Text

Amends 43,43,32 & 32 to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,respectively,revising Action Statement for TS 3.1.3.1, Moveable Control Assemblies & Associated Bases Section
	ML20083E535
Person / Time
Site:	Byron, Braidwood
Issue date:	09/24/1991
From:	Barrett R; Office of Nuclear Reactor Regulation
To:	; Commonwealth Edison Co
Shared Package
ML20083E538	List: ML20083E535; ML20083E544;
References
	NPF-37-A-043, NPF-66-A-043, NPF-72-A-032, NPF-77-A-032 NUDOCS 9110030020
	Download: ML20083E535 (22)
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COMMONWEALTH EDISON COMPANY DOCKET NO. STN-50-454 BYRON STATION, UNIT NO.1 AMENDMENT TO FACILITY OPF'AATING LICENSE Amendment No. 43 License No. NPF-37 1.

The Nuclear' Regulatory Comission (the Comission) has found thati P

A.

The application for amendment by Commonwealth Edison Company-(the licensee) dated January 26, 1990, as supplemented April 8,-

1991, complies with the standtrds and recuirements of the Atomir

Energy-Act of.1'JE4, as amended (the-Act) and the Comission's rules and regulations set forth in 10 CFR Chapter I; B.

The facility will operate in conformity with the application,

'the provisions of the Act, and the rules and regulations of the Comission; C.-

There is reasonable assurance (1) that the activities authorized u

by-this amendment can t,e conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in corrpliance with the Comission's-regulations; L

D.

The issuance of this amendment will. not be inimical to-the comon L

defense and security.or to.the health and safety of the public; L.

and-E._

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

2.

Accordingly, the license is amended by changes to the Technical Specif1-L Tcations as indicated in the attachment to this license amendment, and-E

- paragraph 2.C.(2) of Facility Operating License No. NPF-37 is hereby g

amended to read as follows:

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(2) Technical Specifications

' The Technical Specifications contained in Appendix A as revised through Amendment No. 43 and the Environnental Protection Plan contained in Appendix B, both of which are attached hereto are hereby incorporated linto this license.

The licensee shall operate 1

-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 NUCl. EAR REGULATOSr COMMISSION h

C Rich r J. Barrett, Director Project Directorate 111-2 Division of-Reactor Projects - Ill/IV/V Office of Nuclear Reactor Regulation Attachnent:

Changes to the' Technical

-Specifications Date of lssuance: September. 24, 1991 c

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COMM0mCALTH EDISON COMPANY DOCKET NO. STN 50-455 BYRON STATION, UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 43 License No. NPF-66 1.

The Nuclear Regulatory Conrission (the Comission) has found that:

A.

The application for amendment by Commonwealth Edison Company (the licensee) dated January 26, 1990, as supplemented April 8, 1991, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission'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 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 Comission'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 Comission'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-66 is hereby amended to read as follows:

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. L(2) Technical Specifications-TheTechnical-SpecificationscontainedinAppendixA(NUREG-1113),

as revised through Amendment No.- 43 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 incorporated into this license.

Attachnent-2 contains a revision to Appendix A which is hereby incorporated.into this license. The111censee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3.

This license amendment-is e'fective as of the date of its issuance, FOR THE NUCLEAR REGULATO,R,Y COMMISSION

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Rich d'. Barrett,-Director Projec ' Directorate 111-2.

Division of Reactor Projects - III/IV/V Office of Nuclear Reactor Regulation

Attachment:

Changes-to the-Technical Specifications

,1 Date of Issuance: -September _ 24, 1991 L

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ATTACHMENT TO LICENSE AMENDMENT NOS. 43 AND 43 FACILITY OPERATING LICENSE N05. NPF-37 AND NPF-66, DOCKET NOS. STN 50-454 AND STN 50-455 Revise the Appendix A Technical Specifications by removing the pages identified

.below and inserting the attached pages. The revised pages are identified by-the captior.ed amendment number and contain marginal lines indicating the area cf char.ge. Overleaf pages identified by an asterisk are provided for convenience.

Remove Pages Insert Pages

3/4 1-13

3/4 1-13 3/4 1-14 3/4 1-14 3/4 1-15 3/4 1-15

3/4 1-16

3/4 1-16

B 3/4 1-3

B 3/4 1-3 B 3/4 1-4 B 3/4 1-4 r

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REACTIVITY CONTROL SYSTEMS SURVEILLANCE REQUIREMENTS 4.1.2.6 Each borated water source shall be demonstrated OPERABLE:

a.

At least once per 7 days by:

1)

Verifying the boron concentration in the water, 2)

Verifying the contained borated water level of the water source, and 3)

Verifying the Boric Acid Storage System solution temperature when it is the source of borated water, b.

At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by verifying the RWST temperature when the outside air temperature is either less than 35'F or greater than 100*F, and c,

At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by verifying the RWST vent path temperature to be greater than or equal to 35 F when the outside air temperature is less than 35 F.

BYRON - UNITS 1 & 2 3/4 1-13

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REACTIVITY CONTROL SYSTEMS 3/4.1.3 MOVABLE CONTROL ASSEMBLIES GROUP HEIGHT LIMITING CONDITION FOR OPERATION 3.1. 3.1 All full-length shutdown and control rods shall be OPERABLE and positioned within i 12 steps (indicated position) of their group step counter demand position.

APPLICABILITY:

MODES 1* and 2*.

ACTION:

a.

With one or more full-length rods inoperable due to being immovable as a result of excessive friction or mechanical interference or known to be untrippable, determine that the SHUTDOWN MARGIN require-ment of Specification 3.1.1.1 is satisfied within I hour and be in HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months , b.

With one full-length rod trippable but inoperable due to causes other than addressed by ACTION a, above, or misaligned from its group step counter demand height by more than i 12 steps (indicated position), POWER OPERATION may continue provided that within 1 hour:

1.

The rod is restored to OPERABLE status within the above alignment requirements, or 2.

The rod is declared inoperable and the remainder of the rods in the group with the inoperable rod are aligned to within 12 steps of the inoperable rod while maintaining the rod sequence and insertion limits of Figure 3.1-1.

The THERMAL POWER level shall be restricted pursuant to Specification 3.1.3.6 during subsequent operation, or 3,

The rod is declared inoperable and the SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is satisfied.

POWER OPERATION may then continue provided that:

a)

The THERMAL POWER level is reduced to less than or equal to 75% of RATED THERMAL POWER within the next hour and within the following 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months the High Neutron Flux Trip Setpoint is reduced to less than or equal to 85% of RATED THERMAL POWER.

b)

The SHUTDOWN MARGIN requirement of Specificatien 3.1.1.1 is determined at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ;

See Sptcial Test Exceptions Specifications 3.10.2 and 3.10.3.

BYRON - UNITS 1 & 2 3/4 1-14 AMENDMENT NO. 43

REACTIVITY CONTROL SYSTEMS LIMITING CONDITION FOR OPERATION ACTION (Continued) c)

A power distribution map is obtained from the movable incoredetectorsandF(Z)andFfHare verified to be q

within their limits within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ; and

-d)

A reevaluation of each accident analysis of Table 3,1-1 is performed within 5 days; this reevaluation shall confirm that the previously analyzed results of-these accidents remain valid for the duration of operation under these conditions; 4

c.

With more than one full-length rod trippable but inoperable due to causes other than addressed by ACTION a, above, or misaligned from

-its group step counter demand height by_more than + 12 steps (indicated position), POWER OPERATION may continue provided that:

1 1.

Wittin I hour, the remainder of the rods in the group (s) with the inoperable rods are aligned to within + 12 steps of_the-inoperable rods while maintaining the rod sequence and insertion limits of Figure 3.1-1.

The THERMAL POWER level shall be restricted pursuant to Specification 3.1.3.6 during subsequent operation, and 2.

The inoperable rods shall be restored to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .

Otherwise, be in HOT STANDBY within_6 hours.

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_ SURVEILLANCE REQUIREMENTS e

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-4.1.3.1.1 The position of each full-length rod shall be determined-to be within the group demand limit by verifying the individual rod positions at

1 east: once'per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months except during time intervals when the rod position =

l deviation monitor is inoperable, then_ verify the group positions at least once L

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

r 4.1.3.1.2 Each full-length rod not fully inserted in the core shall be determined OPERABLE by movement of at least 10 steps in any one direction at least once per 31 days.

BYRON - UNITS 1 & 2 3/4 1-15 AMENDMENT NO. 43 tp

TABLE 3.1-1 ACCIDENT ANALYSES REQUIRING REEVALUATION IN THE EVENT OF AN INOPERABLE FULL-LENGTH ROD Rod Cluster Control Assembly Insertion Characteristics.

Rod Cluster Control Assembly Misalignment.

Loss of Reactor Coolant from Small Ruptured Pipes or from Cracks in large Pipes Which Actuates the Emergency Core Cooling System.

Single Rod Cluster Control Assembly Withdrawal at Full Power.

Major. Reactor Coolant System Pipe Ruptures (Loss of Coolant Accident).

Major Secondary _ Coolant System Pipe Rupture.

Rupture of a Control Rod Drive Mechanism Housing (Rod Cluster Control Assembly Ejection).

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. UNITS 1 & 2 3/4 1-16 L

REACTIVITY CONTROL SYSTEMS BASES BORATION SYSTEMS (Continued)

A Boric Acid Storage System lesel of 40% ensures that there is a volume of greater than or equal to 15,780 gallons available.

A RWST level of 89% ensures that there is a volume of greater than of equal to 395,000 gallons available.

With the RCS temperature below 350 F, one Boron Injection System is acceptable without single failure consideration on the basis of the stable reactivity condition of the reactor and the additional restrictions prohibiting CORE ALTERATIONS and positive reactivity changes in the event the single Boron Injection System becomes inoperable.

The limitation for a maximum of one centrifugal charging pump to be OPERABLE and the Surveillance Requirement to verify all charging pumps except the required OPERABLE pump to be inoperable belew 330'F provides assurance that a mass addition pressure transient can be relieved by the operation of a single PORV or an RHR Suction valve.

The boron capability required below 200 F is sufficient to provide a SHUTDOWN MARGIN of T% Ak/k after xenon decay and cooldown from 200 F to 140 F.

This condition requires either 2,652 gallons of 7000 ppm borated water from the boric acid storage tanks or 11,840 gallons of 2000 ppm borated water from the refueling water storage tank (RWST).

A Boric Acid Storage System level of 7% ensures there is a volume of greater than or equal to 2652 gallons available.

An RWST level of 9% ensures there is a volume of greater than or equal to 38,740 gallons available.

The contained water volume limits include allowance for water not available because of discharge line location and other physical characteristics.

The limits on contained water volume and boron concentration of the RWST also ensure a pH value of between 8.5 and 11.0 for the solution retirculated within containment after a LOCA.

This pH band minimizes the evolution of iodine and reinimizes the effect of chlorios and caustic stress corrosion on mechanical systems and components.

The OPERABILITY of one Boron Injection System during REFUELING ensures that this system is available for reactivity control while in MODE 6.

3/4.1.3 MOVABLE CONTROL ASSEMBLIES The specifications of this section ensure that: (1) acceptable power distribution limits are maintained, (2) the minimum SHUTDOWN MARGIN is main-tained, and (3) the potential effects of rod misalignment on associated accident analyses are limited.

OPERABILITY of the control rod position indicators is required to determine control rod positions and thereby ensure compliance with the control rod alignment and insertion limits.

Verification that the Digital Rod Position Indicator agrees with the demanded position within 112 steps at 24, 48, 120, and 228 steps withdrawn for the Control Banks and BYRON - UNITS 1 & 2 B 3/4 1-3

REACTIVITY CONTROL SYSTEMS BASES MOVABLE CONTROL ASSEMBLIES (Continued) 18, 210, and 228 steps withdrawn for the Shutdown Banks provides assurances that the Digital Rod Position Indicator is operating correctly over the full range of indication.

Since the Digital Rod Position System does not indicate the actual shutdown rod position between 18 steps and 210 steps, only points in the indicated ranges are picked for verification of agreement with demanded position.

The ACTION statements which permit limited variations from the basic requirements are accompanied by additional restrictions which ensure that the original design criteria are met.

Inoperability or misalignment of a single,

.trippable rod requires measurement of peaking factors and a restriction in THERMAL POWER.

These restrictions provide assurance of fuel rod integrity during concinued operation.

In addition, those safety analyses affected by an inoperable or misaligned rod are reevaluated to confirm that the results remain valid during future operation.

With multiple inoperable or misaligned, but trippable, rods; alignment of the remaining rods in the bank (t,) to within

+ 12 steps of the inoperable rods, and restriction in THERMAL POWER assures Tuel rod integrity during continued operation.

For Specification 3.1.3.1 ACTIONS b. and c., it is incumbent on the plant to confirm trippability of the inoperable rod (s).

This confirmation may be, for example, by verification of a control system failure, usually electrical in nature (such as an Urgent Failure Alarm), or that the failure is associated with the control rod stepping mechanism.

In the event the plant is unable to verify the rod (s) trippability, it must be assumed to be untrippable and thus falls uoder the requirements of ACTION a.

The maxi.num rod drop time restriction is consistent with the assumed rod drop time used in the safety analyses.

Measurement with T,yg greater than or equal to 550*F and with all reactor coolant pumps operating ensures that the measured drop times will be representative of insertion times experienced during a Rec tor trip at operating conditions.

Control rod positions and OPERABILITi of the rod position indicators are required to be verified on a nominal basis of once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months with more frequent verifications required if a rod position deviation monitor is inoper-able.

These verification frequencies are adequate for assuring that the applicable LCOs are satisfied.

BYRON - UNITS 1 & 2 B 3/4 1-4 AMENDMENT NO. 43

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s COMMONWEALTH EDISON COMPANY-DOCKET NO. STN 50-456 BRAIDWOOD STATION, UNIT NO. I t

AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 32 License No. NPF-72

.1.

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

i A.

The application for amendment by Commonwealth Edison Company (the licensee) dated January 26, 1990, as supplemented by April 8, 1991, complies with the standards and~ requirements of the Atomic Energy Act of 1954, as amended (the Act) and-the Comission's. rules and-regulations set forth in 10 CFR Chaptor I; B.

The facility will o)erate in conformity with the application,

'the provisicas of t1e Act, and the rules and regulations of the Comission; C.

-Thereisreasonableassurance(1)thattheactivitiesauthorized by this amendment can be conducted without endangering the health

-and safety of the public, and (ii) that such activities will be corJucted in compliance with the Comission's regulations; D.

The issuance of this amendment will not be inimical to the comon 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 Comission's regulations and all applicable requirements have been satisfied.

2.-

Accordingly the license.is amended by changes to the Technical Specifi-cationsasIndicatedinthe-attachmenttothislicenseamendment,and paragraph 2.C.(2) of Facility Operating License No. NPF-72 is herebyf

-amended-to read as follows:

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2 (2) Technical Specifications The "achnical Specifications contained in Appendix A as revised through Amendment No. 32 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 wi+h the Technical Specifications and the Environmental Protection ilan.

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

FOR THE NUCLEAR REGULAT0n3 COMMIS010N p'

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Riche d 4. Barrett, Director Project Directorate 111-2 Division of Reactor Frojects

!!!/IV/V Office of Nuclear Recctor Regulation

Attachment:

Changes to the Technical Specifications Date of 155uance: September 24, 1991

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%*..*f COMMONWEALTH EDISON COMPANY DOCKET NO. STN 50-457 BRAIDWOOD STATION, UNIT NO. 2 AMENDMENT T0 FACILITY OPERATING LICENSE Amendment No. 32 1.icense No NPF-7't j

1 1.

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

I I

A.

The application for amendment by Commonwealth Edison Company (thelicensee)datedJanuary 26, 1990, as supplemented April 8, 1991, complies with the standards and re Energy Act of 1954, as amended tthe Act)quirements of the Atomic and the Commist,lon's rules and regulations set forth in 10 CFR Chapter it B.

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

Thereisreasonableassurance(1)thattheactivitiesauthorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in conpliance 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 applicab% 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:

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2 (2) Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 32 and the Environmental Protection Plan contained in Appendix B, both of which were attached to License No. NPP-72, dated July 2, 1987, are hereby incorporated inte 'his license. The licensee shall operate the facility in accor.4nce with the Technical Specifications and the Environmental Pro.:. u on Plan.

3.

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

FOR THE NUCLEAR P.EGULATORY COMMISSION c,A Rich d Bifrrett, Director Project Directorate 111-2 Division of Reactor Projects - !!!/lV/V Office of Nuclear Reactor Regulation

Attachment:

Changes to the Technical Specifications Date of Issuance: September 24. 1991

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ATTACHMENT TO LICENSE AMENDieENT NOS. 32 AND 32 FAtlllTY OPERATING LICENSE NOS. NPF-72 AND HPT-77 DOCKET N05. STN 50-456 AND STN 50-457 Replace the following pages of the Appendix "A" Technical Specifications with the attached pages. The revised pages are identified y amendnent nunber and contain vertical lines indicating the area of change. Overleaf pages identified by an asterisk are provided for convenience.

Remove Paoes insert Pages

$3/4 1-13

3/4 1-13 3/4 1-14 3/4 1-14 3/4 1-15 3/4 1-15

3/4 1-16

3/4 1-16

B 3/41-3

B 3/4 1-3 B 3/4 1-4 B 3/4 1-4

4 REACTIVITY CONTROL SYSTEMS SURVEILLANCE REQUIREMENTS 4.1.2.6 Each borated water source shall be demonstrated OPERABLE:

a.

At least once per 7 days by:

1)

Verifying the boron concentration in the water, 2)

Verifying the contained, orated water level of the water source, and 3)

Verifying the Boric Acid Storage System solution temperature when it is the source of borated water, b.

At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by verifying the RWST temperature when the outside air temperature is either tess than 35'F or greater than 100*f, and c.

At least once per 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months by verifying the RWST vent path temperature to be greater than or equal to 35'F when the outside air temperature is less than 35'f.

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BRAIDWOOD - UNITS 1 & 2 3/4 1-13

REACTIVITY CONTROL SYSTEMS 3/4.1.3 HOVABLE CONTROL ASSEMBLIES GROUP HEIGHT LIMITING CONDITION FOR OPERATION P

3.1.3.1 All full-length shutdown and control rods shall be OPERABLE ard positioned within 1 12 steps (indicated position) of their group step counter demand position.

APPLICABILITY:

MODES 1* and 2*.

ACTION:

a.

With one or more full-length rods inoperable due to being immovable as a result of excessive friction or mechanical interference or known to be untrippable, determine that the SHUTDOWN MARGIN require-ment of Specification 3.1.1.1 is satisfied within I hour and be in HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

b.

With ore full-length rod trippable but inoperable due to causes other than addressed by ACTION a, above, or misaligned from its group step counter demand height by more than i 12 steps (indicated position), POWER OPERATION may continue provided that within 1 hour:

1.

The rod is restored to OPERABLE status within the above alignment requirements, or 2.

The rod is declared inoperable and the remainder of the rods in the group with the inoperable rod are aligned to within i 12 steps of the inoperable rod while maintaining the rod sequence and insertion limits of Figure 3.1-1.

The THERMAL POWER level shall be restricted pursuant to Specification 3.1.3.6 during subsequent operation, or 3.

The rod is declared inoperable and the SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is satisfied.

POWER OPERATION may then continue provided that:

a)

The THERMAL POWER level is reduced to less than or equal to 75% of RATED THERMAL POWER within the next hour and within the following 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months the High Neutron Flux Trip Setpoint is reduced to less than or equal to 85% of RATED THERMAL POWER.

l b)

The SHUTDOWN MARGIN requirement of Specification 3.1.1.1 is determined at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months ; l

See Special Test Exceptions Specifications 3.10.2 and 3.10.3.

l BRAIDWOOD - UNITS 1 & 2 3/4 1-14 Amendment No. 32 1

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i' REACTIVITY CONTROL SYSTEMS LIMITING CONDITION FOR OPERATION ACTION (Continued) c)

A power distribution map is obtained from the tovable incoredetectorsandF(Z)andFhareverifiedtobe i

q within their limits within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months ; and d) lA reevaluation of each accident analysis of Table 3.1-1 is performed within 5 days; this reevaluation shall confirm that the previously analyzed results of these accidents remain valid for the duration of operation under these conditions;-

c.-

With more than one full-length rod trippable but inoperable due to causes other than addressed by ACTION a. above, or misaligned from its group step counter demand heiCht by more than + 12 steps (indicated position), POWER OPERATION may continue provided.that:

1 1.

Within 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months , the remainder of the rods in the group (s) with the inoaerable rods are aligned to within + 12 steps of the inoperaale rods..while maintaining the rod sequence and-insertion limits of Figure 3.1-1.

The THERMAL F0WER level i

shall be restricted pursuant to Specification 3.1.3.6 during subsequent operation, and 2.

The inoperable rods shall be restored to OPERABLE status within 72 hours8.333333e-4 days 0.02 hours 1.190476e-4 weeks 2.7396e-5 months .-

Otherwise, be in HOT STANDBY within 6 hours6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months .

SURVEILLANCE REQUIREMENTS y

--4.1.3.1.1 The position of each full-length rod shall be determined to be.

t

-within the group demand limit by verifying the individual rod positions at least once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months except during. time intervals when the rod position deviation monitor is inoperable, then verify the-group positions at least once per 4 hours4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months .

4.1.3.1.2 Each full-length rod not fully-inserted in the core shall be determined OPEAABLE by movement of at least 10 steps in any one direction at least once per 31 days.

i BRAIDWOOD - UNITS 1 & 2 3/4 1-15 Amendment No. 32

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TABLE 3.1-1 4

ACCIDENT ANALYSES REQUIRING REEVALUATION IN THE EVENT OT~AN INOPERABLE FULL-LENGT'H ROD Rod Cluster Control Assembly Insertion Characteristics.

Rod Cluster Control Assembly Misalignment.

Loss of Reactor Coolant from Small Ruptured Pipes or from Cracks in large Pipes Which Actuates the Emergency Core Cooling System.

Single Rod Cluster Control Assembly Withdrawal at Full Power.

Major Reactor Coolant System Pipe Ruptures (Loss of Coolant Accident).

Major Secondary Coolant System Pipe Rupture.

Rupture of a Control Rod Drive Mechanism Housing (Red Cluster Control Assenbly Ejection).

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- BRAIDWOOD - UNITS 1 & 2.

'3/4 1-16

_-___a_-..._.______..__;_._.._.-.

REACTIVITY CONTROL SYSTEMS BASES BORATION SYSTEMS (Continued)

A Boric Acid Stortge System level of 40% ensures that there is a volume of greater than or equal to 15,780 gallons available.

A RWST level of By% ensures that there is a volume of greater than or equal to 395,000 gallons available.

With the RCS temperature below 350'F, one Boron Injection System is acceptable without single failure consideration on the basis of the stable reactivity condition of the reactor and the additional reestrictions prohibiting CORE ALTERATIONS and positive reactivity changes in the event the single Boron Injection System becomes inoperable.

The limitation for a maximum of one centrifugal charging pump to be OPERABLE and the Surveillance Requirement to verify all charging pump except the required OPERABLE pump to be inoperable below 330*F provides assurance that a mass addition pressure transient can be relieved by the operation of a single PORV or an RHR Suction valve.

The boron capability required below 200*f is suf ficient to provide a SHUTDOWN MARGIN of 1% Ak/k af ter xenon decay and cooldown from 200*F to 140*F.

This condition requires either 2,6F2 gallons of 7000 ppe borated water from the boric acid storage tanks or 11,840 gallons of 2000"pps borated water from the refueling water storage tank (RWST).

A Beric Acid Storage system level of 7% ensures there is a volume of greater than or equoi to 2652 gallons available.

An RWST level of 9% ensures there is a volume of greater than or equal to 38,740 gallons available.

The contained water volume limits in lude allowance for weter not available because of discharge line location and other pny*,ical characteristics.

The limits on contained water volume and buron concentration of the RWST also ensure a pH value of between 8.5 and 11.0 for the solution recirculated within containment after a LOCA.

This pH band minimizes the evolution of fodine and minimites the effect of chloride and caustic stress corrosion on mechanical systems and components.

The OPERABILITY of one Bornn Injection System during REFUELING ensures that this system is available for reactivity control while in MODE 6.

3/4.1.3 MOVABLE CONTROL ASSEMB. LIES The specifications of this section ensure that: (1) acceptable power l

distribution limits are maintained, (2) the minimum SHUTDOWN MARGIN is main-tained, and (3) the potential effects of rod misalignment on associated accident analyses are limited.

OPERABILITY of the control rod position indicators is required to determine contral rod positions and thereby ensure compliance with the control rod alignment and insertion limits.

Verification that the Digital Rod Position Indicator agreas with the demanded position within l

112 steps at 24, 48, 120, and 228 steps withdrawn for the Control Banks and BRAIDWOOD - UNITS 1 & 2 8 3/4 1-3

REACTIVITY CONTROL SYSTEMS BASES HOVABLE CONTROL ASSEMBLIES (Continued) 18, 210, and 228 tteps withdrawn for the Shutdown Banks provides assurances that the Digital Rod Position Indicator is operating correctly over the full range of indication.

Since the Digital Rod Position System does not indicate the actual shutdown rod position between 18 steps and 210 steps, only points in the indicated ranges are picked for verification of egreement with demanded position.

The ACTION statements which permit limited variations from the basic requirements are accompar,ied by additional restrictions which ensure that the original design criteria are met.

Inoperability or misalignment of a single, trippable roc requires measurement of peaking factors and a restriction in THERMAL POWER.

These restrictions provide assurance of fuel rod integrity dunng continued operation.

In addition, those safety analyses affected by an inoperable or misaligned rod are reevaluated to confirm that the results remain valid during future operation.

With multiple inoperable or misaligned, but trippable, rods; alignment of the remaining rods in the bank (s) to within

+ 12 steps of the inoperable rods, and restriction in THERMAL POWER assures Yuel rod integrity during continued operation.

For Specification 3.1.3.1 ACTIONS b. and c., it is incumbent on the plant to confirm trippability of the inoperable rod (s).

This confirmation may be, for example, by verification of a control system failure, usually electrical in nature (such as an Urgent Failure Alarm), or that the failure is associated with the control rod stepping mechanism.

In the event the plant is unable to verify the rod (s) trippability, it must be assumed to be untrippable and thus falls under the requirements of ACTION a.

The maximum rod drop time restriction is consistent with the assumed rod drop time used in the safety analyses.

Measurement with T,yg greater than or equal to 550 F and with all reactor coolant pumps operating ensures that the measured drop times will be representative of insertion times experienced during a Reactor trip at operating conditions.

Control rod positions and OPERABILITY of the rod position indicators are required to be verified on a nominal basis of once per 12 hours1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months with more frequent verifications required if a rod position deviation monitor is inoper-able.

These verification frequencies are adequate for assuring that the applicable LCOs are satisfied.

I I

I BRAIDWOOD - UNITS 1 & 2 B 3/4 1-4 Amendment No. 32 1

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ML20083E535

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