Text

Amend 83 to License NPF-43,revising TS 3.0.4 to Define When Provisions Apply
	ML20101T161
Person / Time
Site:	Fermi ; (NPF-43-A-083, NPF-43-A-83)
Issue date:	06/25/1992
From:	Marsh L; Office of Nuclear Reactor Regulation
To:	;
Shared Package
ML20101T162	List: ML20101T161; ML20101T169;
References
	NUDOCS 9207200318
	Download: ML20101T161 (55)
	v • d • e

.

S

[

4 k';

UNIT ED STATES NUCLEAR REGULATORY COMMISSION wassmovow. o.c. rosss gv /

....+

DETROIT EDISON COMPANY, FERMI-2

@CKET NO. 50-341 AMENDMENT 10 FACILITY OPERATI%j,1 CENSE Amendment No. 83 License No. NPF-43 1.

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

A.

The application for amendment by the Detroit Edisen Company (the licensee) dated May 24, 1988 as supplemented February 27, 1991, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I; B.

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

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

The issuance of this amendment will not be inimical to the common defense and security or to the health'and safety of the public; and E.

The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment and paragraph 2.C.(2) of Facility Operating License No. NPF-43 is hereby amended to read as follows:

Technical Specifications and Environmental Protection Plan The Technical Specifications contained in Appendix A, as revised through Amendment No. 83, and the Environmental Protection. Plan contained in Appendix B, are hereby incorporated in the license.

Deco shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

9207200318 920625 PDR-ADOCK 05000341 P

PDR

}

t ATTACHMENT TO LICENSE AMENDMENT NO. 83 FACIllTY OPERATING LICENSE NO. NPF-43 DOCKET NO. 50-341 Replace the following pages of the Appendix "A" Technical Specifications with the attached pages. The revised pages are identified by Amendment number and contain a vertical line indicating the area of change.

REMOVE INSERT 3/4 0-1 3/4 0-1 3/4 1-4 3/4 l'4 3/4 1-5*

3/4 1-5*

i 3/4 1-6 3/4 1-6 3/4 1-7*

3/4 1-7*

3/4 1-8 3/4 1-8 3/4 1-9 3/4 1-9 3/4 1-10 3/4 1-10 3/4 1-11 3/4 1-11 3/4 1-14 3/4 1-14 3/4 1-16 3/4 1-16 3/4 2-7 3/4 2-7 3/4 3-1 3/4 3-1 3/4 3-9 3/4 3-9 3/4 3-26 3/4 3-26 3/4 3-38 3/4 3-38 3/4 3-47 3/4 3-47 3/4 3-48*

3/4 3-48*

3/4 3-51 3/4 3-51 3/4 3-52*

3/4 3-52*

3/4 3-53*

3/4 3-54 3/4 3-54

-3/4 3 -3/4 3-65 3/4 3-66 3/4 3-66 3/4-3-70 3/4 3-70 3/4 3-76 3/4 3-76 3/4 4-1 3/4 4-1 3/4 4-13 3/4 4-13 3/4 4-14*

3/4 4-14*

3/4 4-23*

3/4 4-24 3/4 4-24 3/4 4-25 3/4 4-25 3/4 6-7*

3/4 6-7*

3/4 6 3/4 6-8 3/4 6-19*

3/4 6-19*

3/4 6-20 3/4 6-20 3/4 7-6 3/4 7-6 3/47-6.

3/4 7-6a

0verleaf pages provided to maintain document completeness.

No changes contained in these pages.

~

ATTACHMENT 10 ll{ENSE AMENDMENT NO. 83 FAClliTY OPERATING LICENSE-NO. NPF-43 DOCKET NO. 50-341 7

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

T1e revised pages are identified by Amendment number and contain-a vertical line indicating the area of change.

t EBQXI ltlSlfil j.

3/4 7-21*

3/4 7-22 3/4 7-22 3/4 B-17 3/4 8-17 3/4 8-18*

3/4 8-18*

3/4 11-7 3/4 11-7 8 3/4 0-1 0 3/4 0-1 B 3/4 0-2 B 3/4 0-2 B 3/4 0-3 8 3/4 0-3 B 3/4 0-4 B 3/4 0-5 B 3/4 0-6 B 3/4 0-7

0verleaf pages provided to maintain document completeness.

No changes contained in these pages.

?

3/4.0 AppLlCABitITY LIMITjNGCONDITIONFOROPERATl0N 3.0.1 Compliance with the limiting Conditions for Operation contained in the succeeding Specifications is r2 quired 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 Noncompliante with a Specification shall exist when the requirements of 6

the Limiting Condition for Operation anr' associated ACTION requirements are not met within the specified time intervah.

If the Limiting Condition for Operation is restored prior to expiration of the spECified time intervals, completion of the ACTION requirements is not required.

3.0.3 When a limiting Condition for Operation is not met, except as provided in the associated ACTION requirements, within one hour action shall b2 initiatea to place the unit in an OPERA 110NAL 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 .

Where corrective measures are completed that permit operation under the ACTION requirements, the ACTION may be taken in accordance with the specified time limi+ s as measured from the tire of f ailure to meet the limiting Condition for Operation.

Exceptions to these requirements are stated in the individual Specifications.

This Specification is not applicable in OPERATIONAL CONDITION 4 or 5.

3.0.4 Entry into an OPERATIONAL CONDil10N or other specified condition shali I

not be made when the conditions for the Limiting Conditions for Operation at e I

not ret and the associated ACTION requires a shutdown if they are not met I

within a specified tire interval.

Entry into an OPERATIONAL CONDll10N or I

other specified condition may be made in accordance with the ACTION I

requirements when conformance to them permits continued operation of the facility for an unlimited period of time.

This provision shall not prevent I

I passage through or to OPERA 110NAL CCNDITIONS as required to comply with ACTION I

require ents.

Exceptions to these requirements are stated in the individual Specifications.

FERMI - UNIT 2 3/4 0-1 Amendment No. 83

REACTIVITY CONTROL SYSTEMS LIMITING CONDITION FOR OPERATION (Continued)

ACTION:

(Continued) 2.

If the inoperable control rod (s)-is inserted, within I hour 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 .

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

4 e.

With any scram discharge volume vent valve (s) and/or any scram discharge volume drain valve (s) otherwise inoperable, restore the 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 SHUTDOWN within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

SURVElllANCE RE0VIREMENTS 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, 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.

lhese valves may be closed intermittently for testing under administrative controls.

- May be rearme, ntermittently, under administrative control, to permit testing associated with restoring the control rod to OPERABLE status.

FERMI - UNIT 2 3/4 1-4 Amendment No. E7, 83,

~_

- -. = -. _ -

i REACTIVITY CONTR01. SYSTEMS SURVElllANCE RE0VIREMENTS (Continued) 4.1.3.1.3 All control rods shall be demonstrated OPERABLE by performance of Surveillance Requirements 8.1.3.2, 4.1.3.4, 4.1.3.5, 4.1.3.6, and 4.1.3.7.

4.1.3.1,4 The scram discharge volume shall be determined OPERABLE by demonstrating:

a.

The scram discharge volume drain and vent valves OPERABLE at least once per 18 months, by verifying that the drain and vent valves:

1.

Close within 30 seconds after receipt of a signal for control rods to scram, and 2.

Open when the scram signal is reset.

b.

Proper float response by verificatior of proper float switch actuation within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months after each scram from a press.urized condition greater than or equal to 900 psig.

P 1

i FERMI - UNIT 2 3/4 1-5

~-.

E[ ACTIVITY CONTROL SYST[M1 CONTROL ROD MAXIMUM SCRAM INSERTION TIMES LIMITING CONDITION FOR OPERATION 3.1.3.2 The' maximum scram insertion time of each control rod from the fully withdrawn position to notch positior 6, based on deenergization of the scram pilot vrive solenoids as time zerc, shall not exceed 7 seconds.

APPLICABILITY:

OPERATIONAL CONDITIONS I and 2.

AG M:

a.

With the maximum scram insertion time of one or more co. trol 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 control rods with maximum scram insertion times ir. 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 .

l E.URVEILLANCE RE0UIREMENTS 4.1.3.2

.The maximum scram insertion time of the control rods shall be demonstrated through measurement with reactor coolant pressure greater than or equal to 950 psig and, during single control rod scram time tests, the control rod' drive pumps isolated from the accumulators:

For all control rods prior to THERMAL POWER exceeding 40% of RT )

a.

THERMAL POWER follow'-] CORE ALTERATIONS or after a reactor shutdown that is greater than 120 days.

b.

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.

i l

l FERMI'- UNIT 2 3/4 ?-6 Amendment No. 83

9 REACTIVITY CONTROL SYSTEMS Q?{TROLPJD AVERAGE SCRAM lilSERTION TlHES.

MQUiG CONDIT101 FOR OPERATION 3.1.3.3 The average scram insertion time of all OPERABLE cor. trol rods from the f ully withdrawn position, based on de-energization of the scrcn pilot valve solenoids as time zero, shall not exceed any of the following:

Position Inserted from Average Scram insertion Time

._ fr.)h_WlthdrJFL___

. - MLC7Edik 46 0.358 36 1.096 26 1.860 6

3.419 Apr'LIC ABILITY:

OPERATIONAL C0!l01110f15 1 and 2.

ACTION:

With the average scram insertion time exceeding any of the above limits, be in at least HOT SHUTDOWil within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

SURVEltLAfKE REQUIREMENTS 4.1.3.3 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 - Utili 2 3/4 1-7

I REACTIVITY CONTROL SYSTEMS FOUR CONTROL ROD' GROUP 3 CRAM INSERTION TIMES

{

llMITING CONDITION FOR ODERATION-1.1.3.4 The average scram ir,sertion time, from the fully withdrawn position, Tsi the three fastest control rods in each group of four control rods arranged in a two by-two. array, based on deenargization of the scram pilot valve solenoids as time zero, shall not exceed any of-the following:

7 Position Inserted From Average Scram Insertion Time r lly Withdrawn (Seconds) 6 u

e 46-0.379 36 1.161 26 1.971 6

3.624 APPLICABILITY:- OfERATIONAL CONDITIONS I and 2.

ACTION:

With the hverage scram insertion times of control rods exceeding the a.

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 slow 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 aver. age' scram insertion time (s) in excess of the iverage 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 .

- ).U3yDUJJLCL%QMIREMENTS v.,

.i All control rods shail be demonstrated OPERABLE by scram time testing fully withdrawn position as required by Surveillance Requirement

,,e I

l FERMI - UNIT 2 3/4 1-8 Amendment No.83 l

h

REACTIVITY CONTROL SYSTEM 1 i

CONTROL ROD SCRAM ACCUMULATORS LIMITING 'JNDITION FOR OPERATION

- 3.1.3.5 All ci ci-ol rod scram accumulators shall be OPERABLE.

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

J ALIl23:

a.

In OPERATIONAL CONDITION 1 or 2:

1.

With one control rod scram accumulator inoperable, within 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 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 it hours.

2.

With more than one control rod scram accumulator inoperable, declere the associated control rods inoperable and:

a)

If the control rod associated with any inoperable scram accumulator is withdrawn, immediately 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 a 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 .

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.

CERMI - UNIT 2 3/4 1-9 Amendment No. 83 l

REACTIVITY CONTROL SYSTEMS 4

L]MITINGCONDITIONFOROPERATION(Continued)

A(TlDB: (Cantinued) b.

In OPERATIONAL CONDITION 5*:

1.

With one withdrawn control red with its associated scram 1

accumulator inoperable, insert the affected control rod and disarm the associtted directional control valves within I hour, either:

a)

Electrically, or b)

Hydraulically by closing the drive water and exhaust water isolation valves.

2.

With more than one withdrawn control rod with the associated scram accumulator inoperable and no control rod drive pump operating, immediately place the reactor mode switch in the

$1utdown position.

SURVElllANCE RE0VIREMENTS 4.1.3.5 Each control rod scram accumulator shall be determined OPERABLE:

At least once per 7 days by verifying that the indicated pressure a.

is greater than or equal to 940 psig unless the control rod is inserted-and disarmed or scrammed.

b.

At least once per 18 months by:

1.

Performance of a:

a)

CHANNEL FUNCTIONAL TEST of the leak detectors, and b)

CHANNEL CALIBRATION of the pressure detectors, and verifying an alarm setpoint of greater than or equal to 940 psig on decreasing pressure.

2.

Measuring and recording the time for at least 10 minutes that each individual accumulator check valve maintains the associated accumulator pressure above the alarm set point with no control rod drive pump operating.

At least the accumulator associated with each withdrawn control rod.

Not applicable to control rods iemoved per Specification 3.9.10.1 or 3.9.10.2.

FERMI - UNIT 2 3/4 1-10 Amendment No. E,B3

- )

J

q i

REACTIVITY C0'4 Trpl SYSTEMS

]

CONTROL ROD ORIVE COUPLING LIMIT]NGCONDITIONFOROPERATION 3.1.3.6 All control rods shall be coupled to their drive mechanisms.

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

]

ACllpff:-

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 RWM, insert the control rod drive mechanism to accomplish recoupling and verify recoupling by withdrawing the control rod, and:

a)

Observing any indicated response of the nuclear instrumentation, and b)

Demonstrating that the control rod will not es to the overtravel position.

2.

1, recoupling is not accomplished on the first attempt or, if not permitted by-the RWM, then until permitted by the RWM, declare the control rod inoperable, 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.

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 .

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 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.

i

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 testing associated with restoring the control rod to OPERABLE status.

_ FERMI'- UNIT 2 3/4 1-11 Amendment No. E7,83

. ~ -.

r

. [_

REACTIVITY CONTROL SYSTEMS 1JH11U1GCONDITIONFOROPERATION(Continued)

ACTION:' (Continued) b.

In OPEPAT10NAL CONDITION 5' with a withdrawn control rod position indicator inoperable, move the control rod to a position with an OPERABLE 7 '-

position indicator or insert the control rod, j,URVEILI.ANCEREQUIREMENTS_

4.1.3.7

-The control rod psition indication system shall be determined 4

ODERABLE 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 performing Surveillance Requirement 4.1.3.1.2,.and c.

That the control rod position indicator corresponds to the control rod position indicated by the " Full _out" position indicator when r

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 Amendment No. 57,83, 1

-e s.

Rf ACTIVITY rRJ1QL SYSTEMS 3/4, L 4 _ CONTROL @D PROGRA110El@LS R0D WORTH MIN 141Z1E t MITING CONDITION _FOR OPERATION 3.1.4.1 The rod worth minimizer (RWM) shall be OPERACLE.

1 APPLL(fJlLITY: OPE ATIONAL CONDITIONS I and 2*, when THERMAL POVER is less than or equal to 10% 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. -The use of this arovision during reactor startup prior to the first 12 control rods seing fully withdrawn is restricted to one startup per calendar year. Otherwise, control rod movement may be only by actuating the

. manual scram or placing the reactor mode switch in the shutdown position.

l

-SURVElttANCE REQUIREMENTS 4.1.4.1 The RWM shall be demonstrated OPERABLE:

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 I hour after RWM automatic initiation 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 B hours prior to withdrawal of control rods for the purpose of.iaking the reactor critical, by-verifying the rod block function by demonstrating inability to withdraw an out.f-senuence control rod (after seier. tion of first control ?oa;.

c.

In OPERATIONAL CONDITION 1 within I hour after RWM automatic

-initiation when reducing THERMAL POWER, by demonstrating the withdraw block and insert block functions.

d.

By demonstrating that the Banked Position Withdrawal sequence input to the RWM ccmputer is correctly loaded following any loading of the program into the esmputer.

Entry into OPERATIONAL CONDITION 2 and withdrawal of selected control rods is permitted for the purpose of determining the OPERABILITY of the RWM prior to withdrawal of control rods for t' e purpose of bringing the reactor to criticality.

FERMI - UNIT 2 3/4 1-16 Amendment No. /2, E7,83,

t '.

EQWER DISTRIBUTION L))i115 2/4.2.3 MINIMUM CRITICA M 0WER RATIO

},JjijTING CONDITION FOR OPERATION APPLIClQlulf.:

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

AC.Il03:

a.

With MCPR less than the applicable MCPR limit in the COLR, 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 ineperable and/or the moisture separator reheater inoperable per Specification 3.7.9, operation may continue provided L

r that, within one hour, MCPR is determined to be equal to or greater than the applicable MCPR. limit in the COLR.

SURVElllANCE REQUIREMENTS 4.2.3.1 MCPR, with.

.a.

t-1.0 prior to performance of the initial scram time ~ measurements for the cycle in accordance with Specification 4-l.3.2, or b.

t as defined in Specification 3.2.3 used to determine the limit within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .of the conclusion of each scram time surveillance test required by Specification 4.1.3.2, shall be determined to be equal to or greater than the applicable MCPR limit specified in the CORE OPERATING LIMITS REPORT (COLR):

a.

At least on a per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , b.

.Within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months after completion of the a THERMAL POWER increase of at least 15% of PATED THERMAL POWER, and c.

Initially an't at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months when the reactor is operating with

'a LIMITING CONTROL R0D PATTERN for MCPR.

d..

The provisions of Specification 4.0.4 are not applicable.

4.2.3.2 Prior to the use of a MCPR limit which is based upon a specific control rod pattern and whenever Surveillance Requirement 4.2.3.1 is performed while using a MCPR limit based upon a specific control rod pattern, the required control rod pattern shall be verified.

FERMI - UNIT 2 3/4 2-7 Amendment No. //, //, EA,33,

r

'gl N

3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR PROTECTION SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERAT!0N 3.3.I' As a minimum, the reactor protection system instrumentation channels shown in Table 3.3.1-1 shall be OPERABLE with the REACTOR PROTECTION SYSTEM RESPONSE TIME as shown in Table 3.3.1-2.

a 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:

1.

Within I hour, verify that caen Functional Unit within the affected trip system contains no more than one inoperable channel or place the inoperable channel (s) and/or that tri!

system in the tripped condition *.

2.

If placing the inoperable channel (s) in the tripped condition would cause a scram, the inoperable channel (s) shall be restored to OPERABLE status within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months or the ACTION required by Table 3.3.1-1 for the affected Functional Unit shall be taken.

3.

If placing the inoperable channel (s) in the tripped condition would not cause a scram, place the inoperable channel (s) and/or that trip system in the tripped conditicn withi.i 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

l b.

With the number of OPERABLE channels less than required by the Minimur "T3LE Channels per Trip System requirement for both trip system /. ob 3 at least one trip s/ stem ** in the tripped condition within i ? > 2r ani take the ACTION required by Table 3.3.1-1.

An inoperable channel need not be placed in toe tripped condition where this would.cause a scram to occur.

In the::e 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 after the channel was first determined to be inoperable n the ACTION required by Table 3.3.1-1 for that Functional Unit shall be t k

- The trip system need not t

aced in the tripped condition if this would cause a scram to occur.

knen a trip system can be placed in the tripped condition without causing a scram to occur, place the trip system with the L

mort inoperable cht.iels in the tripped condition; if both systems have the j

same number of inoperable channels, place either trip system in the tripped l

condition.

l-FER511 - UNIT 2 3/4 3-1 Amendment No. 7E,83

f INSTRUMENTATlqH 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 OPEP.ABLE 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 TlHE as shown in Table 3.3.2-3.

APPLICABIL11X: As shown in Table 3.3.2-1.

.A_(ILQU:

a.

With an isolation actuation instrumentation 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 r2 tored to CPERABLE 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:

1.

If placing the inoperable channel (s) in the tripped condition would cause an isolation, the iroperable channel (s) shall be restored to OPERABLE status within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months or the ACTION required by Table 3.3.2-1 for the affected trip function shall be taken.

2.

If placing the inoperable channel (s) in the tripped condition would not cause an isolation, the inoperable channel (s) and/or that trip system shall be placed in the tripped condition within:

a) 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months for trip functions common to RPS Instrumentation; and b) 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months for trip functions not' common to RPS Instrumentation.

I c.

With the number of OPERABLE ch..nnels less than required by the Minimum OPERABLE rhannels per Trip System requirement for both trip systems, place at least one trip system

in the tripped condition within one hour and take the ACTION required by Table 3.3.2-1.

Place one trip system (with the most inoperable channels) in the tripped condition. The trip system need not be placed in the tripped conditior when this would cause the isolation to occur.

FERlli - UNIT 2 3/4 3-9 Amendment No. /J, 7E, 83,

TABLE 3.3.3-1 (Continued)

EMERGENCY CORE' COOLING SYSTEM ACTUATION INSTRUMENTATION ALIl0N STATEMENTJ, 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, place that trip system in the tripped condition within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or declare the associated ECCS l_

inoperable.

b.

For both trip systems, declare the associated ECCS inoperable.

ACTION 31 -

With the number of CPERABLE channels less than required by the Minimum OPERABLE Channels per Trip System requirement, declare the associated ADS Trip System inoperable within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

ACTION 32 -

With the number of OPERABLE channels less than required by the Minimum 0PERABLE Channels per Trip System requirement, place the inoperable channel in the tripped condition within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

ACTION 33 -

Restore the manual initiation and/or manual inhibit function to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or declare the associated ECCS or ADS Trip System inoperable.

ACTION 34 -

With the number of OPERABLE channels less than rcQuired by the t

Minimum OPERABLE Channels per Trip System requirement, place at least one inoperable channel in the tripped condition within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months , align the HPCI system to take suction from the suppression 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 o

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 and take the ACTION required by Specification 3.8.1.1 or 3.8.1.2, as appropriate.

l I

l l

FERM1 - UNIT 2 3/4 3-26 Amendment No. JE, /E, 83,

.=

'ABLE 3.3.5-1 (Continued) i EEACTOR CORE 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 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or declare the RCIC system inoperable, b.

For both trip systems, declare the RCIC system inoperable.

With the number of OPERABLE channels less than required by the ACTION 51 -

tiinimum OPERABLE Channels per Trip System requirement, place at least one inoperable channel in the tripped condition within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or align RCIC to take suction from the suppression pool or declare the RCIC system inoperable.

ACTION 52 -

Restore the manual initiation function to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or declare the RCIC system inoperable.

l FERM1 - UNIT 2 3/4 3-38 Amendment No. 7E, EG,

INSTRUMENTATION 1/4.3.7 MONITORING INSTRUMENTATION RADIATION MONITORING INSTRUMO.TATlQy LIMITING C_0NDITION FOR OPERATION 3.3.7.1 The radiation monitoring instrumentation channela shown in Table 3.3.7.1-1 shall be OFiRABLE 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 setpoint exceeding the valta shown in Table 3.3.7.1-1, adjust the setpoint to within the limit within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months or declare the channel inoperable, b.

With one or more radiation monitoring channels inoperable, take the ACTION required by Table 3.3.7.1-1.

c.

The provisions of Specification 3.0.3 are not applicable, j

SURVElllANCE 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 CAllBRATION operations for the

~

conditions and at the frequencies shown in Table 4.3.7.1-1.

FERMI - UNIT 2 3/4 3-47 Amendment No. 83, 1

z TABLE 3.3.7.1-1 b

RADIATION MONITORING INSTRUMENTATION b

HINIMUM CilANNELS APPLICABLE ALARM /rRIP

[

INSTRUMENTATION OPERABLE CONDITIONS SETPOINT ACTION 1.

Control Center Normal 2

1,2,3,5 and

s 340 cpm 70 Makeup Air Radiation (s 5 mR/hr)

Monitor 2.

Area Monitors a.

Criticality Monitors

1) New Fuel 1

2 5 mR/hr 71 Vault s 20 mR/hr 1

Y

2) Fuel Storage Pool 2

a 5 mR/hr 72 l

and s 20 mR/hr(a) b.

Control Roem Direct I

At all times s 0.5 mR/hr(a) yg Radiation Monitor E

a

.i!F 1

-=

w:

e e

-INSTRUMENTATION-SEISMIC MONITORING =1NSTRUMENTAT10N LIMITING CONDITION FOR OPERATION 3.3.7.2 The -seismic monitoring instrumentation shown in Table 3.3.7.2-1 shall be OPERABLE.

APPLICABIL111: At all times.

ACTION:

a.

With one or more of the above required seismic monitoring 1 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 outlin'ing the cause of the malfunction and' the plans for restoring the instrument (s) to OPERABLE status, b.

The' provisions: of Specification 3.0.3 are not applicable.

l SURVEILLANCE RE0U.1REMENTS

'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 FUNCTIONAL 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 CAllBRATION 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.

FERMI - UNIT 2 3/4 3-51 Amendment No. Eg,

~.

p.

,c TABLE 3.3.7.2-1 SEISMIC MONITORING INSTRUMENTATION MINIMUM-

-MEASUREMENT INSTRUMENTS-

-INSTRUMENTS'AND SENSOR LOCATIONS RANGE OPERABLE

-s,

- 1.

~ Active' Triaxial. System a.

LActive Triaxial Accelerometers 1)

HPCI Room 11 g 1.

2)

Base of RPV Pedestal. In'Drywell.

il 9 1

b.

_ Active. Seismic Recording System

1);

. Relay Room; Auxiliary Building NA 1**

c.-

Active Seismic-Playback. System 1)

Relay Room, Auxiliary Building -

NA NA 2.

Passive Triaxial Peak Sh'ock Recorders Ta.

HPCILRoom

-1

'b.

Relay Room, Auxiliary Building.

1

c.

Refuel Floor;-Reactor Building 1

d.

-Diesel Generator Room,-RHR Complex-1-

-e.

Pump Room,.RHR' Complex-ll f.

Cooling Tower, RHR-Complex 1

~

Includingseismicftrigger.

**With reactor control room annunciation.

- - Each passive accelerometer-bas 12-reeds, each monitoring a different

frequency. EThe: f requencies correspond-to varying ' accelerations.

The widest-range is i 90 g.

-FERMI UNIT 2 3/4 3-52 i

i

- c...

TABLE 4.3.7.2-1 SEISMIC MONITORING INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL CHANNEL FUNCTIONAL CHANNEL

. INSTRUMENTS AND SENSOR LOCATIONS CHECK TEST CALIBRATION 1.

Active Triaxial System a.

Active Triaxial Accelerometers

-1) '

HPCI Room' NA SA R

2)

Base of RPV Pedestal, In Drywell.

NA SA R

b.

Active Seismic Recording System

1)

Relay Room, Auxiliary Building **

M(a)

SA R

c.

Active seismic Playback System

1).

Relay Room, Auxiliary Building M

SA R

2.

Passive Triaxial Peak Shock Recorders a.

'HPCI Room NA NA R

b.

Relay Room, Auxiliary Building NA NA R

c.

~ Refuel Floor, Reactor NA.

R Building NA d.

Diesel Generator Room, RHR Complex NA NA R

e.

= Pump Room, RHR Complex NA NA R

f.

Cooling Tower RHR Complex NA NA R

~* Including seismic trigger.

- With. reactor control room annunciation.

(a)Except seismic trigger.

l FERMI - UNIT 2 3/4 3-53

[

INSTRUMENTATION

. METEOR 01QGICAL MONITORING INSTRUMENTATION llMITING CONDITION FOR OPERATION

.3.3.7.3-The meteorological monitoring instrumentation channels shown in Table 3.3.7.3-1 shall be OPERABLE.

-3 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 instrurnentation to OPERABLE status.

b.

The provisions of Specification 3.0.3 are not applicable.

l j-

' SURVEILLANCE RE0VIPEMENTS 4.3.7.3 Each of the above~ required meteorological monitoring instrumentation channel; shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK and CHANNEL CAllBRATION operations at the frequencies shown in Table 4.3.7.3-1.

4 i

FERMI - UNIT 2 3/4 3-54 Amendment No.83,

=

- - ~ - - -

'114STRUMENTAT10N'

. 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 are not applicable.

l SURVEILLANCE RE0VIREMENTS 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.

0nly the detector (s) in the required measurement location (s) are required to be OPERABLE.

FERMI - UNIT 2 3/4 3-65 Amendment No. 83,

INSTRUMENTATION CHLORINE DETECT 10N' SYSTEM LIMITING CONDITION FOR OPERATION 03.3.7.8 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.

APPLICABillTY:

All '0PERATIONAL -CONDITIONS.

ACTION:

With one chlorine ' detector inoperable, restore the inoperable detector a.

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 emergency intakes by-placing the HVAC system in the chlorine mode of operation.

b.

With both chlori.ne 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.

I SURVE!LLANCE-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 CALIBRAT?0N at least once per 18 months.

FERMI - UNIT 2 3/4 3-66 Amendment No. 83,

INSTRUMENTATION i

1,00SE-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 d

the channel (s) to OPERABLE status.

b.

The provisions of Specificatior. 3.0.3 are not applicable, j

SURVEILLANCE RE0VIREMENTS 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 CAllBRATION at least once per 18 months.

f, 1

FERMI - UNIT 2 3/4 3-70 Amendment No. 83,

^~^

,g L.(

^

INSTRUMENTATION-l EXPLOSIVE GASlMONITORING INSTRUMENTATION:

=

fLIMITING CONDITION FOR OPERATION 3.3.7.12 The explosive gas monitoring-instrumentation channel shown in-Table-

=3.3.7.12-1 shall be OPERABLE with its-alarm. setpoint set to ensure that the -

t11mits-of Specification-3.ll.2.6 are not exceeded.

APPLICABillTY: ;AsLshown in Table-3.3.7.'12-1 ACTION:'

a.

With-aniexplosive _ gas monitoring instrumentation _ channel alarm _.

setpoint less conservative than required by the above Specification, declare the channel; inoperable:and take ACTION shown in Table a L3.3.7.12-1; or change.the1setpointiso it is acceptably: conservative.

b.-

With1dTs;thantheminimumnumberofexplosivegasmonitoring-

= instrumentation channels OPERABLE, take the' ACTION shown in Table

+

3. 3.~ 7.12 - 1. Mestore thefinoperable instrumentation ^ to OPERABLE status within 30-days and, if unsuccessful, prepare and submit a

special. report to the-Commission-pursuant to Specification 6.9.2 to

-explain-why_this inoperability was notfcorrected in a timely manner.

c6 11he. provisions of Specification 3.0.3 are not _ applicable.-

l SURVEILLANCE REQUIREMENTS 4.3.7.121 Each explosive gas monitoring instrumentation channel shall be

~

' demonstrated OPERABLE by performance of the CHANNEL CHECK, CHANNEL CALIBRATION fand CHANNEL' FUNCTIONAL TEST operations at the frequencies shown in_ Table 413;7.12-1;.

t SP a

8

.i

' FERMI LUNIT?2

-3/4 3-76 Amendment No. //, E2, 83,,

,, J, O G

__L-.,'..

es.-~-

r-.c.

..-.v-r y-,--

-.-,.--2

-e

3/4.4 REACTOR COOLANT SYSTEM 3/4.4.1 RECIRCULATION SYSTEM RECIRCULATION LQQ21 LIMITING CONDITION FOR OPERATION 3.4.1.1 Two reactor coolant system recirculation loops shall be in operation.

APPLICABILITY:

OPERATIONAL CONDITIONS 1 and 2*.

ACTION:

a.

With one reactor coolant system recirculation loop not in operation:

1.

Within 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months s:

a)

Place the ir,Jividual recirculation pump flow controller for the operating recirculation pump in the Manual mode, b) Reduce THERMAL POWER to less than or equal to 70% of RATED THERMAL POWER.

c)

Limit the speed of the operating recirculation pump to less than or equal to 75% of rated pump speed.

d)

Increase the MINIMUM CRITICAL POWER RATIO (MCPR) Safety Limit by 0.01 to 1.08 per Specification 2.1.2.

e)

Reduce the Maximum Average Planar Linear Heat Generation Rate (MAPLHGR) limit.per Specification 3.2.1.

f)' Reduce the Average Power Range Monitor (APRM) Scram and Rod Block Trip Setpoints and Allowable Values # o those applicable for t

single recirculation loop operation per Specifications 2.2.1 and 3.3.6.

g)

Perform Surveillance Requirement 4.4.1.1.4 if THERMAL POWER is less than or equal to 30% of RATED THERMAL POWER or the recirculation loop flow in the operating loop is less than or equal to 50% of rated loop flow.

, 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 .

l b.

With no reactor coolant system recirculation loop in operation while in OPERATIONAL CONDITION 1, immediately place the Reactor Mode Switch in the SHUTDOWN position.

c.

With no reactor coolant system recirculation loops in operation, while in OPERATIONAL CONDITION 2, initiate measures to place the unit in at least

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

See Special Test Exception 3.10.4.

APRM gain adjustments may be made in lieu of adjusting the APRM Flow Biased Setpoints to comply with the single loop values for a period of up to l

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

FERMI - UNIT 2 3/4 4-1 Amendment No. EJ, Ef, E9,83, t

i

't 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.

APPLICABillTY:

At all times.

ACTION:

a.

In OPERATI0!lAL 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 Commission, i

2.

With the conductivity, chloride concentration or pH exceeding the j

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 SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN 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 3.4.41 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 SHUT 00Wil within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months anu 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 condition on the structural integrity of the reactor coolant system. Determine that the structural integrity of the reactor coolant system remains acceptable for continued operation prior to proceeding to OPERATIONAL CONDITION 3.

2.

The provisions of Specification 3.0.3 are not applicable.

FEFMI - UNIT 2 3/4 4-13 Amendment No. 83,

REACTOR COOLANT SYSTEM SURVEllLANCE REQUIREMENT 4.4.4 The reactor coolant shall be dttermined to be within the specified chemistry limit by:

a.

Measurement prior to pressurizing the reactor during each startup, if not performed within the previous 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

b.

Analyzing a sample of the reactor coolant for:

1.

Chlorides at least once per:

a) 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , and b) 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months whenever conductivity is greater than the limit in Table 3.4.4-1.

\\

2.

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

3.

pP at least once per:

a) 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months , and b) 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months whenever conductivity is greater than the limit in Table 3.4.4-1.

c.

Continuously recerding the conductivity of the reactor coolant, or, when the continuous recording conductivity monitor is inoperable by obtaining an in-line conductivity measurement at least once per:

1.

4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months in OPERATIONAL CONDITIONS 1, 2, and 3, and 2.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 6' all other times.

d.

Performance of a CHANNEL CHECK of the continuous conductivity monitor with an in-line flow cell at least once per:

1.

7 days, and 2.

24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months whenever conductivity is greater than the limit in Table 3.4.4-1.

FERMI - UNIT 2 3/4 4-14 1

REACTOR COOLANT SYSTEM

~ REACTOR-STEAM DOME

'llMITING CONDITION FOR OPERATION' 3.4.6.2-The pressure in the reactor steam dome shall-be _less than'1040 psig.

APPLICABILITY:

0PERATIONAL CONDITIONS l* and 2*.

3

-ACTION:

With the reactor steam dome pressure exceeding 1040 psig, reduce the. pressure to less than 1040 psig within 15 minutes or be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

SURVEILLANCE RE0VIREMENTS 4.4;6.2 The reactor steam dome pressure shall be verified to be less than 1040 psig at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

1 a

Not applicable during anticipated transients.

FERMI - UNIT 2 3/4 4-23

e I

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 2 -

than or_ equal tr n seconds.

APPllCABILITY:

OPERATIONAL CONDITIONS 1, 2, and 3.

i 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 .

i SURVEILLANCE REQUIREMENTS 4.4.7-Each of ~the Labove required MSIVs shall be demonstrated OPERABLE by

' verifying full closure between 3 and-5. seconds ! en tested pursuant to Specification 4.0.5.

FERMI - UNIT 2 3/4 4-24 Amendment No. 83

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

o.

APPllCABillTY:

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

u 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 NDT considerations, b.

With the structural' integrity of any ASME Code Class 2 component (s) not conforming to the above requirements, restore the structural integrity of the affected component (s) to within its. limit or isolate the affected component (s) prior to increasiry the reactor coolant system temperature above 200*F.

c.

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

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

l 1pRVEILLANCE RE_QUIREMENTS

- 4.4.8 No requirements other than Specification 4.0.5.

FERMI - UNIT 2 3/4 4-25 Amendment Nc. E2, 83,

, i ".,

J'

. CONTAINMENT SYSTEMji

~

SURVEILLANCE RE001REMENTS (Continued) g.

ECCS and RCIC containment isolation valves in hydrostatically' tested

-lines which penetrate the primary containment shall be leak tested at least_ once per 18 months.

h.

Purge supply and exhaust isolation valves with resilient material seals shall be tested and' demonstrated OPERASLE per Specification 4 F.1.8.2.

i.

The-provisions of Specification 4.0.2 3re not applicable to Specifications 4.6.1.2a., 4.6.1.2b. and 4.6.1.2c.

l l

l FERMI - UNIT 2 3/4 6-7

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

Both doors closed except when the air lock is being used for normal a.

~ 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.

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

ACTION:

With one primary containment air lock dcor inoperable:

a.

1.

Maintain at least the OPERABLE air lock door closed and either restore _ the inoperable eir lock door to GPERABLE 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 required 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 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 .

l b.

With the-primary containment air -lock inoperable, except as a result of an inoperable air lock-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.

FERMI - UNIT 2 3/4 6-8 Amendment No. 83,

i CONTAINMENT SYSTEMS SUPPRESSION POOL COOLING LIMITING CONDITION FOR OPERATION 3.6.2.3 The suppression pool cooling mode of the residual heat removal (RHR) system shall be OPERABLE with two independent loops, each locp consisting of:

a.

One OPERABLE RHR pump, and b.

An OPERABLE flow path capable of recirculating water from the suppression chamber through an RHR heat exchanger.

APPLICABILITY:

OPERATIONAL CONDITIONS 1, 2, and 3.

ACTION:

a.

With one suppression pool cooling loop inoperable, restore the inoperable loop to OPEPABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 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 , b.

With both suppression pool cooling loops inoperable, be in at least HOT SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN

within the next 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

SURVER LANCE REQUIREMENTS 4.6.2.3 The suppression pool cooling mode of the RHR syr'em 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 that is not locked, sealed, or otherwise secured in position, is in its correct position.

b.

By verifying that each of the required RHR pumps develops a flow of at least 10,000 gpm on recirculation flow through the RHR heat exchanger and the suppression pool when tested pursuant to Specification 4.0.5.

Whenever both RHR subsystems are inoperable, if unable to attain COLD SHUTDOWN as required by this ACTION, maintain reactor coolant temperature as

-low as practical by use of alternate heat removal methods.

FERMI - UNIT 2 3/4 6-19

CONTAINMENT SYSTEMS 3/4.6.3 PRIMARY CONTAINMENT ISOLATION-VALVES LIMITING CONDITION FOR OPERATION J {.

3.6.3 The primary' containment isolation valves and the reactor instrumentation line excess flow check valves 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.

1 ACTION:

a.

With one or more of the primary centainment 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 0PERABLE status, or 2.

Isolate each affected penetration by use of at least one deactivated 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.*

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 'Loperable, operation may continue and the provisions of Specification 3.0.3 are not l

- applicable' 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 Amendment No. 83 l

1

O PLANT SYSJLMS ULTIMATE HEAT SINK

{1MITING CONDITION FOR OPERATION 3.7.1.5 The Ultimate Heat Sink, comprised of two one-half capacity residual heat removal (RHR) reservoirs with the capability of being cross-connected, shall be OPERABLE with:

a.

A minimum water volume of 2,900,000 gallons in each reservoir (equivalent to an indicated water level of 25 feet or 580 feet elevation),

b.

A inaximum average water temperature of less than or equal to 80*F for each reservoir, c.

At least one OPERABLE cooling tower with two cooling fans for each reservoir.

d.

A minimum combined water volume in the two reservoirs of 5,980,000 gallons.

e.

A maximum combined average water temperature for the two reservoirs of less than or equal to 80 F.

f.

A minimum average water temperature of greater than or equal to 41*F for each reservoir.

g.

Two reservoir cross-connect lines, each with two OPERABLE motor operated cross-connect valves.

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

(

ACT'10N:

a.

With one or more of the requirements of Specification 3.7.1.5.a, b, and c not satisfied declare the affected reservoir (s) inoperable and take the ACTION required by d. or e. below.

'b.

With the combined water volume requirement of Specification 3.7.1.5.d or the combined average water temperature of Specification 3.7.1.5.e not satisfied declare both reservoirs inoperable and take the ACTION required by e. below.

c.

With one or more rese voir cross-connect valves inoperable, within 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months open and de-energize both valves in at least one cross-connect line and vr-d fy that these valves remain open and de-energized at least once per 7 days.

Otherwise, declare both l

reservoirs inoperable and take the ACTION of e. below.

When handling irradiated fuel in the secondary containment.

FERMI - UNIT 2 3/4 7-6 Amendment No. EJ, 83,

4

. PLANT SYSTEMS LIMITING CONDITION FOR OPERAJ,p_(Continued)

ACTION:

(Continued)

~-

With one reservoir inoporab'e declare the associated RHRSW system d.

subsystem, EESW system subsystem, and diesel generator cooling water subsystem inoperable and take the ACTION required by Specifications 3.7.1.1, 3.7.1.3 and 3.7.1.4.

e.

With both-reservoirs inoperable:

1.

In OPERATIONAL CONDITIONS 1, 2 or 3, be in at least h0T SHUTDOWN within 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUTDOWN within the next 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

2' In OPERATIONAL CONDITIONS 4 or 5, declare the RHRSW system, the EESW system and the diesel generator cooling water systems inoperable and take the ACTION required by Specifications 3.7.1.1, 3.7.1.3 and 3.7.1.4.

3.

In OPERATIONAL CONDITION *, declare the diesel generator cooling water systems inoperable and take the ACTION required by Specification 3.7.1.4.

The provisions of Specification-3.0.3 are not applicable.

f.

With the requirements of Specification 3.7.1.5.f for one or both reservoirs not satisfied, perform a visual inspection of the reservoir (s) at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months to verify that no ice has formed.

If ice is observed, demonstrate the OPERABILITY of each

-safety related pump in the reservoir (s) by running each safety related pump at leas + once per 8 hours9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months .

l l

FERMI -LUNIT 2 3/4 7-6a Amendment No. EI, g3,

4

\\

10 9

8

/

REJECT j

6 r

C-5

}

CONTINUE TESTING 3

'2 ACCEPT 1

,e

/

1 0

10 20 30 40 50 60 70 80 90 100 N

FIGURE 4.7.5-1 SAMPLE PLAN 2) FOR SNUBBER FUNCTIONAL TEST FERMI - UNIT 2 3/4 7-21

PLANTSYSTEMI-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 f

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 contamination in excess of the above limit, withdraw the sealed source from use and either:

1.

Decontaminate and repair the sealed source, or 2.

Dispose of the sealed source in accordance with Commission Regulations.

b.-

The provisions of Specification 3.0.3 are not applicable, j

SURVEILLANCE RE0VIREMENTS 4.7.6.1 Test Reauirements - 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, 14.7.6.2 Test -Frecuencies - Each category of sealed sources, excluding startup sources and fission detectors previously subjected to core flux, :.1all be

-tested at the frequency described below.

a.

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

1.

- With a half-life greater than 30 days, excluding Hydrogen 3, and-2.

In any form other than gas.

FERMI - UNIT 2 3/4 7-22 Amendment No. 83

li LLECTRICAL POWER SYSTEMS PRIMARY C0tITAl!4MEf41 pef 4ETRAT10fl (0!4DUCTOR OVERCURRElli PROTECTIVE DEVICES L1MITif4GC0t@lT10tlFOROPERAT10t1 3.8.4.2 All primary containment penet"ation conduttor overturrent protective devices shown in Table 3.8.4.21 shal. be OPERABLE.

APPLIC ABillT_Y:

OPERAT10!4AL C0t4DIT10!iS 1, 2, and 3.

ACT10ti:

With one or more of the primary containment penetration conductor l

overcurrent protective devices shown in Table 3.8.4.2-1 inoperable, declare the affected system or component inoperable and apply the appropriate ACT10tl statement for the affected system, and 1.

For 4,'.6-kV circuits, deenergize the 4.16 kV circuit (s) by tripping the associated circuit breaker (s) within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months and verify the circuit breaker to be tripped at least once per 7 days thereafter.

2.

For ".'+ volt circuit devices, remove the inoperable device (s) from service by racking out or removing the device within 72. hours and verify the inoperable device (s) to be ra-ked out or removed at least once per 7 days thereafter.

Otherwise, b( in at least HDT SHUTDOWil within the next 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months and in COLD SHUT 00Wil within the following 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

l SURVElllAtJCE REQUIREMEllTS 4.8.4.2 Each cf the primary containment penetration condMtor overcurrent protective devices shown in Table 3.8.4.2-1 shall be demo otrated OPERABLE:

a.

At least once per 18 months:

1.

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

a)

A CHAtit4EL CAllBRAT10f4 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 associated circuit breakers and overcurrent control circ >iits function as designed.

FERM1 - Uf!!T 2 3/4 8-17 Amendment flo. 83,

ELECTRICAL POWER SYSTEMS SVRVElltANCE REQUIREMENTS (Continued) 2.

By functionally testing the 480 volt circuit breakers.

Testing of these circuit breakurs shall consist of injecting a current in excess of 120% of the breakers nominal setpoint and measuring the response time. The measured respense time will be compared to the manufacturer's data to insure that it is less than or equal to a value specified by the manufacturer.

Circuit breakers found inoperable during functional testing shall be restored to OPERABLE status prior to resuming operation of the affected equipment.

D.

At least once per 60 months by subjecting each circuit breaker to sr.

inspection and preventive maintenance in accordance with procedures preparsi in conjunction with its manufacturer's recommendations.

{

FERMI - UNIT 2 3/4 8-18

)

~

RADI0 ACTIVE EFFtVENTS L1101D HOLDUP TANKS LIMITING CONDITION FOR OPERATION 3.11.1.4 The quanti).y 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.

APPLICABillTY:

At all times.

K11911' a.

With the quantity of radioactive material in any of the above tanks exceeding the above limit, immediately suspend all additions of radioactive material to the tank, within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months reduce the tank contents to within the limit, and describe the events leading to this condition in the next Semiannual Radioactive Effluent Release Report, pursuant to Specification 6.9.1.8.

The provirions of Specification 3.0.3 are not applicable.

l r

EURVElttANCE REQUIREMENTS 4.11.1.4 The quantity of radioactive material contained in each of the above thnks shall be determined to be within the above limit by analyzing a representative sample of the tank's contents at least once per 7 days when rad,icactive materials arr. being added to the tank.

FERMI - UNIT 2 3/4 11-7 Amendment No. 83, 4

o i

l 3/4 llMITING CONDITIONS FOR OPERATION AND SURVElllANCE RE0VIREMENis l

l J/4;0 APPLICABILITY l

BASES I

Specifications 3.0.1 throuch 3.0.4 establish the general requirements I

applicable to Limiting Conditions for Operation.

These requirements are based I

on the requirements for Limiting Conditions for Operation stated in the Code of federal Regulations,10 CFR 50.36(c)(2):

l I

" Limiting-conditions for operation are the lowest functional cap.uility I

or performance levels of equipment required for safe operation of the I

facility.

When 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 the technical specification until the condition can be met."

j I

Specificittion 3,01 establishes the Applicability statement within each i

I individual specification as the requirement for when (i.e., in which I

OPERATIONAL CONDIfl0NS or other specified conditions) conformance to the I

Limiting Conditions for Operation is required for safe operation of the I

facility. The ACTION requirements establish those remedial measures that-must I

be taken within specified time lim;ts when the requirements of a limiting I

Condition for Operation are not met.

It is not intended that the shutdown I

ACTION requirements be used as an operational convenience which permits I

(routine) voluntary removal.of a system (s) or component (s) from service in I

lieu.of other alternetives that would not result in redundant systems or components b ng inoperable.

l There are two basic types of ACTION requirements. The first specifies the l

remedial measures that permit continued operation of the facility which is not I

further restricted by the time limits of the ACTION requirements.

In this i

I case, conformance to the ACTION requirements provides an acceptable level of I

safety for unlimited continued operation as long as the ACTION requirements I

-continue to be met. The second type of ACTION requirement specifies a time limit in which conformance to the conditions of the LimiJne Condition for

)I Operation must be met.

This time limit is the allowable cuEau time to I

restore an inoperable' system or component to OPERABLE status or for restoring I

parameters _within specified limits.

If these actions are not completed within I

the allowable outage time limits, a shutdown is required to place the facility l

in an OPERATIONAL CONDITION or other specified condition in which the l

specification no longer applies.

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

[

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 i

system or component is removed from service for surveillance testing or j

L investigation of / operational problems.

Individual specifications may include a.specified time limit for the completion of a Surveillance Requirement when L

I FERMI - UNIT 2 B 3/4 0-1 Amendment No. 83,

. s

- _ ~ _ -.. -.

3/4.0 APPLICABILITY BASES (Con't) equipment is removed from service.

In this case, the allowable outage time limits of the ACTION requirements are applicable when this limit expires if the surveillance 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 the ACTION requirements would apply from the point in time that the new specification becomes applicable if the requirements of the Limiting Condition for Operation are not met.

Specification 3.0.2 establishes that noncompliance with a specification exists when the requirements of the Limiting Condition for Operation are not met and the associated ACTION requirements have not been implemented within the specified time interval. The purpose of this specification is to clarify that (1) implementation of the ACTION requirements within the specified time interval constitutes compliance with a specification and (2) completion of the remedial measures of the ACTION requirements is not required when compliance with a limiting Condition of Operation is restored within the time interval specified in the associated ACTION requirements.

j Specification 3.0.3 establishes the shutdown ACTION requirements that must be implemented 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 l

maintained within the limits for safe operation defined by the Limiting l

Conditions for Operation and its ACTION requirements.

It is not intended to be used as an operational convenience which permits (routine) voluntary l

removal of recundant systems 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 operation.

This time permits the operator to coordinate the reduction in electrical generation with the load dispatcher to ensure the stability and availability of the electrical grid.

The time limits specified to reach lower CONDITIONS of operation permit the shutdown to proceed in a controlled and orderly manner that is well within the specified maximum cooldown rate and within the cooldown capabilities of the facility assuming only the minimum required equipment is OPERABLE.

This reduces thermal stresses on components of the primary coolant system and the potential for a plant upset that could challenge safety systems under conditions for which this specification applies.

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

Therefore, the shutdown may be terminated f

if the ACTION requirements have been met or the time limits of the ACTION I

requirements have not expired, thus providing an allowance for the completion I

of the required actions.

l FERMI - UNIT 2 B 3/4 0-2 Amendment No. EE, 83

~ _

l 1

4 3/4.0 APPLICABILITY BASES-(Con't)

The 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 is 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 time to reach COLD SHUTDOWN, or other OPERATIONAL C0f1DIT10fi, 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

.ch HOT SHUTDOWN is not reduced from the allowable limit of 13 hours1.50463e-4 days 0.00361 hours 2.149471e-5 weeks 4.9465e-6 months .

Therefore, if remedial measures are completed that would permit a return to p0WER operation, a penalty is not incurred-by having to reach a lower CONDITION of operation in less than the total time allowed.

The same principle applies wit' m ed to the allowable outage time limits of the ACTION requirements, if ci p h w i,the ACTION requirements for one specification results in entry b o u Mi

'tAL C0!4DIT104 or condition of operation for another specifics *h.e k y

!, 4 - requirements of the Limiting Condition for Operation are not m.

< he c.tw specification becomes applicable in less time than specifieu, the difference may be added to the allowable outage time limits of the second specification. However, the allowable outage time limits of ACT10f* requirements for a higher CONDITION of l

operation may not be used to extend the allowable outage time that is applicable when a Limiting Condition for Operation is not met in a lower CONDITION of operation.

The shutdown requirements of Specification 3.0.3 do not apply in CONDITIONS 4 and 5, because the ACTION requirements of individual specifications define the remedial measures to be taken.

Specification LO.4 establishes limitations on a change in OPERATIONAL CONDITIONS when a Limiting Condition for Operation is not met.

it precludes placing 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 requirements if a change in CONDITIONS were permitted.

The purpose of this specification is to ensure that facility operation is not initiated or that higher CONDITIONS of operation are not entered when corrective action is being i

taken to obtain compliance with a specification by restoring equipment to OPERABLE status or parameters to specified limits.

Compliance with ACTION requirements that permit continued operation of the facility for an unlimited period of time provides an acceptable level of safety for continued operation without regard to the status of the plant before or after a change in OPERATIONAL CONDITIONS.

Therefore, in this case, entry into an OPERATIONAL CONDITION or other specified condition may be made in accordance with the s

provisions of the ACTION requirements.

The provisions of this specification should not, however, be interpreted as endorsing the failure to exercise good I

I practice in restoring systems or components to OPERABLE status before plant startup.

FERMI - UNIT 2 B 3/4 0-3 Amendment No. H,83,

r 3/4.0 APPLICABILITY BASES (Con't)

When a shutdown is required to comply with AC110N requirements, the provisions of Specification 3.0.4 do not apply because they would delay placing the

' facility in a lower CONDITION of operation.

Specifications 4.0.1 throuah 4.0.5 establish the general requirements applicable to Surveillance Requirements.

These requirements are based on the Surveillance Requirements 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 maintained, t. hat facility operation will be within safety limits, and that the limiting conditions of operation will be met."

SDecification 4.0.1 establishec the requirement that surveillances must be performed during the OPERATIONAL CONDITIONS or other conditions for which the requirements of the Limiting Conditions for Operation apply unless otherwise stated in an individual Surveillance Requirement.

The purpose of this specification is to ensure that surveillances are performed to verify the operational status of systems and components and that parameters are within specified limits to ensure safe operation of the facility when the plant is in an OPERATIONAL CONDITION or other specified condition for which the individual Limiting 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 apply unless otherwise specified.

The Surveillance Requirements I

associated with a Special Test Exce) tion are only applicable when the Special Test Exception is used as an allowa>1e exception to the requirements of a specification.

Specification 4.0.2 establishes the limit for which th specified time interval for Surveillance Requirements may be extended.

It permits an allowable extension of the normal surveillance interval to facilitate surveillance scheduling and consideration of plant operating conditions that may not be suitable for conducting the surveillance; e.g., transient conditions or other ongoing surveillance or maintenance activities.

It also provides flexibility to accommodate the length of a fuel cycle for surveillances that are performed at each refueling outage and are specified with an 18 month surveillance interval.

It is not intended that this provision be used repeatedly as a convenience to extend surveillance intervals bayond that specified for surveillances that are not performed during

-refueling outages. The limitation of Specification 4.0.2 is based on engineering judgement and the recognition that the most probable result of any particular surveillance being performed is the verification of conformance with the Surveillance Requirements.

This provision is sufficient to ensure that the reliability ensured through surveillance activities is not significantly degraded beyond that obtained from the specified surveillance interval.

Specification 4.0.3 establishes the failure to perform a Surveillance Requirement within the allowed surveillance interval, defined by the provisions of Specification 4.0.2, as a conditior that constitutes a failure FERMI - UNIT 2 B 3/4 0-4 AmenG.ent No. 83, j

l t

3/4.0 APPLICABillTY l

BASES (Con't)

I to meet the OPERABILITY requirements for a Limiting Condition for Operation.

I Under the provisions of this specification, systems and components are assumed I

to be OPERABLE when Surveillance Requirements have been satisfactorily performed within the specified time interval.

However, nothing in this l

provision is to be construed as implying that systems or components are I

OPERABLE when they are found or known to be inoperable although still meeting the Surveillance Requirements.

This specification also clarifies that the l

ACT10f1 requirements are applicable when Surfeillance Requirements have not I

been completed within the allowed surveillance interval and that the time I

limits of the ACT10ft requirements apply from the point in time it is I

identified that a surveillance has not been performed and not at the time that I

^

the allowed surveillance interval was exceeded.

Completion of the Surveillance Requirement within the allowaole outage time limits of the ACT10!1 l

requirerents restores compliance with the r(quirements of Specification 4.0.3.

I However, this does not negate the fact that the failure to have performed the surveillance within the allowed surveillance interval, defined by the provisions of Specification 4.0.2, constitutes a failure to meet the I

OPERABILITY requirements for a Limiting Condition for Operation and any I

reports required by 10 CFR 50.73 shall be determined based on the length of time the surveillance interval has been exceeded, and the corresponding Limiting Conditions for Operation ACT10t1 time requirements, as discussed in t;UREG-1022, Supplement 1.

If the allowable outage time limits of the ACTIO!1 requirements are less then 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or a shutdown is required to comply with ACT10fl requirements, e.g.,

I Specification 3.0.3., a 24-hour allowance is provided to pcrmit a delay in I

irplementing the ACT10!1 requirements. This provides an adequate time limit to I

complete Surveillance Requirements that have not been performed.

The purpose I

of this allowance is to permit the completion of a surveillance before a I

shutdown would be required to comply with AC110!1 requirements or before other I

remedial measures would be required that may preclude the completion of a I

surveillance. The basis for this allowance includes consideration for plant conditi ns, adequate planning, availability of personnel, the time required to I

perform the surveillance, and the safety significance of the delay in I

completing the required surveillance.

This provision also provides a time I

limit for the completion of Surveillance Requirements that become applicable

~

I as a consequence of C0!iDIT10!i changes imposed by ACT10ti requirements and for I

completing Surveillance Requirements that are applicable when an exception to I

the requirements of Specification 4.0.4 is allowed.

If a surveillance is not I

completed within the 24-hour allowance, the time limits of the ACT10t1 I

requirements are applicable at that time.

When a surveillance is performed I

within the 24-hour allowance and the Surveillance Requirements are not met, I

the time limits of the AC110!1 requirements are applicable at the time that the surveillance is terminated.

I Surveillance Requirements do not have to be performed on inoperable equipment because the ACTIO!1 requirements define the remedial measures that apply.

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

i i

FERMI - VillT 2 B 3/4 0-5 Amendment tio. 83

[

P

f*

3/4.0 APPLICABILITY BASES (Con't)

Specification 4.0.4 establishes the requirement that all applicable surveillances must be met before entry into an OPERATIONAL CONDITION or other condition of operation specified in the Applicability statement.

The purpose 4

of this specification is to ensure that system and component OPERABILITY I

requirements or parameter limits are met before entry into an OPERATIONAL I

CONDITION or other specified condition for which these systems and components I

ensure 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.

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

When 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 facility in a lower CONDITION of operation.

l Specification 4.0.5 establishes the requirement that inservice inspection of I

ASME Code Class 1, 2, and 3 components and inservice testing of ASME Code I

Class 1, 2, and 3 pumps and valves shall be performed in accordance with a I

~

periodically updated version of Section XI of the ASME Boiler and Pressure Vessel Code and Addenda as required by 10 CFR 50.55a.

These requirements I

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

l This specification includes a clarification of the frequencies for performing the 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 I

throughout the Technical Specifications and to ramove any ambiguities relative l

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

Under the terms of this specification, the more restrictive requirements of l

the Technical Specifications take precedence over the ASME Boiler and Pressure Vessel Code and applicable Addenda.

The requirements of Specification 4.0.4 to perform surveillance activities befora entry into an OPERATIONAL CONDIT10!t l

or other specified conditiin takes precedence over the ASME Boiler and-Pressure Vessel Code provision that allows pumps and valves to be tested up to l

onc week after return to normal operation.

The Technical Specification I

definition of OPERABLE does not allow a grace period before a component, which is not capable of performing its specified function, is declared inoperable and tain precedence over the ASME Boiler and Pressure Vessel Code provision that allows a valve to be incapable of performing its specified function for up to 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months before being declared inoperable, i

FERMI - UNIT 2 B 3/4 0-6 Amendment No.83 f

i APPLICABILITY BASES liRC Generic Letter 88 01 identified NRC's position on intergranular stress corrosion cracking (IGSCC) in BWR Stainless Steel weldments. This letter establishes requirements to inspect these weldments to a special i

schedule and by procedures, personnel and equipment that are qualified under a j

formal program approved by the NRC.

l FERMI - UNIT 2 B 3/4 0-7 Amendment No. 83 l

..

Person / Time
ML20101T161
Site:	Fermi (NPF-43-A-083, NPF-43-A-83)
Issue date:	06/25/1992
From:	Marsh L Office of Nuclear Reactor Regulation
To:
Shared Package
ML20101T162	List: ML20101T161 ML20101T169
References
NUDOCS 9207200318
Download: ML20101T161 (55)
v • d • e

ML20101T161

Text

Navigation menu

Search