Text

Amends 49 to Licenses NPF-37 & NPF-66 & Amends 38 to Licenses NPF-72 & NPF-77,respectively,revising TS Re GL 87-09 Concerning LCO & Surveillance Requirements of TS 3.0 & 4.0
	ML20099H607
Person / Time
Site:	Byron, Braidwood
Issue date:	08/11/1992
From:	Barrett R; Office of Nuclear Reactor Regulation
To:	; Commonwealth Edison Co
Shared Package
ML20099H610	List: ML20099H607; ML20099H625;
References
	NPF-37-A-049, NPF-66-A-049, NPF-72-A-038, NPF-77-A-038 NUDOCS 9208190115
	Download: ML20099H607 (114)
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UNITED STATES i

E NUCLEAR REGULATORY COMMISSION o

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@CKET NO. STN 50-454 BYRON STATION. UNIT NO. 1 AMENDMENT TO FAClllTY OPERATING LICENSE Amendment No. 49 License No. NPF-37 1.

The th'-lear Regulatory Commission (the Commission) has found that:

A.

The application for amendment by Commonwealth Edison Company (the licensee) dated November 30, 1988, as supplemented on May 30, 1990, April 19, 1991, and February 27, 1992, complies with the standards and requirements of the Atomic Energy Act of 1964, as amended (the Act) and the Commission's rules and regulations set forth in 10 CFR Chapter 1; B.

The facili y will operate in conformity with the application, the provisione of the Act, and the rules and regulations of the Commissior.;

C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the pubile, and (ii) that such activities will be conducted in compliance with the Commission's regtlations; 0.

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 ten satisfied.

2.

Accordingly, the license is amended by changes to the Technical Specifi-cations as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-37 is hereby amended to read as follows:

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Technical __Jecifications The Technical Specifications contained in Appendix A as revised through Amendment No. 49 and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license.

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

3.

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

FOR lHE NUCLEAR REGU T0RY COMMISS10';

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Richa

. Barrett, Director Project Directorate III-2 Division of Reactor Projects - III/IV/V Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

August 11, 1992 i

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NUCLEAR REGULATORY COMMISSION t

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COMMONWEALTH EDISON COMPANY

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DOCKET NO. STN 50-455 BYRON STATION. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 49 License No. NPF-66 i

1.

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

A.

The appilcation for amendment by Commonwealth Edison Company (the licensee).. dated November 30, 1988, as supplemented on May 30,

-1990, April 19, 1991, and February 27, 1992, complies with the standards-and requirements of tha Atomic Energy Act of 1954, as amended (the Act) 'and the Commission's rules and regulations set forth in 10 CFR Chaptr

1; 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 i.ompliance 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 l

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E.

The. issuance of this amendn.ent is in accordance with 10 CFR Part i

51 of the Commission's regulations and all applicable requirements l-have-been satisfied.

/

2.

Accordingly, the license is amended by changes to the Technical Specifi-f cations.as indicated in the attachment to this license amendment, and i-L paragraph 2.C.(2)ofFacilityOperatingLicenseNo.NPF-66ishereby l:

amended to read-as follows:

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Technical Specifications The Technical Specifications contained in Appendix A (NUREG-lll3),

as revised through Amendment No. 49 and. revised by Attachment 2 to NPf-66, and the Environmental Protection Plan contained in Appendix B, both of which were attached to License No. NPF-37, dated February 14, 1985, are hereby inco.corateo into this license. Attachment 2 contains a revision to Appendix A which is hereby incorporated into this license.

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

3.

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

FOR THE NUCLEAR REGULATORY COMMISSION (l'

y Richard J'/ Barrett, Director Project Directorate 111-2 Division of Reactor Projects - Ill/IV/V Office of iluclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance:

August 11, 1992 a

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ATTACHMENT TO LKf3jil_f2f303ENT N05. 49 AND 49 ffCILITY OPERATING LICENSE N05. NPF-37 AND NPT-66 QQGE_t[QS. STN 50-454 AND STIL50-455 Revise the Appendix A Technical Specifict,tions by removing the pages identified below and inserting the attached pages.

The revised pages are identified by the captioned a.nendment number and contain marginal lines indicating the area of change. Overleaf paget 1dentified by an asterisk are provided for convenienta.

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3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS S/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 MODES 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 Limitina Condition for Operation and associated ACTION requirements are nnt met witEn the specified time intervals.

If the Limiting Condition for Operatina 4 estored prior to expiration of the specified time intervals, completion of tue ACTICN 'equirements is not required.

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

a.

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

.b.

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

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

Where corrective measures are completed that permit operation under the ACTION requirements, the action may be taken in accordance with the specified time limits as measured from the time of failure to meet the Limiting Condition for Operation.

Exceptions to these requirements are stated in the individual specifications.

This specification is not applicable in MODE 5 or 6.

3.0.4 Entry into an OPERATIONAL MODE 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 interval.

Entry into an OPERATIONAL MODE or specified condition may be made in accordance with ACTION reovirements when conformance to them permits continued operation of the faciliv fo an unlimited period of time.

This provision shall not prevent passage through or to OPERATIONAL MODES as required to comply with ACTION requirements.

Exceptions to these requirements are stated in the individual specifications.

3.0.5 Limiting Conditions for Operation including the associated ACTION require-ments shall apply to each unit individually unless otherwise indicated as follows:

a.

Whenever the Limiting Conditions for Operation refers to systems or components which are shared by both units, the ACTION requirements will apply to both units simultaneously.

b.

Whenever the limiting Conditions for Operation applies to only one unit, this will be identified in the APPLICABILITY section of the specification; and l

c.

Whenever certain portions of a specification contain operating param-eters, Setpoints, etc., which are different for each unit, this will l

be identified in parentheses, footnotes or body of the requirement.

BYRON - UNITS 1 & 2 3/4 0-1 AMENDMENT N(. 49

i APPLICABILITY SURVEILLANCE REQUIREMENTS 4.0.1 Surveillance Requirements shall be met during the OPERATIONAL H0 DES or other conditions specified for individual Limiting Conditions for Operation unless otherwise stated in an individual Surveillance Requirement.

l 4.0.2 Each Surveillance Requirement shall be performed within the specified time interval with a maximum allowable extension not to exceed 25% of the specified surveillance interval.

4.0.3 Failure to perform a Surveillance Requirement within the allowed sur-veillance interval, defined by Specification 4.0.2, shall constitute noncompli-ance 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 MODE or other specified condition shall not be made unless the Surveillance Requirement (s) associated with a Limiting Condition for Operation has been performed within the stated surveillance interval or as otherwise specified.- This provision shall not prevent passage through or to OPERATIONAL MODES as required to comply with ACTION requirements.

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

a.

Inservice inspection of ASME Code Class 1, 2, and a cenponets 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 Part 50, Section 50.55a(g), except where specific written relief has been granted by the Commission pursuant to 10 CFR Part 50, Section 50.55a(g)(6)(1);

b.

Jurveillance intervals specified in Section XI, 1980 Edition, Winter 1981 Addenda, of the ASME Boiler and Pressure Vessel Code for the inservice inspection and testing activities shall be applicable as follows in these Technical Specifications:

BYRON - UNITS 1 & 2 3/4 0-2 AMEWDMENT NO. 49

3/4.2 POWER DISTRIBUTION LJ41TS 3/4.2.1 AXIAL FLUX DIFFERENCE LIMITING CONDITION FOR OPERATION 3.2.1 The indicated AXIAL FLUX OIFFERENCE (AFD) shall be maintained within the i

following target band (flux difference units) about the target flux difference:

a.

1 5% for Cycle 1 core average accumulated burnup of less than or i

equal to 5000 MWD /MTU, and b.

+ 3%, -9% for Cycle 1 core average accumulated burnup of greater than 5000 MWD /MTV, and c.

+ 3%, -12% for each subsequent cycle.

The indicated AFD may deviate outside the above required target band at greater than or equal to 50% but less than 90% of RATED THERMAL POWER provided the indi-cated AFD is-within the Acceptable Operation Limits of figure 3.2-1 and the cumulative penalty deviation time does not exceed 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months during the previous 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

The indicated AFD may deviate outside the above required target band at greater than 15% but less than 50% of RATED THERMAL POWER provided the cumulative penalty deviation time does not exceed 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months during the previcus 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

APPLICABILITY:

MODE I above 15% of RATED THERMAL POWER *.

ACTION:

a.

With the indicated AFD outside of the above required target band and with THERMAL POWER greater than or equal to 90% of RATED THERMAL POWER, within 15 minutes, either:

1.

Restore the indicated AFD to within the above required target band limits, or 2.

Reduce THERMAL POWER to less than 90% of RATED THERMAL POWER.

b.

With the indicated AFD outside'of the above required target band for more than 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months of cumulative penalty deviation time during the previous 24' hours or outside the Acceptable Operation Limits of Figure 3.2-1 and with THERMAL POWER less than 90% but equal to or greater than 50% of RATED THERMAL POWER, reduce:

1.

THERMAL POWER to less than 50% of RATED THERMAL POWER within 30 minutes, and 2.

The Power Range Neutron Flux - High Setpoints to less than or equal to 55% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

See Special Test Exceptions Specification 3.10.2.

urveillance testing of the Power' Range Neutron Flux channel may be performed S

pursuant to Specification 4.3.1.1 provided the indicated AFD is maintained within the Acceptable Operation Limits of Figure 3.2-1.

A total of 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months operation may be accumulated with the AFD outside of the above required target band during testing without penalty deviation.

BYRON - UNITS 1 & 2 3/4 2-1

LIMITING CONDITION FOR OPERATION ACTION (Continued) c.

With the indicated AFD outside of the above required target band for more than I hour of cumulative penalty deviation time during the previous 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and with THERMAL POWER less than 50% but greater than 15% of RATED THERHAL POWER, the THERMAL POWER shall not be increased equal to or greater than 50% of RATED THERMAL POWER until the indicated AFD is within the above required target band.

SURVEILLANCE REQUIREMENTS

4. 2.1.1 The indicated AFD shall be determined to be within its limits during POWER OPERATION above 15% of RATED THERMAL POWER by:

a.

Monitoring the indicated AFD for each OPERABLE excore channel:

1)

At least once per 7 days when the AFD Monitor Alarm is OPERABLE, and 2)

At least once per hour for the first 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months efter restoring the AFD Monitor Alarm to OPERABLE status, b.

Monitoring and logging the indicated AFD for each OPERABLE excore channel at least once per hour for the first 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and at least once per 30 minutes thereafter, when the AFD Monitor Alarm is inoperable.

The logged values of the indicated AFD shall be assumed to exist during the interval preceding each logging.

4.2.1.2 The indicated AFD shall be considered outside of its target band when two or more OPERABLE excore channels are indicating the AFD to be outside the target band.

Penalty deviation outside of the above required target band shall be accumulated on a time basis of:

a.

One minute penalty deviation for each 1 minute of POWER OPERATION outside of the target band at THERMAL POWER levels equal to or above 50% of RATED THERMAL POWER, and b.

One-half minute penalty deviation for each I minute of POWER OPERATION outside of the target band at THERMAL POWER levels between 15% and 50% of RATED THERMAL POWER.

4. 2.1. 3 The initial determination of target flux difference following a refuel-ing outage shall be based on design predictions.

Otherwise, the target flux difference of each OPERABLE excore thannel shall be determined by measurement at least once per 92 Effective Full Power Days.

l

4. 2.1. 4 The target flux difference shall be updated at least once per 31 Effective Full-Power Days by either determining the target flux difference pursuant to Specification 4.2.1.3 above or by linear interpolation between the

-most recently measured value and the predicted value at the end of the cycle i

life.

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l BYRON - UNITS 1 & 2 3/4 2-2 AMENDMENT NO. 49 g

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FIGURE 3.2-2 3

h K(Z) - NORMAL.IZED F (Z) AS A FUNCTION 9

f 0F CORE HEIGHT

i PG#2R DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS 4.2.2.1 The provisions of Specification 4.0.4 are not applicable.

4.2.2.2 F

shall ba evaluated to determine if F (Z) is within its limit by:

g Using the movable incore detectors to obtain a power distribution a.

map at any THERMAL POWER greater than 5% but prior to exceeding 50%

of RATED THERMAL POWER following a refueling outage.

The 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months completion time provisions of Specification 4.0.3 are not applicable.

b.

Increasing the measured F component of the power distribution map xy by 3% to account for manufacturing tolerances and further increasing the value by 5% to account for measurement uncertainties; c.

Comparing the F computed (F

) obtained in Specification 4.2.2.2b.,

above, to:

xy 1)

The F limits for RATED THERMAL POWER (FRTP) for the appropriate xy x

measured core planes given in Specifications 4.2.2.2e and f.,

below, and 2)

The relationship:

F

=FRTP [140.2(1-P))

x Whsre F is the limit for fractional THERMAL POWER operation expressed as a function of F and P is the fraction of RATED THERMAL POWER at which F was measured, xy d.

Remeasuring F according to the follwing schedule:

xy 1.

When F is greater than the F limit for the. appropriate x

measuredcoreplanebutlessthantheFfrelctionship, additional x

RTP power distribution maps shatl be taken and F compared to F x and F :

a)

Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after exceeding by 20% of RATED THERMAL C

POWER or greater, the THERMAL POWER at which F*Y was last determined, or l

b)

At least once per 31 EFPD, whichever occurs first.

L BYRON - UNITS 1 & 2' 3/4 2-6 AMENDMENT NO. 49

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L

POWER DISTRIBUTION LIMITS LIMITING CONDITION FOR OPERATION ACTION (Continued) b.

Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of initially being outside the above limits, verify through incore flux mapping and RCS total flow ate comparison that the combination of F"H and RCS total flow rate are restored to within the above limits, or reduce THERMAL POWER to less than 5% of RATED THERMAL POWER within the next 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ; and c.

Identify and correct the cause of the out-of-limit condition prior to increasing THERMAL POWER above the reduced THERMAL POWER limit required by ACTION a.2. and/or b. above; subsequent POWER OPERATION may proceed'provided that the combination of F and indicated RCS H

total flow rate are demonstrated, through incore flux mapping and RCS total flow rate comparison, to be within the region of acceptable operation defined by Specification 3.2.3 prior to exceeding the fol-lowing THERMAL POWER levels:

1.

A nominal 50% of RATED THERMAL POWER, 2.

A nominal 75% of RATED THERMAL POWER, and 3.

Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of attaining greater than or equal to 95% of RATED THERMAL ?0WER.

SURVEILLANCE REQUIREMENTS 4.2.3.1 The provisions of Specification 4.0.4 are not applicable.

N 4.2.3.2 The combination of indicated RCS total flow rate and F " shall be 0

determined to be within the region of acceptable operation of Specification 3.2.3:

a.

Prior to operation above 75% of RATED THERMAL POWER after each fuel loading, and b.

At least once per 31 Effective Full Power Days.

4.2,3.3 The indicated RCS total flow rate shall be verified to be within the region of acceptable operation of Specification 3.2.3 at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months whenthemostrecentlyobtainedvalueofFfH, btained per Specification 4.2.3.2, is assumed to exist.

4.2.3.4 The RCS total flow rate indicators shell be subjected to a CHANNEL CALIBRATION at least once per 18 months.

l 4.2.3.5 The RCS total flow rate shall be determined by precision heat balance measurement prior to completion of PHYSICS TESTS after each fuel loading.

The 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months completion time provisions of Specification 4.0.3 are not applicable.

The measurement instrumentation shall be calibrated within seven days prior to the performance of the calorimetric flow measurement.

Prior to the precision heat balance measurement, at least two of the four feedwater flow meter venturis shall be visually inspected and, if fouling is found, all venturis shall be cleaned.

BYRON - UNITS 1 & 2 3/4 2-9 AMENDMENT NO. 49

POWE4 DISTRIBUTION LIMITS 3/4.2.4 QUADRANT POWER TILT RATIO s.

LIMITING CONDITION FOR OPERATION 3.2.4 The QUADRANT POWER TILT RATIO shall not exceed 1.02 above 50% of RATED THERMAL POWER.

APPLICABILITY:

MODE 1*.

' ACTION:

a.

With the QUADRAN1 POWER TILT RATIO determined to exceed 1.02 but less than or equal to 1.09:

1.

Calculate the QUADRANT POWER TILT RATIO at least once per hour until either:

a)

The QUADRANT POWER TILT RATIO is reduced to within its limit, or b)

THERMAL POWER is reduced to less than 50% of RATED THERMAL.

-POWER.

2.

Within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months either:

a)

Reduce the QUADRANT POWER TILT RATIO to within its limit, or b)

Reduce THERMAL POWER at least 3% from RATED THERMAL POWER for each 1% of indicated QUADRANT POWER TILT RATIO in excess of I and similarly reduce the Power Range Neutron Flux-High Trip Setpoints within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

3.

Verify that the QUADRANT POWER TILT RATIO is within its limit within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after exceeding the limit or reduce THERMAL POWER to less than 50% of RATED THERMAL PUWER within the next 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and reduce the Power Range Neutron flux-High Trip Setpoints to less than or equal to 55% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , and 4.

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

or greater RATE 0 THERMAL POWER.

See Special Test Exceptions Specification 3.10.2.

l BYRON - UNITS 1 & 2-3/4 2-10

POWER DISTRIBUTION LIMITS LIMITING CONDITION FOR OPERATION ACTION (Continued) b.

With the QUADRANT POWER TILT RATIO determined to exceed 1.09 due to misalignment of either a shutdown or control rod:

1.

Calcu? ate the QUADRANT POWER TILT RATIO at least once per hour until either:

a)

The QUADRANT POWER TILT RATIO is reduced to withir.

its limit, or b)

THERMAL POWER is reduced to less than 50% of NATED THERMAL POWER.

2.

Reduce THERMAL POWER at least 3% frum RATED THERMAL POWER for each 1% of indicated QUADRANT POWER TILT RATIO in excess of 1, within 30 minutes; 3.

Verify that the QUAD 4 ANT POWER TILT RATIO is within its limit within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months after exceeding the-limit or reduce THERMAL POWER to less than 50% of RATED THERMAL POWER within the next 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and reduce the Power Range Neutron Flux-High Trip Setpoints to less than oc equal to 55% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; and-4.

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

or greater RATED THERMAL POW 2R.

c.

With the QUADRANT POWER TILT RATIO determined to exceed 1.09 cg6 ta causes other than the mitalignment of either a shutdown or control rod:

1.

Calculate the QUADRANT POWER TILT RATIO at least once per hour until either:

a)

The QUADRANT POWER TILT RATIO is reduced to within its -limi t, or b)

THERMAL POWER is reduced to less than 50% of RATED THERMAL POWER.

l' BYRON - UNITS 1 & 2 3/4 2-11

a.

POWER DISTRIBUTION LIMITS LIMITING CONDITION FOR OPERATION ACTION (Continued) 2.

Reduce THERMAL POWER to less than 50% of RATED THERMAL POWER within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and reduce the Powei Range Neutron Flux-High Trip Setpoints to less than or equal to 55% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; and 3.

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

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

a.

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

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

4.2.4.2 The QUADRANT POWER TILT RATIO shall be determined to be within the limit when above 75% of RATED THERMAL POWER with one Power Range-channel inoperable by usifig the movable incore detectors to confirm that the normalized symmetric power distribution, obtained from two sets of four symmetric thimble L

locations or a full-core flux map, is consistent with the indicated QUADRANT l

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

l l

BYRON - UNITS 1 & 2 3/4 2-12 AMENDMENT NO. 49

3/4.3 INSTRUMENTATION 3/4.3.1 REACTOR TRIP SYSTEM INSTRUMENTATION LIMITING CONDITION FOR OPERATION i

3.3.1 As a minimum, the Reactor Trip System instrumentation channels and interlocks of Table 3.3-1 shall be OPERABLE.

l APPLICABILITY: As shown in Table 3.3-1.

-ACTION:

As shown in Table 3.3-1.

SURVEILLANCE REQUIREMENTS 4.3.1.1 Each Reactor Trip System instrumentation channel and interlock and the automatic trip logic shall be demonstrated OPERABLE by the performance of the Reactor Trip.5ystem Instrumentation Surveillance Requirements specified in Table 4.3-1.

4.3.1.2 The REACTOR TRIP SYSTEM RESPONSE TIME of each Reactor trip function shall be demonstrated to be within its limit at least once per 18 months.

Each test shall include at least one train such that both trains are tested at least once per 36 months and one channel per function such that all channels are tested at least once every N times 18 months where H is the total number of redundant channels in a specific Reactor trip function as shown in the

" Total No. of Channeis" column of Table 3.3-1.

BYRON - UNITS 1 & 2 3/4 3-1 Av.ENDMENT NO. 23

m

-- g

.g TABLE 3.3-1 REACTOR TRIP SYSTEM INSTRUMENTATION c-MINIMUM 5

TOTAL NO.

CHANNELS CHANNELS APPLICABLE d

FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE-MODES ACTION e.

1.

Manual Reactor Trip 2

1 2

1, 2

.1 co 2

1 2

3 *, 4*, 5*

10 2.

Power Range, Neutron Flux a.

.High'Setpoint 4

2 3

1, 2 2

b.

Low Setpoint-4 2

3 1###, 2 2

3.

Power Range, Neutron Flux 4

2 3

1, 2 2

High Positive Rate R

4.

Power' Range, Neutron Flux, 4

2 3

1, 2 2

High Negative Rate Y

5.

Intermediate Range, Neutron Flux 2

1 2

1###, 2 3

6.

Source Range, Neutron Flux a.

Startup.

2 1

2 2##**

4 b.

Shutdown 2

1 2

3,4,5 5

7.

Overtemperature AT 4

2 3

1, 2 6

8.

Overpower AT 4

2 3

1, 2 6

l 9.

Pressurizer Pressure-Low k

(Above P-7) 4 2

3 1

6***

5 lR

'i 5

TABLE 3.3-1 (Continued) h REACTOR TRIP SYSTEM INSTRUMENTATION E

MINIMUM TOTAL NO.

CHANNELS CHANNELS APPLICABLE c$

FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION d

10.

Pressurizer Pressure-High' 4

2 3

1, 2

'6 l

g e-

11.. Pressurizer Water Level-High y

-(Above P-7) 3 2

2 1

6 l-12.

Reactor Coolant Flow-Low a.

Single Loop (Above P-8) 3/ loop 2/ loop in 2/ loop in 1

6 l

any oper-each oper-ating loop ating loop b.

Two Loops (Above P-7 and 3/ loop 2/ loop in 2/ loop in 1

6 l

q below P-8) two oper-each oper-A ating loops ating loop w

13.

Steam Generator Water 4/stm. gen.

2/stm. gen.

3/stm. gen.

1, 2 6***

l Level-Low-Low in any each operating operating stm. gen.

stm. gen.

14.

Undervoltage-Reactor Coolant Pumps (Above P-7) 4-1/ bus 2

3 1

6***

l 15.

Underfrequency-Reactor Coolant Pumps (Above P-7) 4-1/ bus 2

3 1

6 l

E 16.

Turbine Trip y

(Above P-7 or P-8)****

x E

a.

Emergency Trip Header Pressure 3/ Train P/ Train 2/ Train 1

6

[

b.

Turbine Throttle Valve Closure 4

1 1

6 9

g

- - - A Reactor trip or Turbine trip is enabled above P-7 (10%) until the modification is implemented which enables Reactor trip on Turbine trip above P-8 (30%).

=

~

g TABLE-3.3-1 (Contir,aed) h REACTOR TRIP SYSTEM INSTRUMENTATION c:

MINIMUM.

i'i TOTAL NO.

CHANNELS-CHANNELS APPLICABLE d

FUNCTIONAL UNIT OF CHANNELS TO TRID-OPERABLE.

MODES

' ACTION 17.

Safety Injection Input m

-from ESF

'2 1

2 1, 2 9

18.

Reactor Coolant " ump Breaker Position Trip-Above P-7 1/ breaker 2

1/ breaker 1

11 per operating loop 19.

Reactor Trip System Interlocks R

a.

Intermediate Range Neutron Flux, P-6 2

1 2

2##

8 Y

b.

Low Power Reactor Trips Block, P-7 P-10 Input 4

2 3

1 8

or P-13 Input

.2 1

2 1

8 c.

Power Range Neutron Flux, P-8 4

2 3

1 8

d.

Power Range Neutron Flux, P-10 4

2 3

1, 2 8

>$g e.

Turbine Impulse Chamber E

Pressure, P-13 2

1 2

1 8

i 20.

Reactor Trip Breakers 2

1 2

1, 2 12 2P 2

1 2

3*, 4*, 5*

10 s

S 21.

Automatic Trip and Interlock Logic 2

1 2

1, 2 9

2 1

2 3*, 4*, 5*

10 22.

Reactor Trip Bypass Breakers 2

1 1

13

TABLE 3.3-1 (Continued)

TABLE NOTATIONS

With the Reactor Trip System breakers in the closed position and the Control Rod Drive System capable of rod withdrawal.

- The boron dilution flux doubling signals may be blocked during reactor startup.

- - These channels also provide inputs to ESFAS.

The Action Statement for the channels in Table 3.3-3 is more conservative and, therefore, controlling.

i

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

I

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

@Whenever the Reactor Trip Bypass Breakers are racked in and closed for bypass-ing a Reactor Trip Breaker.

ACTION STATEMENTS ACTION 1 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in H0T STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

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

a.

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

The Minimum Channels OPERABLE requirement is met; however, the inoperable channel may be bypassed for up to 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months for surveillance testing of other channels per Specification 4.3.1,1; and c.

Either, THERMAL POWER is restricted to less than or equal to 75% of RATED THERMAL POWER and the Power Range Neutron Flux Trip Setpoint is reduced to less than or equal to 85% of RATED THERMAL POWER within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; or, the QUADRANT POWER TILT RATIO is monitored at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months per Specification 4.2.4.2.

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

a.

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

Setpoint, restore the inoperable channel to OPERABLE status prior to increasing THERMAL POWER above the P-6 Setpoint; and b.

Above the P-6 (Intermediate Range Neutron Flux Interlock)

Setpoint but below 10% of RATED THERMAL POWER, restore the inoperable channel to OPERABLE status prior to increasing l

l THERMAL POWER above 10% of RATED THERMAL POWER.

L

-BYRON - UNITS 1 & 2 3/4 3-5 AMENDMENT NO. 49

TABLE 4.3-1 (Continued)

TABLE NOTATIONS

With the Reactor Trip System breakers closed and the Control Rod Drive System capable of rod withdrawal.

- These channels also provide inputs to ESFAS.

The Operational Test Frequency for these channels in Table 4.3-2 is more conservative and, therefore, controlling.

- - A Reactor trip on Turbine trip is enabled above P-7 (10%) until the modifica-tion is implemented which enables Reactor trip on Turbine trip above P-8 (30%)

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

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

(1) If not performed in previous 7 days.

(2) Comparison of calorimetric to excore power indication above 15% of RATED THERMAL POWER.

Adjust excore channel gains consistent with calorimetric power if absolute difference is greater than 2%.

The provisions of Speci-fication 4.0.4 are not applicable for entry into MODE 2 or 1.

(3) The initial single point comparison of incore to excore AXIAL FLUX DIFFERENCE following a refueling outage shall be performed prior to exceeding 75% of RATED TERMAL POWER.

Otherwise the single point com-parison cf incore to excure AXIAL FLUX DIFFERENCE shall be performed above 15% of RATED THERMAL POWER.

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

The provisions of Specification 4.0.4 are not applicable for entry into MODE 2 or 1.

For the purposes of this surveillance, monthly shall mean at least once per 31 EFPD.

The 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months completion time provisions of Specification 4.0.3 are not applicable.

(4) Neutron detectors may be excluded from CHANNEL CALIBRATION.

(Sa) Initial plateau curves shall be measured for each detector.

Subsequent plateau curves shall be obtained, evaluated and compared to the initial curves.

For the Intermediate Range and Power Range Neutron Flux channels the provisions of Specification 4.0.4 are not applicable for entry into MODE 2 or 1.

(Sb) With the high voltage setting varied as recommended by the manufacturer, an initial discriminator bias curve shall be measured for each detector.

Subsequent discriminator bias curves shall be obtained, evaluated and compared to the initial curves.

(6) Incore - Excore Calibration, above 75% of RATED THERMAL POWER.

The provi-sions of Specification 4.0.4 are not applicable for entry into MODE 2 or 1.

For the purposes of this surveillance, quarterly shall mean at least once per 92 EFPD.

(7) Each train shall be tested at least every 62 days on a STAGGERED TEST BASIS.

(8) With power greater than or equal to the interlock Setpoint the required ANALOG CHANNEL OPERATIONAL TEST shall consist of /erifying that the inter-lock is in the required state by observing the permissive annunciator window.

BYRON - UNITS 1 & 2 3/4 3-12 AMENDMENT NO. 49

.~

TABLE 4.3-l'(Continued)

. TABLE-NOTATIONS

(9) cSurveillance'in MODES-3*i 4*, and 5* shall'also include verification that permissives P-6'and P-10-areLin'their required state for existing, plant'

-conditions by observation:of the. permissive annunciator window.

Surveil-

-lance:shallLinclude verification of the. Boron Dilution Alarm Setpoint ofiless~than or equal to an. increase of twice the count rate within a 10-minute period.

4

.(10)LSetpoint verification is not applicable.

'(11) TheLTRIP ACTUATING-DEVICELOPERATIONAL TEST shall be performed such that' each train is=testedfat least every!62 days on a STAGGERED TEST BASIS and' following maintenance or' adjustment of the Reactor' Trip-Breakers-and shall include independenteverification of the OPERABILITY of the Undervoltage

-and_ Shunt Trip Attachments of the Reactor Trip Breakers.

L(12) Attleast once per 18 months during shutdown verify that on.a simulated

' Boron Dilution Doubling. test signal CVCS valves 112D and E open and

=1128 and-C close within 30 seconds.

(13) CHANNEL CALIBRATION:shall include the RTD bypass loops flow rate.

.(14) Verify that th'e aparopriate signals-reach the-Undervoltage and Shunt Trip 1 Relays, for both tie _ Reactor Trip and Bypass-Breakers 1from the Manual Trip Switches.-

((15)'ManualJShuntLTrip prior to the Reactor Trip Bypass Breaker _being' racked inland. closed-for bypassing a Reactor Trip Breaker.

((16)AutomaticUndervoltage. trip.

=

)

f

BYRON'- UNITS--I & 2 3/4 3-12a AMENDMENT NO. 49 J

e3

. TABLE 3.3-3 55 Ej ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION c:

MINIMUM EE TOTAL NO.

. CHANNELS CHANNELS APPLICABLE.

g; : FUNCTIONAL UNIT-0F CHANNELS TO TRIP-OPERABLE MODES ACTION w

1.

Safety Injection (Reactor g.

Trip, Feedwater Isolation,.

n, Start Diesel Generators, Containment Cooling fans, Control Room Isolation, Phase'"A" Isolation, Turbine Trip, Auxiliary Feedwater, Containment Vent Isolation, and Essential Service Water).

a.

Manual Initiation 2

1 2

1,2,3,4 18 s

[,

b.

Automatic' Actuation 2

1 2

1,2,3,4 14 4,

Logic and Actuation Relays u

c.

Containment 3

2 2

1,2,3 15 l

Pressure-High-1 d.

Pressurizer Pressure-4 2

3 1, 2, 3#

19 Low (Above P-11) e.

Steam Line Pressure-3/ steam line 2/ steam line 2/ steam line 1, 2, 3#

15 l

Low (Above P-11) any steam line 5{

2.

Containment Spray

a gj a.

Manual Initiation 2 pair 1 pair 2 pair 1,2,3,4 18' f[5 b.

Automatic Actuation 2'

1 2

1,?,3,4 14 Logic and Actuation Relays e

c.

Containment Pressure-4 2

3 1,2,3 16 High-3

TABLE 3.3-3 (Continued)-

ENGINEERED SAFETY FEATURES ACTUATION SYSTEll INSTRUMENTATION e

MINIMUM c:

TOTAL NO.

CHANNELS CHANNELS APPLICABLE

[h FUNCTIONAL UNIT OF CHANNELS 10 TRIP OPERABLE MODES ACTION w

w 3.

Containment Isolation e.

os a.

Phase "A" Isolation 1)

Manual Initiation 2

1 2

1,2,3,4 18 2)

Automatic Actuation 2

1 2

1,2,3,4 14' logic and Actuation Relays 3)

Safety Injection See Item 1. above fer all Safety Injection initiating functions and requirements.

)$

b.

Phase "B" Isolation

}l 1)

Manual Initiation 2 pair 1 pair 2 pair 1,2,3,4 18 os 2)

Automatic Actuation 2

1 2

1,2,3,4 14 Logic and Actuation Relays 3)

Containment 4

2 3

1,2,3 16 Pressure-High-3 c.

Cor.tainment Vent Isolation 1)

Automatic' Actuation 2

1 2

1,2,3,4 17 Logic and Actuation Relays 2)

Manual Phase "A" See Item 3.a.1 for all manual Phase "A" Isolttion initiating Isolation functions and requirements.

3)

Manual Phase "B" See. Item 3.b.1 for all manual Phase "B" Isolation initiating Isolation functions and requirements.

4)

Safety Injection See Item 1. above for all Safety Injection initiating functions and requirements.

- _ ~

. TABLE 3.3-3 (Continued) 5

.g ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION C3-MINIMUM TOTAL NO.

CHANNELS CHANNELS APPLICABLE g

. OF CHANNELS T0. TRIP OPERABLE MODES ACTION FUNCTIONAL UNIT g

[

4.

. Steam Line Isolation a.

Manual Initiation 1)-

Individual 1/ steam line 1/ steam line 1/ operating 1,2,3 23-

' steam line 2)

System 2

1 2

1,2,3 22 b.

Automatic Actuation 2

1 2

1,2,3 21 Logic and Actuation Relays y

c.

Containment Pressure-3 2

2 1, 2,' 3 15 l

High-2 T

d.

Steam Line 3/ steam line 2/ steam line 2/ steam line 1, 2, 3#

15 l

gu Pressiere-Low any steam (above P-11) line e.

Steam Line Pressure -

3/ steam line 2/ steam line 2/ steam line 3##

15 l

Negative Rate-High' any steam (below P-11F line S.

Turbine Trip &

Feedwater Isolation a.

Automatic Actuation 2

1 2

1, 2 24 Logic and Actuation Relays E

b.

Steam Generator 4/stm.- gen.

2/stm. gen.

3/stm. gen.

1, 2 19 z

Water Level-in any oper in each oper-High-High (P-14) ating stm.

ating stm.

x gen.

gen.

c.

Safety Injection See Item 1. above for all Safety Injection initiating functions and g

requirements.

TABLE 3.3-3 (Continued)

. co.

A

- SE ENGINEERED. SAFETY FEATURES ACTUATION SYST2M INSTRUMENTATION C5 MINIMUM gj TOTAL NO.

. CHANNELS CHANNELS APPLICABLE-FUNCTIONAL UNIT' 0F CHANNELS TO TRIP OPERABLE.

MODES ACTION g

D*

6.

Auxiliary Feedwater to a.

Manual Initiation 2

1 2

1.,

2, 3 22 b.

Automatic Actuation Logic 2

1 2

1,2,3 21 and: Actuation Relays c.

Stm. Gen. Water Level-Low-Low

'1) ' Start Motor-l Driven Pump 4/stm. gen.

2/stm. gen.

3/stm. gen.

1, 2, 3 19 R3 in any opera-in each ting stm gen.

operating y

stm. gen.

o$

2) Start Diesel-Driven Pump 4/stm. gen.

2/stm. gen.

3/stm. gen.

1,2,3 19 in any in each.

operating operating stm. gen.

stm. gen.

d.

Undervoltage - RCP 4-1/ bus 2

3 1, 2 19 Bus-Start Motor-Driven Pump.and Diesel-Driven Pump

.3 e.

Safety Injection -

gg Start Motor-Driven Pump See Item 1. above for all Safety Injection initiating functions and g

and Diesel-Driven Pump requirements.

m 5

f.

Division 11 for Unit 1 g

(Division 21 for Unit 2)

ESF Bus Undervoltage-a Start Motor-Driven Pump (Start as part 2

2 2

1,2,3,4 25a i

of DG sequencing)

-.1.

TABLE 3.3-3 (Continued) c, I

.- g!

ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION n

C'5 MINIMUM d

TOTAL NO.

CHANNELS.

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

e 6.

Auxiliary Feedwater (Continued) -

n, g.

Auxiliary Feed-water Pump Suction Pressure-Low (Transfer to Essential Service Water) 2-2 2

1,2,3 15 7.

Automatic Opening of Containment Sump Suction 3:

Isolation Valves

[

a.

Automatic Actuation Logic 2

1 2

1,2,3,4 14 and Actuation Relays e

b.

RWST Level - Low-Low 4-2 3

1,2,3,4 16 Coincident With Safety Injection See Item 1. above for Safety Injection initiating functions and requirements.

8.

Loss of Power a.

ESF Bus Undervoltage 2/ Bus 2/ Bus 2/ Bus 1, 2, 3, 4 25a b.

Grid Degraded Voltage 2/ Bus 2/ Bus 2/ Bus 1,2,3,4 2Sb M

E E

Ei i

.Es

.q..

j.

q

' TABLE 3.3-3 (Continued) g.

. ENGINEERED SAFETY FEATURES-ACTUATION SYSTEM INSTRUMENTATION

'j MINIMUM y

'0F CHANNELS TO. TRIP-OPERABLE MODES

- ACTION'-

TOTAL NO.

CHANNELS CHANNELS.

APPLICABLE:

' FUNCTIONAL UNIT w

9.

Engineered : Safety Features N

Actuation System Interlocks a.

Pressurizer Pressure',

.3 2

.2 1, 2, 3 '

J20

- P-11-.

b.

~.leactor. Trip, P-4

'4-2/ Train 2/ Train 2/ Train-1,2,3 22-Low-Low T,yg, P-12 4

2 3

1, 2, 3 '-

20 c.

s d.

Steam Generator' Water Level, 4/stm.

2/stm.' gen.

3/stm.

1, 2 20-

[

P-14 (High-High) gen.

in any gen. in i

operating each e

E$

stm. gen.

. operating stm. gen.

1

'I i

i i

5 l

f

-*7y

.e-e e

W

TABLE 3.3-3 (Continued)

TABLE NOTATIONS

Trip function may be blocked in this MODE below the P-11 (Pressurizer Pressure Interlock) Setpoint.

1. Trip function automatically blocked above P-11 and may be blocked below P-11 when Safety Injection on low steam line pressure is not blocked.

ACTION STATEMENTS ACTION 14 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, be in at least HOT STANP3Y within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months ; however, one channel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing per Specification 4.3.2.1, provided the other channel is OPERABLE.

ACTION 15 - With the number of OPERABLE channels one less than the Total Number of Channels, operation may proceed until performance of the next required ANALOG CHANNEL OPERATIONAL TEST provided the inoperable channel is placed in the tripped condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

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

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

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

ACTION 18 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

BYRON - UNITS 1 & 2 3/4 3-21 AMENDMENT N0. 49

TABLE 3.3-3 (Continued)

ACTION STATEMENTS (Continued)

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

a.

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

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

ACTION 20 - With less than the Minimum Number of Channels OPERABLE, within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months determine _by observation of the associated permissive annunciator window (s) that the interlock is in its required state for the existing plant condition, or apply Specification 3.0.3.

ACTION 21 - With the number of OPERABLE Channels one less than the Minimum Channels OPERABLE requirement, be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; however, one channel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing per Specification 4.3.2.1 provided the other channel is OPERABLE.

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

ACTION 23 With the number of OPERABLE channels one less than the Total Number of Channels, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or declare the associated valve inoperable and take the ACTION required by Specification 3.7.1.5.

ACTION 24 - With the number of OPERABLE channels one less than the Minimum Channels OPEFABLE requirement be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; however, one channel may be bypassed for up to 2 hcurs for surveillance testing per Specification 4.3.2.1 provided the other channel is OPERABLE.

ACTION 25 - a.

With the number of OPERABLE channels one less than the

-Minimum Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the inoperable channel is placed in l

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

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

b.

With the number of OPERABLE channels or.e less than the Mini-mum Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the inoperable channel is placed in the l

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

l BYRON - UNITS 1 & 2 3/4 3-22

INSTRUMENTATION 3/4.3.3 MONITORING INSTRUMENTATION RADIATIONMONITORINGFORPLANTOPERfTIONS LIMITING' CON 0! TION FOR CPERATION 3.3.3.1 The radf ation monitoring instrumentation channels for plant operations shown in Tabic 3.3-6 shall be OPERABLE with their' Alarm / Trip Setpoints within the specified. limits, f0PLICABILITY:

As shown in Table 3.3-6.

ACTION:

a.

With a radiation monitorir.g channel Alarm / Trip Setpoint for plant operations exceeding the value shown in Table 3.3-6, 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 for plant operations inoperable, take the ACTION shown in Table 3.3-6.

c.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.3.1 Each radiation monitoring instrumentation channel for plant uperations shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and DIGITAL CHANNEL OPERATIONAL TEST for the MODES and at the frequencies shown in Table 4.3-3.

BYRON - UNITS 1 & 2 3/4 3-39 AMENDMENT NO. 49

TABLE 3.3-6 L

to

[

g RADIATION MONITORING INSTRUMENTATION FOR PLANT OPERATIONS l

S f11NIMUM CilANNELS CHANNELS APPLICABLE ALARM / TRIP j

5 d

FUNCTIONAL UNIT TO TRIP / ALARM OPERABLE

, MODES SETPOINT ACTION i

1.

Fuel Building Isolation-p.

Radioactivity-High and l

Criticality (ORE-AR055/56) 1 2

<5 mR/h 29 y

f 2.

Containment Isolation-Containment Radioactivity-High 26 a) Unit 1 (1RE-AR011/12) 1 2

All 26 b) Unit 2 (2RE-AR011/12) 1 2

All t'

3.

Gaseous Radioactivity-RCS. Leakage Detection Y

a) Unit 1 (IRE-PR0118)

N.A.

I 1,2,3,4

'N.A.

28 f.;

b) Unit 2 (2RE-PR0118)

N.A.

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

28

'4.

Particulate Radioactivity-RCS Leakage Detection a) Unit 1 (1RE-PR011A)

H.A.

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

28 b) Unit 2 (2RE-PR011A)

N.A.

I 1,2.3,4 H.A.

28 I

5.

Main Control Room Isolation-Outside Air Intake-Gaseous l

Radioactivity-High l

(ORE-PR031B/32B and ORE-PR033B/348) 1 2 per All

< 2 mR/h 27 intake

INSTRUMEI4TATION MOVABLE INCORE DETECTORS LIMITING CONDITION FOR OPERATION 3.3.3.2 The Movable Incore Detection System shall be OPERABLE with:

a.

At least 75% of the detector thimbles, b.

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

Sufficient movable detectors, drive, and readout equipment to map these thimb'es.

APPLICABILITY: When the Movable Incore Detection System is used for:

a.

Recalibration of the excore neutron flux detection system, or b.

Monitoring the QUADRANT POWER TILT RATIO, or MeasurementofFfg,F(2)andF c.

9 xy' ACTION:

W4+h +"e Movable Incore Detection System inoperable, do not use the system for tne.

se applicable monitoring or calibration functions.

The provisions of Specifi ation 3.0.3 are not applicable.

l SURVEILLANCE REQUIREMENTS 4.3.3.2 The Movable Incore Detection System shall be demonstrated OPERABLE at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by normalizing each detector output when required for:

a.

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

Monitoring the QUADRANT POWER TILT RATIO, or H, F (Z), and Fxy.

c.

Measurement of F q

BYRON - UNITS l'& 2 3/4 3-43 AMENDMENT NO. 49

[

b

i o,

INSTRUMENTATION 3,

SEISMIC INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.3 The seismic monitoring it.strumentation shown in Table 3.3-7 shall be

)

OPERABLE.

APPLICABILITY: 'At all times.

ACTION:

With one or more of the above required seismic monitoring instruments e

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 are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.3.3.1 The seismic monitoring instrumentation shall be determined OPERABLE:

At least once per 31 days by verifying operable status indications of a.

the seismic monitoring-instrumentation.

b.

At _least once per 92' days by verifying that:

1)

The triaxial acceleration sensors and the tine-history accelero-graphs properly process the equipment internal test signals.

2)

The response spectrum analyzer properly executes its diagnostic

routine, c.

At least once per 184 days by_ verifying that the triaxial acceleration sensors and the time-history accelerographs properly record the equipment internal test signals.

The test may be performed in lieu of the test required by Specification 4.3.3.3.1.b.1), and d.

At least once per 18 months by:

1)

Verifying the electronic calibration of the time-history accelerographs.

2)-

Installing fresh magnetic recording plates in the triaxial peak accelerographs.

4.3.3.3.2 Upon actuation of the seismic monitoring instruments, the equipment listed in-Table 3.3-7 shall be restored to OPERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 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 14 days describing the magnitude, frequency spectrum and resultant effect upon-facility features important to safety.

j-BYRON - UNITS 1 & 2 3/4 3-44 AMENDMENT NO. 49

INS 7RUMENTATION METEOROLOGICAL INSTRUMENTATION l

LIMITING CONDITION FOR OPERATION 3.3.3.4 The meteorological monitoring instrumentation channels given in Table 3.3-8 shall be OPERABLE.

APPLICABILITY:

At all times.

ACTION:

a. -With one or more required meteorological monitoring channels inoperable for more than 7 days, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 within the next 10 days outlining the cause of the malfunction and the plans for restoring the channel (s) to OPERABi.E status.

b.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.3.4 Each of the above meteorological monitoring instrumentation channels shall be demonstrated.0PERABLE by the performance of the CHANNEL CHECK and CHANNEL-CALIBRATION operations at the frequencies given in Table 4.3-5.

BYRON - UNITS 1 & 2 3/4 3-47 AMENDMENT.NO. 49

~**

TABLE 3.3-8 METEOROLOGICAL MONITORING INSTRUMENTATION MINIMUM INSTRUMENT LOCATION OPERABLE 1.

Wind Speed Nominal Elev. 30 ft 1

Nos.'nal Elev. 250 ft 1

2.

Wind Direction Nominal Elev. 30 ft 1

Nominal Elev 250 ft 1

3.

Air Temperature - AT Nominal Elev. 30 ft/250 ft 1

i BYRON - UNITS 1 & 2 3/4 3-48 L

l

. g-INSTRUMENTATION LOOSE-PART DETECTION SYSTEM LIMITING CONDITION FOR-OPERATION 3.3.3.8 The Loose-Part Detection System shall be OPERABLE.

, APPLICABILITY:

MODES 1 and 2.

ACTION:

a.

With one or.r re 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 malfuncti'on and the plans for restoring the channel (s) to OPERABLE status.

b.

The provisions of Specification 3.0.3 are not applicable.

' SURVEILLANCE REQUIF.EMENTS 4.3.3.8 Each channel of the Loose-Part Detection Systems 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.

An ANALOG CHANNEL OPERATIONAL TEST except for verification of setpoint at least once per 31 days, and c.

A CHANNEL CALIBRATION at least once per 18 months.

1.

-. BYRON - UNITS _1 & 2 3/4 3-58 AMENDMENT NO. 49 L

i.

INSTRUMENTATION--

EXPLOSIVE GAS MONITORING INSTRUMENTATION-LIMITING CONDITION FOR OPERATION 3.3.3.10 The explosive gas monitoring instrumentation channels shown in Table 3.3-13 shall be OPERABLE with their Alarm / Trip Setpoints set to ensure that the limits of-Specification 3.11.2.5 are not exceeded.

APPLICABILITY:

As shown in-Table 3.3-13 ACTION:

With an explosive gas monitoring instrumentation channel Alarm / Trip a.

Setpoint less conservative than required by the above specification, declare the channel inoperable and take the ACTION shown in Table 3.3-13.

b.

With less than the minimum number of explosive gas monitoring instru-mentation channels OPERABLE, take the ACTION shown in Table 3.3-13.

Restore the inoperable instrumentation to OPERABLE status within 30 days and, if unsuccessful, prepare and submit a Special Report to the Commission within the next 30 days pursuant to Specification 6.9.2 to explain why this inoperability was not corrected in a timely manner, c.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.3.10 Each exple 'ive gas monitoring instrumentation channel shall be demonstrated OPERABLE by-performance of the CHANNEL CHECK, CHANNEL CALIBRATION and DIGITAL Ct:ANNEL 0PERATIONAL TEST at the frequencies shown in Table 4.3-9.

BYRON - UNITS 1 & 2 3/4 3-60 AMENDMENT NO. 49

INSTRUMENTATION HIGH ENERGY LINE BREAK ISOLATION SENSORS LIMITING CONDITION FOR OPERATION 3.3.3.11 The high energy.line break instrumentation shown in Table 3.3-14 shall be OPERABLE.

APPLICABILITY:

As shown in Table 3.3-14.

ACTION:

a.

With the number of OPERABLE auxiliary steam isolation instruments less than the_ Minimum Channels OPERABLE as required by Table 3.3-14, restore the inoperable instrument (s) to OPERABLE status within 7 days, or suspend the supply of auxiliary steam-to the Auxiliary Building, or establish a continuous watch in the affected area (s) until the inoperable sensors are restored to OPERABLE status.

-b.

With the number of-0PERABLE steam generator blowdown line isolation instru-ments-less than the Minimum Channels 0PERABLE as. required by Table 3.3-14, restore the inoperable instrument (s) to OPERABLE status within 7 days, or limit the_ total steam generator blowdown flow rate to less than or_ equal to 60 gpm or establish a continuous watch in the affected area (s) until the inoperable sensors are restored to OPERABLE status.

c.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.3.12 Each of the above high energy line break isolation instruments shall be demonstrated OPERABLE by the performance of an ANALOG CHANNEL OPERATIONAL

-TEST AND CHANNEL CALIBRATION at least once per 18 months.

BYRON - UNITS 1 & 2 3/4 3-63 AMENDMENT N0. 49 b-

--d-

.v J.

A

r 9,.

10 9

8 7

REJECT 6

V-3 g#

CONTINUE

/

TESTING j

2 3

r 2

'1 ACCEPT 1

r-s 0

10 20 30 40 50 60 70 80 90 100 N

FIGURE 4.7-1 SAMPLE PLAN 2) FOR SNUBBER FUNCTIONAL TEST' l-BYRON - UNITS I & 2 3/4 7-27 l

=

PLANT-SYSTEMS 3/4.7.9 SEALED SOURCE CCNTAMINATION 1

LIMITING CONDITION FOR OPERATION 3.7.9 Each_ sealed source containing radioactive material either in excess of 100 microCuries of beta and/or gamma emitting material or 5 microCuries of alpha emitting material shall be free of greater than or equal to 0.005 microcurie of removable contamination, APPLICABILITY:

At all times.

ACTION:

a.

With a sealed source having removable contamination in excess of the above limits, immediately 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.

' SURVEILLANCE REQUIREMENTS 4.7.9.1 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 26 Agreement State.

The test method shall have a detection sensitivity of at least 0.005 microcurie per test sample.

4.7.9.2 Test Frequencies - Each category of sealed sources (excluding startup; sources and fission 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 materials:

1)

With a half-life greater than 30 days (excludirn "vdrogen 3),

and 2)

In any form other than gas.

BYRON - UNITS 1 & 2 3/4 7-28 AMENDMENT N0. 49

~. -

j REFUELING OPERATIONS 3/4.9.6 REFUELING MACHINE I

tlMITING CONDITION FOR OPERATION 3.9.6 The refueling machine ', hall be used for movement of drive rods or fuel assemblies and shall be OPERABLE with:

The refueling machine used for movement of fuel assemblies having:

a.

1)

A capacity equal to or greater than 2850 pounds, and 2)

An overload cutoff limit less than or equal to 2850 pounds.

b.

The auxiliary hoist used for latching and unlatching drive rods having:

1)

A capacity equal to or greater than 2000 pounds, and 2)

A load indicator which shall be used to prevent lifting loads in excess of 1000 pounds.

APPLICABILITY:

Ouring movement of drive rods or fuel assemblies within the reactor vessel.

ACTION:

With the requirements for refueling machine and/or hoist OPERABILITY not satis-fied, suspend use of any inoperable refueling machine and/or auxiliary hoist from operations involving the movement of drive rods ad fuel assemblies within the reactor vessel.

SURVEILLANCE REQUIREMENTS 4.9.6.1 Each refueling machine used for movement of fuel assemblies within the reactor vessel shall be demonstrated OPERABLE within 100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months prior to the start of such operations by performing a load test of at least 3563 pNnds and demonstrating an automatic load cutoff when the crane load exceeds 2850 pounds.

4.9.6.2 Each auxiliary hoist and associated load indicator used for movement of drive rods within the reactor vessel shall be demonstrated OPERABLE within 100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months prior to the start of such operations by performing a load test of at least 2500 pounds.

. BYRON - UNITS 1 & 2 3/4 9-7

~ - _ _

~

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

REFUELINGOPERATIO3 3/4.9.7 CRANE TRAVEL - SPENT FUEL STORAGE FACILITY LIMITING CONDITION FOR OPERATION 3.9.7 Loads in excess of 2000 pounds shall be prohibited from travel over fuel assemblies in the spent fuel storage facility.

APPLICABILITY:

With fuel assemblies in the spent fuel storage facility.

ACTION:

a.

With the rquirements of the above specification not satisfieJ, place the crane load in a safe condition.

b.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.9.7 Crane interlocks and physical stops which prevent crane travel with loads 'a excess of 2000 pounds over fuel assemblies shall be demonstrated OPERABLE within 7 days prior to crane use and at least once per 7 days

'thereafter during crane operation.

t BYRON - UNITS 1 & 2 3/4 9-8 AMENDMENT NO. 49

o. -

_ REFUELING OPERATIGNS

-\\.

3/4.9.9 CONTAINMENT PURGE 150LA110N SYSTEM LIMITING CONDITION FOR OPERATION 3.9.9 The Containment Purge Isolation System shall be OPERABLE.

APPLICABILITY:

During CORE ALTERATIONS or movement of irradiated fuel within the containment.

ACTION:

a.

With the Containment Purge Isolation System inoperable, close each of the purge valves providing direct access from the containment atmosphere to the outside atmosphere, b.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.9.9 The Containment Purge Isolation System shall be demonstrated OPERABLE within 100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months prior to the start of and at least once per 7 days during CORE. ALTERATIONS by verifyiig that co7tainment purge isolation occurs on an ESF.

test signal from each of tht containment radiation monitoring instrumentation channels.

e s

l l

L

. BYRON - UNITS 1 & 2 3/4 9-11 AMENDMENT NO. 49 l

..~

Rff0ELING OPERATIONS 3/4.9.10 WATER LEVEL - REACTOR VESSEL LIMITING CONDIT!0N FOR OPERATION 3.9.10 At least 23 feet of water shall be maintained over the top of the reactor vessel flange.

APPLICABILITY:

During movement of fuel assemblies or control rods within the containment when either the fuel assemblies being moved or the fuel assemblies seated within the reactor vessel are irradiated while in MODE 6.

ACTIO',,

With the requirements of the above specification not satisfied, suspend all operations involving movement of fuel assemblies or control rods within the reactor vessel.

SURVEILLANCE REQUIREMENTS 4.9.10 The water level shall be determined to be at least its minimum required depth within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months prior to the start of and at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter during movement of fuel assemblies or control rods.

BYRON - UNITS 1 & 2 3/4 9-12

,--w--

,,--r

-ve

' ~'

l l

REFUELING OPERATIONS 3/4.9.11 WATER LEVEL - STORAGE P00i LIMITING CONDITION FOR OPERATION l

3.9.11 At least 23 feet of water shall be maintained over the top of irrtalated fuel assemblies seated in the storage racks.

APPLICABILITY:

Whenever irradiated fuel assemblies are in the storage pool.

ACTION:

a.

With the requirements of the above specificat en not satisfied, suspend all movement of fuel assemblies and crane coerations-with loads in the fuel storage areas and restore the water level to within its limit within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , b._

The p-ovisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS

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

BYRON - UNITS 1 & 2

./4 9-13 AMENDMENT NO. 49

REFUELING OPERATIONS.

3/4.9.12 FUEL HANDLING BUILDING EXHAUST FILTER PLENUMS LIMITING CONDITION FOR OPERATION 3.9.12 Two independent Fuel Handling Building Exhaust Filter Plenums shall be j

OPERABLE.

APPLICABILITY:

Whenever irrauiated fuel is in the storage pool ACTION:

a.

With one Fuel Handling Building Exhaust Filter Plenum inoperable, fuel movement within the storage pool, or crane operation with loads over the storage pool, may proceed provided the OPERABLE Fuel Handling Building Exhaust Filter Plenum is capable of being powered t

from an OPERABLE emergency power source and is in operation and j

taking suction from at least one train of HEPA filters and charcoal adsorbers.

b.

With no Fuel Handling Building Exhaust Filter Plenums OPERABLE, suspend all operations involving movement of fuel within the storage pool, or crane operation with loads over the storage pool, until at least one Fuel Handling Building Exhaust Filter Plenum is restored to OPERABLE status, c.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.9.12 The_above required Fuel Handling Building Exhaust Filter Plenums shall be demonstrated OPERABLE:

a.

At least once per 31 days on a STAGGERED TEST BASIS by initiating, from the control room, flow through the HEPA filters and charcoal adsorbers and verifying that the system operates for at least 15 minutes; b.

At least once per 18 months, or (1) after any structural maintenance on the HEPA filter or charcoal adsorber housings, or (2) following painting, fire, or chemical release in any ventilation zone communicating with the system, by:

BYRON-- UNITS 1 & 2 3/4 9-14 AMENCHENT NO. 49 I

3/4.11 RADIOACTIVE EFFLUENTS l

3/4.11.1 LIQUID EFFLUENTS LIQUID HOLDUP TANKS LIMITING CONDITION FOR OPERATION 3.11.1.1 Deleted 3.11.1.2 Deleted 3.11.1.3 Deleted 3.11.1.4 The quantity of radioactive material, excluding tritium and dissolved or entrained noble gases, contained in any outside. tanks shall be limited to the following:

a.

Primary Water Storage Tank 5 2000 Curies, and b.

Outside Temporary Tr.nk

< 10 Curies.

APPLICABILITY:

At all times.

ACTION:

a.

With the quantity of radioactive material in any of the above listed 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 6.9.1.7.-

b.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 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 representative sample of the tank's contents at least once per 7 days when radioactive materials are being added to the tank.

l l

BYRON - UNITS 1 & 2 3/4 11-1 AMENDMENT NO. 49 L

.--~.-

~_

RADIDACTIVE EFFLUENTS 3/4.11.2 GASEOUS EFFLUENTS EXPLOSIVE GAS MIXTURE LIMITING CONDITION FOR OPERATION 3.11.2.1 Deleted 3.11.2.2 Deleted 3.11.2.3 Deleted 3.31.2.4 Deleted 3.11.2.5 The concentration of oxygen in the WASTE GAS HOLOUP SYSTEM shall be limited to less than or equal to 2% by volume whenever the hydrogen concentration exceeds 4% by volume.

APPLICABILITY: _ At all times.

~

ACTION:

a.-

With-the-concentration of oxygen in the WASTE GAS HOLDUP SYSTEM

~

greater than 2% by volume but less than or equal to 4% by volume, reduce the-oxygen concentration ~to the above limits within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months .

b.

With the concentration of oxygen in the WASTE GAS HOLDUP SYSTEM greater than 4% by. volume and the hydrogen concentration greater than 4% by volume,-immediately suspend all additions of waste gases to the system and reduce the concentration of oxygen to less than or equal to 4% by volume, then take ACTION a above, c.

The provisions'of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS-4.~ 11. 2. 5 The concentrations-of hydrogen and oxygen in the WASTE GAS HOLDUP SYSTEM shall be determined to be within the above limits by continuously monitoring the wasteLgases in the WASTE GAS HOLDUP SYSTEM with the hydrogen

.and oxygen monitors required OPERABLE by Table 3.3-13 of Specification 3.3.3.10.

BYRON - UNITS 1 & 2 3/4 11-2 AMENDMENT NO. 49 a

l 4

RADIOACTIVE EFFLUENTS CAS DECAY TANKS LIMITING CONDITION FOR OPERATION I

3.11.2.6 The quantity of radioactivity contained in each gas decay tank shall be limited to less than or equal to 5x104 Curies of noble gases (considered as Xe-133 equivalent).

APPLICABILITY:

At all times.

ACTION:

a.

-Wo.h the quantity of radioactive material in any gas decay tank exceeding the above limit, immediately suspend all additions of radioactive material to the tank and, 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 tu this condition in the next Semiannual Radioactive Effluent Reicase Report, pursuant to Specification 6.9.1.7.

b.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.11.2.6 The quantity of radioactive material contained in each gas decay tank shall be determined to be within the above limit at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when radioactive materials are being added to the tank.

l l

BYRON - UNITS 1 & 2 3/4 11-3 AMENDMENT NO. 49

3/4 LIMIT' 4G CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.0 APPLICABILITY BASES Specification 3 0.1 through 3.0.5 establish the general requirements applicable to Limiting Conditions for Operation.

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

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

When a limiting condition for operation 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."

Specification 3.0.1 establishes the Applicability statement within each individual specITication as the requirement for when (i.e., in which OPERATIONAL MODES or other sper:ified conditions) confornance to the Limiting Conditions for Operation is required for safe cperation of the facility.

The ACTIOk requirements establish those remedial measures that must be taken within specified time limits when the requirements of a Limiting Condition for Operation are not met.

There are two basic types of ACTION requirements.

The first specifies the

. remedial measures that permit continued operation of the facility which is not further restricted by the time limits of the ACTION requirements.

In this case, conformance to the ACTION requirements provides an acceptable level of safety for unlimited continued operation as long as the ACTION requirements continue to be ret.

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

This time limit is the allowable outage time tr restore an inoperable system or component to OPERABLE status or for restt* ng parameters within specified limits.

If these actions are not completed within the allowable outage time lim ts -a shutdown is required to place the facility in a-MODE or condition in which the specification no longer applies.

It is not-intended that the shutdown ACTION requirements be used as an operational convenience which permits (routine) voluntary removal of a system (s) or component (s) f rom service in lieu of other alternatives that would not result in redundant systems or components being inoperable.

The specified time limits of the ACTION requirements are applicable from the point in time it is identified that a Limiting Condition for Operation is not met.

The time limits of the ACTION requirements are also applicable when a system or component is removed from service for surveillance tesung or investigation of operational problems.

Individual specifications may include a specified time limit for the completion of a Surveillance Requirement when equioment is removed from service.

In this case, the allowable outage time BYRON - UNITS 1 & 2 B 3/4 0-1 AMENDMENT N0. 49

.u, _

3/4.0 APPLICABILITY BASES limits of the ACTION requirements are applicable when this limit spires if the surveillance has not been completed.

When a shutdown is required to comply with ACTION requirements, the plant may have entered a MODE 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 specifi-catitn becomes applicable if the requirements of the Limiting Condition for Operation are not met, S3ecification 3.0.2 establishes that noncompliance with a specification exists w1en theIrequirements of the Limiting Condition for Operation are not met and the associated ACTION requirements have not been implemented within the speci-fied 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.

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 assocised ACTION requirements.

The purpose of this specification is tc delineate the time limits for placing the unit in a safe shutdown MODE when plant operation cannot be maintained within the limits for safe operation defined by the Limiting Conditions for Operation and its ACTION requirements.

It is not intended to be used as an operational convenience which permits (routine) voluntary removal of redundant 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 MODES of opera', ion 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 there was a failure to meet a Limiting Condition for Operation.

Therefore, the shutdown may be terminated if the ACTION requirements have been met or the time limits of the ACTION requirements have not expired, thus providing an allowance for the completion of the required actions.

BYRON - UNITS 1 & 2 B 3/4 0-2 AMENDMENT NO. 49

h 3/4.0 APPLICABILITY BASES 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 the COLD SHUTDOWN MODE when a shutdown is required during the POWER MODE of operation.

If the plae is in a lower MODE of operation when a shutdown is required, the time limit. for reaching the next lower MODE of operation ap-plies.

However, if a lower MODE of operation is reached in less time than allowed, the total allowable time to reach COLD SHUTDOWN, or other applicable MODE, is not reduced.

For example, if HOT STANDBY 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 SHOTDOWN 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 POWER ooeration, a penalty is not incurred by having to reach a lower MODE of operation in less than the total time allowed.

The same principle applies with regard to the allowable outage time limits of the ACTION requirements, if compliance with the ACTION requirements for one specification results in entry into a MODE or condition of operation for another specification in which the requirements of the Limiting Condition for Operation are not met.

If the new specification becomes applicable in less time than specified, the difference may be added to the allowable outage time limits of the second-specification.

However, the allowable outage time limits of ACTION requirements for a higher MODE of 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 MODE of operation.

The shutdown requirements of Specification 3.0.3 do not apply in MODES 5 and 6, because the ACTION requirements of individual specifications define the remedial measures to be taken.

Specification 3.0.4 establishes limitations on MODE changes when a Limiting Condition for Operation is not met.

It precludes placing the facility in a higher MODE of operation when the requirements for a Limiting Condition for Operation are not met and continued noncompliance to these conditions would result in a shutdown to comply with the ACTION requirements if a change in MODES were permitted.

The purpose of this specification is to ensure that facility operation is not initiated or that higher MODES of operation are net entered when corrective action is being 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 accept-able level of safety for continued operation without regard to the status of the plant before-or after a MODE change.

Therefore, in this case, entry into an OPERATIONAL MODE 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 is endorsing the failure to exercise good practice in restoring systems or components to OPERABLE status before plant startup.

BYRON - UNITS 1 & 2 B 3/4 0-3 AMENDMENT N0. 49 1

______._._m 3/4.0 APPLICABILITY BASES When 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 facility in a lower MODE of operation.

Spectfication 3.0.5 delineates the applicability of each specification to j

Unit I and Unit 2 operation.

Specification 4.0.1__through 4.0.6 establish the general requirements applicable lo Surveillance Recuirements.

These requiren, ants are baced on the Surveillance Requirements statec in the Code of Federal Regulations,10 CFR 50.36(c)(3):

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

Specification 4.0.1 establishes ti pq*cmer.t that surveillances must be performed during the OPERATIONAL MUbL or other conditions for which the requirements of the Limiting Conditions for Operation apply unless otherwise stated in an individual Surveillance Re'uirement.

The purpose of this speci-fication is to ensure that surveillance, are )erformed to verify the opera-tional_ status of systems and components and t1at parameters are within speci-fied limits to ensure safe operation of the facility when the plant is in a MODE or other specified condition for which the associated limiting Conditions for Operation are applicable.

Surveillance Requirements do not have to be performed when the facility is in an OPERATIONAL MODE for which the requirements of the associated Limiting Condition for Operation do not apply unless otherwise specified.

The Surveillance Requirements associated with a Special Test Exce)-

tion are only applicable when the Special Test Exception is used as an allowaale

. exception to the. requirements of a specification.

Specification 4.0.2 establishes the limit for which the 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.c., transient conditions or other ongoing surveillance or maintenance activities.

It also provides flexibility to accommodate the length of 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 intervels beyond that spccified for surveillances that are not performed during refueling outages.

ThelimitationofSpecification4.0.2isbased.onengineeringjudgementand the recognition that most probable result of any particular surveillance being performed is the verification of conformance with.he 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, defi vd by the provisions of Specification 4.0.2, as a condition that constitutes a failure to meet the OPERABILITY _ requirements for a Limiting Condition for Operation.

BYRON - UNITS 1 & 2 B 3/4 0-4 AMEN 0 MENT NO. 49

3/4.0 APPLICABILITY BASES Under the provisions 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 Requirements.

This specification also clarifies that the ACTION requirements are applicable when Surveillance Requirements have not Deen completed within the allowed surveillance interval and that the time limits of the ACTION requirements apply from the point in time it is identi-fied that a surveillance has not been performed and not at the time that the allowed surveillance interval was exceeded.

Completion of the Surveillance Requirement within the ellowable outage time limits of the ACTION requirements restores compliance with the requirements of Specification 4.0.3.

However, this does not negate the fact that the failure to have performed the surveil-lance within the-allowed surveillance interval, defined by the provisions of Specification 4.0.2, was a violation of the OPERABILITY requirements of a Limiting Condition for Operation that is subject to enforcement action.

Further,'the failure to perform a surveillance within the provisions of Specification 4.0.2 is a violation of a Technical Specification requirement and is, therefore, a reportable event under the requirements of 10 CFR 50.73(a)(2)(1)(B) because it is a condition prohibited by the plant's Technical Specifications.

If 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 or a shutdown is required to comply with ACTION requirements, e.g.,

Specification 3.0.3, a 24-hour allowance is provided to permit a delay in implementing the ACTION requirements.

This provides an adequate time limit to complete Surveillance Requirements that have not been performed.

The purpose of this allowance is to permit the completion of a surveillance before a shutdown is required to comply with ACTION requirements or before other remedial reasures would be required that may preclude completion of a surveillance.

The basis for this allowance includes consideration for plant conditions, adequate plcnning, availability of personnel, the time required to perform the surveillance, and the safety significance of the delay in completing the required surveillance.

This provision also prcvides a time limit for the completion of Surveillance Requirements that become applicable as a consequence of MODE changes imposed by ACTION requirements and for completing Surveillance Requirements that are applicable when an exception to the requirements of Specification 4.0.4 is allowed.

If a surveillance is not completed within the 24-hour allowance, the time limits of the ACTION requirements are applicable at that time.

When a surveillance is performed within the 24-hour allowance and the Surveillance Requirements are not met, the time limits of the ACTION requirements are applicable at the time that the surveillance is terminated.

l Surveillance Requirements do not have to be performed on inoperable equipment because the ACTJON 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.

l BYRON - UNITS 1 & 2 B 3/4 0-5 AMENDMENT NO. 49 l

l

3,/4. 0 APPLICABILITY BASES Specification 4.0.4 establishes the requirement that all applicable surveillances must be met before entry into an OPERATIONAL MODE or other condition of operation specified in the Applicability statement.

The purpose of this specification is to ensure that system and component OPERABILITY requirements or parameter limits are met before entry into a MODE or condition for which these systems and components ensure safe operation of the facility.

This provision applies to changes in OPERATIONAL MODES or other specj,fied conditions associated with plant shutdown as well as startup.

Under the provisions of this specification, the applicable Surveillance Requirements must be performed within the specified surveillance interval to i

ensure that the Limiting Conditions for Operation are met during initial i

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 MODE of operation.

Specification 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 parformed in accordance with a 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 apply except when relief has been provided in writing by the Commission.

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 throughout the Technical Specifications and to remove any ambiguities relative to the frequencies for performing the required inservice inspection and testing activities.

under the terms of this specification, the more restrictive requirements of the Technical Specifications take precedence over the ASME Boiler and Pressure Vessei Code and applicable Addenda.

The requirements of Specification 4.0.4 to perform surveillance activities before entry into an OPERATIONAL MODE or other specified condition takes precedence over the ASME Boiler and Pressure Ve'ssel Code provision which allows pumps and valves to be tested up to one week after return to normal operation.

The Technical Specification definMion of OPERABLE does not allow a-grace period before a component, that is not capeble of performing its specified function, is declared inoperable and takes precedence over the ASME Boiler and Pressure Vessel Code provision which 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.

Specification 4.0.6 delineams tne applicability of the surveillance activities to Unit 1 and Unit 2 operations.

BYRON - UNITS 1 & 2 B 3/4 0-6 AMENDMENT NO. 49

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3' E

'n UNITED STATES i

NUCLEAR REGULATORY COMMISSION 8

WASHINGTON. D C. 20066 o

's,.....

COMMONWEALTH EDIS0N COMPANY DOCKET NO. STN 59-456 fLRAIDWOOD STAT 10N,.J1NLT_30d AMENDMENT TO FAClllTY OPERATING LICENSE Amendment No. 38 License No, NPF-77.

1.

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

A.

The application for amendment by Commonwealth Edison Company (the licensee) dated November 30, 1988, as supplemented on May 30, 1990, April 19, 1991, and February 27, 1992, 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 confo:mity 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 Specifi-cations as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. NPF-72 is here'oy amended to read as follows:

1

(2)

Technical Snecifications The Technical Specifications contained in Appendix A as revised through Amendment No. 38 and the Environmental Protection Plan contained in Appendix B, both of which are attached hereto, are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

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

FOR THE NUCLEAR REGULATORY COMMISSION f*

r U

offlwt i

Richard J. Barrett, Director Project Directorate III-2 Division of Reactor Projects - III/IV/V Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of issuance:

August 11, 1992 l

l

[ps atow N

UNITED STATES

.C -

.i NUCLEAR REGULATORY COMMISSION

$ ',k+ v 1 11

'/

WASHINoToN. D C. MA

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COMMONWEALTH EDIS0N COMPANY DOCKET NO. STN 50-457 Bl&10F00D $ TAT 10N. UNIT NO. 2 AJ[@B(([T TO FACillTY OPERATING llCENSE Amendment No. 38 License No. NPF-77 1.

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

A.

The application for amendment by Commonwealth Edison Company (the licensee) dated November 30, 1988, as supplemented on May 30, 1990, April 19, 1991, and February 27, 1992, 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 1:

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 tiis 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 Specifi-cations as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of facility Operating License No. NPF-77 is hereby amended to read as follows:

? (2)

Jachnical Specificationi The Technical Specifications contained in Appendix A as revised through Amendment No. 38 and the Environmental Protection Plan contained in Appendix B, both of which were attached to License No. NPF-72, dated July 2, 1987, are hereby incorporated into this license. The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection i

Plan.

3.

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

.FOR THE NUCLEAR REGULATORY COMMISSION Cf(l' g(n Richat'd If Ba'rrett, Director Project Directorate !!!-2 Division of Reactor Projects - 111/IV/V Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: August 11, 1992

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ATTACHMENT TO LICENSE AMENDMENT N05. 38 AND 38 FACILITY OPERATING LICENSE NOS. NPF-72 AND NPT-77 DOCKET NOS. STN 50-456 AND STN 50-457 Replace the following pa es of the Appendix "A" Technical Specifications with v

the attached pages.

The revised pages are identified by amendment number and contain vertical lines indicating the area of change.

Remove Paaes Insert Paoes 3/4 0-1 3/4 0-1 3/4 0-2 3/4 0-2

3/4 2-1

3/4 2-1 3/4 2-2 3/4 2-2

3/4 2-5

3/4 2-5 3/4 2-6 3/4 2-6 3/4 2-9 3/4 2-9 i

3/4 2-10

3/4 2-10

3/4 2-11

3/4 2-11 3/4 2-12 3/4 2-12

3/4 3-1

3/4 3-1 3/4 3-2 3/4 3-2 3/4 3-3 3/4 3-3 3/4 3-4 3/4 3-4 3/4 3-5 3/4 3-5 3/4 3 3/4 3-12 3/4 3-12a 3/4 3-12a 3/4 3-15 3/4 3-15 43/4 3 *3/4 3-16 3/4 3-17' 3/4 3-17 3/4 3-18 3/4 3-18 3/4 3 3/4-3-19

3/4 3-20

3/4 3-20 3/4 3-21 3/4 3-21

3/4 3-22

3/4 3 3/4 3-39 3/4 3-39

3/4 3-40

3/4 3-40 3/4 3-43 3/4 3-43 3/4 3 3/4 3-44 t

-3/4 3-47 3/4 3-47

3/4 3-48

3/4 3-48 3/4 3-58 3/4 3-58 3/4 3-60 3/4 3-60 3/4 3-63 3/4 3-63

3/4 7-25

3/4 7-25 3/4 7-26 3/4 7-26

3/4 9-7

3/4 9-7 3/4 9-8 3/4 9-8 3/4 9-11 3/4 9-11

3/4 9-12_

3/4 5-12

i j

, i Remove Paoes Insert Paaes 3/4 9-13 3/4 9-13 3/4 9-14 3/4 9-14 3/4 11-1 3/4 11-1 3/4 11-2 3/4 11-2 3/4 11-3 3/4 11-3 8 3/4 0-1 B 3/4 0-1 B 3/4 0-2 8 3/4 0-2

- i B 3/4 0-3 8 3/4 0-3 l

B 3/4 0 4 B 3/4 0-5 B 3/4 0-6 I

f.'.

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W" pe r W** P t M ?O P m%= k W pr -

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3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 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 MODES or other conditions specified therein; except that upon failure to tieet the Limiting Conditions for Operation, the associated ACTION requirements shall be met.

3.0.2 Noncompliance with a specification shall exist when the requirements of the Limiting Condition for Operation and associated ACTION requirements are not met within the specified time intervals.

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

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

a.

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

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

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

Where corrective measures are completed that permit operation under the ACTION requirements, the action may be taken in accordance with the specified time limits as measured from the time of failure to meet the Limiting Condition for Operation.

Exceptions to these requirements are stated in the individual specifications.

This specification is not applicable in MODE 5 or 6.

3.0.4 Entry into an OPERATIONAL MODE 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 interval.

Entry into an OPERATIONAL MODE or specified condition may be made in accordance with 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 MODES as required to comply with ACTION requirements.

Exceptions to these requirements are stated in the individual specifications.

3.0.5 Li W M Concitions for Operation including the associated ACTION require-ments i s ly te each unit individually unless otherwise indicated as follows:

a.

'wer the Limiting Conditions for Operation refers to systems or ri6 onents which are shared by both units, the ACTION requirements e il apply to both units simultaneously.

b.

Whenever the Limiting Conditions for Operation applies to only one unit, this will be identified in the APPLICABILITY section of the specification; and c.

Whenever ; 'tain portions of a specification contain operating param-etera - 7 lats, etc., which are different for each unit, this will be iud W in parentheses, footnotes or body of the requirement.

BRAIDWOOD - UNITS 1 & 2 3/4 0-1 AMENDMENT N0. 38

l

~*

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

4.0.2 Each Surveillance Requirement shall be performed within the specified time interval with a maximum allowable extension not to exceed 25% of the specified surveil 16nce interval.

4.0.3 Failure to perform a Surveillance Requirement within the allowed sur-l veillance interval, defined by Specification 4'.0.2, shall constitute noncompli-ance 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 hourt Surveillance Requirements do not have to be performed on inoperable equipment.

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

This provision shall not prevent passage through or to OPERATIONAL. MODES as required to comply with ACTION requirements.

4.0.5 Surveillance Requirements for inservice inspection and testing of ASME Code Class 1, 2, and 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 Part 50, Section 50.55a(g), except where specific written relief has been granted by the Commission pursuant to 10 CFR Part 50, Section50.55a(g)(6)(1);

b.

Surveillance intervals specified-in Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda for the inservice inspec-tion and testing activities sna11 be applicable as follows in these Technical Specifications:

.BRAIDWOOD - UNITS 1 & 2 3/4 0-2 AMENDMENT NO. 38

3/4.2 POWER DISTRIBUTION LIMITS 3/4.2.1 AXIAL i'UX DIFFERENCE LIMITING CONDITION FOR OPERATION 3.2.1 The indicated AXIAL FLUX DIFFERENCE (AFD) shall be maintained within the following target band (flux difference units) about the target flux difference:

a.

15% for Cycle 1 core average accumulated burnup of less than or equal to 5000 MWD /MTU, and b.

+ 3%, -9% for Cycle I core average accumulated burnup of greater than 5000 MdD/MTU, and c.

+ 3%, -12% for each subsequent cycle.

The indicated AFD may deviate outside the above required target band at greater than or equal to 50% but less than 90% of RATED THERMAL POWER provided the indi-cated AFD is within the Acceptable Operation Limits of Figure 3.2-1 and the cumulative penalty deviation time does not exceed I hour during the previous 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

The indicated AFD may deviate outside the above required target band at greater than 15% but less than 50% of RATED THERMAL POWER provided the cumulative penalty deviation time does not exceed I hour during the previous 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months .

APPLICABILITY:

MODE I above 15% of RATED THERMAL POWER *.

ACTION:

- a.

With the indicated AFD outside of the above required target band and with THERMAL. POWER greater than or equal to 90% of RATED THERMAL POWER, within 15 minutes, either:

1.

Restore the indicated AFD to within the above required target band limits, or 2.

Reduce THERMAL POWER to less than 90% of RATED THERMAL POWER.

b.

With the indicated AFD outside of the above required target band for more than I hour of cumulative penalty deviation time during the previous 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months or outside the Acceptable Operation Limits of Figure 3.2-1 and with THERMAL POWER less than 90% but equal to or greater than 50% of RATED THERMAL POWER, reduce:

1.

THERMAL POWER to less than 50% of RATED THERMAL POWER within 30 minutes, and

-2.

The Power Range Neutron Flux - High Setpoints to less than or equal to 55% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

See Special Test Exceptions Specification 3.30.2.

Surveillance testing of the Power Range Neutron Flux channel may be performed pursuant to Specification 4.3.1.1 provided the indicated AFD is maintained within the Acceptable Operation Limits of Figure 3.2-1.

A total of 16 hours1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months operation.may be accumulated with the AFD outside of the above required ~ target band _during testing without penalty deviation.

BRAIDWOOD'-: UNITS 1 & 2 3/4 2-1

LIMITING CONDITION FOR OPERATION ACTION (Continued) c.

With the indicated AFD outside of the above required target band for more than I hour of cumulative penalty deviation time during the previous 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and with THERMAL POWER less than 50% but greater than 15% of RATED THERMAL POWER, the THERMAL POWER shall not be increased equal to or greater than 50% of RATED THERMAL POWER until the indicated AFD is within the above required target band.

-SURVEILLANCE REQUIREMENTS 4.2.1.1 The-indicated AFD shall be determined to be within its limits during POWER OPERATION above 15% of RATED THERMAL POWER by:

a.

Monitoring the indicated AFD for each OPERABLE excore channel:

1)

At least once per 7 days when the AFD Monitor Alarm i: OPERABLE, and-

-2)

At 1mst once per hour for the first 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months af ter restoring

' the J Monitor Alarm to OPERABLE status, b.

Monitoring and. logging the indicated AFD for each OPERABLE excore channel at least once per hour for the first 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months and at least once per 30 minutes thereafter, when the AFD Monitor Alarm is.

-inoperable.

The logged values of-the indicated AFD shall be assumed to exist during the interval preceding each logging.

4.2.-l.2 The indicated AFD shall be considered outside of its target band

~

when two or more OPERABLE excore channels are indicating the AFD to be outside the target band.

Penalty deviation outside of the above required target band shall be accumulated on a time basis of:

a.

10ne minute penalty deviation for each 1 minute of POWER OPERATION outside of the target band.at THERMAL POWER levels equal to or above 50% of RATED THERMAL POWER, and b.

One. half minute penalty deviation for each 1 minute of POWER OPERATION outside of the target band at THERMAL POWER levels between 15%'and 50% of RATED THERMAL POWER.

4.2.1.3 -The initial determination-of_ target flux difference following a refuel-

'ing outage shall_be based on design predictions.

Otherwise, the target flux

. difference of each OPERABLE excore channel shall be determined by measurement at least once-per 92 Effective. Full Power Days.

j

--4.2.1-4 -The target flux difference shall be updated at least once per-

31. Effective-Full Power Days by either determining the target flux difference pursuant to Specification 4.2.1.3 abovelor by linear interpolation between the Emost recently measured value and the predicted value at the end of the cycle life.

BRAIDWOOD - UNITS 1 & 2 3/4 2-2 AMENDMENT NO. 38 w~

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e

POWER DISTRIBUTION LIMITS SURVEILLANCE REQUIREMENTS 4.2.2.1 The provisions of Specification 4.0.4 are nnt applicable.

4.2.2.2 F shall be evaluated to determine if F (2) is within its limit by:

xy 9

a.

Using the.novable incore detectors to obtain a power distribution map at any THERMAL POWER greater than 5% but prior to exceeding 50%

of RATED THERMAL F0WER following a refueling outage.

The 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months completion time provisions of Specification 4.0.3 are not applicable; b.

Increasing the measured F component of the power distribution map xy by 3% to account for manufacturing tolerances and further increasing the value by 5% to account for measurement uncertainties; c.

Comparing the F computed (F

) obtained in Specification 4.2.2.2b.,

xy above, to:

R 1)

The F limits for RATED THERMAL POWER (F

) for the appropriate xy x

measured core planes given in Specifications 4.2.2.2e, and f.,

below, and 2)

The relationship:

F

=FRTP[1+0.2(1-P)]

x l

Where F*Y is the limit 'or fractional THERMAL POWER operation RTP expressed as a function oi e and P is the fraction of RATED xy THERMAL POWER at which F was measured.

xy d.

Remeasuring F according to the fc11owing schedule:

xy hP WhenFfisgreaterthantheFj limit for the appropriate 1.

y x

measured core plane but lass than the F relationship, additional compared to F,P RT power distribution maps sna11 be taken dF L

and Fxy a)

Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months after exceeding by 20% of RATED THERMAL POWER or greater, the THERMAL POWER at which F was last x

determined, or b)

At least once per 31 EFPD, whichever occurs first.

BRAIDWOOD - UNITS 1 & 2 3/4 2-6 AMENDMENT N0. 38

POWER DISTRIBUTION LIMITS LIMITING CONDITION FOR 0.oERATION ACTION (Continued}

b.

Within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of initiL11y being cutside the above limits, verify through incore flux mapping and RCS total flow rate comparison that the comoination of F and RCS total flow rate are restored to H

within the above limits, or reduce THERMAL POWER to less than 5% of RATED THERMAL POWER within the next 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months ; and c.

Identify and correct the cause of the out-of-limit condition prior to increasing THERMAL POWER above the reduced THERMAL POWER limit required by ACTION a.2. and/or F above; subsequent POWER OPERATION may proceed provided that the combination of F and indicated RCS g

total flow rate are demonstrated, through incore flux mapping and RCS total flow rate comp 6rison, to be within the region of acceptable operation defined by Specification 3.2.3 prior to exceeding the fol-lowing THERMAL POWER levels:

4 1.

A nominal 50% of RATED THERMAL POWER, 2.

A nominal 75% of RATED THERMAL POWER, and 3.

Within 24 hourt of attaining greater than or equal to 95% of RATED THERMAL POWER.

SURVEILLANCE RE0VIREMENTS 4.2.3.1 -The provisions of Specification 4.0.4 are not applicable.

ThecombinationofindicatedRCStotalflowrateandFfg 4.2.3.2 shall be determir.ed to be within the region of acceptable operation of Specification 3.2.3:

a.

Prior to operation above 75% of RATED THERMAL POWER after each fuel loading, and b.

At least once per 31 Effective Full Power Days.

4.2.3.3 The indicated RCS total flow rate shall be verified to be witt.in the region of acceptable operation of Specification 3.2.3 at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months whenthemostrecentlyobtainedvalueofFh,obtainedperSpecification4.2.3.2, is assumed to exist.

4.2.3.4 The RCS total flow rate indicators shall be subjected to a CHANNEL CALIBRATION at least once per 18 months.

l 4.2.3.5 The RCS total flow rate shall be determined by precision heat balance measurement prior to completion of PHYSICS TESTS after each fuel loading.

The 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months completion time provisions of Specification 4.0.3 are not applicable.

The measurement instrumentation shall be calibrated within seven days prior to the performance of the calorimetric flow measurement.

Prior to the precision heat balance measurement, at least two of the four feedwater flow meter venturis shall be visually inspected and, if fouling is found, all venturis shall be cleaned.

I BRAIDWOOD - UNITS 1 &.

3/4 2-9 AMENDMENT NO. 38

POWER DISTRIBUTION LIMITS 3/4.2.4 QUADRANT POWER TILT RATIO

-LIMITING CONDITION FOR OPERATION 3.2.4 The QUADRANT POWER TILT RATIO shall not excevd 1.02 above 50% of RA THERMAL. POWER.

APPLICABILITY:

HODE 1*.

ACT[0h With the QUADRANT POWER TILT RATIO.determi ed to exceed 1.02 but a.

less than or equal to 1.09:

1.

Calculate the QUADRANT POWER TILT RATIO at least once per hour until either:

a)

The QUADRANT POWER TILT RATIO is reduced to within its limit, or b)

THERMAL POWER is reduced to less than 50% of RATED THERMAL POWER.

2.

ithin 2 hou.s either:

a)

Reduce the QUADRANT POWER TILT RATIO to within its limit, or b)

Reduce THERMAL POWER at least 3% from RATED THERMAL POWER for each 1% of indicated QUADRANT P0WER TILT RATIO in

-Gxcess of I and similarly reduce the Power Range Neutron Flux-High Trip Setpoints within the'next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

3.

Verify thei < - QUADRANT POWER TILT RATIO is within its limit within 24 ars sfier exceeding the-limit or reduce THERMAL POWER to i..s ti a 50% of RATED. THERMAL POWER within the next 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months t ' red ce the Power Range Neutron Flux-High Trip Setpoirits.. less than or aqual to 55% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , and 4.

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

or greater RATED THERMAL POWER.

' a r. ^o--ial Test Excep', ions Specification 3.10.2.

p BRAIDWOOD - UNITS 1 & 2 3/4 2-10

1y v

s-POWER'01STRIBUTION LIMITS 1 LIMITING CONDITION FOR OPERATION-'

ACTION:' Continued) b.

With the QUADRANT POWER TILT RATIO determined to exceed 1.09 due to i

misalignment'of either a shutdown or control rod:

-1.

Calculate the QUADRANT POWER TILT RATIO at least once per hour until either; a)

The QUADRANT POWER TILT RATIO is reduced to within

-its limit, or b)'

THERMN POWER is reduced to less than 50% of RATED THERMAL POWER.

Reduce T_ERMAL POWER at least 3% from RATED THERMAL POWER for H

2.

each 1% of indicated QUADRANT POWER TILT RATIO in excess of 1, within 30 minutes; 3.

-Verify that the QUADRANT POWER-TILT RATIO is within its limit within 2' hours after exceeding the limit or reduce THERMAL POWER to less than 50% of RATED THERMAL POWER within the next 2-hours and reduce the-Power Range-Neutron Flux-High Trip Stpoints to less than.or equal to 55% of RATED THERMAL POWER

/ thin the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; and 4.

Identi.fy and correct the cause of the= out-of-limit condition prior to increasing THERMAL POWER; subsequent POWER OPERATION above 50% of RATED THERMAL POWER may proceed provided-that the

--QUADRANT POWER TILT RATIO is verified within its limit at least once per hour for 12-hours or until verified acceptable.at 95%

~

-or-greater RATED THERMAL POWER.

With the QUADRANT POWER TILT-RATIO determined to exceed 1.09 due to c

c.

causes other than the misalignment of either' a shutdown or control rod:

1.

Calculate the QUADRANT POWER TILT. RATIO at least once per hour until either:

a)

The: QUADRANT POWER. TILT RATIO is reduced to within

~its;11mit,-or b)

THERMAL POWER is reduced to less than 50% of RATED THERMAL POWER.

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

POWER DISTRIBUTION LIMITS LIMITING C0f!DITION FUR OPERATION ACTION (Continued) 2.

Reduce THERMAL POWER to less than 50% of RATED THERMAL POWER within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months and reduce the Power Range Neutron Flux-High Trip Setpoints to less than or equal to 55% of RATED THERMAL POWER within the next 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; and 3.

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

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

a.

Calculating the ratiu at least once per 7 days when the alarm is OPERABLE, and b.

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

4.2.4.2 The QUADRANT POWER TILT RATIO shall be determined to be within the limit when above 75% of RATED THERMAL POWER with one Power Range channel inoperable by using the movable incore detectors to confirm that the normalized symmetric power distribution, obtained from two sets of four symmetric thimble locations or a full-core flux map, is consistent with the indicated QUADRANT POWER T!LT RATIO at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months .

BRAIDWOOD - UNITS 1 & 2 3/4 2-12 AMENDMENT NO. 38

.1,

-3/a.3-INSTRUAIENTATION:

3 /4. 3.1 REACTOR-TRIP SYSTEM INSTRUMENTATION

' LIMITING CONDITIdN FOR OPERATION 3.3.-l. As a minimum, the Reactor Trip System instrumentation channels and interlocks of Table-3.3-1-shall be OPERABLE.

l APPLICABILITY: As shown in Table 3.3-1.

ACTION:

As1 shown in Table 3.3-1.

SURVEILLANCE REQUIREMENTS 4.3.1.1 Each Reactor Trip System instrunientation channel and interlock and the automatic trip logic shall be demonstrated OPERABLE by the performance.of the Reactor Trip System Instrumentation Surveillance Requirements specified in

Table 4.3-1.

4.3.1.2:- The REACTOR. TRIP SYSTEM RESPONSE ~ TIME of each Reactor trip function shall be demonstrated.to-be within its limit at least once per 18 months.

'Each test shall include'at least:one train such that'both trains are tested at least once per 36 months and oneLchannel per function such that all channels are tested at 1 east once every N times 18 months where N is-the-total number of redundant channels in a specific Reactor trip' function as shown in the

' Total No. of Channels" column of Table 3.3-1.

i 1

f BRAIDWOOD 1 UNITS 1 & 2 3/4 3-1 AMENDMENT NO.12

TABLE 3.3-1 m

' BI.

G.

REACTOR TRIP SYSTEM INSTRUMENTATION 6-8 MINIMUM

TOTAL h0.

CHANNELS CHANNELS-APPLICABLE FUNCTIONA'. UNIT OF CHANNELS TO TRIP OPERABLE MODES ACTION c_5d.

1.

Manual Reactor Trip 2

1 2

1, 2 1-

.~

2

'l 2

3*,

4*, 5*

10 e

2.

' Power Range,-Neutron Flux y

a.

-High Setpoint 4

2 3

1, 2 2

b.

Low Setpoint 4

2 3

1###, 2 2

l 3.

Power Range, Neutron Flux 4

2 3

1, 2 2

High Positive Rate 4.

Power Range, Neutron Flux,-

4 2

3 1, 2 2

~ igh Hegative Rate H

l m'E 5.

Intermediate Range, Neutron Flux 2

1 2

1###, 2 3

6.

Source D'nge, Neutron Flux a.

Stortup-2

.1 2

2##**

4 b.

Shutdown 2

1 2

3,4,5 5

7.

Overtemperature iT 4

2 3

1, 2 6

l 8.

Overpower AT 4

2 3

1, 2 6

l Eg 9.

Pressurizer Pressure-Low g

(Above P-7) 4 2

3 1

6***

9

.O

TABLE 3.3-1 (Continued) m 5

'G' REACTOR TRIP SYSTEM INSTRUMENTATION 6

8:

MINIMUM

. TOTAL.NO.

CHANNELS CHANNELS APPLICABLE-FUNCTIONAL UNIT OF CW,NNELS '

TO TRIP-OPERABLE MODES ACTION

.g h-10.

Pressurizer Pressure-High 4

2 3

1, 2 6'

ll 11.

Pressurizer Water Level-High~

g.

(Above P-7) 3 2

2 1

6 m

12.

Reactor Coolant Flow-Low l'.

a.

Single Loop'(Above,,P-8)

.3/ loop 2/ loop in 2/ loop in 1

6 any oper-each oper-ating loop ating loop b.

Two Loops (Above P-7 and 3/ loop 2/ loop in-2/ loop in 1

6 l

below P-8) two oper-each oper-w J,

ating loops ating loop 13.

Steam Generator Water 4/stm. gen.

2/sta. gen.

3/stm. gen.

1, 2 6***

Level-Low-Low in any

.each operating operating stm. gen.

stm. gen.

14.

Undervoltage-Reactor Coolant Pumps (Above P-7) 4-1/ bus 2

3 1

6***

4:

15.

Underfrequency-Reactor Coolant Pumps (Above P-7) 4-1/ bus 2

3 6

Eg 16.

Turbine Trip (Above P-7 or P-8)****

5 a.

Emergency Trip Header Pressure 3/ Train 2/ Train 2/ Train 1

6 g

b.

Turbine Throttle Valve Closure 4

4 1

1 6

- - - A Reactor trip on Turbine trip is enabled above P-7 (10%) until the modification is implemented which enables Reactor trip on Turbine trip above P-8 (30%).

TABLE:3.3-1 (Continued)

,.g-g REACTOR ^ TRIP SYSTEM INSTRUMENTATION 6g MINIMUM TOTAL NO.

CHANNELS-

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

c5g

.17.

Safety Injection Input g-from ESF 2

1 2

1, 2 9'

18.

Reactor Coolant Pump Breaker Position Trip N

Above P-7 1/ breaker 2

1/ breaker 1

11.

per, operating loop 19.

Reactor Trip. System Interlocks a.

Intermediate Range y

Neutron Flux, P-6 2

1 2

2##

8

-[

b.

Low Power Reactor Trips Block, P-7

.P-!O Input 4

2 3

1 8

or P-13 Input 2

1 2

1 8

c.

Power Range' Neutron Flux, P-8 4

2 3

1 8

d.

Power Range Neutron Flux, P 4 2

3 1, 2 8

e.

Turbine' Impulse Chamber h

Pressure.P-13 2

1 2

1 8

e E

20.

Reactor Trip Breakers 2

1 2

1, 2 12 2

1 2

3*, 4^, 5*

10 5

21.

Automatic Trip and Interlock' Logic 2

1 2

1, 2.

9 2

1 2

3*, 4*, S*

10 m

w 22.

Reactor Trip Bypass Breakers 2

1 1

13 i

i i

l TABLE 3.3-1 (Continued)

TABLE NOTATIONS

With the Reactor Trip System breakers in the closed position and the Control Rod _ Drive System capable of rod withdrawal.

- The boron dilution flux doubling signals may be blocked during reactor startup.

- - These channels also provide inputs to ESFAS.

The Action Statement for the channels in Table 3.3-3 is more conservative and, therefore, controlling.

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

l

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

@Whenever the Reactor Trip Bypass Breakers are racked in and closed for bypass-ing a Reactor Trip Breaker.

ACTION STATEMENTS ACTION 1 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in H0T STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

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

a.

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

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

Either, THERMAL POWER is restricted to less than or equal to 75% of RATED THERMAL POWER.and the Power Range Neutron Flux Trip Setpoint is reduced to less than or equal to l

85% of RATED THERMAL POWER within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ; or, the QUADRANT POWER TILT RATIO is monitored at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months per Specification 4.2.4.2.

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

a.

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

Setpoint, restore the inoperable channel to OPERABLE status prior to increasing THERMAL POWER above the P-6 Setpoint; and b.

Above the P-6 (Intermediate Range Neutron Flux Interlock)

Setpoint but below 10% of RATED THERMAL POWER, restore the inoperable channel to OPERABLE status prior to increasing THERMAL POWER above 10% of RATED THERMAL POWER.

BRAIDWOOD - UNITS 1 & 2 3/4 3-5 AMENDMENT NO. 38

l

'w.

+

TABLE'4.3-1 (Continued)

TABLE NOTATIONS

'*With the Reactor Trip System breakers closed and-the Control Rod Drive System capable of rod withdrawal.

1**These channelsJalso provide inputs to ESFAS.- The Operational Teet frequency for these channels in= Table 4.-3-2-is more conservative and,,therefore, controlling.

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

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

(1) 'If not_ performed in previous ~7 days.

(2) Comparison of calorimetric to excore power indication above 15% of RATED THERMAL POWER.

Adjust excore channel gains consistent with calorimetric.

power if. absolute difference is greater than 2%.

The provisions of-Speci-

=fication 4.0.4 are not applicable for entry into MODE 2 or 1.

(3) The initial single point comparison of incore to excore AXIAL FLUX OIFFERENCE following a refueling outage shall be performed prior to

" exceeding 75% of RATED THERMAL Power.

Otherwise the single point com-parison of incore to excore AXIAL FLUX DIFFERENCE shall be performed above 15% of RATED THERMAL POWER.

Recalibrate if the absolute difference is greater than or equal to 3%. -The provisions of-Specification 4.0.4 are not applicable for' entry into MODE-2 or 1.

For the purposes of this surveillance,= monthly _shall mean at least once per 31 EFPD.

The 24 hour2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months completion time. provisions of Specification 4.0.3 are not applicable.

~(4) Neutron detectors may be excluded from CHANNEL CALIBRATION.

_(Sa)_ Initial plateau curves shall be measured for each detector.

Subsequent plateau = curves shall be obtained, evaluated and compared to the initial curves.

For the Intermediate Range and Power Range Neutron Flux channels the provisions of Specification 4.0.4 are not applicable for entry into MODE 2.or 1.

--(5b) With the high voltage _ setting varied as recommended by the manufacturer,

.-an initial' discriminator bias ' curve shall be measured-for each-detector.

-Subsequent discriminator bias curves shall be obtained, evaluated and compared to the-initial' curves.

(6) 'Incore "Excore Calibration, above 75% of RATED THERMAL POWER.

The provi-

sf ons; of Specification 4.0.4 are not applicable for entry into MODE 2 or 1.

For the purposes of this surveillance, quarterly shall mean at least once per 92 EFPD.:

!(7)__ Each train shall-be' tested at least every 62 days _ on a STAGGERED TEST BASIS.

(8)- With power greater than or equal to the interlock Setpoint the required ANALOG CHANNEL OPERATIONAL TEST _-shall consist of verifying that the inter-lock is in the required state-by observing the permissive annunciator window.

-(9) Surveillance:in MODES-3*, 4*, and-5* shall also include-verification that permissives.P-6 and P-10: are -in their-required -state for existing plant conditions by observation of the permissive annunciator. window.

Surveil-

-lance shall include verification of the Boron Dilution Alarm Setpoint of.less than.or equal to an increase of twice the count rate within a.

10-minute period.

BRAIDWOOD - UNITS 1 & 2 3/4 3-12 AMENDMENT NO. 38

4 TABLE 4.3-1 (Continued)

TABLE NOTATIONS (10) Setpoint verification is not applicable.

s (11) Th TRIP ACTUATING DEVICE OPERATIONAL TEST shall be performed such that each train is tested at 1 cast every 62 days on a STAGGERED TEST BASIS and following maintenance or adjustment of the Reactor Trip Breakers and shall include independent verification of the OPERABILITY of the Undervoltage and Shut Trip Attar.hments of the Reactor Trip Breakers.

(12) At least once per 18 months during shutdown verify that on a simulated Boron Dilution Doubling test signal CVCS valves 1120 and E open and 1128 and C close within 30 seconds.

(13) CHANNEL CALIBRATION shall include the RTD bypass loops flow rate.

(14) Verify that the appropriate signals reach the Undervoltage and Shunt Trip relays, for both the Reactor Trip and Bypass Breakers from the Manual Trip Switches.

l (15) Manual Shunt Trip prior to the Reactor Trip Bypass Breaker being racked in and closed by bypassing a Reactor Trip Breaker.

(16) Automatic undervoltage trip.

l l

BRAIDWOOD - UNITS 1 & 2 3/4 3-12a AMENDMENT NO. 38

.m c..

as

. TABLE 3.3-3 55 Es ENGINEERED' SAFETY FEATURES' ACTUATION SYSTEM INSTRUMENTATION 6.

' El.

MINIMUM TOTAL NO.

CHANNELS CHANNELS APPLICABLE

' FUNCTIONAL UNIT OF CHANNELS' T,0 TRIP OPERABLE MODES ACTION c:.

z w

U?

1.

Safety Injection (Reactor Trip, Feedwater Isolation, p.

Start Diesel Generators, Containment Cooling' Fans, no Control Room Isolation, Phase "A" Isolation, Turbine Trip, Auxiliary Feedwater, Containment Vent Isolatior,.

and Essential Service Water).

}{

a.

Manual Initiation 2

1 2

1, 2, 3,.4 18' T

b.

Automatic Actuation 2

1 2

1,2,3,4 14 y

Logic and Actuation Relays c.

Containment

'3 2

2 1,2,3 15 Pressure-High-1 l

d.

Pressurizer Pressure-4 2

3 1, 2, 3#

19 l

Low (Above P-11) e.

Steam Line Pressure-3/steaa line 2/ steam line 2/ steam line 1, 2, 3#

15

-l 3;

Low (Above P-11) any steam gg line gg 2.

Containment Spray w

a.

Manual Initiation 2 pair 1 pair 2 pair 1, 2, 3, 4 18 jg w

b.

Automatic Actuation 2

1 2

1,2,3,4 14 Logic and Actuation Relays c.

Containment Pressure-4 2

3 1,2,3 16 High-3

TABLE 3.3-3 (Continued)

' ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION o

k MINIMUM TOTAL NO.

CHANNELS CHANNELS APPLICABLE

' FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE-MODES ACTION Ey 3.

Containment Isolation a.

Phase "A" Isolation e-1)

Manual Initiation 2

1 2'

1, 2, 3, 4 18 2)

Automatic Actuation 2

1 2

1,2,3,4 14 Logic and Actuation Relays 3)

Safety Injection See Item 1. above for all Safety Injection initiating functions and requirem2nts.

w1 b.

Phase "B" Isolation 1)

Manual Initiation 2 pair 1 pair 2 pair 1, 2, 3, 4 18 2)

Automatic Actuation 2

1 2

1,2,3,4 14 Logic and Actuation Relays 3)

Containment a

2 3

1,2,3 16 Pressure-High-3 c.

Containment Vent Isolation 1)

Automatic Actuation 2

1 2

1,2,3,4 17 Logic and Actuation Relays 2)

Manual Phase "A" See Item 3.a.1 for all manual Phase "A" Isolation initiating Isolation functions and requirements.

3)

Manual Phase "B" See Item 3.b.1 for all manual Phase "B" Isolation initiating Isolation functions and requirements.

4)

Safety Injection See Item 1. above for all Safety Injection initiating functions and requirements.

TABLE 3.3-3 (Continued)

o>

g ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION 6

l 8

MINIMUM TOTAL NO.

CHANNELS CHANNELS; APPLICABLE-c i_.z FUNCTIONAL UNIT OF CHANNELS TO TRIP OPERABLE

' MODES ACTION

. --e L [

4.

Steam Line Isolation

+

a.

Manual Initiation N

1).

Individual 1/ steam-line 1/ steam 1ine 1/ operating 1,2,3 23 steam line 2).

System 2

1 2

1. 2, 3 22' b.

Automatic Actuation 2

1 2

1. 2, 3 21 Logic and Actuation Relays

{

l c.

Containment. Pressure-3

'2 2

1,2,3 15 High-2 h

d.

Steam Line 3/ steam.line 2/ steam line 2/ steam line 1, 2, 3#

15 l-Pressure-Low any steam (above P-11) line e.

Steam Line Pressure -

3/ steam line 2/ steam line 2/ steam line 3##

15 l

i Negative Rate-High any steam (below-P-11) line 5.

Turbine. Trip &

Feedwater Isolation a.

Automatic Actuation 2

1 2

1, 2 24 E

Logic and Actuation "g

Relays

(

b.

Steam Generator 4/stm. gen:

2/stm. gen.

3/stm. gen.

1, 2 19 a

Water Level-in any oper

-in each oper-g High-High (P-14) ating'stm.

ating stm.

gen.

c.

Safety Injection See Item 1. above for all Safety Injection initiating functions and requirements.

y vy ITABLE 3.3-3 (Continued)-

~5g ENGINEERED SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION-

.T, c-g MINIMUM:

' TOTAL"NO.

CHANNELS CHANNELS APPLICABLE.

{ FUNCTIONAL UNIT:-

0F: CHANNELS TO TRIP OPERABLE MODES FACTION d

'6.

. Auxiliary. Feedwater :

u w

e-

'a.

Manual. Initiation

.' ' 2 L 1

2 1, 2, 3=

22' m

b.

Automatic Actuation 1 Logic 2

1 2

1, 2. 3 21.

and Actuation: Relays-c.

Stm. Gen. Water Level-Low-Low 4

1) Start Motor-

-Driven Pump 4/stm. gen.

'2/stm. gen.

3/stm. gen.

1,2,3 19

.g in any opera

.in each ting.stm gen.

operating-a w

i stm. gen.

w*

2) Start Diesel-Driven Pump 4/stm. gen.

2/sts. gen.

3/stm. gen.

1,2,3 19 in any in'each operating operating

.:t l

l stm. gen.

stm. gen.

d.

Undervoltage - RCP

~ 4-1/ bus.

2 3

1, 2 19-Bus-Start Motor--

Driven Pump and i

Diesel-Driven Pump e.

Safety Injection -

M Start Motor-Dr-iven Pump See Item 1. above for all Safety Injection initiating functions and y

and Die'sel-Driven Pump requirements.

k

= f.

Division'11 for Unit 1 (Division-21 for Unit 2) ll zP ESF. Bus Undervoltage-w Start Motor-Driven Pump (Start as part 2-2 2.-

1,2,3,4'

-25a 1

of DGLsequencing) i 4

,-_.c_.

-m

. TABLE 3.3-3 (Continued) oo

- :o E;

ENGINEERED SAFETY FEATURES ACTUATION SYSTEM' INSTRUMENTATION 6

8

. MINIMUM c: -

' TOTAL NO.

CHANNELS CHANNELS APPLICABLE 2g.

FUNCTIONAL UNIT OF CHANNELS" TO TRIP OPERABLE MODES ACTION.

f$

6.

- Auxiliary Feedwater (Continued)

- e.

n, g.

-Auxiliary Feed-water Pump Suction Pressure-Low (Transfer to Essential Service Water) 2 2

2 1,2,3 15 7.

Automatic Opening of Ri Containment Sump Suction Isolation Valves Y

- t; a.

Automatic Actuation Logic 2

1 2

1, 2, 3, 4 14 and Actuation Relays b.

RWST Level - Low-Low 4

2 3

1,2,3,4

.16 Coincident With Safety InjectionL See' Item 1. above for Safety Injection initiating functions and requirements.

8.

Loss of Power g

a.

ESF Bus Undervoltage' 2/ Bus 2/ Bus 2/ Bus 1, 2, 3, 4 25a-9 gg b.

Grid Degraded Voltage' 2/ Bus 2/ Bus 2/ Bus 1,'2, 3, 4 2Sb E.

5 T

m r

= =.

. TABLE'3.3-3 (Continued)-

~

' ENGINEERED' SAFETY FEATURES ACTUATION SYSTEM INSTRUMENTATION O'6

. 8' MINIMUM TOTAL NO.

CHANPiELS CHANNELS APPLICABLE c:

' FUNCTIONAL"15IT.

' 0F CHANNELS

-TO TRIP OPERABLE MODES ACTION 5

d.'

'9.

Engineered Safety Features Actuation. System Interlocks w

e.

- m-a.

Pressurizer Pressure, 3

2 2

1,2,3 20 P-11

-b.

Reactor Trip,'P-4' 4-2/ Train 2/ Train 2/ Train 1, 2, 3 22 Low-Low T,yg, P-12 4

2 3

1.-2, 3 20-c.

. R d.

Steam Generator Water Level, 4/sta.

2/sta. gen.

'3/sta.

1, 2

'20 P-14 (High-High) gen.

in any gen. in T

op'erating each E$

stm. gen.

operating stm. gen.

1 4

1 l

s s

i 4

TABLE 3.3-3 (Continued)

TABLE NOTATIONS

Trip function may be blocked in this MODE below the P-11 (Pressurizer Fressure Interlock) Setpoint.

1. Trip function automatically blocked above P-11 and may be blocked below P-11 when Safety Injection on low steam line pressure is not blocked.

l ACTION STATEMENTS ACTION 14 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, be in at least H0T STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ano in COLD SHUTDOWN within the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months ; however, one channel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing per Specification 4.3.2.1, provided the other channel is OPERABLE.

ACTION 15 With the number of OPERABLE channels one less than the Total Number of Channels, operation may proceed until performance of the next. required ANALOG CHANiiEL OPERATIONAL TEST provided the inoperable channel is placed in the tripped condition within I hour.

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

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

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

ACTION 18 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE requirement, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in at least HOT STANDBY within the next 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in COLD SHUTDOWN within-the following 30 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

l l

BRAIDWOOD - UNITS 1 & 2 3/4 3-21 AMENDMENT N0. 38

TABLE 3.3-3 (Continued)

ACTION STATEMENTS (Continued)

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

The inoperable channel is placed in the tripped condition a.

i within I hour, and b.

The Minimum Channels OPERABLE requirement is met; however, the l

inoperable channel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for sur-i veillance testing of other channels per Specification 4,3.2.1.

ACTION 20 - With less than the Minimum Number of Channels OPERABLE, within I hour I

determine by observation of the associated permissive annunciator window (s) that the interlock is in its required state for the existing plant condition, or apply Specification 3.0.3.

ACTION 2.' - With the number of OPERABLE Channels one less than the Minimum Channels OPERABLE requirement, be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in at least HOT SHUTDOWN within the following 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; however, one channel may be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing per Specification 4.3.2.1 provided the other channel is OPERABLE.

ACTION 22 - With the number of OPERABLE channels one less than the Total Number of Channels, restore ti.) inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months and in at least HOT SHUTDOWN within tne fnllowing 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

ACTION 23 - With the number of OPERABLE channels one less than the Total Number of Channels, restore the inoperable channel to OPERABLE status within 48 hours5.555556e-4 days 0.0133 hours 7.936508e-5 weeks 1.8264e-5 months or declare the associated valve inoperable and take the ACTION required by Specification 3.7.1.5.

ACTION 24 - With the number of OPERABLE channels one less than the Minimum Channels OPERABLE require.%ent be in at least HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months ; however,.one enannel r.ay be bypassed for up to 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months for surveillance testing per Specification 4.3.2.1 provided the other channel-is OPERABLE.

ACTION 25 - a.

With the number of OPERABLE channels one less than the Minimum Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the inoperable channel is placed in the tripped condition within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

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

b.

With the number of OPERABLE channels one less than the Mini-mum Number of Channels, STARTUP and/or POWER OPERATION may proceed provided the inoperable channel is placed in the tripped condition within I hour.

URAIDWOOD - UNITS 1 & 2 3/4 3-22

7

'e, R* * '

INSTRUMENTATION 3/4.3.3-MONITORING-INSTRUMENTATION RADIATION MONITORING FOR PLANT OPER'TIONS A

LIMIflNG CONDITION F0F,0PER.ATION

-3.3.3.1 The radiation monitoring instrumentation channels for plant operations

-shown in Table 3.3-6 shall be OPERABLE with_their Alarm / Trip Setpoints within the specified limits.

APPLICABILITY:- As shown in Table 3.3-6.

ACTION:-

a..

With-a radiation monitoring channel Alarm / Trip Setpoint-for plant operations exceeding the value shown in Table 3.3-6, 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.

ib.

With one or more radiation monitoring channels for plant operaticns inoperable; take the ACTION shown in-Table-3.3-6.

c.

The frovisions of-Specification 3.0.3 are-not applicable.

SURVEILLANCE REQUIREMENTS

-. 4.3.3.1l Each radiation monitorina instrumentation channel for plant operations shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK,-CHANNEL -

' CALIBRATION.and DIGITAL CHANNEL OPERATIONAL TEST for the MODES-and-at-the e

frequencies shown-in Table 4.3-3.

[-

o j:

l l-I BRAIDWOOD - UNITS 1 & 2 3/4 3-39 0.; MENT NO. 38 E

4 TABLE 3.3-6 E);

RADIATION MONITORING' INSTRUMENTATION FOR PLANT OPERATIONS

E8 MINIMUM CHANNELS CHANNELS

-APPLICABLE ALARM / TRIP

= si FUNCTIONAL: UNIT-LTO TRIP / ALARM OPERABLE MODES SETPOINT ACTION Z

v' 1.

' Fuel Building Isolation.

S' Radioactivity-High and-

}

Criticality (ORE-AR055/56) 1 2

<5 mR/h 29 2.

= Containment Isolation-Containment Radioactivity-High-a) Unit 1.(IRE-AR011/12) 1 2

All 26

.b) Unit-2'(2RE-AR011/12) 1 2

All 26 to);

3.

Gaseous Radioactivity-RCS Leakage Detection c,

4 a) Unit 1 (1RE-PR0118)

N. A.

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

28 c) b) Unit 2 (2RE-PR0118)

R. A.

I 1,'2, 3, 4 N.A.

28 4.

Particulate Radioactivity-RCS Leakage Detection a) Unit 1 (IRE-PR011A)

N.A.

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

28 b) Unit 2 (2RE-PR011A)

N.A.

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

28 5.

Main Control Room Isolation-Outside Air Intake-Gaseous t

Radioactivity-High (ORE-PR0318/328 and ORE-PR033B/348) 1 2 per All

< 2 mR/h 27' intake.

.l t

i INSTRUMENTATION MOVABLE INCORE DETECTORS LIMITING CONDITION FOR OPERATION 3.3.3.2 The Movable Incore Detection System shall be OPERABLE wit.h:

a.

At least 75% of the detector' thimbles, b.

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

Suf ficie.it movable detectors, drive, and readout equipment to map these thimbles.

APPLICABILITY: When the Movable Incore Detection System is used for:

a.

Recalibration of the excore neutron flux detection system, or b.

Monitorin0 the QUADRANT POWER TILT RATIO, or c.

Measurement of F H' F (Z) and Fxy' 9

-ACTION:

With the Movable Incore Detection System inoperable, do not use the system for

.the above applicable monitoring or calibration functions.

The provisions of Specification 3.0.3 are not applicable.

. SURVEILLANCE REQUIREMENTS 4.3.3.2 The Movable Incore Detection System shall be demonstrated OPERABLE at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by normalizing each detector output when required for:

a.

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

Monitoring the QUADRANT POWER TILT RATIO, or q, F (Z), and Fxy*

c.

Measurement of F q

BRAIDWOOD - UtlITS 1 & 2 3/4 3-43 AMENDMENT NO. 38

4 T..

INSTRUMENTATION-SEISMIC INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.3 The seismic monitoring instrumentation shown in Taple 3.3-7 shall be OPERABLE.

APPLICABILITY:

At all times.

ACTION:

-a.

With one or more of the above required seismic monitoring 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 are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.'3.3.1 The seismic monitoring instrumentation shall be determined OPERABLE:

a.

At least once per 31 days by verifying operable,tatus indications of the seismic monitoring instrumentation.

b.

At least once per 92 days by verifying that:

1)

The triaxial acceleration sensors and the time-history accelero-graphs properly process the equipment internal test signals.

2)

The response spectrum analyzer properly executes its diagnostic routine.

c.

At least _once per 184 days by verifying that the triaxial acceleration sensors and the time-history accelerographs properly record the equipment internal test signals.

The test may be performed in lieu of the test required by Specification 4.3.3.3.1.b.1), and d.

At-least once per 18 months by:

1).

Verifying _the electronic calibration of the time-history accelerographs.

i.

2)

Installing fresh magnetic recording plates in the triaxial peak accelerographs.

l_

4.3.3.3.2 Upon actuation of the seismic monitoring instruments, the equipment listed in Table 3.3-7 shall be restored to-0PERABLE status within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months 4

L following the seismic event.

Data shall be retrieved from actuated instruments and analyze'd 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 14 days describing the magnitude, frequency spectrum l

and resultant effect upon facility features important to safety.

BRAIDWOOD - UNITS 1 & 2 3/4 3-44 AMENDMENT NO. 38

~

-INSTRUMENTATION METEOROLOGICAL INSTRUMENTATION LIMITING CONDITION FOR OPERATION 3.3.3.4 The meteorological monitoring instrumentation channels givnn in Table 3.3-8 shall be OPERABLE.

APPLICABILITY:

At all times.

ACTION:

a.

With one or more required meteorological monitoring channels inoperable for more than 7 days, prepare and submit a Special Report to the Commission pursuant to Specification 6.9.2 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 are not applicable.

SURVEILLANCE REQUIREMENTS 4.3.3.4 Each of the above meteorological monitoring-instrumentation channels shall-be demonstrated OPERABLE by the performance of the CHANNEL CHECK and CHANNEL CALIBRATION operations at the frequencies given in lable 4.3-5.

BRAIDWOOD - UNITS 1 & 2 3/4 3-47 AMENDMENT NO. 38

i..

TABLE 3.3-8 METEOROLOGICAL MONITORING INSTRUMENTATION MINIMUM INSTRUMENT-LOCATION OPERABLE 1.

Wind Speed Nominal Elev. 34 ft 1

Nom'!nal Elev. 203 ft 1

2.

Wind Direction Nominal Elev. 34 ft 1

Nominal Elev. 203 ft 1

3.

Air Temperature - AT Nominal Elev. 30 ft/199 ft 1

BRAIDWOOD - UNITS 1 & 2 3/4 3-48

4 _

INSTRUMENTATION LOOSE-PART DETECTION SYS$EM LIMITING CONDITION FOR OPERATION

.3.3.3.8 The Loose-Part Detection System shall be OPERABLE.

APPLICABILITY:

MODES 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 are not applicable.

SURVEILLANCE RFQUIREMENTS 4.3.-3.8 Each channel of the Loose-Part Detection Systems 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.

An ANALOG CHANNEL OPERATIONAL TEST except for verification of setpoint at least once per 31 days, and c.'

--A CHANNEL CALIBRATION at least once per 18 months.

BRAIDWOOD - UNITS 1 & 2 3/4 3-58 AMENDMENT NO. 38

~_.

INSTRUMENTATION-

EXPLOSIVE GAS MONITORING INSTRUMENTATION

-LIMITING CONDITION FOR OPERATION 3.3.3.10- The explosive gas monitoring instrumentation channels shown in Table 3.3-13 shall be OPERABLE with their Alarm / Trip Setpoints set to ensure that the limits of Specification 3.11.2.5 are not exceeded.

APPLICABILITY:

As shown in Table 3.3-13 ACTION:

a.

With an explosive gas monitoring instrumentation channel Alarm /.jp Setpoint less conservative than required by the above specification, declare the channel inoperable and take the ACTION shown in Table 3.3-13.

b.

With less than the minimum number of explosise gas monitoring instru-

. mentation channels OPERABLE, take the ACTION shown in Table 3.3-13.

Restore the inoperable instrumentation to OPERABLE status within 30 days and, if unsuccessful, prepare and submit a Special Report to the Commission within the next 30 days pursuantEto Specification 6.9.2 to explain why this inoperability was not corrected _in a timely manner, c.

-The provisions of Specification 3.0.3 are not applicable.-

SURVEILLANCE' REQUIREMENTS 4.3.3.10 Each explosive gas monitoring instrumentation channel shall be demonstrated OPERABLE by performance of the CHANNEL CHECK, CHANNEL CALIBRATION

-and DIGITAL CHANNEL OPERATIONAL-TEST ~at the frequencies-shown in Table 4.3-9.

l BRAIDWOOD - UNITS 1 & 2-3/4 3-60 AMENDMENT No. 38

a'.

'5-INSTRUMENTATION HIGH ENERGY LINE BREAK ISOLATION SENSORS LIMITING CONDITION FOR OPERATION 3.3.3.11 -The high energy line break instrumentation shown in Table 3.3-14 shall be OPERABLE.

APPLICABILITY:

As shown in Table 3.3-14 ACTION:

a.

With the number of OPERABLE auxiliary steam isolation instruments less than the Minimum Channels OPERABLE as required by Table 3.3-14, restore the-inoperable instrument (s) to OPERABLE status within 7 days, or suspend the supply of auxiliary steam to the Auxiliary Building, or establish a continuous watch in the affected area (s) until the inoperable sensors are restored to OPERABLE status, b.

With the number of CPERABLE steam generator blowdown line isolation instru-ments less than the Minimum Channels OPERABLE as required by Table 3.3-14, restore the inoperable instrument (s)'to OPERABLE status within 7 days, or limit the-total steam generator blowdown flow rate to less than or equal

'to 60 gpm or establish a continuous watch in the affected area (s) until the inoperable sensors-are restored _to OPERABLE status, c.

The provisions of Specificati n 3.0.3 are not-applicable.

SURVEILLANCE REQUIREMENTS 4.3.3.12 Each of the above high energy line break isolation instruments shall be demonstrated'0PERABLE by-the performance of an ANALOG CHANNEL OPERATIONAL-TEST and CHANNEL CALIBRATION at least once per 18 months.

l L

l BRAIDWOOD UNITS 1 & 2 3/4 3-63 AMENDMENT NO. 38 o

)

1:

10 i

9 8

/

REJECT j

6 r

G)

CONTINUE TESTING 2

/

2 ACCEPT 1

r

/

)

i 0

10 20 30 40 50 60 70 80 90 100 N

FIGURE 4.7-1 SAMPLE PLAN 2) FOR SNUBBER FUNCTIONAL TEST BRAIDWOOD - UNITS 1 & 2 3/4 7-25

PLANT SYSTEMS 3/4.7.9 SEAL 2D SOURCE CONTAMINATION LIMITING CONDITION FOR OPERATION 3.7.9 Each sealed source containing radioactive material either in excess of 100 microcuries of oeta 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 c.ontamination in excess of the above limits, immediately 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 provistors of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.7.9.1 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 l

. microcurie per test sample.

i 4.7.9.2. 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 materials:

.1)

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

and 2)

In any form other than gas.

1 j.

BRAIDWOOD_- UNITS 1 & 2 3/4 7-26 AMENDMENT NO. 38

d REFUELING OPERATIONS 3/4.9.6 REFUELING MACHINE i

LIMITING CONDITION FOR_0PERATION 3.9.6 The refueling machine shall be used for movement of drive rods or fuel assemblieL and rita11 be OPERABLE with:

a.

The refueling machine used for movement of fuel assemblies having:

1)

A capar.My equal to or greater than 2850 pounds, and 2)

An overload cutoff limit less than or equal to 2850 pounds.

6 The auxiliary hoist used for latching and unlatching drive rods having:

A capacity equal to or greater than 2000 poundt, and 2)

A load indicator which shall be used to prevent lifting loads in excess of 1000 pounds.

APPLICABILITY:

During movement of drive rods or fuel assemblies within the reactor vessel.

ACTION:

With the requirements for refueling machine and/or hoist OPERABILITY not satis-fied, suspend use of any inoperable refueling machine and/or auxiliary hoist from operations involving the movement of drive rods and fuel assembl{es within the reactor vessel.

SURVEILLANCE REQUIREMENTS 4.9.6.1 Each refueling machine used for movement of fuel assemblies within the reactor vessel shall be demonstrated OPERABLE within 100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months prior to the start of such operations by performing a load test of at least 3563 pounds and demonstrating an automatic load cutoff when the crane load exceeds 2850 pounds.

4.9.6.2-Each auxiliary hoist and associated load indicator use t for movement i

of drive rods within the reactor vessel shall be demonstrated / PERABLE within 100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months prior to the start of such operations by performing load test of at least 2500 pounds.

l l

BRAIDWOOD - UNITS 1 & 2 3/4 9-7

l REFUELING OPERATIONS 3/4.9.7 CRANE TRAVEL - SPENi FUEL STORAGE FACILITY L?MITING CONDITION FOR OPERATION 3.9.7 Loads in excess of 2000 pounds shall be prohibited from travel over fuel assemblies in the spent fuel storage facility.

fPPLICABILITY:

With fuel assemblies in the spent fuel storage facility.

ACTION:

a.

With the requirements of the above specification not satisfied, place the crane load in a safe condition.

b.

provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.9.7 Crane interlocks and physical stops which prevent crane travel with loads in excess of 2000 pounds over fuel assemblies shall be demonstrated OPERABLE within 7 days prior to crane use and at least once per 7 days thereaf ter during crane operation.

BRAIDWOOD - UNITS 1 & 2 3/4 9-8 AMENDMENT NO. 38

REFUELING OPERATIONS 3/4.9.9 CONTAINMENT PURGE ISOLATION SYSTEM LIMITING CONDITION FOR OPERATION 3.9.9 The Containment Purge Isolation System shall be OPERABLE.

APPLICABILITY:

During CORE ALTERATIONS or movement of irradiated fuel withii, the containment.

ACTION:

a.

With the Containment Purge Isolation System inoperable, close each of the purge valves providing direct access from the containment atmosphere to the outside atmosphere, b.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.9.9 The Containment Purge Isolation System shall be demonstrated OPERABLE within 100 hours0.00116 days 0.0278 hours 1.653439e-4 weeks 3.805e-5 months prior to the start of and at least once per 7 days ouririg CORE ALTERATIONS by verifying that containment purge isolation occurs on an ESF test signal from each of the containment radiation monitoring instrumentation channels.

l l

BRAIDWOOD - UNITS 1 & 2 3/4 9-11 AMENDMENT NO. 38 l

REFUELING OPERATIONS 3/4.9.10 WATER LEVEL - REACTOR VESSEL LIMITING CONDITION FOR OPERATION 3.9.10 At least 23 feet of water shall be maintained over the top of the reactor vessel flange.

APPLICABILITY:

During movement of fuel assemblies or control rods within the containment when either the fue' cssemblies being moved or the fuel assemblies seated within the reactor vessel are irradiated while in H0DE 6.

ACTION:

With the requirements of the above specification not satisfied, suspend all operations involving movement of fuel assemblies or control rods within the reactor vessel.

t SURVEILLANCE REQUIREHENTS 4.9.10 The water level shall be determined to be at least its minimum required depth within 2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months prior to the start of and at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months thereafter during movement of fuel assemblies or control rods.

l l

?

i BRAIDWOOD - UNITS 1 & 2 3/4 9-12

REFUELING OPERATIONS 3/4.9.11 WATER LEVEL - STORAGE POOL LIMITING CONDITION FOR OilRATION 3.9.11 At least 23 feet of water shall be maintained over the top of irradiated fuel assemblies seated in the storage racks.

l APPLICABILITY:

Whenever irradiated fuel assemblies are in the storage pool.

ACTION:

a.

With the requirements of ib6.$4tvt aci

'ation not satisfied suspend all movement of tw s :' e;+44

'a ne crane operations with loads in the fuel storage asyts t, o 1estore the water levei to within its limit within 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months , b.

The provisions of. Specification 3.0.3 are not applicable.

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

l l

l BRAIDWOOD - UNITS 1 & 2 3/4 9-13 AMENDMENT NO. 38

a REFUELING OPERATIONS 3/4.9.12 FUEL HANDLING BUILDING EXHAUST FILTER PLENUMS LIMITING CONDITION FOR OPERATION 3.9.12 Two independent Fuel Handling Building Exhaust Filter Plenums shall be OPERABLE.

APPLICABILITY:

Whenever irradiated fuel is in the storage pool.

ACTION:

a.

With one Fuel Handling Building Exhaust filter Plenum inoperable, fuel movement within the storage pool, or crane operation with loads over the storage pool, may proceed provided the OPERABLE Fuel Handling Building Exhaust Filter Plenum is capable of being powered from an OPERABLE emergency power source and is in operation and taking suction from at least one train of HEPA filters and charcoal adsorbers, b.

With no Fuel Handling Building Exhaust Filter Plenums OPERABLE, suspend all operations involving movement of fuel within the storage pool, or crane operation with loads over the storage pool, until at least one Fuel Handling Building Exhaust Filter Plenum is restored to OPERABLE status.

c.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 4.9.12 The above required Fuel Handiing Building Exhaust Filter Plenums shall be demonstrated OPERABLE:

a.

At least once per 31 days on a STAGGERED TEST BASIS by initiating, from the control room, flow through the HEPA filters and charcoal adsorbers and verifying that the system operates for at least 15 minutes; b.

At least once per 18 months, or (1) after any structural maintenance on the HEPA filter or charcoal adsorber housings, or (2) following painting, fire, or chemical release in any ventilation zone communicating with the system, by:

BRAIDWOOD - UNITS 1 & 2 3/4 9-14 AMENDMENT NO.

38

O 3/4.11 RADIDACTIVE EFFLUENTS 3/4.11.1 LIQUID EFFLUENTS LIQUID HOLDUP TANKS LIMITING CONDITION FOR OPERATION 3.11.1.1 Deleted 3.11.1.2 Deleted 3.11.1.3 Deleted 3.11.1.4 The quantity of radioactive material, excluding tritium and dissolved or entrained noble gases, contained in any outside tanks shall be limited to the following:

a.

Primary Water Storage Tank 5 2000 Curies, and b.

Outside Temporary Tank 1 10 Curies.

APPLICABILITY:

At all times.

ACTION:

a.

With the quantity of radioactive material in any of the above listed 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 6.9.1.7.

b.

The provisions of Specification 3.0.3 are not applicable.

SURVEILLANCE REQUIREMENTS 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 representative: sample of the tank's contents at least once per 7 days when radioactive materials are being added to the tank.

BRAIDWOOD - UNITS 1 & 2 3/4 11-1 AMENDMENT NO. 38

RAD 0 ACTIVE EFFLUENTS 3/4.11.2 GASEOUS EFFLUENTS EXPLOSIVE GAS MIXTURE LIMITING CONDITION FOR OPERATION i

3.11.2.1 Deleted 3.11.2.2 Deleted 3.11.2.3 Deleted-

'3.11.2.4 Deleted 3.11.2 S The concentration of oxygen in the WASTE GAS HOLDUP SYSTEM shall be limited to-less than or equal to 2% by volume Whenever the hydrogen concentration exceeds 4% by volume.

APPLICABIL11Y:

At all times.

ACTION:-

a.:

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

With the concentration of oxygen in the WASTE GAS HOLDUP SYSTEM greater than 4% by volume and the hydrogen concentration greater.

than 4% by volume, immediately suspend all additions of waste gases to the system and reduce the concentration of oxygen to less than or equal to 4% by volume, then take ACTION a. above, c.

The provisions of Specification 3.0.3 are not applicable.

i 1

SURVEILLANCE REQUIREMENTS 4.11.2.5 The concentrations.of hydrogen and oxygen in the WASTE GAS HOLDUP SYSTEM shall be determined to-be within the above limits by continuously monitoring the waste gases in the WASTE GAS HOLDUP SYSTEM with the hydrogen and oxygen monitors required OPERABLE by Table 3.3-13 of Specification 3.3.3.-10.

l BRAIDWOOD - UNITS 1 & 2 3/4 11-2 AMEN 0 MENT NO. 38 r

- =_ -

1 RADIOACTIVE EFFLUENTS GAS DECAY TANKS LIMITING CONDITION FOR OPERATION 1

.3.11.2.6 The quantity of radioactivity contained in each gas decay tank shall be limited to less than or equal to 5x104 Curies of noble gases (considered as Xe-133 equivalent).

APPLICABILITY:

At all times.

ACTION:

a.

With the quantity of radioactive material in any gas decay tank exceeding the above limit, immediately suspend all additions of radioactive material to the tank and, 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 6.9.1.7.

b.

The provisions of Specification 3.0.3 are not applicable.

l SURVEILLANCE REQUIREMENTS 4.11.2.6 The quantity of radioactive material contained in each gas decay tank shall be determined to be within the above limit at least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months when radioactive materials are being added to the tank.

BRAIDWOOD - UNITS 1 & 2 3/4 11-3 AMENDMENT NO. 38

..~.. -.. -. -

3/4 LIMITING CONDITIONS FOR OPERATION AND SURVEILLANCE REQUIREMENTS 3/4.0 APPLICABILITY BASES Specification 3.0.1 through 3.0.S establish the general requirements applicable to Limiting Conditions for Operation.

These requirements are based on the requirements for Limiting Conditions for Operation stated in the Code of

-Federal Regulations, 10 CFR 50.36(c)(2):

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

When a limiting condition for operation 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."

Specification 3.0.1 establishes the Applicability statement within each individual specification as the requirement for when (i.e., in which OPERATIONAL MODES or other specified conditions) conformance to the Limiting Conditions for Operation is required for safe operation of the facility.

The ACTION requirements establish those remedial measures that must be taken within specified time limits when the requirements of a Limiting Condition for Operation are not met.

There are two basic types of ACTION requirements.

The first specifies the remedial measures that permit continued operation of the facility which is not further restricted by the time limits of the ACTION requirements.

In this case, conformance to the ACTION reouirements provides an acceptable level of safety for unlimited continued operation as long as the ACTION requirements continue to be met.

The second type of ACTION requirement specifies a time limit in which conformance to the conditions of the Limiting Condition for Operation must be met.

This time limit is the allowable outage time to restore an inoperable system or component to OPERABLE status or for restoring parameters within specified limits.

If these actions are not completed within the allowable outage time limits, a shutdown is required to place the facility in-a MODE or condition in which the specification no longer applies.

It is not intended that the shutdown ACTION requirements be used as an operational convenience which permits (routine) voluntary removal of a system (s) or component (s) from service in lieu of other alternatives that would not result in redundant systems or components being inoperable.

The specified time limits of the ACTION requirements are applicable from the point in time it is identified that a Limiting Condition for Operation is not met.

The time-limits of-the ACTION requirements are also applicable when a system or component is removed from service-for surveillance testing or

. investigation of operational problems.

Individual specifications may include a specified time limit for the completion of a Surveillance Requirement when equipment is removed from service.

In this case, the allowable outage time BRAIDWOOD - UNITS 1 & 2 B 3/4 0-1 AMENDMENT NO 38

3/4.0 APPLICABILITY BASES limits of the ACTION rcquirements 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 a MODE 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 specifi-cation 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 speci-fied time interval.

The purpose of this specification is to clarify that (1) implementation of the ACTION requirements within the specified time interval j

constitutes comp 1.ance 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.

Specification 3.0.3 establishes the shutdown ACTION requiremencs 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 MODE when plant operation cannot be maintained within tne limits for safe operation defined by the Limiting Conditions for Operation and its ACTION requirements.

It is not intended to be used as an operational convenience which permits (routine) voluntary removal of redundant systems or components from service in lieu of other alternatives that would not result in redundant systems or components being inoperable.

One hour is

'llowed to prepare for an orderly shutdown before initiating a change in plant eration.

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 MODES 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 plart 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 completu, the shutdown may be terminated.

The time limits of the ACTION requirements are applicable from the point in time there was a failure to taet a Limiting Condition for Operation.

Therefore, the shutdown may be terminated if the ACTION requirements have been met or the time limits of the ACTION requirements have not expired, thus providing an allowance for the completion of the required actions.

BRAIDWOOD - UNITS 1 & 2 B 3/4 0-2 AMENDMENT NO. 38 l

3/4.0 APPLICABILITY BASES l

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 the COLD SHUTDOWN HODE when a shutdown is required during the POWER MODE of operation.

If the plant is in a lower MODE of operation when a shutdown is required, the time limit for reaching the next lower MODE of operation ap-plies.

However, if a lower MODE of operation is reached in less time than allowed, the total allowable time to reach COLD SHUTDOWN, or other applicable MODE, is not reduced.

For example, if HOT STANDBY 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 measures are completed that would permit a return to POWER operation, a penalty is not incurred by having to reach a lower MODE of operation in less than the total time allowed.

The same principle applies with regard to the allowable outage time limits of the ACTION requirements, if compliance with the ACTION requirements for one

. specification results in entry into a MODE or condition of operation for anothe" specification in which the requirements of the Limiting Condition for Operation are not met.

If the new specification becomes applicable in less time than specified, the difference may be added to the allowable outage time limits of the second specification.

However, the allowable outage time limits of ACTION requirements for a higher MODE of 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 MCDE of operation.

The shutdown requirements of Specification 3.0.3 do not apply in MODES S and 6, because the ACTION requirements of individual specifications define the remedial measures to be taken.

Specification 3.0.4 establishes limitations on MODE changes when a Limiting Condition for Operation is not met. 'It precludes placing the facility in a higher MODE of operation when the requirements for a Limiting Condition for Operation are not met and continued noncompliance to these conditions would result in a shutdown to comply with the ACTION requirements if a change in MODES were permitted.

The purpose of this specification is to ensure that facility operation is not initiated or that higher MODES of operation are not entered when corrective action is being taken to obtain compliance with a specification 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 accept-able level of safety for continued operation without regard to the status of the plant before or after a MODE change.

Therefore, in this case, entry into an OPERATIONAL MODE or other specified condition may be made in acc m ance with the provisions of the ACTION requirements.

The provisions of this specification should not, however, be interpreted is endorsing the failure to-exercise' good practice in restoring systems or components to OPERABLE status l

before plant startup.

l BRAIDWOOD - UNITS 1 & 2 B 3/4 0-3 AMENDMENT NO.

38

a 3/4.0 APPLICABILITY BASES When 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 facility in a lower MODE of operation.

Specification 3.0.5 delineates the applicability of each specification to Unit I and Unit 2 operation.

Specification 4.0.1 through 4.0.6 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, calibra-tion, or inspection to ensure that the necessary quality of systems and components is maintained that facility operation will be within safety limits,andthatthelimItingconditionsofoperationwillbemet."

Specification 4.0.1 establishes the requirement that surveillances must be performed during the OPERATIONAL MODES or other conditions for which the requirements of the Limiting Conditions for Operation apply unless otherwise stated in an individcal Surveillance Requirement.

The purpose of this speci-fication is to ensure that surveillances are performed to verify the opera-tional status of systems and components and that parameters are within speci-fied limits to ensure safe operation of the facility when the plant is in a MODE or other specified condition for which the associated Limiting Conditions for Operation are applicable.

Surveillance Requirements do not have to be performed when the facility is in an OPERATIONAL MODE for which the requirements of the associated Limiting Condition for Operation do not apply unless otherwise specified.

The-Surveillance Requirements associated with a Special Test Excep-tion are only applicable when the Special Test Exception is used as an allowable exception to the requirements of a specification.

Specification 4.0.2 establishes the limit for which the 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 activ' ties..It also provides flexibility to accommodate the length of 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 beyond that specified for surveillances that are not aerformed during refueling outages.

Tie limitation of Specification 4.0.2 is sased on engineering judgement and the recognition that 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 Require-ment within the alTowed surveillance interval, defined by the provisions of Specification 4.0.2, as a condition that constitutes a failure to meet the OPERABILITY requirements for a Limiting Condition for_0peration.

BRAIDWOOD - UNITS 1 & 2 P 3/4 0-4 AMENDMENT NO. 38

3/4.0 APP!.ICABILITY BASES Under the provisions 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 i

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

This specification also clarifies that the ACTION requirements are applicable when Surveillance Requirements have not l

been completed within the allowed surveillance interval and that the time limits of the ACTION requirements apply from the point in time it is identi-fied that a surveillance has 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 the requirements of Specification 4.0.3.

However, this does not negate the fact that the failure to have performed the surveil-lance within the allowed surveillance interval, defined by the provisions of Specification 4.0.2, was a violation of the OPERABILITY requirements of a Limiting Condition for Operation that is subject to enforcement action.

Further, the failure to perform a surveillance within the provisions of Specification 4.0.2 is a violation of a Technical Specification requirement and is, therefore, a reportable event under the requirements of 10 CFR 50.73(a)(2)(1)(B) because it is a condition prohibited by the plant's lechnical Specifications.

If 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 or a shutdown is required to comply with ACTION requirements, e.g.,

Specification 3.0.3, a 24-hour allowance is provided to permit a delay in implementing the ACTION requirements.

This provides an adequate time limit to complete Surveillance Requirements that have not been performed.

The purpose of this allowance is to permit the completion of a surveillance before a shutdown is required to comply with ACTION requirements or before other remedial measures would be required that may preclude completion of a surveillance.

The basis for this allowance includes consideration for plant conditions, adequate planning, availability of personnel, the time required to

. perform the surveillance, and the safety significance of the delay in completing the required surveillance.

This provision also provides e time limit for the completion of Surveillance Requirements that become applicable as a consequence of MODE changes imposed by ACTION requirements and for completing Surveillance Requirements that are applicable when an exception to the requirements of Specification 4.0.4 is allowed.

If a surveillance is not completed within the 24-hour allowance, the time limits of the ACTION requirements are applicable at that time.

When a surveillance is performed within the 24-hour allowance and the Surveillance Requirements are not met, the time limits of the ACTION requirements are applicable at the time that the surveillance is terminated.

Surveillance Requirements do not have to be perfe med on inoperable equipment because the ACTION requirements define the reme6 M1 measures that apply.

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

BRAIDWOOD - UNITS 1 & 2 B 3/4 0-5 AMENDMENT NO. 38 l

l 3/4.0 APPLICABILITY BASES Specification 4.0.4 establishes the requirement that all applicable surveillances must be met before entry into an OPERATIONAL MODE or other condition of operation specified in the Applicability statement.

The purpose of this specification is to ensure that system and component OPERABILITY requirements or parameter limits are met before entry into a MODE or condition for which these systems and components ensure safe operation of the facility.

This provision applies to changes in OPERATIONAL MODES or other specified conditions associated with plant shutdown as well as startup.

Under the provisions of this specification, the applicable Surveillance Requirements must be performed within the specified surveillance interval to ensure that the Limiting Conditions for Operation are met during initial plant startup or 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 MODE of operation.

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

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 V(ssel Code and applicable Addenda.

This clarification is provided to ensure consistency in surveillance intervals throughout the Technical Specifications and to remove any ambiguities relative to the frequencies for performing the required inservice inspection and testing activities.

Under the terms of this specification, the more restrictive requirements of 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 before entry into an OPERATIONAL MODE or other specified condition takes precedence over the ASME Boiler and Pressure Vessel Code provision which sllows pumps and valves to be tested up to one week after return to normal operation.

Th 4chnical Specification definition of OPERABLE does not allow a grace period M ore a component, that is not capable of performing its specified function, is declared inoperable and takes precedence over the ASME Boiler and Pressure Vessel Code provision which 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.

Specifica, tion 4.0.6 delineates the applicability of the surveillance activities to Unit 1 and Unit 2 operations.

BRAIDWOOD - UNITS 1 & 2 B 3/4 0-6 AMENDMENT NO. 38

ML20099H607

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