Text

Proposed Tech Specs Supporting Improvements to Sections 3.0.4,4.0.3 & 4.0.4 & Deleting Numerous Tech Spec Statements Which Presently Take Exception to Provisions of Spec 3.0.4
	ML20154H653
Person / Time
Site:	Fermi
Issue date:	05/24/1988
From:	; DETROIT EDISON CO.
To:	;
Shared Package
ML20154H637	List: ML20154H653; NRC-88-0062, Application for Amend to License NPF-43,improving Tech Specs 3.0.4,4.0.3 & 4.0.4 & Deleting Numerous Tech Spec Statements Which Take Exception to Tech Spec 3.0.4,per Generic Ltr 87-09.Fee Paid;
References
	NUDOCS 8805260019
	Download: ML20154H653 (58)
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3/4.0 APPLICABILITY LIMITING CONDITION FOR OPERATION 3.0.1 Compliance with the Limiting Conditions for Operation contained in the succeeding Specifications is required during the OPERATIONAL CONDITIONS or other 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 If the requirements Limiting Condition are for not met within the specified time intervals.

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 one hour action shall be initi-ated to place the unit in an OPERATIONAL CONDITION in which the Specification does not apply by placing it, as applicable, in:

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

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

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

7 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 OPERATIONAL CONDITIONS 4 or 5.

try into an OPERATIONAL CONDITION or other specified condi r Operation are g(,',/a c e not be made u conditions for the Limiting Co nta ne ACTION requirements. This W' TS met without reliance on pro ERATIONAL CONDITIONS as rou g pp provision shall not prevent required to e CTION requirements. Exceptions e uirements n the individual Specifications.

.Ar.a.-6 FERMI - UNIT 2 3/4 0-1 8805260019 880524 DR ADOCK 05000341 DCD

V INSERT PAGE 3/4 0-1 3.0.4 Entry into ar OPERATIONAL CONDITION or other specified condition shall not be made when the conditions for the Limiting Conditions for Operation are not met and the associated ACTION requires a shutdown if they are not met within a specified time inte rval . Entry into an OPERATIONAL CONDITION or other specif!ed condition may be made in accordance with the ACTION requirements when conformance to them permits continued operation of the facility for an unlimited period of time. This provision shall not prevent passage through or to OPERATIONAL CONDITIONS as required to comply with ACTION requirements. Exceptions to these requirements ere stated in the individual Specifications.

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APPLICABILITY SURVEILLANCE REQUIREMENTS 4.0.1 Surveillance Requirements shall be met during the OPERATIONAL CONDITIONS or other conditions specified for individual Limiting Conditions for Operation unless otherwise stated in an individual Surveillance Requirement.

4.0.2 Each Surveillance Requirement shall be performed within the specified time interval with:

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

b. The combined time interval for any 3 consecutive surveillance inter-vals shall not exceed 3.25 times the specified surveillance interval.

. Failure to perform a Surveillance Requirement within the specified interva 1 constitute a failure to meet the OPERABILITY requ s for a Operation. Exceptions to these r ments are stated g[fh7 wi

Limiting Condit in the individual Spec 5. Surveillance ements do not have to be pg performed on inoperable equipmen .

4.0.4 Entry into an OPERAT ONDITION or specified applicable condi-tion shall not be n ess the Surveillance Require associated with the Lim piti tion for Operation have been performed withi a plicable

.syrsertTance interval or as otherwise specified.

4.0.5 Surveillance Requirements for inservice inspection and testing of ASME )

Code Class I, 2, & 3 components shall be applicable as follows:

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

(6) (1).

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

ASME Boiler and Pressure Vessel Required frequencies Code and applicable Addenda for performing inservice terminology for inservice inspection and testirg inspection and testing activities activities Weekly At least once per 7 days Monthly At least once per 31 days Quarterly or every 3 months At least once per 92 days Semiannually or every 6 months At least once per 184 days Every 9 months At least once per 276 days Yearly or annually At least once per 366 days

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FERMI - UNIT 2 3/4 0-2

INSERT PAGE 3/4 0-2 4.0.3 Failure to perform a Surveillance Requirement within the allowed surveillance interval, defined by Specification 4.0.2, shall constitute noncompliance with the OPERABILITY requirements for a Limiting Condition for Operation. The time limits of the ACTION requirements are applicable at the time it is identified that a Surveillance Requirement has not been performed. The ACTION requirements may be delayed for up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months to permit the completion of the surveillance when the allowable outage time limits of the ACTION requirements are less than 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . Surveillance Requirements do not have to be performed on inoperable equipment.

4.0.4 Entry into an OPERATIONAL CONDITION or other specified applicable condition shall not be made unless the Surveillance Requirements (s) associated with the Limiting Condition for Operation have been performed within the applicable surveillance interval or as otherwise specified. This provision shall not prevent passage through or to OPERATIONAL CONDITIONS as required to comply with ACTION requirements.

{

REACTIVITY CONTROL SYSTEMS ~

}

LIMITING CONDITION FOR OPERATION (Continued) _

ACTION: (Continued)

2. If the inoperable control rod (s) is inserted, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months disarm ,

the associated directional control valves ** either:

a) Electrically, or b) Hydraulically by closing the drive water and exhaust water isolation valves.

Otherwise, be in at least HOT SHUTOOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

3. The provhion: Of Spccif'estica 3.0.4 are-not-apiMeath

c. With more than 8 control rods inoperable, be in at least HOT SHUTOOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

d. With one scram discharge volume vent valve and/or one scram discharge volume drain valve inoperable and open, restore the inoperable valve (s) to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in at least HOT SHUTOOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ,

e. With any scram discharge volume vent valve (s) and/or any scram dis-charge volume drain valve (s) otherwise inoperable, restore the I inoperable valve (s) to OPERABLE status within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months or be in at least HOT SHUT 00WN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

SURVEILLANCE REQUIREMENTS 4.1.3.1.1 The scram discharge volume drain and vent valves shall be demonstrated OPERABLE by:

a. At least once per 31 days verifying each valve to be open,* and

b. At least once per 92 days cycling each valve through at least one complete cycle of full travel.

4.1.3.1.2 When above the preset power level of the RWM and RSCS, all withdrawn control rods not required to have their directional control valves disarmed electrically or hydraulically shall be demonstrated OPERABLE by moving each control rod at least one notch:

a. At least once per 7 days, and

b. At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when any control rod is immovable as a result of excessive friction or mechanical interference.

"These valves may be closed intermittently for testing under administrative controls.

- May be rearmed intermittently, under administrative control, to permit y testing associated with restoring the control rod to OPERABLE status.

FERMI - UNIT 2 3/4 1-4 j

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REACTIVITY CONTROL SYSTEMS )

CONTROL R0D MAXIMUM SCRAM INSERTION TIMES LIMITING CONDITION FOR OPERATION 3.1.3.2 The maximum scram insertion time of each taltrol rod from the fully withdrawn position to notch position 6, based on deenergization of the scram pilot valve solenoids as time zero, shall not exceed 7 seconds.

APPLICABILITY: OPERATIONAL CONDITIONS 1 and 2.

ACT!ON:

a. With the maximum scram insertion time of one or more control rods exceeding 7 seconds:

1. Declare the control rod (s) with the slow insertion time inoperable, and

2. Perform the Surveillance Requirements of Specification 4.1.3.2c.

at least once per 60 days when operation is continued with three or more contrcl rods with maximum scram insertion times in excess of 7 seconds.

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

__ b. The prevision: Of Spect'ic: tion 3.0.4-are-n t :pplicable; SURVEILLANCE REQUIREMENTS 4.1.3.2 The maximum scram insertion time of the control rods shall be demon-strated through measurement with reactor coolant pressure greater then or equal to 950 psig and, during single control rod scram time tests, the control rod drive pumps isolated from the accumulators:

a. For all control rods prior to THERMAL POWER exceeding 40% of RATED THERMAL POWER following CORE ALTERATIONS or after a reactor f.hutdown that is greater than 120 days.

L. For specifically affected individual control rods following maintenance on or modification to the control rod or control rod drive system which could affect the scram insertion time of those specific control rods, and

c. For at least 10% of the control rods, on a rotating basis, at least once per 120 days of POWER OPERATION.

d. The provisions of Specification 4.0.4 are not applicable.

)

FERMI - UNIT 2 3/4 1-6

REACTIVITY CONTROL SYSTEMS

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FOUR CONTROL R00 GROUP SCRAM INSERTION TIMES LIMITING CONDITION FOR OPERATION 3.1.3.4 The average scram insertion time, from the fully withdrawn position, for the three fastest control rods in each group of four control rods arranged in a two-by-two array, based on deenergization of the scram pilot valve solenoids as time zero, shall not exceed any of the following:

Position Inserted From Average Scram Inser-Fully Withdrawn tionTime(Seconds}

46 0.379 36 1.161 26 1.971 6 3.624 APPLICABILITY: OPERATIONAL CONDITIONS 1 and 2.

ACTION:

a. With the average scram insertion times of control rods exceeding the above limits:

1. Declare the control rods with the slower than average scram insertion times inoperable until an analysis is performed to )

determine that required scram reactivity remains for the flow four control rod group, and

2. Perform the Surveillance Requirements of Specification 4.1.3.2c.

at least once per 60 days when operation is continued with an average scram insertion time (s) in excess of the average scram insertion time limit.

Otherwise, 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. Th: prev hier.: cf Specif4eatica 3.0.4 ere not epplicetrie- .

SURVEILLANCE REQUIREMENTS 4.1.3.4 All control rods shall be demonstrated OPERABLE by scram time testing from the fully withdrawn position as required by Surveillance Requirement 4.1.3.2.

)

FERMI - UNIT 2 3/4 1-8

k- REACTIVITY CONTROL SYSTEMS CONTROL R00 SCRAM ACCUMULATORS LIMITING CONDITION FOR OPERATION .

3.1.3.5 All control rod scram accumulators shall be OPERABLE.

APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, and 5*.

ACTION:

a. In OPERATIONAL CONDITION 1 or 2:

1. With one control rod scram accumulator inoperable, within 0 hour0 days 0 hours 0 weeks 0 months s:

a) Restore the inoperable accumulator to OPERABLE status, or b) Declare the control rod associated with the inoperable accumulator inoperable.

Otherwise, 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 .

2. With more than one control rod scram accumulator inoperable.

declare the associated control rods inoperable and:

a) If the control rod associated with any ir. operable scram accumulator is withdrawn, immediateiy verify that at least one control rod drive pump is operating by inserting at least one withdrawn control rod at least one notch. If no ,

control rod drive pump is operating: 1) If reactor pressure is > 900 psig, restart at least one control rod drive pump within 20 minutes or place the reactor mode switch in the Shutdown position. 2) If reactor pressure is < 900 psig, place the reactor mode switch in the Shutdown position.

b) Insert the inoperable control rods and disarm the associated control valves either:

1) Electrically, or

> . 2) Hydraulically by closing the drive water and exhaust water isolation valves.

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

f b. In OPERATIONAL CONDITION 5*:

1. With one withdrawn control rod with its associated scram accumulator inoperable, insert the affected control rod and disarm the associated directional control valves within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , l

either: i a) Electrically, or i

b) Hydraulically by closing the drive water and exhaust water j isolation valves,

2. With more than ene withdrawn control rod with the associated l scram accumulator inoperable and no control rod drive pump oper-ating, immsdiately place the reactor mode switch in the Shutdown "

position.

= 0. Th: pr;,i;i;n: Of Sp;;ific tien 3.0.4 ere net epplicebl:.

4 f

i *At least the accumulator associated with each withdrawn control rod. Not

' applicable to control rods removed per Specification 3.9.10.1 or 3.9.10.2.

FERMI - UNIT 2 3/4 1-9

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( REACTIVITY CONTROL SYSTEMS I

CONTROL ROD DRIVE COUPLING LIMITING CONDITION FOR OPERATION 3.1.3.6 All control rods shall be coupled to their drive mechanisms.

APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, and 5*.

ACTION:

a. In OPERATIONAL CONDITION 1 and 2 with one control rod not coupled'to its associated drive mechanism, within 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months s:

1. If permitted by the RW1 and RSCS, insert the control rod drive mechanism to accomplish recoupling and verify recoupling by with-drawing the control rod, and:

a) Observing any indicated response of the nuclear instrumentation, and b) Demonstrating that the control rod will not go to the overtravel position.

2. If recoupling is not accomplished on the first attempt or, 11 not permitted by the RhM or R!.CS, then until permitted by the RhH and RSCS, declare the control rod inoperable, insert the s l

( control rod and disarm the associated directional control

( valves ** either:

a) Electrically, or b) Hydraulically by closing the drive water and exhaust water isolation valves.

Otherwise, 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. In OPERATIONAL CONDITION 5* with a withdrawn control rod not coupled to its associated drive mechanism, within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months either:

1. Insert the control rod to accomplish recoupling and verify recoupling by withdrawing the control rod and demonstrating that the control rod will not go to the overtravel position, or f 2. If recoupling is not accomplished, insert the control rod and

! disarm the associated directional control valves ** either:

a) Electrically, or b) Hydraulically by closing the drive water and exhaust water -

isolation valves.

=-:. The previ:icn: Of Sp :if t::ti n 3.0.4 ere n;t ;pplicable.-

At least each withdrawn control rod. Not applicable to control rods removed per Specification 3.9.10.1 or 3.9.10.2.

- May be rearmed intermittently, under administrative control, to permit C testing associated with restoring the control rod to OPERABLE status.

FERMI - UNIT 2 3/4 1-11

REACTIVITY CONTROL SYSTEMS LIMITING CONDITION FOR OPERATION (Continued)

ACTION: (Continued)

2. With one or more control rod "Full-in" and/or "Full-out" position indicators inoperable, either:

a) When THERMAL POWER is within the preset power level of the RSCS:

1) Within 1 hour: .

(a) Determine the p Mition of the control rod (s) per ACTION a.1.a), above, or (b) Move the control rod to a position with an OPERABLE position indicator, or (c) Declare the control rod inoperabit.

2) Verify the position and bypassing of control rods with inoperable "Full-in and/or Full-out" position indicators by a second licensed operator or other technically qualified member of the unit technical staff.

b) When THERMAL POWER is greater than the preset power level of the RSCS, determine the position of the control rod (s) per ACTION a.1.a), above.

I Otherwise, 5e in at least HOT SHUTOOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

b. In OPERATIONAL CONDITION 5* with a withdrawn control rod position indicator inoperable, move the control rod to a position with an 6 OPERABLE position indicator or insert the control rod.

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SURVEILLANCE REQUIREMENTS 4.1. 3. 7 The control rod position indication system shall be determined OPERABLE by verifying:

a. At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months that the position of each control rod is indicated,

b. That the indicated control rod position changes during the movement of the control rod drive when perf orming Surveillance Requirement 4.1.3.1.2, and

c. That the control rod position indicator corresponds to the control roo position indicated by the "Full out" position indicator when performing Surveillance Requirement 4.1.3.6.b.

At least each withdrawn control rod. Not applicable to control rods removed per Specification 3.9.10.1 or 3.9.10.2. )

FERMI - UNIT 2 3/4 1-14

REACTIVITY CONTROL SYSTEMS

)

3/4.1.4 CONTROL R0D PROGRAM CONTROLS l30 WORTH MINIMIZER

' TING CONDITION FOR OPERATION

. The rod worth minimizer (RWM) shall be OPERABLE.

JABILITY: OPERATIONAL CONDITIONS 1 and 2*, when THERHAL POWER is less than

> . qual to 20% of RATED THERMAL POWER, the minimum allowable preset power level.

ACTION:

a. With the RWM inoperable, verify control rod movement and compliance with the prescribed control rod pattern by a second licensed operator or other technically qualified member of the unit technical staff who is present at the reactor control console. Otherwise, contrei rod movement may be only by actuating the manual scram or placing the reactor mode switch in the Shutdown position.

L. The provisions cf Specificetica 3.0.4 ere rct epplicebic- .

SURVEILLANCE REQUIREMENTS 4.1.4.1 The RWM shall be demonstrated OPERABLE:

I

a. In OPERATIONAL CONDITION 2 within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months prior to withdrawal of control rods for the purpose of making the reactor critical, and in OPERATIONAL CONDITION 1 within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months after RWM automatic initia-tion when reducing THERMAL POWER, by verifying proper indication of the selection error of at least one out-of-sequence control rod.

b. In OPERATIONAL CONDITION 2 within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months prior to withdrawal of control rods for the purpose of n.aking the reactor critical, by veri-fying the rod block function by demonstrating inability to withdraw an out-of-sequence control rod (after selection of first control rod),

c. In OPERATIONAL CONDITION 1 within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months after RWM automatic initiation when reducing THERMAL POWER, by demonstrating the withdraw block and insert block functions.

d. By demonstrating that the control rod patterns and sequence input to the RWM computer are correctly loaded following any loading of the program into the computer.

Entry into OPERATIONAL CONDITION 2 and withdrawal of selected control rods is permitted for the purpose of determining the GPERABILITY of the RWM prior to withdrawal of control rods for the purpose of bringing the reactor to criticality.

)

FERMI - UNIT 2 3/4 1-16

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POWER DISTRIBUTION LlHITS 3/4.2.3 HINIMUM CRITICAL POWER RATIO LlHITING CONDITION FOR OPERATION 3.2.3 The MINIMUM CRITICAL POWER RATIO (MCPR) shall be equal to or greater than the MCPR limit shown in Figure 3.2.3-1 tines the Kf shown in Figure 3.2.3-2, with:

I= (T*** ' TO) t ~I A B

~

where:

T A = 1.096 seconds, control rod average scram insertion time limit to notch 36 per Specification 3.1.3.3, N

1 T ] 0.06, B = 0.852 + 1.65[ n Ng .

I i=1 n

I I

ave = i=1 N4 tg ,

n I Hg );

i=1 n = number of surveillance tests performed to date in cycle, th Ng = number of active control rods measured in the i surveillance test, tg = average scram time to. notch 16 of all rods measured in the i th surveillance test, and N total number of active rods measured in Specification y = 4.1.3.2.a.

APPLICABILITY:

OPERATIONAL CONDITION 1, when THERMAL POWER is greater than or equal to 25% of RATED THERMAL POWER.

ACTION

a. With MCPR less than the applicable MCPR limit shown in Figures 3.2.3-1 and 3.2.3-2, initiate corrective action within 15 minutes and restore MCPR to within the required limit within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or reduce THERMAL POWER to less than 25% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

b. With the main turbine bypass system inoperable per Specification 3.7.9, operation may continue .... .... r........., . . . , , . . . . . . . . . . . . . . . . , . . . . . . .

pplic: b h provided that, within one hour, MCPR is determined to be equal to or greater than the MCPR limit as shown in Figure 3.2.3-1 by the main turbine bypass inoperable curve times the applicable Kg shown in Figure 3.2.3-FERMI - tJNIT 2 3/4 2-6 )

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3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTECTION SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.1 As a minimum, the reactor protection system instrumentation channels shown in Table 3.3.1-1 shall be OPERABLE with tl.e REACTOR PROTECTION SYSTEM RESPONSE TIME as shown in Table 3.3.1-2.

APPLICABILITY: As shown in Table 3.3.1-1.

ACTION:

a. With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip System requirement for one trip system, place the inoperable channel (s) and/or that trip system in the tripped condition

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

. previsiens of Specificativ. 2.C.' cee e t applic=M e

b. With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip System requirement for both trip systems, place at 1 cast one trip system ** in the tripped condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months and take the ACTION required by Table 3.3.1-1.

( SURVEILLANCE REQUIREMENTS 4.3.1.1 Each reactor protection system instrumentation channel shall be demon-strated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST, and CHANNEL CALIBRATION operations for the OPERATIONAL CONDITIONS and at the frequencies shown in Table 4.3.1.1-1.

4.3.1.2 LOGIC SYSTEM FUNCTIONAL TESTS and simulated automatic operation of all channels shall be performed at least once per 18 months.

4.3.1.3 The REACTOR PROTECTION SYSTEM RESPONSE TIME of each reactor trip functional unit shown in Table 3.3.1-2 shall be demonstrated to be within its limit at least once per 18 months. Each test shall include at least one channel per trip system such that all channels are tested at least once every N times 18 months where N is the total number of redundant channels in a specific reactor trip system.

An inoperabie channel need not be placed in the tripped condition where this would cause the Trip Function to occur. In these cases, the inoperable channel shall be restored to OPERABLE status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or the ACTION required by Table 3.3.1-1 for that Trip Function shall be taken.

- The trip system need not be placed in the tripped condition if this would cause the Trip Function to occur. When a trip system can be placed in the tripped conditic.n without causing the Trip Function to occur, place the trip system with the most inoperable channels in the tripped condition; if both systems have the C same number of inoperable channels, place either trip system in the tripped condition.

FERMI - UNIT 2 3/4 3-1 1

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{ INSTRUMENTATION 3/4.3.2 ISOLATION ACTUATION INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.2 The isolation actuation instrumentation channels shown in Table 3.3.2-1 shall be OPERABLE with their trip setpoints set consistent with the values shown in the Trip Setpoint column of Table 3.3.2-2 and with ISOLATION SYSTEM RESPONSE TIME 35 shown in Table 3.3.2-3.

APPLICABILITY: As shown in Table 3.3.2-1.

ACTION:

a. With an isolation actuation instrumentatinn channel trip setpoint less conservative than the value shown in the Allowable Values column of Table 3.3.2-2, declare the channel inoperable until the channel is restored to OPERABLE status with its trip setpoint adjusted consistent with the Trip Setpoint value,

b. With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip System requirement for one trip system, place the inoperable channel (s) and/or that trip system in the tripped condition

within one hour. " : p:ei i:n of Specific:tien 3.0.'-

. u ,, o : ,. e _

g

c. With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip System requirement for both trip systems, place at least one trip system ** in the tripped condition within one hour ar<d take the ACTION required by Table 3.3.2-1.

"An inoperable channel need not be placed in the tripped' condition where this would cause the Trip Function to occur. In these cases, the inoperable channel shall be restored to OPERABLE status within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months or the ACTION required by Table 3.3.2-1 for that Trip Function shall be taken.

- The trip system need not be placed in the tripped condition if this would cause the Trip Function to occur. When a trip system can be placed in the tripped condition without causing the Trip Function to occur, place the trip system with the most inoperable channels in the tripped condition; if both systems have the same number of inoperable channels, place either trip system in the tripped condition.

FERMI - UNIT 2 3/4 3-9

TABLE 3.3.3-1 (Continued) )

EMERGENCY CORE COOLING SYSTEM ACTUATION INSTRUMENTATION ACTION STATEMENTS ACTION 30 - With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip System requirement:

a. For one trip system, pla that trip system in the tripped condition within 1 hou or declare the associated ECCS inoperable.

b. For both trip systems, declare the associated ECCS inoperable.

ACTION 31 - With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip System requirement, declare the associated ECCS inoperable.

ACTION 32 - With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip System requirement, place the inoperable channel in the tripped condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

ACTICN 33 - Restore the manual initiation function to OPERABLE status within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months or declare'the associated ECCS inoperable.

ACTION 34 - With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip System requirement, place at least pjpt inoperable channel in the tripped condition within 1 hou M , align the HPCI system to take suction from the suppres-sion pool, or declare the HPCI system inoperable.

ACTION 35 - With the number of OPERABLE channels:

a. One less than the Total Number of Channels, restore the inoperable channel to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months or declare the associated emergency diesel generator inoperable and take the ACTION required by Specification 3.8.1.1 or 3.8.1.2, as appropriate.

b. Less than the Minimum Channels OPERABLE requirement, declare the associated diesel generator inoperable anJ take the ACTION required by Specification 3.8.1.1 or 3.8.1.2, as appropriate.

The provisicas of Specificouvn 3.0.4 air uvi applicabic.

]

FERMI - UNIT 2 3/4 3-26 i

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TABLE 3.3.5-1 (Continued)

REACTOR t RE ISOLATION COOLING SYSTEM ACTION STATEMENTS ACTION 50 - With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip System requirement:

a. For one trip system, place the inoperable channel (s) and/or that trip system in the tripped condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months or declare the RCIC system inoperable.

b. For both trip systems, declare the RCIC system inoperable.

ACTION 51 - With the number of OPERABLE channels less than required by the Minimum OPERABLE Channels per Trip System requirement, place at least one loperable i channel in the tripped condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months '8 or align RCIC to take suction from the suppres-sion pool or declare the RCIC system inoperable.

ACTION 52 - Restore the manual initiation function to OPERABLE status within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months or declare the RCIC system inoperable.

l

ihe provisions vi 5pecificai.ivo 3.0.4 or a not appikeble.

J FERMI - UNIT 2 3/4 3-38

l INSTRUMENTATION 3/4.3.7 MONITORING INSTRUMENTATION RADIATION HONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.7.1 The radiation monitoring instrumentation channels shown in Table 3.3.7.1-1 shall be OPERABLE with their alarm / trip setpoints within the specified limits.

APPLICABILITY: As shown in Table 3.3.7.1-1.

ACTION:

a. With a radiation monitoring instrumentation channel alarm / trip set-point exceeding the value shown in Table 3.3.7.1-1, adjust the set-point 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 monitoring channels inoperable, take the ACTION required by Table 3.3.7.1-1.

' The provisions of Specification) 3.0.3 and 3.0.4 are not applicable.

c.

SURVEILLANCE REQUIREMENTS 4.3.7.1 Each of the above required radiation monitoring instrumentation channels shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL FUNCTIONAL TEST and CHANNEL CALIBRATION operations for the conditions and at the frequencies shown in Table 4.3.7.1-1.

6 FERMI - UNIT 2 3/4 3-47

INSTRUMENTATION

. SEISMIC MONITORING INSTRUMENTATION MITING CONDITION FOR OPERATION 3.3.7.2 The seismic monitoring instrumentation shown in Table 3.3.7.2-1 shall be OPERABLE.

APPLICABILITY: At all times.

ACTION:

a. With one or more of the above required seismic monitor lng instruments inoperable for more than 30 days, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 10 days outlining the cause of the malfunction and the plans for restoring the instrument (s) to OPERABLE status,

b. The provisions of Specification { 3.0.3 and h^-4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.7.2.1 Each of the above required seismic monitoring instruments shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL FUNC-TIONAL TEST and CHANNEL CALIBRATION operations at the frequencies shown in Table 4.3.7.2-1.

4.3.7.2.2 Each of the above required seismic monitoring instruments 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 5 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 Specification 6.9.2 within 10 days describing the magnitude, frequency spectrum, and resultant effect upon unit features important to safety.

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1 FERMI - UNIT 2 3/4 3-51

n

. l INSTRUMENTATION METEOROLOGICAL MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.7.3 The metec*ological monitoring instrumentation channels shown in Table 3.3.7.3-1 shall be CPERABLE.

APPLICABILITY: At all times.

ACTION:

a. With less than the required channels OPERABLE in Table 3.3.7.3-1 for more than 7 days, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 10 days outlining the cause of the malfunction and the plans for restoring the instrumentation to OPERABLE status,

b. TheprovisionsofSpecification\3.0.3and3.0.4arenotapplicable.

SURVEILLANCE REQUIREMENTS O

4.3.7.3 Each of the above required meteorological monitoring instrumentation channels shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK and CHANNEL CALIBRATION ope ations at the frequencies shown in Table 4.3.7.3-1.

9 FERMI - UNIf 2 3/4 3-54

( INSTRUMENTATION TRAVERSING IN-CORE PROBE SYSTEM LIMITING CONDITION FOR OPERATION 3.3.7.7 The traversing in-core probe system shall be OPERABLE with:

a. Five movable detectors, drives and readout equipment to map the core, and

b. Indexing equipment to allow all five detectors to be calibrated in a common location.

APPLICABILITY: When the traversing in-core probe is used for:

a. Recalibration of the LPRM detectors, and

'b . " Monitoring the APLHGR, LHGR, MCPR, or MFLPD.

ACTION:

With the traversing in-core probe system inoperable, suspend use of the system .

for the above applicable monitoring or calibration functions. The provisions of Specification) 3.0.3 r,d 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.7.7 The traversing in-core probe system shall be demonstrated OPERABLE by normalizing each of the above required detector outputs within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months prior to use when required for the LPRM calibration function.

80nly the detector (s) in the required measurement location (s) are required to be OPERABLE.

(

FERMI - UNIT 2 3/4 3-65

i INSTRUMENTATION )

CHLORINE DETECTION SYSTEM LIMITING CONDITION FOR OPERATION 3.3.7.8 Two independent chlorine detectors shall be OPERABLE with their trip setpoints adjusted to actuate at chlorine concentration of less than or equal to 5 ppm.

APPLICABILITY: All OPERATIONAL CONDITIONS.

ACTION:

a. With one chlorine detector inoperable, restore the inoperable detector 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 isolation of all control room emer-gency intakes by placing the HVAC system in the chlorine mode of operation,

b. With both chlorine detectors inoperable, within I hour initiate and maintain isolation of all control room emergency intakes by placing the HVAC system in the chlorine mode of operation.

c. The previ:ica; cf Sp :iff:: tion 3.0.1 cre r.ct :pplicabic.

I SURVEILLANCE REQUIREMENTS 4.3.7.8 Each of the above required chlorine detectors shall be demonstrated

' OPERABLE by performance of a:

a. CHANNEL FUNCTIONAL TEST at least once per 31 days, and

b. CHANNEL CALIBRATION at least once per 18 months.

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FERMI - UNIT 2 3/4 3-66

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( '

INSTRUMENTATION FIRE DETECTION INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.7.9 As a minimum, the fire detection instrumentation for each fire detection zone shown in Table 3.3.7.9-1 shall be OPERABLE.

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

ACTION:

a. With the number of OPERABLE fire detection instruments in one or more zones:

1. Less than, but more than one-half of, the Total Number of Instruments shown in Table 3.3.7.9-1 for Function A, restore the inoperable Function A instrument (s) to OPERABLE status within 14 days or within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months establish a fire watch patrol to inspect the zone (s) with the inoperable instrument (s) at least once per hour, unless the instrument (s) is located inside the containment, then inspect that containment zone at least once per 8 hcurs or monitor the containment air temperature at least once per hour at the locations listed in, Specification 4.6.1.7.

2. One less than the Total Number of Instruments shown in Table 3.3.7.9-1 for Function B, or one-half or less of the Total Number of Instruments shown in Table 3.3.7.9-1 for Function A,

( or with any two or more adjacent instruments inoperable, within I hour establish a fire watch patrol to inspect the zone (s) with the inoperable instrument (s) at least once per hour, unless the instrument (s) is located inside the containment, then inspect that containment zone at least once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months or monitor the con-tainment air temperature at least once per hour at the locations listed in Specification 4.6.1.7.

b. The provisions of Specification ( 3.0.3 nd 3.0 M are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.7.9.1 Each of the above required fire detection instruments which are accessible during unit operation shall be demonstrated OPERABLE at least once per 6 months by performance of a CHANNEL FUNCTIONAL TEST. Fire detectors which are not accessible during unit operation shall be demonstrated OPERABLE by the performance of a CHANNEL FUNCTIONAL TEST during each COLD SHUTDOWN exceeding 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months unless performed in the previous 6 months.

4.3.7.9.2 The NFPA Standard 720 supervised circuits supervision associated

! with the detector alarms of each of the above required fire detection instruments shall be demonstrated OPERABLE at least once per 6 months.

I 4.3.7.9.3 The non-supervised circuits associated with detector alarms between the instruments and the control room shall be demonstrated OPERABLE at least

(

once per 31 days.

FERMI - UNIT 2 3/4 3-67 l

INSTRUMENTATION )

LOOSE-PART DETECTION SYSTEM LIMITING CONDITION FOR OPERATION 3.3.7.10 The loose part detection system shall be OPERABLE.

APPLICABILITY: OPERATIONAL CONDITIONS 1 and 2.

ACTION:

a. With one or more loose part detection system channels inoperable for more than 30 days, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 10 days outlining the cause of the malfunction and the plans for restoring the channel (s) to OPERABLE status,

b. The provisions of Specification 3.0.3 = d 3.0.' are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.7.10 Each channel of the loose part detection system shall be demonstrated )

OPERABLE by performance of a:

a '. CHANNEL CHECK at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ,

b. CHANNEL FUNCTIONAL TEST at least once per 31 days, and

c. CHANNEL CALIBRATION at least once per 18 months.

)

FERMI - UNIT 2 3/4 3-70

INSTRUMENTATION RADI0 ACTIVE LIQUID EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.7.11 The radioactive liquid effluent monitoring instrumentation channels shown in Table 3.3.7.11-1 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 OFFSITE DOSE CALCULATION MANUAL (00CM).

APPLICABILITY: At all times.

ACTION:

a. 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 effluents monitored by the affected channel, or declare the channel inoperable,

b. With less than the minimum number of radioactive liquid effluent monitoring instrumentation channels OPERABLE, take the ACTION shown

( in Table 3.3.7.11-1. Restore the inoperable instrumentation to OPERABLE within the time specified in the ACTION or, pursuant to Specification 6.9.1.8, explain in the next Semiannual Radioactive Effluent Release Report why the inoperability was not corrected within the time specified.

c. TheprovisionsofSpecification(3.0.3ar.d3.0.4arenotapplicable.

SURVEILLANCE REQUIREMENTS 4.3.7.11 Each radioactive liquid effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CEANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3.7.11-1.

C FERMI - UNIT 2 3/4 3-71

INSTRUMENTATION

)

RADI0 ACTIVE GASEOUS EFFLUENT MONITORING INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.7.12 The radioactive gaseous effluent monitoring instrumentation channels shown in Table 3.3.7.12-1 shall be OPERABLE with their alarm / trip setpoints set to ensure that the limits of Specification 3.11.2.1 are not exceeded. The alarm / trip setpoints of these channels, with the exception of the offgas monitoring system, shall be determined and adjusted in accordance with the methodology and parameters in the ODCM.

APPLICABILITY: As shown in Table 3.3.7.12-1 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 affected channel, or declare the channel inoperable.

b. With less than the minimum number of radioactive gaseous effluent monitoring instrumentation channels OPERABLE, take the ACTION shown in Table 3.3.7.12-1. Restore the inoperable instrumentation to OPERABLE status within the time specified in the ACTION nr, pursuant to Specification 6.9.1.8, explain in the next Semiannual Radioactiva I Effluent Release Report why the inoperability was not corrected within the time specified.

c. The provisions of Specification \ 3.U.3 x d 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.7.12 Each radioactive gaseous effluent monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, SOURCE CHECK, CHANNEL CALIBRATION and CHANNEL FUNCTIONAL TEST operations at the frequencies shown in Table 4.3.7.12-1.

)

FERMI - UNIT 2 3/4 3-76

k, REACTOR COOLANT SYSTEM 3/4.4.4 CHEMISTRY LIMITING CONDITION FOR OPERATION 3.4.4 The chemistry of the reactor coolant system shall be maintained within the limits specified in Table 3.4.4-1.

APPLICABILITY: At all times.

ACTION:

a. In OPERATIONAL CONDITION 1:

1. With the conductivity, chloride concentration or pH exceeding the limit specified in Table 3.4.4-1 for less than 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months during one continuous time interval and, for conductivity and chloride concentration, for less than 336 hours0.00389 days 0.0933 hours 5.555556e-4 weeks 1.27848e-4 months per year, but with the conductivity less than 10 pmho/cm at 25 C and with the chloride concentration less than 0.5 ppm, this need not be reported to the Commissiong nd the previticn: cf Spcci'iccticn

^ 0. 0 = =' :pp! k9h.

2. With the conductivity, chloride concentration or pH exceeding the limit specified in Table 3.4.4-1 for more than 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months during one continuous time interval or with the conductivity and chloride concentration exceeding the limit specified in Table 3.4.4-1 for

( more than 336 hours0.00389 days 0.0933 hours 5.555556e-4 weeks 1.27848e-4 months per year, be in at least STARTUP within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

3. With the conductivity exceeding 10 pmho/cm at 25'C or chloride concentration exceeding 0.5 ppm, be in at least HOT SHUTOOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUT 00WN within the next 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ,

b. In OPERATIONAL CONDITIONS 2 and 3 with the conductivity, chloride concentration or pH exceeding the limit specified in Table 3.4.4-1 for more than 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months during one continuous time interval, 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 and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ,

c. At all other times:

1. With the:

a) Conductivity or pH exceeding the limit specified in Table 3.4.4-1, restore the conductivity and pH to within the limit within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , or b) Chloride concentration exceeding the limit specified in Table 3.4.4-1, restore the chloride concentration to within the limit within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , or perform an engineering evaluation to determine the effects of the out-of-limit conditfon on the structural integrity of the reactor coolant system. Determine that the structural integrity of the reactor coolart system remains acceptable for continued operation prior to proceeding to OPERATIONAL CONDITION 3.

( -

2. The provisions of Specification 3.0.3 are not applicable.

FERMI - UNIT 2 3/4 4-13

REACTOR COOLANT SYSTEM )

3/4.4.7 MAIN STEAM LINE ISOLATION VALVES LIMITING CONDITION FOR OPERATION 3.4.7 Two main steam line isolation valves (MSIVs) per main steam line shall be OPERABLE with closing times greater than or equal to 3 seconds and less than or equal to 5 seconds.

APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, and 3.

ACTION:

a. With one or more MSIVs inoperable:

1. Maintain at least one MSIV OPERABLE in each affected main steam line that is open and within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months , either:

a) Restore the inoperable valve (s) to OPERABLE status, or b) Isolate the affected main steam line by use of a deactivated MSIV in the closed position.

2. Otherwise, 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 and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . )

t. The pr: visions of Sp;;ification 3.0.4 are not applit:bic; SURVEILLANCE REQUIREMENTS 4.4.7 Each of the above required MSIVs shall be demonstrated OPERABLE by verifying full closure between 3 and 5 seconds when tested pursuant to Specification 4.0.5.

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FERMI - UNIT 2 3/4 4-24

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

( REACTOR COOLANT SYSTEM 3/4.4.8 STRUCTURAL INTEGRITY LIMITING CONDITION FOR OPERATION 3.4.8 The structural integrity of ASME Code Class 1, 2, and 3 components shall be maintained in accordance with Specification 4.4.8.

APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, 3, 4, and 5.

ACTION:

a. With the structural integrity 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 reactor coolant system temperature more than 50 F above the minimum temperature required by HDT 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 200F.

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. The previcien: Of Speci'ication 3.0.' :re not :pplic:ble, SURVEILLANCE REQUIREMENTS 4.4.8 No requirements other than Specification 4.0.5 and the guidelines of NUREG-0313, Technical Report on Material Selection and Processing Guidelines for BWR Coolant Pressure Boundary Piping, Revision 1.

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FERMI - UNIT 2 3/4 4-25 i

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CONTAINMENT SYSTEMS PRIMARY CONTAINMENT AIR LOCKS LIMITING CONDITION TOR OPERATION 3.6.1.3 Each primary containment air lock shall be OPERABLE with:

a. Both doors closed except when the air lock is being used for normal transit entry and exit through the containment, then at least one air lock door shall be closed, and ,

b. An overall air lock leakage rate of less than or equal to 0.05 La at P,, 56.5 psig.

APPLICABILITY: OPERATIONAL CONDITIONS 1, 2*, and 3.

ACTION:

a. With one primary containment air lock door inoperable:

1. Maintain at least the OPERABLE air lock door closed and either restore the inoperable air lock door to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or lock the OPERABLE air lock door closed.

2. Operation may then continue until performance of the next re-quired overall air lock leakage test provided that the OPERABLE air lock door is verified to be locked closed at least once per )

31 days.

3. Otherwise, be in at least HOT SHUT 00WN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTOOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months . ,

-4. The previsicris of Specificcticn 3.0.' crc not applicablec

b. With the primary containment air lock inoperable, except as a result of an inoperable air luck door, maintain at least one air lock door closed; restore the inoperable air lock to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

See Special Test Exception 3.10.1.

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FERMI - UNIT 2 - 3/4 6-8

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CONTAINMENT SYSTEMS l

3/4.6.3 PRIMARY CONTAINMENT ISOLATION VALVES )l LIMITING CONDITION FOR OPERATION 3.6.3 The primary containment isolation valves and the reactor instrumentation line excess flow check valvos shown in Table 3.6.3-1 shall be OPERABLE with isolation times less than or equal to those shown in Table 3.6.3-1.

APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, and 3.

ACTION:

a. With one or more of the primary containment isolation valves shown in Table 3.6.3-1 inoperable, maintain at least one isolation valve OPERABLE in each affected penetration that is open and within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months either:

1. Restore the inoperable valve (s) to OPERABLE status, or

2. Isolate each affected penetration by use of at least one de-activated automatic valve secured in the isolated position," or

3. Isolate each affected penetration by use of at least one locked closed manual valve or blank flange.*

I Otherwise, 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 and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ,

b. With one or more of the reactor instrumentation line excess flow check valves shown in Table 3.6.3-1 inoperable, operation may continue and -

theprovisionsofSpecification(3.0.3end2.0.1arenotapplicable provided that within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months either:

1. The inoperable valve is returned to OPERABLE status, or

2. The instrument line is isolated and the associated instrument is declared inoperable.

Otherwise, 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 and in COLD SHUTDOWN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

"Isolation valves closed to satisfy these requirements may be reopened on an intermittent basis under administrative control.

)

FERMI - UNIT 2 3/4 6-20

PLANT SYSTEMS )

3/4.7.6 SEALED SOURCE CONTAMINATION LIMITING CONDITION FOR OPERATION 3.7.6 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 contar.ination in excess of the above limit, withdraw the sealed source from use and either:

1. Decontaminate and repair the scaled source, or

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

b. The provisions of Specification { 3.0.3 eM--Ware not applicable.

SURVEILLANCE REQUIREMENTS

)

4.7.6.1 Test 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.

4.7.6.2 Test Frequencies - Each category of sealed sources, excluding startup sources and fission detectors 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 material:

i 1. With a half-life greater than 30 days, excluding Hydrogen 3, and l

2. In any form other than gas.

)

FERMI - UNIT 2 3/4 7-22 l

l

y PLANT SYSTEMS 3/4.7.7 FIRE SUPPRESSION SYSTEMS i

I FIRE SUPPRESSION WATER SYSTEM LIMITING CONDITION FOR OPERATION 3.7.7.1 The fire suppression water system shall be OPERABLE with:

a. Two fire suppression pumps, each with a capacity of 2500 gpm, with their discharge aligned to the fire suppression header,

b. The general service water intake structure water level > 558 feet, and An OPERABLE flow path capable of taking suction from the general c.

service water intake structure and transferring the water through distribution piping with OPERABLE sectionalizing control or isolation valves to the yard hydrant curb valves, the last valve ahead of the water flow alarm device on each sprinkler or hose i

standpipe and the last valve ahead of the spray system required to l

' be OPERABLE per Specifications 3.7.7.2, 3.7.7.5, and 3.7.7.6.

APPLICABILITY: At all times.

ACTION:

a. With one pump inoperable, restore the inoperable pump to OPERABLE status within 7 days or provide an alternate backup pump. The provisionsofSpecification\3.0.3and3.0.4arenotapplicable.

b. With the fire suppression water system otherwise inoperable, establish a backup fire suppression water systcm within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

SURVEILLANCE REQUIREMENTS 4.7.7.1.1 The fire suppression water system shall be demonstrated OPERABLE:

a. At least once per 7 days by verifying the minimum water supply level,

b. At least once per 31 days by starting the electric motor-driven fire suppression pump and operating it for at least 15 minutes on recirculation flow.

c. At least once per 31 days by verifying that each valve (manual, power-operated, or automatic) in the flow path is in its correct position.

I FERMI - UNIT 2 3/4 7-24

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . _ . _ _ _ _ _ _ _ l

PLANT SYSTEMS

,{

SPRAY AND/0R SPRINKLER SYSTEMS LIMITING CONDITION FOR OPERATION 3.7.7.2 The following spray and sprinkler systems shall be OPERABLE:

ELEVATION TYPE AREA

a. Reactor Building

1. Torus Room 560' Wet Pipe Sprinkler

2. Basement NE Corner Room 540' Wet Pipe Sprinkler

3. HPCI Turbine and Pump Room 540' Wet Pipe Sprinkler

4. First Floor, Railroad Bay 583' Wet Pipe Sprinkler

5. Second Floor, Cable Trays 613' Wet Pipe Sprinkler

6. Fourth Floor, MG Sets 641'6" Wat Pipe Sprinkler

b. Auxiliary Building

1. Basement 551' and 562' Wet Pipe Sprinkler

2. Mezzanine and Cable Tray 583' - 603' Wet Pipe Sprinkler Area Ventilation Equipment 6778 Manual Flooding System 3.

4. Cable Spreading Room 630'6" Manual Sprinkler

( 562' Wet Pipe Sprinkler

5. Corridor

c. RHR Complex

1. Fuel Oil Storage Tank Rooms - Wet Pipe Sprinkler (4)

d. General Service Water Pumphouse

1. Diesel Fire Pump Room - Wet Pipe Sprinkler APPLICABILITY: Whenever equipment protected by the spray and/or sprinkler systems is required to be OPERABLE.

ACTION:

a. With one or more of the above required spray and/or sprinkler systems inoperable, within I hour establish a continuous fire watch with backup fire suppression equipment for those areas in which redundant systems or components could be damaged; for other areas, establish an hourly fire watch patrol.

b. TheprovisionsofSpecification(3.0.3and3.0.tarenotapplicable.

FERMI - UNIT 2 3/4 7-27

1

=

I I

PLANT SYSTEMS 1 I

C0pSYSTEMS LIMITING CONDITION FOR OPERATION 3.7.7.3 The following low pressure CO2 systems shall be OPERABLE:

a. Emergency diesel generators, RHR complex,

b. Standby gas treatment system charcoal filters, Auxiliary Building, elevation 677'6".

c. Cable tray area, Auxiliary Building, elevation 631'.

d. Outside Division II switchgear room, Auxiliary Building, elevation 643'6".

APPLICABILITY: Whenever equipment protected by the CO2 systems is required to be OPERABLE.

ACTION:

a. With one or more of the above required CO 2 systems inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months establish a continuous fire watch with backup fire suppression equipment for those areas in which redundant systems or components could be damaged; for other areas, establish an hourly fire watch patrol.

b. TheprovisionsofSpecification\3.0.3=d3.0Aarenotapplicable.

SURVEILLANCE REQUIREMENTS 4.7.7.3.1 Each of the above required CO, systems shall be demonstrated OPERABLE at least once per 31 days by vePifying that each valve (manual, power operated, or automatic) in the flow path is in its correct position.

systems shall be 4.7.7.3.2 Each of the above required low pressure CO2 demonstrated OPERABLE:

a. At least once per 7 days by verifying the CO 2 storage tank level to be greater than 50% full for systems a and b above and greater than 40% full for systems e and d above, and pressure to be greater than 250 psig but less than 330 psig for all of the systems.

b. At least once per 18 months by verifying:

1. The system, including associated ventilation system fire dampers and fire door release mechanisms, actuates, manually and/or automatically, upon receipt of a simulated actuation signal, and

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

(

3/4 7-29 FERMI - UNIT 2

PLANT SYSTEMS

)

HALON SYSTEMS LIMITING CONDITION FOR OPERATION 3.7.7.4 The following Halon systems shall be OPERABLE with the storage tanks of either the main bank or the reserve bank having at least 95% of the main bank or the reserve bank full charge weight and 90% of the main bank or the reserve bank full charge pressure:

a. Relay room, elevation 613'6".

b. Cable spreading room, elevation 630'6".

c. Computer room, and under floor, elevation 655'6".

APPLICABILITY: Whenever equipment protected by the Halon systems is required to be OPERABLE.

ACTION:

a. With one or more of the above required Halon systems inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months establish a continuous fire watch with backup fire suppression equipment for those areas in which redundant systems or components could be damaged; for other areas, establish an hourly fire watch patrol.

b. The provisions of Specification \ 3.0.3 =d 3.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.7.7.4 Each of the above required Halon systems shall be demonstrated OPERABLE:

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

b. At least once per 6 months by verifying Halon storage tank weight and pressure.

c. At least once per 18 months by:

1. Verifying the system, including associated ventilation system fire dampers and fire door release mechanisms, actuates, manually and automatically, upon receipt of a simulated actuation signal, and

2. Performance of a puff test through all headers and nozzles to assure no blockage.

)

FERMI - UNIT 2 3/4 7-30

( ~

PLANT SYSTEMS FIRE HOSE STATIONS J

LIMITING CONDITION FOR OPERATION l J

3.7.7.5 The fire hose stations shown in Table 3.7.7.5-1 shall be OPERABLE.

APPLICABILITY: Whenever equipment in the areas protected by the fire hose stations is required to be OPERABLE.

ACTION:

a. With one or more of the fire hose stations shown in Table 3.7.7.5-1 inoperable, provide gated wye (s) on the nearest OPERABLE hose sta-tion (s). One outlet of the wye shall be connected to the standard length of hose provided for the hose station. The second outlet of the wye shall be connected to a length of hose sufficient to provide cover-age for the area left unprotected by the inoperable hose station.

Where it can be demonstrated that the physical routing of the fire hose would result in a recognizable hazard to operating technicians, plant equipment, or the hose itself, the fire hose shall be stored in a roll et the outlet of the OPERABLE hose station. Signs shall be mountet above the gated wye (s) to identify the proper hose to use. The above ACTION shall be accomplished within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months if the inoperable fire hose is the primary means of fire suppression; otherwise route the additional hose within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

(

b. TheiovisionsofSpecification\3.0.3and3.0.'arenotapplicable.

SURVEILLANCE REQUIREMENTS 4.7.7.5 Each of the fire hose stations shown in Table 3.7.7.5-1 shall be demonstrated OPERABLE:

a. At least once per 31 days by a visual inspection of the fire hose stations accessible during plant operation to assure all required equipment is at the station.

b. At least once per 18 months by:

1. Visual inspection of the fire hose stations not accessible during plant operation to assure all required equipment is at the station.

2. Removing the hose for inspection and re-racking, and

3. Inspecting all gaskets and replacing any degraded gaskets in the couplings.

c. At least once per 3 years by:

1. Partially opening each hose station valve to verify valve OPERABILITY and no flow blockage.

2. Conducting a hose hydrostatic test at a pressure of 150 psig or at least 50 psig above the maximum fire main operating pressure,

( -

whichever is greater.

FERMI - UNIT 2 3/4 7-31

PLANT SYSTEMS )

YARD FIRE HYDRANTS AND HYORANT HOSE HOUSES LIMITING CONDITION FOR OPERATION 3.7.7.6 The yard fire hydrants and associated hydrant hose houses shown in Table 3.7.7.6-1 shall be OPERABLE.

APPLICABILITY: Whenever equipment in the areas protected by the yard fire hydrants is required to be OPERABLE.

ACTION:

a. With one or more of the yard fire hydrants or associated hydrant hose houses shown in Table 3.7.7.6-1 inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months have sufficient additional lengths of 21/2 inch diameter hose located in an adjacent OPERABLE hydrant hose house to provide service to the unprotected area (s) if the inoperable fire hydrant or associated hydrant hose house is the primary means of fire suppression; otherwise provide the additional hose within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

b. TheprovisionsofSpecification(3.0'ard3.0.0arenotapplicable.

SURVEILLANCE REQUIREMENTS

)

4.7.7.6 Each of the yard fire hydrants and associated hydrant hose houses shown in Table 3.7.7.6-1 shall be demonstrated OPERABLE:

a. At least once per 31 days by visual inspection of the hydrant hose house to assure all required equipment is at the hose house.

b. At least once per 6 months, during March, April or May and during September, October or November, by visually inspecting each yard fire hydrant and verifying that the hydrant barrel is dry and that the hydrant is not damaged.

c. At least once per 12 months by:

1. Conducting a hose hydrostatic test at a pressure of 150 psig or at least 50 psig above the maximum fire main operating pressure, whichever is greater. ,

2. Replacement of all degraded gaskets in couplings.

3. Performing a flow check of each hydrant.

I FERMI - UNIT 2 3/4 7-36

PLANT SYSTEMS y 3/4.7.8 FIRE RATED ASSEMBLIES LIMITING CONDITION FOR OPERATION 3.7.8 All fire rated assemblies, including walls, floor / ceilings, cable tray enclosures and other fire barriers, separating safety related fire areas or separating portions of redundant systems important to safe shutdown within a fire area, and all sealing devices in fire rated assembly penetrations including fire coors, fire dampers, cable, piping and ventilation duct penetration seals and ventilation seals, shall be OPERABLE.

t APPLICABILITY: At all times.

ACTION:

a. With one or more of the above required fire rated assemblies and/or sealing devices inoperable, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months establish a continuous fire watch on at least one side of the affected assembly (s) and/or sealing device (s) or verify the OPERABILITY of fire detectors on at least one side of the inoperable assembly (s) and sealing device (s) and establish an hourly fire watch patrol,

b. TheprovisionsofSpecification\3.0.3=d3.0.'arenotapplicable.

)

SURVEILLANCE REQUIREMENTS 4.7.8.1 Each of the above required fire rated assemblies and penetration sealing devices shall be verified OPERABLE at least once per 18 months by performing a visual inspection of:

a. The exposed surfaces of each fire rated assembly,

b. Each fire damper and associated hardware.

c. At least 10% of each type of sealed penetration. If apparent changes in appearance or abnormal degradations are found, a visual inspection of an additional 10% of each type of sealed ptnetration shall be made.

This inspection process shall continue until a 10% sample with no apparent changes in appearance or abnormal degradation is found.

Samples shall be selected such that each penetration seal will be inspected at least once per 15 years. ,

t FERMI - UNIT 2 3/4 7-38

h ELECTRICAL POWER SYSTEMS PRIMARY CONTAINMENT PENETRATION CONDUCTOR OVERCURRENT PROTECTIVE DEVICES LIMITING CONDIjiCN FOR OPERATION 3.8.4.2 All primary containment penetration conductor overcurrent protective devices shown in Table 3.8.4.2-1 shall be OPERABLE.

APPLICABILITY: OPERATIONAL CONDITIONS 1, 2, and 3.

ACTION:

With one or more of the primary containment penetration conductor

[ overcurrent protective devices shown in Table 3.8.4.2-1 inoperable, declare the affected system or component inoperable and apply the appropriate ACTION statement for the affected system, and

1. For 4.16-kV circuits, deenergize the 4.16-kV circuit (r "

tripping the associated circuit breaker (s) within 72 c.r.ic 5e and verify the circuit breaker to be tripped at lea.

per 7 days thereafter.

2. For 480-volt circuit devices, remove the inoperable devi:e(s) from service by racking out or removing the device within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months and verify the inoperable device (s) to be racked out or removed at least once per 7 days thereafter.

Otherwise, be in at least HOT SHUTOOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUT 00WN within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

'- t. 'h pr vf:f:n: Of Sp::f'ie: tier 3.0.' :r: n:tapplic:ble to-4a ( 16 '" circuits 'hich twe th=4 a c 4 *e"4 '

evercurrent de"ice:

breebaes t-!? ped er te '*0-velt circuite 'htch heve the ineperabia- '

f rcuit breeker recked ettt:-

SURVEILLANCE REQUIREMENTS 4.8.4.2 Each of the primary containment penetration conductor overcurrent protective devices shown in Table 3.8.4.2-1 shall be demonstrated OPERABLE:

a. At least once per 18 months:

1. By verifying that the 4.16-kV circuits are OPERABLE by performing:

a) A CHANNEL CALIBRATION of the associated protective relays, and b) An integrated system functional test which includes simulated automatic actuation of the system and verifying that each relay and assseiated circuit breakers and oveicurrent control circuits function as designed.

FERMI - UNIT 2 3/4 8-17

d RADI0 ACTIVE EFFLUENTS DOSE LIMITING CONDITION FOR OPERATION 3.11.1.2 The dose or dose commitment to a MEMBER OF THE PUBLIC from radio-active materials in liquid effluents released, from each reactor unit, to UNRESTRICTED AREAS (see Figure 5.1.3-1) shall be limited:

a. During any calendar quarter to less than or equal to 1.5 mrems to the total body and to less than or equal to 5 mrems to any organ, and

b. During any calendar year to less than or equal to 3 mrems to the total body and to less than or equal to 10 mrems to any organ.

APPLICABILITY: At all times.

ACTION:

a. With the calculated dose from the release of radioactive materials in liquid effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to Specifica-tion 6.9.2, 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. This Special Report shall also include (1) the results of radiological analyses of the drinking water source and (2) the radiological impact on finished drinking water supplies with regard to the requirements of 40 CFR Part 141, Safe Drinking Water Act.*

b. The provisions of Specification \ 3.0.3 :nd 3.^.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.1.2 Cumulative dose contributions from liquid effluents for the current calendar quarter and the current calendar year shall be determined in accordance with the methodology and parameters in the 00CM at least once per 31 days.

Applicable only if drinking water supply is taken from the receiving water body within 3 miles of the plant discharge.

C FERMI - UNIT 2 3/4 11-5

y RADIOACTIVE EFFLUENTS LIQUID WASTE TREATRENT LIMITING CONDITION FOR OPERATION 3.11.1.3 The liquid radwaste treatment system shall be OPERABLE and appropriate cortions of the system shall be used to reduce the radioactive materials in liquid wastes prior to their discharge when the projected doses due to the liquid effluent, from each reactor unit, to UNRESTRICTED AREAS (see Figure 5.1.3-1) would exceed 0.06 mrem to the total body or 0.2 mrem to any organ in any 31-day pericd.

APPLICABILITY: At all times.

ACTIO3

a. With radioactive liquid waste being discharged and in excess of the above limits and any portion of the liquid radwaste treatment system i

not in operation, prepare and submit to the Commission within 30 days l pursuant to Specification 6.9.2 a Special Report that includes the following information:

1. Explanation of why liquid radwaste was being discharged without complete treatment, 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 1 l

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

are not applicable.

b. The provisions of Specification \ 3.0.3 ud 2.0.

SURVEILLANCE REQUIREMENTS 4.11.1.3.1 Doses due to liquid releases from each reactor unit to UNRESTRICTED AREAS shall be projected at least once per 31 days in accordance with the methodology and parameters in the ODCM.

4.11.1.3.2 The installed liquid radwaste treatment system shall be demonstrated OPERABLE by meeting Specifications 3.11.1.1 and 3.11.1.2.

)

FERMI - UNIT 2 3/4 11-6

( RADIOACTIVE EFFLUENTS i ~ LIQUID HOLOUP TANKS LIMITING CONDITION FOR OPERATION 3.11.1.4 The quantity of radioactive material contained in any outside temporary tank shall be limited to less than or equal to 10 curies, excluding tritium and dissolved or entrained noble gases.

APPLICABILITY: -At all times.

ACTION:

a. With the quantity of radioactive material in any of the above tanks exceeding the above limit, innediately suspend all additions of radioactive materici 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 this condition in the next Semianr,ual Radioactive Effluent Release Report, pursuant to Specification 6.9.1.8.

b. The provisions of Specification \ 3.0.3 r d 3.0.' are not applicable.

(

SURVEILLANCE REQUIREMENTS i

~ 4.11.1.4 The quantity of radioactive material contained in each of the above tanks shall be determined to be within the above limit by analyzing a repre-sentative sample of the' tank's contents at least once per 7 days when radio-active materials are being added to the tank.

(

FERMI - UNIT 2 3/4 11-7

RADIOACTIVE EFFLUENTS )

. DOSE - NOBLE GASES 3

LIMITING CONDITION FOR OPERATION 3.11.2.2 The air dose due to noble gases released in gaseous effluents, from each reactor unit, to areas at and beyond the SITE BOUNDARY (see Figure 5.1.3-1) shall be limited to the following:

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.

APPLICABILITY: At all times.

ACTION

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 6.9.2, 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. TheprovisionsofSpecification\3.0.3and3.0.4arenotapplicable.

SURVEILLANCE REQUIREMENTS 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 niethodology and parameters in the ODCM at least once per 31 days.

FERMI - UNIT 2 3/4 11-12

e RADIOACTIVE EFFLUENTS

(

DOSE - 10 DINE-131,10 DINE-133, TRITIUM, AND RADIONUCLIOES IN PARTICULATE FORM LIMITING CONDITION FOR OPERATION 3.11.2.3 The dose to a MEMBER 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 reactor unit, to areas at and beyond the SITE BOUNDARY (see Figure 5.1.3-1) 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 mrems to any organ.

APPLICABILITY: At all times.

ACTION:

a. With the calculated dose from the release of iodine-131, iodine-133, tritium, and radionuclides in particulate form with half lives greater than 8 days, in gaseous effluents exceeding any of the above limits, prepare and submit to the Commission within 30 days, pursuant to

(. Specification 6.9.2, a Special Report that identifies the cause(s) for exceeding the limit 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 Specification \ 3.0.3 and 3.0.4-are not applicable.

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

FERMI - UNIT 2 3/4 11-13

4 RADIOACTIVE EFFLUENTS )

0FF-GAS TREATMENT SYSTEM LIMITING CONDITION FOR OPERATION 3.11.2.4 The OFF-GAS TREATMENT SYSTEM shall be OPERABLE and shall be in operation.

APPLICABILITY: Whenever the main condenser steam jet air ejectors are in operation.

ACTION:

a. With the OFF-GAS TREATMENT SYSTEM inoperable for more than 7 days, prepare and submit to the Commission within 30 days, pursuant to Specification 6.9.2, a Special Report that includes the following information:

1. Identification of the 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. TheprovisionsofSpecification\3.0.3er.d2.0.4arenotapplicable.

c. The provisions of Specification 4.0.4 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.4 The OFF-GAS TREATMENT SYSTEM shall be demonstrated OPERABLE bj meeting Specifications 3.11.2.1, 3.11.2.2, and 3.11.2.3.

}

FERMI - UNIT 2 3/4 11-14

RADIOACTIVE EFFLUENTS i

VENTILATION EXHAUST TREATMENT SYSTEM LIMITING CONDITION FOR OPERATION 3.11.2.5 The VENTILATION EXHAUST TREATMENT SYSTEM as described in the ODCM shall be OPERABLE and appropriate portions of the system shall be used to reduce radioactive materials in gaseous waste prior to their discharge when the projected doses due to gaseous effluent releases from the site to UNRESTRICTED ,

AREAS (see Figure 5.1.3-1) would exceed 0.3 mrem to any organ in any 31-day period.

APPLICABILITY: At all times.

ACTION:

a. With radioactive gaseous waste being discharged in excess of the above limits and any portion of the VENTILATION EXHAUST TREATMENT SYSTEM not in operation, prepare and submit to the Commission within 30 days pursuant to Specification 6.9.2 a Special Report that includes the following information:

1. Identification of any inoperable equipment or subsystems, and the reason for the inoperability, f- 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. TheprovisionsofSpecification\3.0.3and3.0.4arenotapplicable.

SURVEILLANCE REQUIREMENTS 4.11.2.5.1 Doses due to gaseous releases from the site shall be projected at least once per 31 days in accordance with the methodology and parameters in the 00CM, when any portion of the VENTILATION EXHAUST TREATMENT SYSTEM is not in use.

4.11.2.5.2 The VENTILATION EXHAUST TREATMENT SYSTEM shall be demonstrated OPERABLE by meeting Specifications 3.11.2.1, 3.11.2.2, and 3.11.2.3.

(

FERMI - UNIT 2 3/4 11-15 n

I l

RADI0 ACTIVE EFFLUENTS

)

VENTING OR PURGING LIMITING CONDITION FOR OPERATION 3.11.2.8 VENTING or PURGING of the Mark I containment shall be through the standby gas treatment system or the reactor building ventilation system.

APPLICABILITY: Whenever the containment is vented or purged.

ACTION:

a. With the requirements of the above specification not satisfied, susoend all VENTIt'G and PURGING of the drywell.

b. TheprovisionsofSpecification\3.0.3 cad 3.0.4arenotapplicable.

SURVEILLANCE REQUIREMENTS 4.11.2.8.1 The containment shall be determined to be aligned for VENTING or PURGING through the standby gas treatment system or the reactor building ventilation system within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months prior to start of and at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months during VENTING or PURGING of the containment.

)

4.11.2.8.2 Prior to use of the purge system through the standby gas treatment systen assure that:

a. Both standby gas treatment system trains are OPERABLE whenever the purge system is in use, and

b. Whenever the purge system is in use during OPERATIONAL CONDITION 1 or 2 or 3, only one of the standby gas treatment system trains may be used.

4.11.2.8.3 The containment drywell shall be sampled and analyzed per Table 4.11.2.1.2-1 of Specification 3.11.2.1 within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months prior to the start of and at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months during VENTING and PURGING of the drywell through other than the standby gas treatment system.

)

FERMI - UNIT 2 3/4 11-18

l RADI0 ACTIVE EFFLUENTS j l

3/4.11.3 SOLID RADIOACTIVE WASTE TREATMENT LIMITING CONDITION FOR OPERATION 1

3.11.3 Radioactive wastes shall be SOLIDIFIED or dewatered in accordance with the PROCESS CONTROL PROGRAM to meet 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 transportation requirements, suspend shipment of the inadequately processed wastes and correct the PROCESS CONTROL PROGRAM, the procedures and/or the solid waste system as necessary to prevent recurrence,

b. With SOLIDIFICATION or dewatering not performed in accordance with the PROCESS CONTROL PROGRAM, (1) demonstrate by test or analysis that the improperly processed waste in each container meets the requirements for transportation to the disposal site and for receipt at the disposal site and (2) take appropriate administrative action to prevent recurrence.

r

c. The provisions of Specification \ 3.0.3 =d 3.C.1 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.3 The PROCESS CONTROL PROGRAM shall be used to verify that the properties of the packaged waste meet the minimum stability requirements of 10 CFR Part 61 and other requirements for transportation to the disposal site and receipt at the disposal site.

FERMI - UNIT 2 3/4 11-19 l

l L

o

)

RADIOACTIVE 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 uranium fuel cycle sources shall be limited to less than or equal to 25 mrems to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrems.

APPLICABILITY: At all times.

ACTION:

a. With the calculated doses from the release of radioactive materials in liquid or gaseous effluents exceeding twice the limits of Specifica-tion 3.11.1.2a., 3.11.1.2b., 3.11.2.2a., 3.11.2.2b., 3.11.2.3a., or 3.11.2.3b., calculations should be made including direct radiation contributions from the reactor units and from outside storage tanks to determine whether the above limits of Specification 3.11.4 have been exceeded. If such is the case, prepare and submit to the

".ommission within 30 days, pursuant to Specification 6.9.2, a Special Report that defines the corrective action to be taken to reduce subsequent releases to prevent recurrence of exceeding the above limits and includes the schedule for achieving conformance )

with the above limits. This Special Report, as defined in 10 CFR 20.405c, shall include an analysis that estimates the radiation exposure (dose) to a MEMBER OF THE PUBLIC from uranium fuel cycle sources, including all effluent pathways and direct radiation, for the calendar year that includes the release (s) covered by this report. It shall also describe levels of radiation and concentra-tions 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, the Special Report shall include a request for a variance in accordance with the provisions of 40 CFR Part 190. Submittal of the report is considered a timely request, and a variance is granted until staff action on the request is complete,

b. TheprovisionsofSpecification\3.0.3and3.0.tarenotapplicable.

SURVEILLANCE REQUIREMENTS 4.11.4.1 Cumulative dose contributions from liquid and gaseous effluents 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 00CM.

4.11.4.2 Cumulative dose contributions from direct radiation from the reactor units and from outside storage tanks shall be determined in accordance with the methodology and parameters in the ODCM. This requirement is applicable )

only under conditions set forth in Specification 3.11.4, ACTION a.

FERMI - UNIT 2 3/4 11-20

- RAD 10 LOGICAL-tNVIRONMENTAL MONITORING LIMITING CONDITION FOR OPERATION (Continued)

ACTION: (Continued) locations irom which samples were unavailable may then be deleted from the monitoring program. Pursuant to Specification 6.9.1.8, identify the cause of the unavailability of samples and identify the new location (s) for obtaining replacement samples in the next Semiannual Radioactive Effluent Release Report pursuant to Specifi-cation 6.9.1.8 and also include in the report a revised figure (s) and table for the ODCM reflecting the new location (s). ,

d. The provisions of Specificatior)(3.0.3 =d 3.0.Sare not applicable.

SURVEILLANCE REQUIREMENTS 4.12.1 The radiological environmental monitoring samples shall be collected pursuant to Table 3.12.1-1 from the specific locations given in the table and figure (s) in the ODCM, and shall be analyzed pursuant to the requirements of Table 3.12.1-1 and the detection capabilities required by Table 4.12.1-1.

)

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FERMI - UNIT 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 8 km (5 miles) the location in each of the 16 meteorological sectors of the nearest milk animal, the nearest residence and the nearest garden

of greater than 50 m2 (500 ft ) p:oducing broad leaf vegetation.

2 APPLICABILITY: At all times.

ACTION:

a. With a land use census identifying a location (s) that yields a calcu-lated dose or dose commitment greater than the values currently being calculated in Specification 4.11.2.3, identify the new location (s) in the next Semiannual Radioactive Effluent Release Report, pursuant to Specification 6.9.1.8.

b. With a land use census identifying a location (s) that yields a calculated dose or dose commitment (via the same exposure pathway) 20% greater than at a location from which samples are currently being obtained in accordance with Specification 3.12.1, add the f

1.

new location (s) to the radiological environmental monitoring program within 30 days. The sampling location (s), excluding the control station location, having the lowest calculated dose or dose commitment (s), via the same exposure pathway, may be deleted from this monitoring program after October 31 of the year in which this land use census was conducted. Pursuant to Specification 6.9.1.8, identify the new location (s) in the next Semiannual Radioactive Effluent Release Report and also include in the report a revised figure (s) and table for the ODCM reflecting the new location (s),

c. The provisions of Specification \ 3.0.3 :nd 3.0.' are not applicable, i

SURVEILLANCE REQUIREMENTS 4.12.2 The land use census shall be conducted during the growing eeason at least once per 12 months using that information that will provide the best results, such as by a door-to-door survey, visual survey, aerial survey, or by consulting local agriculture authorities. The results of the land use census shall be included in the Annual Radiological Environmental Operating Report pursuant to Specification 6.9.1.7.

Broad leaf vegetation sampling of at least three different kinds of vegetation may be performed at the SITE BOUNDARY in each of two different direction sectors with the highest predicted D/Qs in lieu of the garden census. Specifications

( for broad leaf vegetation sampling in Table 3.12.1-1, Part 4.c. , shall be followed, including analysis of control samples.

FERMI - UNIT 2 3/4 12-13

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RADIOLOGICAL ENVIRONMENTAL MONITORING

)

3/4.12.3 INTERLABORATORY COMPARISON PROGRAM .

LIMITING CONDITION FOR OPERATION 3.12.3 Analyses shall be performed on radioactive materials supplied as part of an Interlaboratory Comparison Program that has been approved by the Commission.

APPLICABILITY: At all times.

ACTION:

a. With analyses not being performed as required above, report the corrective actions taken to prevent a recurrence to the Commission in the Annual Radiological Environmental Operating Report pursuant to Specification 6.9.1.7.

b. TheprovisionsofSpecification\3.0.3:nd3.0.'arenotapplicable.

SURVEILLANCE REQUIREMENTS 4.12.3 The Interlaboratory Comparison Program shall be described in the ODCM.

A summary of the results obtained as part of the above required Inter-3 laboratory Comparison Program shall be included in the Annual Radiological Environmental Operating Report pursuant to Specification 6.9.1.7.

t i

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FERMI - UNIT 2 3/4 12-14 l

'3/4.0 APPLICABILITY BASES Sp;cifications 3.0.1 through 3.0.4 establish the general requirements applicable to Limiting Conditions for Operation. These requirements are based on the rsquirements for Limiting Conditions for Operation stated in the Code of Federal Ragulations 10 CFR 50.36(c)(2):

"Limiting conditions for operation are the lowest functional capability or p2rformance levels of equipment required for safe operation of the facility.

Whtn a limiting condition for operation of a nuclear reactor is not met, the licensee shall shut down the reactor or follow any remedial action permitted by th2 technical specification until the condition can be met."

Specification 3.0.1 establishes the Applicability statement within each individual specification as the requirement for when (i.e., in which OPERATIONAL CONDITIONS or other specified conditions) conformance to the Limiting Conditions for Operation is required for safe operation of the facility. The ACTION rsquirements establish those remedial measures that must be taken within epscified time limits when the requirements of a Limiting Condition for Operation are not met. Voluntary removal of a system (s) or component (s) from corvice and thus entering an ACTION requirement is permitted. However, voluntary entry into ACTION requirements, particularly those which require a plcnt shutdown, is not intended to be used solely as an operational convenience but should be done only after consideration of other alternatives and the ovarell benefit to plant safety.

Th2re are two basic types of ACTION requirements. The first specifies the rsmidial measures that permit continued operation of the facility which is not further restricted by the time limite of the ACTION requirements. In this case, conformance of the ACTION requirements provides an acceptable level of safety for unlimited continued operations as long as the ACTION requirements continue to be met. The second type of ACTION requirement specii~fes a time limit in which conformance to the conditions of the Limiting Condition for Operation must ba mat. This time limit is the allowable outage time to restore an inoperable systtm or component to OPERABLE status or for restoring parameters within sptcified limits. If these actions are not completed within the allowable outage time limits, a shutdown is required to place the facility in an OPERATIONAL CONDITION or other specified condition in which the specification no longer applies.

Tha 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 systets or component is removed from service for surveillance testing or investigation of operational problems. Individual specifications may include a spreified time limit for the completion of a Surveillance Requirement when B 3/4 0-1 l

l

APPLICABILITY BASES cquipment is removed from service. In this case, the allowable outage time litits of the ACTION requirements are applicable when this limit expires if the curvaillance has not been completed. When a shutdown is required to comply with ACTION requirements, the plant may have entered an OPERATIONAL CONDITION in which a new specification becomes applicable. In this case, the time limits of ths ACTION requirements would apply from the point in time that the new epscification becomes applicable if the requirements of the Limiting Condition for Operation are not met.

Spreification 3.0.2 establishes that noncompliance with a specification exists wh:n the requirements of the Limiting Condition for Operation are not met and tha associated ACTION requirements have not been implemented within the apscified time interval. The purpose of this specification f.s to clarify that (1) implementation of the ACTION requirements within the specified time interval constitutes compliance with a specification and (2) completion of the remedial c2csures of the ACTION requirements is not required when compliance with a Liniting Condition for Operation is restored within the time interval specified in the associated ACTION requirements.

Sp2cification 3.0.3 establishes the shutdown ACTION requirements that must be i plamented when a Limiting Condition for Operation is not met and the condition is not specifically addressed by the associated ACTION requirements. The purpose of this specification is to delineate the time limits for placing the unit in a safe shutdown CONDITION when plant operation cannot be maintained within the limits for safe operation defined by the Limiting Conditions for ,

Oparation and its ACTION requirements. It is not intended to be used as an opsrational convenience which permits (routine) voluntary removal of redundant ayatsms or components from service in lieu of other alternatives that would not result in redundant systems or components being inoperable. One hour is allowed to prepare for an orderly shutdown before initiating a change in plant op2 ration. This time permits the operator to coordinate the reduction in oisctrical generation with the load dispatcher to ensure the stability and svsilability of the electrical grid. The time limits specified to reach lower CONDITIONS of operation permit the shutdown to proceed in a controlled and ordarly manner that is well within the specified maximum cooldown rate and within the cooldown capabilities of the facility assuming only the minimum raquired equipment is OPERABLE. This reduces thermal stresses on components of the primary coolant aystem and the potential for a plant upset that could challenge safety systems under conditions for which this specification applies.

If rsmedial 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 of the ACTION requirements are applicable from tha point in time there was a failure to meet a Limiting Condition for Oparation. Therefore, a shutdown begun under the provisions of Specification 3.0.3 may be terminated if the facility is restored to compliance with the Limiting Conditions for Operation or unexpired ACTION requirements. This provides an allowance for the completion of any remaining ACTION requirements.

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APPLICABILITY BASES Thy time limits of Specification 3.0.3 allow 37 hours4.282407e-4 days 0.0103 hours 6.117725e-5 weeks 1.40785e-5 months for the plant to be in COLD SHUTDOWN when a shutdown is required during POWER operation. If the plant io in a lower CONDITION of operation when a shutdown is required, the time limit for reaching the next lower CONDITION of operation applies. However, if a lower CONDITION of operation is reached in less time than allowed, the total allowable tin 2 to reach COLD SHUTDOWN, or other OPERATIO?ULL CONDITION, is not reduced.

For example, if STARTUP is reached in 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months , the time allowed to reach HOT SHUTDOWN is the next 11 hours1.273148e-4 days 0.00306 hours 1.818783e-5 weeks 4.1855e-6 months because the total time 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 at: cures are completed that would permit a return to POWER operation, a penalty is not incurred by having to reach a lower CONDITION of operation in less than ths total time allowed.

Th3 came principle applies with regard to the allowable outage time limits of the ACTION requirements, if compliance with the ACTION requirements for one spacification results in entry into an OPERATIONAL CONDITION or condition of oparation for another specification in which the requirements of the Limiting Condition for Operation are not met. If the new specification becomes cpplicable in less time than specified, the difference may be added to the cllowable outage time limits of the second specification. However, the ellowable outage time limits of ACTION requirements for a higher CONDITION of op2 ration may not be used to extend the allowable outage time that is applicable whin a Limiting Condition for Operation is not met in a lower CONDITION of operation.

I Tha shutdown requirements of Specification 3.0.3 do not apply in CONDITIONS 4 End 5, because the ACTION requirements of individual specifications define the rsnadial measures to be taken.

Spscification 3.0.4 establishes limitations on a change in OPERATIONAL CONDITIONS when a Limiting Condition for Operation is not met. It precludes piccing the facility in a higher CONDITION of operation when the requirements for a Limiting Condition for Operation are not met and continued noncompliance to these conditions would result in a shutdown to comply with the ACTION raquirements if a change in CONDITIONS were permitted. The purpose of this spreification is to ensure that facility operation is not initiated or that highar CONDITIONS of operation are not entered when corrective action is being tgksn to obtain compliance with a specification by restoring equipment to OPERABLE stetus or parameters to specified limits. Compliance with ACTION rsquirements that permit continued operation of the facility for an unlimited p2riod of time provides an acceptable level of safety for continued operation without regard to 'he status of the plant before or after a change in OPERATIONAL CCRJITIONS. Therefore, in this case, entry into an OPERATIONAL CONDITION or other specified condition may be made in accordance with the provisions of the ACTION REQUIREMENTS. The provisions of this specification should not, however, be interpreted as endorsing the f ailure to exercise good practice in restoring systems or components to OPERABLE status before plant startup.

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s APPLICABILITY

-BASES Wh;n a shutdown is required to comply with ACTION requirements, the provisions of Specification 3.0.4 do not apply because they would delay placing the fccility in a lower CONDITION of operation.

Specification 4.0.1 through 4.0.5 establish the general requirements applicable to Surveillance Requirements. These requirements are based on the Surveillance R3quirements stated in the Code of Federal Regulations, 10 CFR 50.36(c)(3):

"Surveillance requirements are requirements relating to test, calibration, or inspection to ensure that the necessary quality of systems and components is taintained, that facility operation will be within safety limits, and that the limiting conditions of operation will be met".

Sp cification 4.0.1 establishes the requirement that 6. veillances must be parformed during the OPERATIONAL CONDITIONS or other conditions for which the rsquirements of the Limiting Conditions for Operation apply unless otherwise etcted in an individual Surveillance Requirement. The purpose of this spscification is to ensure that surveillances are performed to verify the oporstional status of systems and components and that narameters are within sp;cified limits to ensure safe operation of the facility when the plant is in cn OPERATIONAL CONDITION or other specified condition for which the individual Liniting Conditions for Operation are applicable. Surveillance Requirements do not have to be performed when the facility is in an OPERATIONAL CONDITION for which the requirements of the associated Limiting Condition for Operation do not opply unless otherwise specified. The Surveillance Requirements associated with c Sp:cial Test Exception are only applicable when the Special Test Exception is ursd as an allowable exception to the requiremente of a specification.

Spscification 4.0.2 establishes the conditions under which the specified time interval for Surveillance Requirements may be extended. Item a. permits an ellowable extension of the normal surveillance interval to facilitate curvaillance scheduling and consideration of plant operating conditions that may not be suitable for conducting the surveillance; e.g., transient conditions or oth2r ongoing surveillance or maintenance activities. Item b. limits the use of the provisions of item a to ensure that it is not used repeatedly to extend the survaillance interval beyond that specified. The phrase "at least" associated with a surveillance frequency does not negate this allowable extension; instead, it parmits the more frequent performance of surveillance activities. The limits of Specification 4.0.2 are based on engineering judgment and the recognition th:t the most probable result of any particular surveillance being performed is th2 verification of conformance with the Surveillance Requirements. These provisions are sufficient to ensure that the reliability ensured through curvoillance activities is not significantly degraded beyond that obtained from tha specified surveillance interval.

Sptcification 4.0.3 establishes that the failure to perform a Surveillance R1quirement within the allowed surveillance interval, defined by the provisions of Specification 4.0.2, is a condition that constitutes a failure to meet the B 3/4 0-4

.ge u o

a APPLICABILITY BASES OPERABILITY requirements for a Limiting Condition for Operation. Under the previsions of this specification, systems and components are assumed to be OPERABLE when Surveillance Requirements have been satisfactorily performed within the specified time interval. However, nothing in this provision is to be construed as implying that systems or components are OPERABLE when they are found or known to be inoperable although still meeting the Surveillance R quirements. This Specification also clarifies that the ACTION requirements are applicable when Surveillance Requirements have not been completed within the ellowsd surveillance interval and that the time limits of the ACTION r quirements apply from the point in time it is identified that a surveillance h s not been performed and not at the time that the allowed surveillance interval was exceeded. Completion of the Surveillance Requirement within the allowable outage time limits of the ACTION requirements restores compliance with th2 rsquirements of Specification 4.0.3. However, this does not negate the fact th2t the failure to have performed the surveillance within the allowed survaillance interval, defincl by the provisions of Specification 4.0.2, constitutes a failure to meet the OPERABILITY requirements for a Limiting Condition for Operation and any reports required by 10 CFR 50.73 shall be dsterained based on the length of time the surveillance interval has been excecded, and the corresponding Limiting Conditions for Operation ACTION time rGquirements, as discussed in NUREG 1022, supplement 1,Section II, Item 2.0.

If th2 allowable outage time limits of the ACTION requirements are less than 24 hours2.777778e-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.,

Spscification 3.0.3, a 24-hour allowance is provided to permit a delay in itplcmenting the ACTION requirements. This provides an adee< time limit to complete Surveillance Requirements that have not been performed. The purpose of l thic allowance is to permit the completion of a surveillance before a shutdown

! would be required to comply with ACTION requirements or before other remedial l cassures would be required that may preclude the completion of a surveillance.

Th3 basis for this allowance includes consideration for plant conditions, cdsquate planning, availability of personnel, the time required to perform the l

survsillance, and the safety significance of the delay in completing the required surveillance. This provision also provides a time limit for the co3pletion of Surveillance Requirements that become applicable as a consequence of CONDITION changes imposed by ACTION requirements and for completing Survaillance Requirements that are applicable when an exception to the rsquirements of Specification 4.0.4 is allowed. If a surveillance is not completed within the 24-hour allowance, the time limits of the ACTION rGquirements are applicable at that time. When a surveillance is performed within the 24-hour allowance and the Surveillance Requirements are not met, the tico limits of the ACTION requirements are applicable at the time that the curvsillance is terminated.

Surveillance Requirements do not have to be performed on inoperable equipment b:ccuse the ACTION requirements define the remedial measures that apply.

Hsw2ver, the Surveillance Requirements have to be met to demonstrate that inoparable equipment has been restored to OPERABLE status.

B 3/4 0-5

. .* L^

A APPLICABILITY BASES Specification 4.0.4 establishes the requirement that all applicable

.curvoillances must be met before entry into an OPERATIONAL CONDITION or other condition of operation specified in the Applicability statement. The purpose of thic specification is to ensure that system and component OPERABILITY rsquirements or parameter limits are met before entry into an OPERATIONAL CONDITION or other specified condition for which these systems and components cn ure safe operation of the facility. This provision applies to changes in OPERATIONAL CONDITIONS or other specified conditions associated with plant shutdown as well as startup.

Under the provisions of this specification, the applicable Surveillance R quirements must be performed within the specified surveillance interval to coeume that the Limiting Conditions for Operation are met during initial plant otertup or following a plant outage.

WhIn a shutdown is required to comply with ACTION requirements, the provisions of Specification 4.0.4 do not apply because this would delay placing the fccility in lower CONDITION of operation, r Sp cification 4.0.5 establishes the requirement that inservice inspection of ASME Code Class 1, 2, and 3 components and inservice testing of ASME Code Class 1, 2, and 3 pumps and valves shall be performed in accordance with a p riodically updated version of Section XI of the ASME Boiler and Pressure Vcoasi Code and Addenda as required by 10 CFR 50.55a. These requirements apply cxespt when relief has been provided in writing by the Commission.

This specification includes a clarification of the frequencies for performing th9 inservice inspection and testing activities required by Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda. This clarification is provided to ensure consistency in surveillance intervals throughout the Tachnical Specifiestions and to remove any ambiguities relative to the frcquencies for performing the required inservice inspection and testing cetivities.

Under the terms of this specification, the more restrictive requirements of the Tschnical Specifications take precedence over the ASME Boiler and Pressure Vocoal Code and applicable Addenda. The requirements of Specification 4.0.4 to p2rform surveillance activities before entry into an OPERATIONAL CONDITION or

othat specified condition takes precedence over the ASME Boiler and Fressure Vassal Code provision that allows pumps and valves to be tested up to one week af tor return to normal operation. The Technical Specification definitir a of OPERABLE does not allow a grace period before & compo Not, which is not capable of parforming its specified function, is declared inoperable and teke prcccdence over the ASME Boiler and Pressure ' Code pros.sion that allowt 3

velva to be incapable of performing its spec 3' ' o ts fuc up to 24 hosts b2 fore being declared inoperable.

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ML20154H653

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