Coolant System temperature above 200'F.

c. With the structural integrity of any ASME Code Class 3 component (s) not conforming to the above requirements, restore the structural ,

integrity of the affected component (s) to within its limit or isolate the affected component (s) from service.

-d. he-p ro v4 si on s-o f-Spe c444ca ti on-3.-A4-a re-not-appl 4caMe-SURVEILLANCE REQUIREMENTS 4.4.10.1 Not Used r .

b -

4.4.10.2 In addition to the requirements of Specification 4.0.5, each reactor coolant pump flywheel shall be inspected per the recommendations of Regulatory Position C.4.b of Regulatory Guide 1.14, Revision 1. August 1975.

4.4.10.3 In addition to the requirements of Specification 4.0.5, the four main steam _ lines and feedwater lines from the containment penetration flued head

{ outboard welds, up to the first five way restraint, shall:be inspected. The extent of the inservice examinations completed during each inspection interval (ASME circu. Code Section mferential andXI) shall provide longitudinal 100,topercent welds volumetric the extent practical. examination of V0GTLE UNITS - 1 & 2 3/4 4-37

o P

CONTAINMENT SYSTEMS

_N_.4

._.. 6. 3 CONTAINMENT ISOLATION VALVES LIMITING CONDITION FOR OPERATION 3.6.3 The containment isolation valves shall be OPERABLE. )

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

ACTION:

With one or more of the containment isolation valve (s) inoperable, maintain at i least one isolation valve OPERABLE in each affected penetration that is open and:

a. Restore the inoperable valve (s) to OPERABLE status within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , or

b. Isclate ea:h affected penetration within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months by use of at least one deactivated automatic valve secured in the isolation position, or .

c. Isolate each affected penetration within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months by use of at leart one closed manual valve or blind flange, or -

d. 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 I SHUT 00VN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

-er The-provisions-of-Specification-3.0A-are-wt-app 14 cable-provided /g

-that the-af fected penetration-is-isolated-in-accordance-with-ACTION y

--b-o r-c-abover and-provided-that-the-essociated-systee -if-app r 14 cable

-i s-d e cl a re d-4 nope ra ble-a n d-the-a pp rop ri a te 4CT 10N -s ta tement s-for r#

--tnat-system-are-performed v SURVEILLANCE REQUIREMENTS 4.6.3.1 The containment isolation valves shall be demonstrated OPERABLE prior )

to returning the valve to service after maintenance, repair or replacement work l is perforted on the valve or-its associated actuator, control or power circuit by performance of a cycling test, and ver'ification of isolation time.

)

V0GTLE UNITS - 1 & 2 3/4 6-16

l i

.P.LANT SYSTEMS AUXILIARY FEEDWATER SYSTEM I

MMITINGCONDITIONFOROPERATION

)

3.7.1.2 ' At least three independent steam generator auxiliary feedwater pumps and associated flow paths shall be OPERABLE with:

a. Two motor-driven auxiliary feedwater pumps, each capable of.being powered from separate emergency busses, and ,.

I

b. One steam turbine-driven auxiliary feedwater pump capable of being i powered from an OPERA 8LE. steam supply system.

APPLICABILITY: H0 DES 1, 2, and 3._- l ACTION:

. 1

a. With one auxiliary feedwater pump inoperable, restore the required i auxiliary feedwater pumps to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or be: -)

in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in H0' SHUTDOWN l within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months . !

l

b. With two auxiliary feedwater pumps inoperable, be in at least HOT -

i STANDRY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in HOT SHUTDOWN within the following 6 7 hours8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months . ;.

c. With three auxiliary feedwater pumps inoperable' immediately initiate- 3 corrective action to restore at least one auxillary feedwater pump i

.to OPERABLE status as soon as possible. nh in10 Oh CPERATI L MODE D' Difer s ciRed. Wadition uh er 1[ oyigiaqg ; -

t' Ion 3 .f, Sha.LL not te Wt eon 1 OrU wa er (EM P5 inopavbl.e. >

SURVEILLANCE REQUIREMENTS

.4.7.1.2.1 Each auxiliary feedwater pump shall be demonstrated _0PERABLE:

a. At least once per 31 days on a STAGGERED TEST BASIS by:.- ) .

i

1) Verifying that each motor-driven pump develops a discharge pressure of greater than or equal to 1605 psig at a flow :

of greater-than or_equalLto 150 gpa_(FI-15101, FI-15102);;

2)_ Verifying that the steara turbine-driv.en pump' develops a; dis-- ,L charge pressure of greater than or equal to 1675 psig at a flow-of greater than or equal.'to -145 gps '(FI-15100) when the is secondary steam supply The pressure provisions of Specificat ion _4.0.4 (PI-5105A 'PI-51058) greater than 900 psig.

' are not applicable'for entry into MODE 3.-

8

. f

.(

'V0GTLE UNITS'- 1 & 2- 3/4 7-4 Amendment;No.21((Unit [1)

-Amendment No.

- 2 Unit 2) y ,

FLANT SYSTEMS ,

MAIN STEAM LINE ISOLATION VALVES

{' LIMITING CONDITION FOR OPERATION 3.7.1.5 Twomainsteamlineisolationsystems(eachsystemconsistingofa main steam isolation valve (MSIV) and its associated bypass valve (MSIBV)) per

- steam line shall be OPERABLE.*

APPLICABILITY: H0 DES 1, 2, and 3. .

ACTION:

MODE 1:

a. With two main steam line isolation systems in any one steam line inoperable; POWER OPERATION may continue provided each MSIV in the

(- affected steam line is open and at least one main steam line isola-tion system in the affacted steam line is restored to OPERABLE status within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; othe mise reduce power to less than or equal to 5% of RATED THERMAL POWER within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

b. With one main steam line isolation system inoperable power opera-tionmaycontinueprovidedtheMSIVintheaffectedIsolationsystem is open and the inoperable system is restored to OPERABLE status within 3 days. Othe mise, reduce power to less than or equal to 5% of RATED THERMAL POWER within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months .

MODES 2 and 3:

a. With two main steam line isolation systems in any one steam line'

( inoperable, subsequent operst. ion in MODES 2 or 3 may proceed provided at least one main steam line isciation system in the affected steam line is maintained c1psed. -The-provisions-of-Spec 4f4catter 3.0.'

-are-not-app 14 cable.J0therwise, be in HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b. With one main steam line isolation system inoperable but closed, subsequent operation in MODES 2 or 3 may prcceed provided that the

. isolation system in the affected steam line is maintained closed.

The -prov4 s t ons-of-Specif4 cation-3,0A-ara-not-app 14cabl e.--. #

l c. With one main steam line isolation system inoperable but open, either

! close the OPERABLE isolation system or restore the inoperable system to OPERABLE status within 7 days. Othe mise 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 SHUTDOWN within the following

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

l SURVEILLANCE REQUIREMENTS

! 4.7.1.5 Each MSIV and MSIBV shall be demonstrated OPERABLE by verifying full

closure within 5 seconds ~when tested pursuant to Specification 4.0.5. Yhe l

( provisions of Specification 4.0.4 are not applicable for entry into MODE 3.

An OPERABLE main steam line isolation system can consist of an OPERABLE MSIV and an inoperable associated'HSIBV provided the inoperable MSIBV is maintained closed.

V0GTLE UNITS 1&2 3/4 7-9

PLANT SYSTEMS

( 3/4.7.9 SEALED SOURCE CONTAMINATION LIMITING CONDITION FOR OPERATION 3.7.9 Each sealed source containing radioactive material either in excess of 100 microcuries of beta and/or gamma emitting material or 5 microCuries of alpha emitting material shall be free of greater than or equal to 0.005 microcurie of removable contamination.

APPLICABILITY: At all times.

ACTION:

a. With a sealed source having removable contarination in excess of the ;

above limits, immediately withdraw the sealed source from use and i either:

1. Decontaminate and repair the sealed source, or

2. Dispose of the sealed source in accordance with Commission Regulations.

b.

TheprovisionsofSpecificatio$3.03-and3.0.4 /arenotapplicable.

(

SURVEILLANCE REQUIREMENTS 4.7.9.1 lest Requirements - Each sealed source shall be tested for leakage and/or contamination by:

a. The licensee, or

b. Other persons specifically authorized by the Commission or an Agreement State.

The test method shall have a detection sensitivity of at least 0.005

( microcurie per test sample.

4.7.9.2 Test Frequencies - Each category of sealed sources (excluding startup sources and fission aetectors previously subjected to core flux) shall be tested at the frequency described below.

a. Sources in use - At least once per 6 months for all. sealed sources-containing radioactive materials:

1) With a half-life greater than 30 days (excluding Hydrogen 3),

and

{' 2) In any form other than gas.

V0GTLE UNITS - 1 & 2 3/4 7-25 .

l

_ PLANT SYSTEMS

( 3/4.7.30 AREA TEMPERATURE MONITORING L1HITING CONDITION FOR OPERATION 3.7.10 The Maximum Normal Temperature of each area shown in Table 3.7-3 shall 5 not be exceeded for more than 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months and the Maximum Abnormal Temperature of Table 3.7-3 shall not be exceedad.

APPLICABILITY: Whenever the eqJipment in an affected area is required to be DPERABLE.

{

ACTION:

a. With one or more areas exceeding the Maximum Normal Temperature limit (s) shown in Table 3.7-3 for more than 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , prepare and submit to the Commission within 30 days, pursuant to Specifica- -

tion 6.8.2, a Special Report that provides a record of the cumulative time and the amount by which the temperature in the affected area (s) exceeded the limit (s) and an analysis to demonstrate the continued y OPERABIL}TY of the affect,ed equipment. The provisions of Specifi-catio@'3.0.3 and-3,0Alare not applicable.

b. With one or more areas exceeding the Maximum Abnormal Temperature

( limit (s) shown in Table 3.7-3 prepare and submit a Special Report as required by ACTION a. above and within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months either restore the area (s) to within the temperature limit (s) or declare the equip-ment in the affected area (s) inoperable.

SURVEILLANCE REQUIREMENTS 4.7.10 The temperature in each of the areas shown in Table 3.7-3 shall be determined to be within its limit at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

(

C C

V0GTLE UNITS - 1 & 2 3/4 7-27

- _ _ _ . . - - - - - - - - - - _ ---- . _ . - J

i 3/4.8.4 ELECTRICAL EQUIPMENT PROTECTIVE DEVICES ;

k CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTF.CTIVE DEVICES AND FEEi+R BREAAERS TO ISOLATION TRANSFORMER 5 BETWEEN 480 V CLASS 1E BUS $E5 AND NONi'~

CLASS lE EQUIPMENT LIMITING CONDITION FOR OPERAT)0N ,

. _. I 3.8.4.1 All containment penetration conductor overcurrent protective devices and feeder breakers to isolation transformers between 480 V Class IE busses and non Class IE equipment shall be OPERABLE.

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

(. ACTION: ,

With one or more of the containment penetration conductor overcurrent protective device (s) or feeder breakers to isolation transformers between 480 V Class IE busses and nen Class 1E equipment inoperable:

a. Restore the protective device or feeder breaker to OPERABLE status or deenergize the circuit (s) by racking out, locking open, or removing.

the inoperable circuit breaker or protective device and tripping the associated backup circuit breaker within 72 hourt, declare the affected system or component inoperable, and verify the inoperable circuit removed breaker at leastoronce protective per 31 device racked days thereaf out, locked openefor Y ter;-the-previs40n

( -Specification 3A4-are-not-app 14 cable 40-overcurrent dev4ces-or-.M #j

-feeder-breakers in-circuits-which-have-their-backup-c4rcutt-breaker

-tr4ppedr-their- inoperable-circuit-breakers-racked-oukr-or-r+ moved / +dr '

b. Deenergize the circuits by racking out, locking open, or removing the inoperable circuit breaker or protective device within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , '

declare the affected system or component inoperable, and verify the

' inoperable circuit breaker or protective device racked out, locked open or removed at least once per 7 days thereafter;-the-prev 4s4 ens #

-of-Specif4 cat 4ca-3A4-are-not-app 14eable-to-cnrcurr+nt-dev4ces--or #

-fesder-breakers in-circuits-whichrhave-their-inoperable-c4r-cuit-- p'

- b rea ke r-rac ke d-outgr-removed /lir ,

( c. 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 .

SUdVEILLANCE REQUIREMENTS ,

( 4.8.4.1 All containment penetration conductor overcurrent protective devices and feeder breakers to isolation transformers between 480 V Class IE bushes and non Class IE equipment shall be demonstrated CPERABLE:

a. At least once per 18 months:

' ( 1) By verifying that the 13.8 kV ch cuit breakers are OPERABLE by selecting, on a rotating basis, at least ore of the circuit breakers, and perforting the following:

V0GTLE UNITS - 1 & 2 3/4 P-19

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

REFUELING OPERATIONS

_ 3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE AREAS !

LIMITING CONDITION ,F_0R OPERATION 3.9.7 Loads in excess .of 2300 pounds shall be prohibited from travel over fuel assemblies in the storage pool.

APPLICABILITY: With irradiated fuel assemblies in the storage pool.

( ACTION: ,

a. With the requirements of the above specification not satisfied, place ,

the crane load in a safe condition.

b. The provisions of Specificatio 0.3 e M 3.0 3 re not applicable.

(

SURVEILLANCE REQUIREMENTS 4.9.7 Crane interlocks and physical stops which prevent crane travel with

loads in excess of 2200 pounds over fuel assemblies shall be demonstrated ,

OPERABLE within 7 days prior to crane use and at least once per 7 days i thereafter during crane operation.

l . . .

C .

O .

V0GTLE' UNITS - 1 & 2 3/4 9-7

_.____.__,.._..__..._,._..__.__.__._..___,._.u.- -

. _ . ~ - -

1 r

REFUELINGOPER,47103

$. 9. 9 CONTAINHENT VENTILATION !$0LATION $YSTEM i

LIMITING CONDITION FOR OPERATION '

j 3.9.9 The Containment Ventilation Isolat. ion System shall be OPERABLE. )

APPLICABIL11Y: During CORE ALTERATIONS or movement of irradiatec fuel within the containmeat.

ACTION:

i

a. With the Containment Ventilation Isolation System inoperable, close each of the Ventilation penetrations providing direct access from the centainment atmosphere to the outside atmosphere.

b. The provisions of Specificatio 0. 3 ed *. 0. ' re not applicable. I

?

SURVEILLANCE REQUIREMENTS 4.9.9 The Containment Ventilation Isolation System shall be demonstrated OPERABLE witMn 100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months prior to the start of and at least once per 7 days during CORE ALTERATIONS by verifying that contvinment ventilation isolation occurs on a Hfgh Radiation test signal from each of the containment radiation monitoring instrumentation channels (RE-0002, RE-0003 .RE-2565).

)

. 9-

-)

V0GTLE UNITS - 1 & 2 3/4 9-10

_ - . - . . _ , . . . . _ , _,......-.,_-~,....u,

._..-,__,.,[.,_ _

1 REFUEL 1HG OPERATIONS l

3/4.9.11 WATER LEVEL - STORAGE POOL LIMIT]NG CONDITION FOR OPERATION -

3,9.11 At least 23 feet of water shall be maintained over the top of irradiated fuel assemblies setted in the storage racks.

Appl 1CABIL17Y: Whenever irradiated fuel assembifes are. in the storage pool.

A$ TION: '

4. With the requirements of the above specification not satisfied, suspend all movement of fuel assemblies and crane operations over the sprat fuel pool and restore the veter level to within its limit '

within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

TheprovisionsofSpecificatiorf)3.0.3:nd3.0.iaren,otapplicable.

I b.

SURVEILLANCE REQUIREMENTS 4.9.11 The water level in the storage pool shall be deter.nined to be at least its minimum required depth at least once per 7 days when irradiated fuel assemblies are in the fuel storage pool.

l e

4 6

e G

4

.9 l V0GTLE UNITS - 1 & 2 3/4 9-13 l-

RErVELING OPERA 7!ONS 3/4.9.12 FUEL HANDLING BUILO!NG POST ACCIDENT VENTILATION SYSTEM (COMON $YSTEM) j L1H] TING COND,jTION FOR OPERATION 3.9.12 Two independent Fuel Handling Building Pnst Accident Ventilation I Systems shall be OPERABLE.

AfPLICAB1(ITY: Whenever irradiated fuel is in either storage pool.

ACTION:

e. With one Fuel Handling Building Post Accident Ventilation System inoperable, fuel movement within either storage pool or crane opera-tion with loads over either storage pool may proceed provided the OPERABLE Fuel Handling Building Post Accident Ventilation System is capable of being powered from an OPERABLE emergency power source and is in operation and discharging through at least one train of HEPA filters and charcoal adsorbers,

b. With no Fuel Handling Building Post Accident Ventilation System OPERABLE, suspend all operations involving movement of fuel within either storage pool or crane operation with loads over either storage pool until at least one Fuel Handling Building Post Accident Ventilation System is restored to OPERABLE status.

c. The provisions of Specificatio 3.0.3 = d 3.0.' re not applicable.

-1 I

l SURVEILLANCE REOUIREMENTS

l. i 4.9.12 The above reasired Fuel Handling Building Post Accident Ventilation Systems shall be demonstrated OPERABLE:

\

i

a. Atleastonceper31daysonaSTAGGEREDTESTBASISbyinitiating, from the control room, flow through the HEPA filters and charcoal l

adsorbers and verifying that the system operates for at least g_

10 continuous hours with the heater control circuit energizedi

b. At least once per 18 months or (1) after any structural saintenance on the HEPA filter or charcoal adsorber housings, or (2) following painting, fire, r chemical release in any ventilation zone "

communicating witn the system by: ,

V0GTLE UNITS 1&2 3/4 9-14 .

9 W

e m==

y , . . . _ . ...y.-, .r.

3/4.11 RADIDACTIVE EFFLUENTS

(

3/4.11.1 LIQUID EFFLUENTS ' '

CONCENTRATION LIMITING CONDITION FOR OPERATION L^

3.11.1.1 The concentration of radioactive material released in liquid eff Nents to' UNRESTRICTED AREAS (see Figures 5.1-1 and 5.1-2) shall be limited to the concentrations specified in 10 CFR Part 20, Appendix 8. Table II, Column 2 for radionuclides other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2 x 10 4

( microcurie /ml total activity. -

APPLICABILITY: At all times.

ACTION:

a. With the concentration of radioactive material released in liquid effluents to UNRESTRICTED AREAS exceeding the above limits, immedi-ately restore the concentration to within the above limits.

b. The provisions of Specificatio 3. 0. 3 4nd-3AA re not applicable.

SURVEILLANCE REQUIREMENTS 4.11.1.1.1 Radioactive liquid vastes shall be sampled and analyzed according to the sampling and analysis program of Table 4.11-1.

4.11.1.1.2 The results of the radioactivity analyses shall be'used in accordance with the methodology and parameters in the ODCM to assure that the concentrations at the point of release are maintained within the limits'of Specification 3.11.1,1.

e

(~ -

lC C.

4 V0GTLE UNITS - 1 & 2 3/4 11-1

I i

RADIDACTIVE EFFl0ENTS EE.1E L!_MITING CONDITION FOR OPERATION 3.11.1.2 The dote or dose commitment to a MEMBER OF THE PUBLIC from radioactivw mater'ials in liquid effluents released, from each unit, to UNRESTRICTED AREAS :

(see Figures 5.1-1 and 5.1-2) shall be limited: ,

s. During any calendar quarter to less than or equal to 1.5 arems to i the whole body and to less than or equal to 5 arems to any organ, and

b. During any calendar year to less than or equal to 3 arems to the .

whole body and to less- than or equal to 10 mreas to any organ. l APPLICABILITY: At all times.

s ACTION:

it

a. With the calculated drese from the release of radioactive materials in liquid ef fluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Specifipation 6.8.2, a Special Report that identifies the cause(s) for exceeding '

the limit (s) and defines the corrective actions that have been taken to reduce the releases and the proposed corrective actions to be taken to assure thtt subsequent releases will be in compliance with the above limits.

b. Theprovisions'ofSpecification@f3.0.3and3.Or*I sre not applicable.

SURVEILLANCE REQUIREMENTS J.11.1.2 Cumulative dose contributions from liquid et,.uents for the current calendar quarter and the current' calendar year shall be determined in accordance with the methodology and parameters in the ODCH at least once per 31 days.

.' e e

.V0GTLE UNITS - 1 & 2 3/4 11-5

RADIDACTIVE EFFLUENTS 1

L10010 RADWASTE TREATMENT SYSTEM LIMITING CONDITION FOR OPERATION 3.11~1.3 fhe Liquid Radwaste Treatment System shall be OPERABLE and appropriate )

portions of the system shall be used to reduce releases of radioactivity wher.

the projected doses due to the liquid effluent, from each unit, to UNRESTRICTED AREAS (see Figures 5.1 1 and 5.1 2) would exceed 0.06 mrem to the whole body or 0.2 arem to any organ in a 31-day period.

APPLICABILITY: At all times.

ACTION:

a. With radioactive liquid waste being discharged without treatment and in excess of the above limits and any portion of the Liquid Radweste Treatment System not in operation, prepare and submit to the Commis-sion within 30 days, pursuant to Specification 6.8.2, a Special Report that includes the following informations a

1. Explanation of why liquid radwaste was being discharged without treaticent, identification of any inoperable equipment or subsystems, and the reason for the inoperability, ,

2. Action (s) taken to restore the inoperable equipment to OPERABLE status, and

3. Summary description of action (s) taken to prevent a recurrence,

b. The prevtsions of Specificatio 3.0.3 r.d 3.0.' re not applicable.

SURVEILLANCE REQUIREMENTS .,

4.11.1.3.1 Doses due to liquid releases from each unit to UNRESTRICTr0 AREAS ,

shall be projected at.least once per 31-days in accordance with tha methodology l and parameters in the ODCM when Liquid Radwaste Treatment Systems are not being ~

fully utilized. .

~

4.11.1.3.2 The installed Liquid Radwaste Treatment System shall be j considered OPERABLE by meeting Specifications 3.11.1.1 and 3.11.1.2.

h, l

- s V0GTLE UNITS - 1 & 2 3/4 11-6

4 e RADI0 ACTIVE EFFLUENTS LIQUID HOLDUP TANK $

LIMITING CONDITION FOR OPERATION , _

3.11.k. ' The quantity of radiosctive material contained in each outside f temporary ;ank shall be limited to less than or equal to 10 curies, excluding s

tritium and dissolvad or entrained noble gases.

APPLICABILITY: At all times.

ACTION:

a. With the quantity of radioactive material in any of the outside temporary tanks exceeding the above limit, immediately suspend all additions of radioactive material to the tank, within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months reduce the tank contents to within the limit, and describe the events leading to tnis condition in the next Semiannual Radioactive Effluent Release Report, pursuant to Specification 6.8.1.4. g

b. TheprovisionsofSpecificatioq{f3.0.3:nd3.0.'arenotapplicable.

SURVEILLANCE REQUIREMENTS 4.11.1.4 The quantity of radioactive material contained in each of the above listed tanks shall be determined to be within the above limit by analyzing a representative sample of either the tank's contents at least once per 7 days when radioactive materials are being added to the tank or each batch of radio-active material prior to its addition to the tank. .

l e

V0GTLE UNITS - 1 & 2 3/4 11-7

. . RAD 10 ACTIVE EFFLUENTS J/4.11.2 GASEOUS EFFLUENTS : .

ESERATE j'. HIT]NGCONDITIONFOROPERATION 3.11.2.1 The dose rate due to radioactive materitis released in gaseous )

effluents from the site to areas at ar1 beyond the SITE SOUNDARY (see Figures 5.1 1 and 5.1 2) shall oe limited to the following:

a. For noble gases: Less than or equal to 500 mrems/yr to the whole body and less than or equal to 3000 mrams/yr to the skin, and

b. For lodine-131, for Iodine 133, for tritium, and for all radio- -

nuclides in particulate forn with half-lives greater than 8 days:

Less than or equal to 1500 arems/yr to any organ.

APPLICABILITY: At all times.

ACTION:

a. With the dose rate (s) exceeding the ab6ve limits, immediately restore the release rate to within the above limit (s),

b. The provisions of Specification . 0.3 end L O.' re not applicable.

SURVE!LL Af t E REQUIREMENTS _

4.11.2.1.1 The dose rate due to noble gases in gaseous effluents shall be determined to be within the above limits in accordance with the methodology and parameters in the ODCM.

4.11.2.1.2 The dose rate due to lodine 131. Iodine-133, tritium, and all- -

radionuclides in particulate form with half-lives greater than 8 days in gaseous offluents shall be determined to be within the above limits in accordance with the methodology and-parameters in the ODCM by obtaining representative samples and performing analyses in accordance with the sampling and analysis program specified in Table 4.11,2.

V0GTLE UNITS - 1 & 2 3/4 11-8 Sp 4 .

4

..w- , , . ~ . _ , , v.. . . . . ---2, ..s- - - - . - . - , - n- -- -- . . . e-

t

.RADI0 ACTIVE EFFLUENTS :

r DOSE - N0BLE GASES 1 !

LIMITING CONDITION FOR OPtxATION 3.11.2.2 The air dose due to nobit gases released in gaseous effluents, from !

each unit, to areas-st and beyond the $1TE BOUNDARY (see-Figures 5.1-1 and 5.1-2) shall be limited to the following:

)

L

a. During any calendar quarter: Less than or equal to 5 mrads for >

gamma radiation and less than or equal to 10 mrads for beta radiation, and

b. During any calendar year: Less than or equal to 10 mrads for gamma radiation and less-than or equal to 20 mrads for beta radiation.

APPLI(ABILITY: At all times. .. .

ACT!/)N ,

I

a. With the calculated air dose from radioactive noble gases in gaseous effluents exceeding any of the above--limits, prepare and submit to the Commission within 30 days, pursuant to Specification 6.8.2, a .

Special Report that identifies the cause(s) for exceeding the limit (s) and defines the corrective actions that have been taken to reduce ,

the releases and the proposed corrective actions to be taken to '

assure that subsequent releases will be in compliance with the above '

limits,

b. The provisions of Specificatle . 0. 3 4ad-AC,N re not-applicable.

SURVEILLANCE RE00!REMENTS _

]

4.11.2.2 Cumulative dose contributions for the' current: calendar quarter and.

current calendar year for noble gases shall be determined in accordance with the methodology and parameters in the 00CM at least once pee 31 days.

)

f.

k, V0GTLE UNITS .1 & 2 3/4 1192 .

L Die e

-,iw-+ . , - ,, ,v4-~ ,- ,--..r....,,,,.y..y%-_,,y _,._,y.,.y ~.,,,,,,,,.w,- , .,,wm,ry.u..w.,,,,cw,_,m...,,m ._ n,-----

RADIDACTIVE EFFLUENTS DOSE - 2001NE-131, 10 DINE-133, TRITIUM, AND RADI0 ACTIVE MATERIAL IN PARTICULATE FORM LIMITING CONDIITON FOR OPERATION

( 3.11.2.3 The dose to a MEM M OF THE PUBLIC from Iodine-131. Iodine-133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluents released, from each unit, to areas at and beyond the SITE BOUNDARY (see Figures 5.1-1 and 5.1-2) shall be limited to the following:

a. During any calendar quarter: Less than or equal to 7.5 mrems to any '

organ and,

b. During any calendar year: Less than or equal to 15 mre.ns to any organ.

APPLICABILITY: -At all tirnes. g ACTION:

a. With the calculated dose from the release of Iodine-131, lodine-133, tritlum, and radionuclides in particulate form with half-lives greater than 8 days, in gaseous effluents exceeoing any.cf the above limits, prepare and submit to the Com:nission within 30 days, pursuant to Specification 6.8.2, a Special Report that identifies the cause(s) for exceeding the limit (s) end cofines the corrective actions that have been taken to reduce the releases and the proposed ccrrective actions to be taken to assure that subsequent releases will be in compliance with the above limits,

b. The provisions of Specificatio 3.0.3 ed-3A4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.3 Cumulative duse contributions for the current calendar quarter and current calendar year for lodine-131, Iodine-133, tritium and radionuclides in particulate form with half-lives greater than 8 days thall be determined in accordance with the methodology 6nd parameters in the ODCM at least once per 31 days.

l l

v0GTLE UNITS - 1 & 2 3/4 11-13

JAD!0ACTIVEEFFLUENTS CA.(EOUS RADWASTE TREATMENT SYSTEM j LIMITING CONDITION FOR OPERATION 3.11.2.4 The VENTILATION EXHAUST TREATMENT SYSTEM and the SASE005 WASTE PROCESSING SYSTEM shall be OPERABLE and appropriate portions of these systems )

shat 1 be used to reduce releases of radioactivity when the projected doses in 31 days due to gaseous effluent releases, from each unit, to areas at and beyond the SIT.E BOUNDARY (see Figures 5.1-1 and 5.1-2) would exceed:

a. 0.2 mrad to tir from gamma radiation, or ,

b. 0.4 mrad to air from beta radiation, or

c. 0.3 mrem to any organ of a MEMBER OF THE PUBLIC, APPLICABILITY: At all times.

ACTION:

a. With radioactive gaseous waste being discharged without treatment and in excess of the above limits, prepare and submit to the Commission within 30 days pursuant to Specification 6.8.2, a Special Report that includes the following information:

1. Identifir.ation of any inoperable equipment or subsystems, and the reason for the it perability,

2. Action (s) taken to restore the inoperable equipment to OPERABLE status, and

3. Summary description of actior,(s) taken to prevent a recurrence,

b. The provisions of Specificatio .0.3 :nd 3.0.' are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.4 Doses due to gaseous releases from esch unit to areas at and beyond the SITE BOUNDARY shall be projected at least once per 31 days in accordance with the methodology and parameters in the ODCM when Gaseous Radwaste Treatment-Systems are nut being fully utilized.

(

i e I V0GTLE UNITS - 1 & 2 ,

3/4 11-14

RADI0 ACTIVE EFFLUENTS EXPLOSIVE GAS MIXTURE ,

LIMITING CONDITION FOR OPERATION 3.11.j.5 The concentration of oxygen in the GASEOUS WASTE PROCESSING SYSTEM shall be -limited to less than or equal to 2% by volume whenever the hydrogen concentration exceeds 4% by volume.

APPLICABILITY: At all times.

ACTION:

a. With the concentration of oxygen in the GASEOUS WASTE PROCESSING SYSTEM greater than 2% by volume but less than or equal to 4% Dy volume, reduce the oxygen concentration to the above limits within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months . -

b. With the concentration of oxygen in the GASEOUS WASTE PROCESSING SYSTEM greater than 4% by volume and the hydrogen concentration greater than 4% by volume, immediately suspend oxygen addition and all additions of waste gases to the system and reduce the concentra-tion of oxygen to less than or equal to 4% by. volume, then take ,

ACTION a., above.

/

c. TheprovisionsofSpecificationd)43.0.3and?.0.'g/ are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.5 TheconcentrationsofhydrogenandoxygenintheGASEbUSWASTE PROCESSING SYSTEM shall be determined to be within the above limits _by continu-ously monitoring the waste gases in the GASEOUS WASTE PROCESSING SYSTEM with the hydrogen and oxygen monitors required CPERABLE by Table 3.3-10 of Specification 3.3.3.10.

V0GTLE UNITS - 1 & 2 3/4 11-15

RADI0 ACTIVE EFFLUENTS GAS DECAY TANKS )

LIMITING CONDITION FOR OPERATION 3.11.2.6 The quantity of radioactivity contained in each gas decay tank shall be k4mited to less than or equal to 2.0 x 105 curies of noble ga.as (censidered )-

as Xe-133 equivalent).

APPLICABILITY: At all times.

ACTION:

a. With the quantity of radioactive material in any gas decay' tank exceeding the above limit, immediately suspend all additions of radioactive material'to the tank, within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months tvduce the tank contents to within the limit, and describe the events leading to this condition in the next Semiannual Radicactive Effluent Release Report, pursuant to Specification 6.8.1.4.

b. The provisions o.' Specification {f3.0.1 ach'3.0 *)are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.6 The quantity o. radioactive material contained in each gas decay _

tank shall be determined to be within the above limit at least once per.24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when radioactive materials have been added to the tank during the previous 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

l <

t V0GTLE UNITS - 1 & 2 3/4 11-16

~

- w-,,w- y w- 9 y 9 v--

..s . .-+-se.n a -

.mu.., -

8- s-n n .- a.--a v u - ---e an- a n s.s- g -e .u.on...w+n-w.~.-au.-.--

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N RADI0 ACTIVE EFFLUENTS :

.3/4.11.3 SOLID RADIDACTIVE-WASTES LIMITING CONDITION FOR OPERATION 3.11 3 R6dioactive wastes-shall be solidified or dewatered in accordance with the P.ROCESS CONTC L PROGRAM to aeet shipping and transportation requirements during transit, and disposal site requirements when received at the disposal site.

APPLICABILITY: At all times. ,

ACTION:

a. With SOLIDIFICATION or dewatering not meeting disposal site and shipping and transpo*tation requirements, suspend shipment of the inadequately processed wastes and correct _the PROCESS CONTROL PROGRAM,_

the procedures, and/or the Solid Waste System as ns.:essary to prevent recurrence,

b. With SOLIDIFICATION or dewatering not performGd in.accordance with sed waste in the eachPROCESS CONTROL PROGRAM, testground the improperly procep,d' shipping container to ensure that 'it meets burial an requirements and take appropriate administrative action to prevent-recurrence. / f

c. The provisions of Specification 3. 0. 3 -d ' ^ ' $renotapplicable.

SURVEILLANCE REQUIREMENTS-4.11.3 SOLIDIFICATION of at least one representative test specimen from at least every tenth batch of each type of wet radioactive _ wastes.(e.g.,' filter

!~ sludges, spent resins, evaporator bottoms, boric acid solutions,=and-sodium sulfate solutions) shall be verified in accordance-with the PROCESS CONTROL ~

PROGRAM:

a. If any test specimen fails to< verify SOLIDIFICATIDN,: the SOLIDIFICATION of the batch under test shall be suspended until such' tis.e as additional test specimens _can be'obtained.-alternative SOLIDIFICATION parameters can be determined in accordance with the. PROCESS CONTROL fROGRAM, and a subsequent test. verifies SOLIDIFICATION. tSOLIDIFICATION of-

~

the batch may then be: resumed using the alternative SOLIDIFICATION parameters determined by:the PROCESS CONTROL PROGRAM;

b. If the initial test specimen from.a batch of_ waste failsito verify

_. SOLIDIFICATION, the' PROCESS CONTROL PROGRAM shall provide for.the collectioniand testing of representative test specimens:from:each consecutive batch of the same type of. wet waste until at least three.

consecutive 11nitial test specimens demonstrate SOLIDIFICATION.

The PROCESS CONTROL PROGRAM shall be modified as required, as.provided in SpecificatiorJ6.12, to' assure SOLIDIFICATION of-subsequent batches of waste; and'

c. With the installed equipment incapaole of meeting Specification -

-+ 3.11.-3 or declared inoperable.,restorf the equipment'to OPERABLE status or provide:for contract capability to process wastes as '

necessary to satisfy all applicable transportation and disposal-requirements. .

[V0GTLE UNITS =1 & 2 3/4 11-17

RAD 10 ACTIVE EFFLUENTS 3/4.11.4 TOTAL DOSE ,

LIMITING CONDITION FOR OPERATION ,

3.11.4 The annual (calendar year) dose or dose commitment to any MEMBER OF' THE PUBLIC due to releases of radioactivity and to radiation from vranium fuel- )

cycle sources shall be limited to less than or equal to 25 areas to the whole-body or any organ, except the thyroid, which shall be limited to less than or equal to 75 arems. ,

APPLICABILITY: At all times. .

ACTION:

a. With the calculated doses from the release of radioactivv materials in liquid or gaseous effluents exceeding twice the limits of Specifi-catior 3.11.1.2a., 3.11~.1.2b., 3.11.2.2a., 3.11.2.2b., 5.11.2.3a., or 3.11.2.3b., calculations shall be made including direct radiation contributions from the unit (including outside storage _ tanks etc.)_

to determine whether the above limits of Specificatlon 3.11.4 have been exceeded. If such is the case, prepare and submit to.the Commis-sion within 30 days, pursuant to Specification 6.8.2, a Special Report that defines the corrective action to be taksn to reduce subsequent releases to prevent recurrence of exceeding the above limits and-includes the schedule for ach hving conformance with the above limits. This Special Report, as defined in-10 CFR 20.405(c),

shall include an~ analysis that estimates the radiation' exposure-(dose) to a MEMBER OF.THE PUBLIC from uranium fuel cycle sources, including all ef fluent pathways and direct-rcdiation,'for the. calendar year that includes the release (s) covered by this report. It shall also describe levels of radiation and concentrations of radioactive material involved, and the cause of-the exposure levels or concentrations.. If the-estimated dose (s)-exceeds the above. limits', and if the release condition resulting in violation of 40 CFR Part 190 has not already been corrected, j

the Special Report shall iglude a request for a variance in accor .

dance with the provisions o 40 CFR Part 190. Submittal of:the report is corsidered a timely request, and a variance.~1s. granted until-staff l

L action on the request is complete,

b. The provisions of Specification @ 3.0.3 :M 3 a.' are not applicable.

. SURVEILLANCE REQUIREMENTS

'4.11.4.1 Cumulative dose contributions from liquid and gaseous effhsents-shall be determined in accordance with Specifications 4.11.1.2, 4.11.2.2, and 4.11.2.3, and in accordance with the methodology _and parameters in the ODCM.

l 4.11.4.2- Cumulative dose contributions from direct radiation from-each unit

-(including outside storage tanks etc.) shall be determined in-accordance with the methodology and parameters in the ODCM. This requirement is applicable only under conditions. set forth in ACTION a. of Specification 3.11.4. .

s 4

4 V0GTLE UNITS - 1 & 2 3/4 11-18 .

,,,e ,,, -m,s ---s e v - w -g,w ,m--

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

RADIOLOGICAL ENVIRONMENTAL MONITORING LIMITING CONDITION FOR OPERATION )

ACTION (Continued),

c. With milk or vegetation samples. unavailable- from one or more of the sample locations required by Table 3.12-1, identify specific locations for obtaining replacement samples and add them within 30 days to the )

Radiological Environmental Monitoring Program given in the ODCM - The specific-locations from which samples were unavailable may then be deleted from the monitoring program. Pursuant to Specification-6.13, submit in the next Semiannual Radioactive Effluent Release Report documentation for a change in the ODCM including a revised figure (s) )

and table for the ODCM reflecting the new location (s) with supporting information identifying the cause of:the unavailability of samples and justifying the selection of the new location (s) for obtaining samples.

d. The provisions of Specificatio 0. 3 and 3. 0. 8 9are not applicable.

SURVEILLANCE REQUIREMENTS 4.12.1 The radiological environmental monitoring samples shall be collected pursuant to Table 3.12-1 from the specific locations' given in the table and figure (s) in the ODCM, and shall be analyzed pursuant to the requirements of !

Table 3.12-1 and the detection capabilities required by Table 4.12-s

)

.)

?

L ' V0GTLE UNITS - 1 & 2 3/4 12-2

RADIOLOGICAL ENVIRONMENTAL MONITORING

-3/4.12.2 LAND USE, CENSUS LIMITING CONDITION FOR OPERATION 3.12.2 A Land Use Census shall be conducted and shall identify within a distance of 5 alles the. location in each of the 16 meteorological sectors of the nearest milk animal, the nearest residence, and the nearest garden of greater than 500 ft2 producing broad leaf vegetation. Land within the Savannah River Plant may be excludad from this survey.

APPLICABILITY: At all times.

ACTION:

a. With a Land Use Census identifying a location (s) that yleids a calculated dose or dose commitment greater than the values currently being calculated in Specification 4.11.2.3, pursuant to Specifica-tion 6.8.1.4, identify the new location (s) in the next Semiannual Radinactive Effluent Release Report. ,

b. With a Land Use Census identifying a location (s) that yields a ,

calculated dose or dose commitment (via the same exposure pathway) i 20% greater than at a location from which samples are currently being obtained in accordance with Specification 3.12.1, add the new location (s) within 30 days to the Radiological Environmental Moni-toring Program given in the 00CM, if samples are available. The sampling location (s), excluding the control station location, having the lowest calculated dose or dose commitment (s), via the same expo-sure pathway, may then be deleted from this monitoring program. Pur -

suant to Specification 6.13, submit in the next Semiannual Radioactive Effluent Release Report documentation for a change in the ODCM includ-ing a revised figure (s) and table (s) for the ODCM reflecting the new location (s) with information supporting the change in sampling locations.

c. The provisions of Specificatio 5.0.3 = d 3.C.i are not applicable.

l I

SURVEILLANCE REQUIREMENTS l .

l l 4.12.2 The Lar.d Use Censu~s shall be conducted during the growing season at least once per 12 months using that information that will provide good results, such.as by a door-to-door survey, by visual survey from automobile or aircraf t, by consulting local agriculture authorities, or by some combination of these methods as feasible. The resulti, of the Land Use Census shall be included in l

the Annual Radiological Environmental Surveillance Report pursuant to Specification 6.8.1.3.

l V0GTLE UNITS - 1 & 2 3/4 12-13

l RADIOLOGICAL ENVIRONMENTAL MONITORING l

3/4.12.3 INTERLABORATORY COMPARISON PROGRAM LIMITING CONDITION FOR OPERATION 3.12.3 Analyses sht11 be performed on all radioactive materials, supplied ac i part of an Interlaboratory Compariton Program that has been approved oy the r Commission, that correspond to sampics and analysis required by Table 3.12-1.

APPLICABILITY: At all times.

ACTION:

a. With analyses not being perfereed as required above, report the corrective actions taken to prevent a recurrence to-the Commission in the Annual Radiological Environmental Surveillance Report pursuant to Specification 6.8.1,3.

k

b. TheprovisionsofSpecification$3.0.3:nd3.0.4arenotapplicable.

SURVEILLANCE REQUIREMENTS 4.12.3 The Interlaboratory Compsrison Program shall be described in the ODCH.

A summary of the results obtained as part of the above required Interlaboratory Comparison Program shall be. included in the Annual Radiological Environmantal Surveillance Report pursuant to Specification 6.8.).3.

i h

V0GTLE UNITS - 1 1 2 . 3r 12-14

4 4 .

3/4.0 APPLICABILITY

-1ASES

\ /

The specifications of this section provide-the~ general _ requirements; appl able to each'of the Limiting Conditions:for:0peration.and Surveilla e ents within Section 3/4. In the event.of a disagreement betwee the Requi require nts stated in these Technical Specifications and those: stated n an applicabl Federal Regulation or Act,-the requirements stated in the pplicable Federal Re lation or Act shall take precedence and shall be met.

3.0.1 is specification defines the applic. ability of each ecification in terms of de ned OPERATIONAL MODES or other specified condit ns and.is~ pro-vided to delinea a specificallywheneachspecification-isap/picable.

3.0.2 This s cification defines those conditions nec9ssary to constitute compliance with the erms of an individualnLimiting Condit bn for Operation and associated ACTION req rement. ;

3.0.3 . The_ specific tion delineates the measures be taken for those circumstances not direct 1 provided for in the ACTIO statements ~and whose ,

occurrence would. violate th intent ofia decificat n. , For example,:Specifica-tion 3.5.2 requires two inde ndent ECCS subsyste to be OPERABLE and provides explicit ACTION requirements.i 'one ECCS-subsyst is inoperable. Under the requirements of Specification 3. 3, if both t ; required ECCS subsystems are inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months measure must be in' iated to-place tha_ unit in at1 least HOT STANDBY within the next' hours, d'in at-least HOT SHUTDOWN within .

the fo11owing-6 hours. As a further xampJe,LSpecification 3.6.2.1 raquires '

two Containment Spray Systems to be O Rp5LEandprovidesexplicitACTION-requirements-if one Spray System is ino rable. -_Under the requirements of.

, Specification 3.0.3,-if both the requ e ontainment:. Spray Systems are-inoper-able, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months measures must be initi ed to place the uni.t.in.at least

-HOT STANDBY within the next 6 hour6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , in.at 1 stLHOT SHUTDOWN within the: follow-ing 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ,-and in COLD SHUTDOW within_the s bsequent 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .- Ittis accept-able to initiate and complete a eduction in OP ATIONAL MODES in a: shorter time. -

interval than' required;in the- TION, statement an to add the unused portion ofL this allowable out-of-servic time to that' provide 'for operation.in subsequent -

lower OPERATION H0DE(S). S ated allowable out-of-se vice-times are applicable-regaroless oflthe_0PERATI AL MODE (S) in which the in erability is discovered but the times provided f r achieving a mode: reduction a not! applicable if-the inoperability is disco red in a~ mode lower than-the app ' cable. mode. For exem-ple if the Containme Spray. System was discovered to be i perable while :in -

t_

STARTUP,: the - ACTION tatement would allow.up to'156l hours)to chieve COLD SHUT- -

DOWN. If HOT-STA BY-is= attained in 16-hours rather than the 110wed 78 hours9.027778e-4 days 0.0217 hours 1.289683e-4 weeks 2.9679e-5 months , L- 140 hours0.00162 days 0.0389 hours 2.314815e-4 weeks 5.327e-5 months would ill be'available before the plant would be re ired to be in p COLD SHUTDOWN- owever, if this system wr.s' discovered to be inop able while'ini u HOTiSTANDBY,- e--6 hours provided to achieve HOT STANDBY would not e additive i to the' time vailable.to achieve COLD SHUTDOWN so that the total al able time-L is reduced rom:156 hours to 150 hours0.00174 days 0.0417 hours 2.480159e-4 weeks 5.7075e-5 months .

3.0 4 - This: specification provides that entry into an OPERATIONAL DE or

, other ecified applicability condition must be made withi .(1) the full' mple-ment- f required systems, equipment, or: components.0PERABLE and (2) all ot r; par eters as specified .in the_ Limiting Conditions .fer Operation being met w' hout-regard for-allowable deviations'and out-of-service provisions containe

' 'the ACTION-statements.

lV0GTLE UNITS - 1:& 2 B 3/4 0-1

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

~. .

3/4.0 APPLICABILITY BASES NThe intent of this provision is to ensure that facility operation is r' with either required equipment or syster.s inoperabin er et _speci-initist iqs axceeded.

)

f[edlimits ~s.

Exceptions to thlisprovision have been providedJ a limited number of it would specifications when startu Np h inoperable equ ION statements not affect plant rafety. These exceptions are s in th of the appro-priate specifications.

3.0.5 This specifica delineates the a cability of each specifica-operations. In order to a the Technical Specifica-tion to both Unit I a specification, tions as clear a oncise as possible the provisions of including t miting Condition for Operation and associated require-ments, a e equally applicable to Ur.it 1 or Unit 2 unless a speciff tion ja-noted within the specification.

. 4 l

l l

\ .

l V0GTLE UNITS - 1 & 2 . B 3/4 0-1a

APPLICABILITY .

BASES 4.0.1 This- specification provides that surveillance activities necessar to nsure the Liatting Conditions for Operation are met and will be.perfo duri the OPERATIONAL MODES or other conditions for which the Limiting e _Co di .

tiens or Operation are applicable.- Provisions for additional-surveilla DES- i activit sonditionsto be-perfomed without regard to the applicable OPERATIONA ments.-

er other are provided in the individual Surveillance Requi Surveillan't Requirements for Special-Test Exceptions need only be an p rformed when the_ Spe ial Test-Exception is being utilized as' an exception individual sp ification. -

4.0.2 The revisions of this specification provide allow nlethe td er'ances_

nominal for performing su eillance activities beyond those'specified These tolerances are necessary to prions. vide The operational surveillance inter 1. phrase flexibility because .f scheduling and performance consideret negate this 3 "at least" associatt9 ith a surveillance frequency doese and pemits the perfor allowable tolerance va surveillance activities.'

The allowable toleran alsoprovidesflexibi1}ytoaccommodatethe erformed at each refueling-length of a fuel cycle for s rveillances that are ance interval.9 It is not-outage and are specified-witn n 18 month:s avei 5-a convenience-to extend-intended'that this provision be used repeatedlyspecified f r-surveillances .that are n surveillance intervals beyond th The-lim ation of' Specification 4.0.2.is-performed during refueling outages reco ition that the most probab e l

based on engineering judgment and t performed is the verificatinn of result of any particular surveillance be ents. This povision is sufficient conformance with-the Survcillance Requ rough surveillance activities is not-to ensure that the reliability ensure from the specified surveillance significantly degraded beyond that o ain ,

interval.

4.0.3 The provisions of t - thespecificat\nsetforththecriteriafor 0PERABILITY requirements of the Limiting determination of compliance Un wf r these criteria, quipment.: systems _or_compo-Conditions for Operation.

-nents'are assumed to be OPE LE if the associaten urveillance me interval. activities Nothinghav6 in-been satisfactorily perfor ed within the spe:ified-nstrued as defining equipme t, sy

~this provision is to be are found or known to be inop able although still OPERABLE when such item e Requirements. Items'may be.det reined inoperable meeting the Surveilla veillance tests, or in Accordance w h this specification.

during use, during's etivities-4.0.4 This ecification ensures.that the surveillance Limiting Condition for Operation-have been p rformed DE or other within associated with the specified ime interval prior to entry into' an OPERATIONALThe inten 1-dition.

l spplicable e its have been satisfactorily demonstre;ed on a curren ' basis as-lance activ meet the OPERABILITY requireme_nts-of--the Limiting Condit on for required Operatic .

lant nder the terms of this specification, for example, during initial STA UP or following extended plant outages, the applica L acing or returning the. system or equipment'into OPERABLE status. Am 8 3/4 0-2 V0GTLE UNITS - 1 &' 2 Amendment No.13 (Unit 2)

,,n., ;-r +.,.e,,,,,,:,,,- ,,-,,.,wn..r.,~ v..-+,w ,,4-,.w --g, v ,y-

, APPLICABILITY BASES 0.5 This specification ensures that inservice inspection of ASM ode

( Clas,s 1, and 3 components and inservice testing of ASME Code Class J, 2 and va 3 pumps version of and S he ion (lves willASME XI of the be performed Boiler and in Accordance Pressure Vessel with a periodic Cod and Addenda11y updated as required by 10 CFR s 50.55a. Relief from any of the above r uirements has been provided in wM ng by the Commission and is not a par of these Technical Specifications.

This specification i Nudes a clarification off he frequencies for per-forming the inservice inspect n and testing act #1 ties required by Section XI of the ASME Boiler and Pressu(re Y ssel Code apt) applicable ThisAddenda.

clarification is provided to ensur onsistency in surveillance intervals and to remove any ambiguities relative throughout these Technical Specificaticny , ired inservice inspection and test tothefrequenciesforperformingthey s

activities.

Under the terms of this 3pecification, the re restrictive requirements of the Technical Specificat)cns take precedence ove\the ASME Boiler and 1 Pressure Vessel Code andj pplicable Addenda. For examp , the requirements of Specification 4.0.4 tcyperform surveillance activities p r to entry into an OPERATIONALMOC;ofrther specified applicability conditio 4akes precedence overtheASMEB)1weekafterreturntonormaloperation.o be tested up to 4er Andand Pressure Vessel Code p

_ fohexample, the Technical Specification definition of OPERABLE does not grant a race period b.ef6re a device that is not capable of performing its specifie unction is dec1sre<1 inoperable and takes precedence over the ASME_ Boiler and Pre re Vesdl Code provision which allows a valve to be incapable of performing it -

ppecified function for up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months before being declared inoperable.

l l

G V0GTLE UNITS - 1 & 2 B 3/4 0-3

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REDUIREMJyli

, 3/4.0 APPLICABILITY BASES ,,

{pecifications 3.0.1 throuch 3.0.4 establish the general requiremergs-applicable to Limiting Conditions for Operation. These requirements are based en the requirements for Limiting Conditions for Operation stated in the Code of Federal Regulations,10 CFR 50.36(c) (2):.

Limiting canditions for operation are the lowest functional capability or performance levels of equipment required for safe operation of the facility. When a limiting condition.for_ operation for a nuclear reactor is not met, the licensee shall shut down the reactor or follow any remedial-action permitted by the technical specification until the condition.r.an-be met."

Specification 3.0.1 establishes the Applicability statemtnt within each individual specification as the requirement for when (i.e., in which OPERATIONAL MODES or other specified conditions) conformance to the Limiting-Conditions for Operation is required for-safe operation of the facility. The ACTION requirements est3blish those remedial measures that must be taken within specified time limits when the requirements of a Limiting Condition for Operation are not met.

y1 These are two basic types of ACTION requirements. The first specifies ihe remedial measures that permit continued coeration of the facility which is not T further restricted by the time limits of the ACTION requirements. In this FO .

case, conformante-to the ACTION requirements provides an acceptable level of safety for unlimited continued operation as long as the ACTION requirements- 4 y_

continue to be met. The second type;of ACTION requirement specifies a time l

limit in which conformance to the conditions of the Limiting Condition for y)

Operation must be met. This time limit is the allowable outage time to 9; R

restore an inoperable system or component to CPERABLE status or for_ restoring parameters within specified limits. If these actions are not completed within '

the allowable outage time limits,-a shutdown is required to_ place the facility i

in a MODE or condition in which the specification no longer applies. It is not intended that the shutdown ACTION requirements be used as an operational i convenience which pernits (routine) voluntary removal of a system (s) or-component (s) f rom service in lieu of other alternatives that would _not result in redundant systems or components being inoperable.

l The specified time limits of the ACTION requirements are applicable from the.

point in time it is identified that a Limiting Condition for Operation is not met.- The time limits of the ACTION requirements are also applicable when a ,

system or component is removed from service for surveillance testing or investigation of operational problems. Individual: specifications may include a specified time limit for the completion of ~s1 Surveillance Requirement when equipment is removed from service. In this case the allowable outage time-limits of the ACTION requirements-are applicable when this limit expires if the surveillance hat not been completed. . When a shutdown is' required to a

V0GTLE UNITS - 1 & 2 B 3/4 0-1

, --#,- 4>.-w-,.,w, e~, .

l i ,

3/4.0 APPjtCABILITY psts ._

temply with AC710N requirements, the plant may have entered a MODE in which a new specification becomes applicable.' In this case, the time limits of the AC110N requirements would apply from the point in time that the new specification becomes applicable if.the requirements of the Limitin~g Condition for Operation are not met. ~.

Specification ,0.2 establishes that noncomplianctwith a specification exists '

when the requirements of the' Limiting Condition for Operation are not met and the associated ACTION requirements have not been implemented within the specified time interval.- The purpose of this specification is to clarify that (1) implementation of the ACTION requirements withir. ihe specified time interval constitutes compliance with a specificatf Aand (2) completion of the remedial measures of the ACTION requirements is rot-required when compliance with a Limiting Condition of Operation-is restored within the time interval specified in the associated ACTION requirements.

Specification 3.0.3 establishes the shutdown ACTION requirements that must be implemented when a Limiting Condition for Operation is not opt and the condition-is not specifically addressed by the associated ACT'10N requirements.

The purpose of this specification is to delineate the time limits for placing the unit in a safe shutdown MODE.when plant operation cannot be maintained within the limits for safe operation defin6d by the Limiting Conditions for Operation and its ACTION requirements. It is not intended to be used as an {I .

operational convenience which permits (routine)-voluntary removal of redundant systems or components being inoperable. One hour is _ allowed to prepare for an -

(

m orderly shutdown before initiating a change in plant operation. This time W-L permits the operator to coordinate the reduction in electrical generation with:

l the load dispatcher to ensure the stability and svailability of the eledrical d' grid. The time limits-specified to reach lower MODES of operation permit the- tu -

shutdown to proceed in a controlled and orderly manner that is well within the 0 ;

specified maximum cooldown rate and withir the cooldown: capabilities of.the facility assuming only the minimum required equipment'is OPERABLE. This '

reduces thermal stresses on components:of the primary coolant syster snd the potential for a plant upset that could challenge safety systems under-b conditions for which this specification' applies.

If remedial measures permitting limited continued operation of the facility-under the provisions of the ACTION requirements are completed, the-shutdown may be terminated. The time limits 1of the ACTION requirements are applicable from the point in time there was a failure to meet a Limiting Condition for Operation. Therefore, the shutdown may be teminated if the ACTION-

-requirements have been met or the time limits of the ACTION requirements have l not expired.:thus providing an allowance for the' completion of the required-actions.

L The time limits of specification 3.0.3.a11ow 37 hours4.282407e-4 days 0.0103 hours 6.117725e-5 weeks 1.40785e-5 months for the plant to be in '

the COLD SHUTDOWN MODE when a shutdown is required.during the POWER MODE of-9 VDGTLE UNITS - 1 & 2 83/40-2

l 3/4.0 APPLICABIL1TY sAsEs operation. If the plant is in a Iwer MODE of operation when a shutdown is required, the time limit for reaching the next lower MODE of operation

applies. However, if' a lower MODE of operation' is reached in less time than allwed, the total allowable time to reach COLD SHUTDOWN, or other'hnplicable-

~

MODE, is not reduced. for example, if NOT STANDBY is reached in I hours -the time allowed to reach NOT $HUTDOWN is the next 11 hours1.273148e-4 days 0.00306 hours 1.818783e-5 weeks 4.1855e-6 months because the to to reach HOT SHUTDOWN is not reduced from the allowable limit of 13 hours1.50463e-4 days 0.00361 hours 2.149471e-5 weeks 4.9465e-6 months Therefore, if remedial measures are completed that would permit a return to p0WER operation, a cenalty is not incurred by having to reach a lower . MODE of operation in less than the total time allowed.

The same principle epplies with regard to the allowable outage time limits of-the ACTION requirements, if compliance with the ACT!DN requirements for one specification results in entry into a MODE or condition of operation for another specification in which the requirements of the. Limiting Condition for Operation are not met. If the new specification becomes applicab10.in less-time than specified, the dif ference may be added to the allowable outage time limits of the second specification. However, the allwable outage time limits of ACTION requirnents for a higher MODE of operation may not 6e used to extend the allowable outage time that is applicable whenFor a Limiting example-if Condition the k-for Operation is not met in a lower MODE of operation. D-Containment Spray System was discovered to be inoperable while in STARTUP, the @

ACTION 5tatement would allow up to 156 hours0.00181 days 0.0433 hours 2.579365e-4 weeks 5.9358e-5 months to achieve COLD SHUTOOWN.?!f HDTT STANDBY is attained in 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months rather than the allowed 78 hours9.027778e-4 days 0.0217 hours 1.289683e-4 weeks 2.9679e-5 months ,140 hours would still be available before the plant would be required to be in COLD SHUTOOWN.

However.-if this system was discovered to be inoperable while in .

NOT STANDBY, tb 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months provided to achieve HOT STANDBY would not be additive to the time available to achieve COLD SHUTOOWN so that the total allwable L

time is reduced f rom 156 hours0.00181 days 0.0433 hours 2.579365e-4 weeks 5.9358e-5 months to 150 hours0.00174 days 0.0417 hours 2.480159e-4 weeks 5.7075e-5 months .

The shutdown requirements of Specification 3.0.3 do not apply in MODES 5 and 6, because the ACTION requirements of individual specifications define the ~

remedial measures to be taken.

soecification 3.0.4 establishes lim *tations on MODE changes when a-Limiting Condition for Operation is-net met. It precludes placing the facility in a.

higher MODE of operation when the requirements for a Limiting Condition for-Operation are not met and continued noncompliance to these ennditions would result in a shutdown to comply with the ACTION rer uirements if a change in MODES were per:nitted.- The purpose of this specification is to ensure .that facility operation is not initiated or that higher MODES-of operation are not entered when corrective action is being taken to obtain compliance with a-specification specified limits. by restoring equipment to OPERABLE status or param l

cperation of the facility for an unlimited period of time provides an accept-able level of safety for continued operation without regard to the status of -

L the plant before or af ter a MODE change.

Therefore, in this case, entry into

- an CPERATIONAL MODE or other specified condition may be made in accordance V0GTLE UNITS - 1 & 2 8 3/4 0-3

244_ d APPLICABILITY sAsts with the provisions et the ACTID:t requirements. The provisions of this specification should nct, however, be interpreted as endorsing the failure to exercise good practice in restoring systems or components to OPERAKE status befbre plant startup. , ,

i When a shutdown is required to comply with ACTION requirements, the provisions s of Specification 3.0.4 do not apply because they would delay placing the facility in a lower MODE of operation.

Specifications 4.0.1 throuch 4.0,5 establish the general requiremenn applicable to Surveillance cequirements. These requirements are b:. sed on the Surveillance Requirements stated in the Code of Federal Regulations,10 CFR 50.36(c)(3):

" Surveillance requirements are requirements relating to test, calibra-tion, or inspection to ensure that the necessary quality of systems and corrponents is maintained, that facility operation will be within safety limits, and that the limiting conditions of operation will be met."

.. i Specification 4.0.1 establishe) ihe requirement that surveillances must be ;

performed during the OPERATIONE MODES or other conditions for which the

! requiremeats of the Limiting Conditions for 0;'eration apply unless otherwise T stated in an individual Surveillance Requirement. The purpose of this speci- %

j fication is to ensure that surveillances are performed to verify the opera-tional status of systems and components and that parameters are within speci- O fied limits to ensure safe operation of the facility when the plant is in a j

MODE or other specified condition for which the associated Limiting Conditions for Operation are applicable Survaillance Requirements do not have to be f

performed when the f acility is in an OPERATIONAL MODE for which the k -

requirements of the associated Limiting Condition for Operation do not apply unless otherwise specified. The Surveillance Requirements associated with a Special Test Exception are only applicable . shen the Special 1est Exception is used as an allowable exception to the requirements of a specification.

}oeci*1 cation 4.0.2 establishes the conditioris under which the specified tine interval for Surveillance Require nents my be extened. Item a. permits an allowable extension of the normal surveillance v terval tu facilitate sur-weillance scheduling and censideration of plant operating conditions that may not be suitable for condu:ti 3 the surveillance; e.g., trcnsient conditions or other ongoirg surveillance w maintenance activities. Item b. limits the use of the provisions of item a. to ensure that it is not used repeatedly to extend the surveillance interval beyond that specified. The limits of Jpecificetion 4.0.2 are based on engineering judgnent and the recognition that the most probable result of any particular surveillance being performed is the verification of conformance with the Surveillance Requirements. These provisions are sufficient to ensure that the reliability ensured through surveillance activities is not significantly degraded beyond that obtained from the specified surveillance interval. ,

e VDGTLE LHITS - 1 & 2 83/40-4 ,

}f4.0 APK1cAsttity nsts _ _ , ,

ecification 4.0J establishes the f ailure to perform a Surveillance Sp'quirement Re within the allowed s^veillance interval, defin9d by the .

provisions of Specification 4.0.<, as a condition that constitutesJ failurc to meet the OPERABILITY recuirements for a Limiting Co to be OPERABLE when Surveillance Requirements However, have nothingbeenin satisfactorily this 8 perferned within the specified time interval.

provision is to be construed as implying that systems ur components are 0FERABLE when they are found Thisorspecification known to be also inoperable :larifiesalthough that the still meeting the Surveillance Requirements.

ACTION requirements are applicable when Surveillance Requirements have not been completed within the allowed surveillance interval and that the time limits of the ACTION requirements apply from the point in Completion of the the allowed surveillance interval was exceeded. Surveillance Requ requirements restores compliance with the requirements of Specification 4.0.3. However, this does not negate the f act that the f ailure to have performed the surveillance within the allowed surveillance interval, defined by the provisians of specificatic,n 4.0.2, was a violation

rf e-

:erv:'":r:: uith % th: pr: ( o l

ment action. Furth:r,-th; h i h r: t:

I v':hn: ef !;;;; H44 hr ' .0,Fh -: chhtkr :f : T::Ph:'. ;;;'!h:th; p'q ,

ces'.r:::nt :nd h , tt:r- b re, : : p : rt+Me-+4e+wml OP 50.?3(:)(2)(1)(B) h::::: 't S : ::nd't hr ;rek h: H e:1 !;::P h: tie m If the allowable outage time limits of the ACTION requirements are lest than f(

o 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or a shutdown is required to comply with ACTION requirements, e.g., CL Specification 3.0.3, a 24-hour allowance is provided to pernit a delayRinT implementing the ACTION requirements. The purpose g ccmplete Surveillance Requirements that have not been performed. -

of this allowance is to pemit the completion of a surveillance before a shutdown is required to comply with ACTION requirements or before other remedial surveillance.

measures would be required that may preclude comple conditions, adequate planning, availability of personnel, the time required to perfom the surveillance, and the safety U significance h pr:vh* r of the 21:: delay :int'--

r: >M::

completing the required surveillt.nce. ;;;1ht h-P-it *:r th: :: ;Sthe :'-Era;'1hn;; ?:q;'r:::nt; tht h;n:

n : cen:nuna.4-6 : Sew. "m;n:d A *.NO" r:qde::;r.t:-- nf Mr --M e m ::;thr te 4e;htM ter/M'hnt: S ;e44 e e m th:t : :-t;;1 h:Med: If a surveillance is not th: re;d r: + h M-Steo# 4est hr '.0. ' h :1 hu:d.

completed within the 24-hour allowance, the time limits of the ACTIONWhen requirements are appliceble at that time.

within ti.e 24-hour ellowance and the Surveillance Requ surveillance is teminated.

e V0GTLE UNITS - 1 & 2 B 3/4 0-5 em

+ o i 3/4.0 APPLICABILITY tasts -

Surveillance Requirements do not have to be performed on inoperable equipment- ,

because the ACTION requirements defint the remedial measurts that apply, ,

Nowever, the Surveillance Requirements have to be met to demonstratp that -

inoperable equipment has been restored to OPERABLE status, a 50etification 4.0.4 establishes the requirement that all applicable survei--

lances must be met before e9 try into an CPERATIONALThe MODEpurposeor other of-this conditien of I operatien specified in the Applicability statement, specification is to ensure that.systen, and componer,t OPERAllLITT requirements or parameter limits are met before entry into a MODE or condidon for which these systems and components ensure safe operation of the facility. This provision applies to changes in OPERATIONAL MODE 5 or other specified conditions associeted with plant shutdown as well as startup.

Under the provisions of this specification, the applicable Surveillance -

Requirements must be performed within the specified surveillance interval to ensure that the Limiting Conditions- for Operation are met during initial plant-startup or follwing a plant outage.

When a s u down is require 6 a; comply with ACTION requirements, the provisions ,

of Specif tcation 4.0.4 do obt apply because this would delay placing the :

facility in a lower MODE of operation.

7 -

p' Specifica} ion 4.0.5 establishes the requirement thet inservice inspection of ASME Code Class 1. 2. end 3 csmponents and inservice testing of A5ME Code Class 1, 2, and 3 pumps and valves shall be performed in accordance with a O periodically updated version of Section XI of the APE toiler Theseand pressure '

requirements iQ ;

Vessel Code and Addenda as required by 10 CFR 50.55a.

apply except when relief has been provided in writing by the Commission.

@VJ -.

This specification includes a clarification of the frequentfes for performing-L the inservice inspection ar.d testing activities required-by Section X1 of the ASME Boiler and-Pressure Yessel Code and applicable Addenda. This clarifica-L tion is provided to ensure consistency in surveillance intervals throughout the Technical Specifications and to remove any ambiguities relative'to the -

frequencies for-performing the required inservice inspection and testing activities.

L Under the terms of ,this specification..the more restrictive requirements.of '

l the Technical Specifications take precedents over the ASME do11er and Pressure L Vessel Code and applicable Addenda. The requirements:of Specification 4.0.4 L

!' to perform surveillance activities before entry into an OPERATIONAL MODE or I other-specified condition takes precedence over the ASME Soller and Pressure Vessel Code provision which allows pumps and valves to be-tested up to one-week af ter return to normal operation. ~ The Technical Specification definition of OPERABLE does not allow a grace period before a component, that is not _

capable of performing its specified function is declared inoperable end takes

. -precedente over the A5ME. toller and-Pressure Vessel Code provision which allows a valve to be incapable.of perfonning its specified functier, for up to

-24 hours before being declared inoperable. -

VDGTLE UNITS - 1 & 2 4 3/4 0-6

- . - - # -- - w., ~..,..,,,_...-wo---w~~.;-n---mm.m.am...-

ML20101B243

Text

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