ML20099F672

Amends 48 to Licenses NPF-37 & NPF-66 & Amends 37 to Licenses NPF-72 & NPF-77,revising TS 3.3-6 & 4.3-3 Re Outside Air Intake Radiation Monitors

ML20099F672
Person / Time
Site:	Byron, Braidwood
Issue date:	08/05/1992
From:	Barrett R Office of Nuclear Reactor Regulation
To:	Commonwealth Edison Co
Shared Package
ML20099F675	List: ML20099F672
References
NPF-37-A-048, NPF-66-A-048, NPF-72-A-037, NPF-77-A-037 NUDOCS 9208130158
Download: ML20099F672 (18)

Text

_

ll ceatoufk

+

.6 UNITED' STATES -

5

.i NUCLEAR REGULATORY. COMMISSION '

WASHINGTON. D.C. 20Mi6 -

o COMMONWEALTH EDISON COMPANY-DOCKET NO. STN 50-454L BYRON STATION. UNIT-NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE AmendmentNo.L48.

License Noi NPF,-37; 1.

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

A.

The application-for amendment byfCommonwealth Edison Company,(the

-licensee) dated November 6,- 1987, as' supplemented by letters-. dated 1

February 8,1991, January 13: and February 6, :1992,: complies with '

y thc standards andcrequirements:of the. Atomic' Energy Act of 1954,..

as amended (the Act)1and the Commission _'s rules 7and_ regulations; set forth in 10 CFR Chapter I;!

B.

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

There is' reasonable ' assurance l(i).that -the activities authorized by this amendment can be conducted without. endangering the health 7 and safety of the'public, and :(ii)1that such activities. willLbe q

conducted in compliance with _ the_ Commission's_ regulations;1 i

D.

The: issuance of this amendment willinot be inimical to the" common defense and security or to the health' and safety of t_he public;:

and E.

The Issuance of'this-amendment is51n accordance withe 10 CFR Part-51 of the Commission's-regulations and all; applicable requirements i

have been' satisfied.

2.

Accordingly,. the license -is amended byichanges to the -Technical LSpecifi--

cations as> indicated-in the attachment to-this license' amendment, and-paragraph 2.C.(2) nf Facility.0perating License:No. NPF-3711s.hereby-amended to read as follows:

~

i 9208130158 920805-..

PDR -ADOCK 0S000450 p.

PDR1

_ = _ _ _-

(2)

TechnicaLSpecifications The Technical Specifications contained in Appendix A as revised through Amendment No. 48 and the f.nvironmental Protection Plan contained in Appenaix B, both of t<hich 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.

Thic iicense amendment is effective as of the date of its issuance.

FOR THE NUCLEAP REGULATORY COMMISSION 0

)f-.

i Ric het irector Project Directorate III-2 Division of Reactor Projects - III/IV/V Office of Huclear Reactor Regulation.

Attachment:

Changes to the Technical Specifications Date of Is uance:

August 5, 1992 l

1 l

l i

p* Mog

['

'n UNITED STATEE E

i NUCLEAR REGULATORY COMMISSION

'#[

o, WASHINoToN, D C 20566 COMMONWEALTH EDISON COMPANL DOCKET NO. STN 50-455 BYRON STATION. UNIT NO. 2 AMENDMENT TO FACILITY GPERATING LICLNSI Amendment No. 48 License No. NPF-66 1.

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

A.

The application for amendment by Commonwealth Edison Company (the

' licensee): dated November 6, 1987, as_ supplemented by letters dated February 8,1991, January.13 and February 6, -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;l; 1

B.

The facility will operate in conformity _ with the application, the provirions of the Act', and the rules and regulations of the.

Commission; C.

There is reascnable 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 Commissian's regulations;-

D.

The issuance of this amendme't will not be' inimical to the common n

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 4

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-66 is-hereby,-

amended to read as-follows:

1

^'

1

. (2)_

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

J as. revised through Amendment No. 48 and revised by Attachment 2 l

to NPF-66, and the Environmental Protection Plan contained in Appendix B, both of which were attached to l.icense No. NPF-37, dated February 14, 1985, are hereby incorporated 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 effective as of the date of its issuance.

FOR THE hUCLEAR REGULATORY COMMISSION aARY Richard

. B&rrett, 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 5, 1992

~

ATTACBEENT TO LICENSE AMEN 0 MENT NOS. 48 AND 48 FAClllTY OPERATING llCENSE NOS. F""-37 AND NPF-66 DOCKET NOS. STN 50-454 Aha 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 captioned amendment number and contain marginal lines indicating the area of char.ge. Overleaf pages identified by an asterisk are provided for convenience.

Remove Paoes Insert Paaes 3/4 3-39*

3/4 3-39*

a 3/4 3-40 3/4 3-40 3/4 3-41 3/4 3-41 3/4 3-42 3/4 3-42 I

_ _ _ _. _ _ =.. _.._

~.

INSTRUMENTATION 3/4.3.3 MONITORING INSTRUMENTATION RADIATION MONITORING FOR PLANT OPERATIONS LIMITING CONDITICN FOR OPERATION 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:

With a radiation monitoring channel Alarm / Trip Setpoint for plant a.

operations exceeding t'he value shown in Table 3.3-6, adjust the Setpoirt to within the limit within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> or declare the channel inoperable.

With one or more radiation monitoring channels for plant operations b.

inoperable, take the ACTION shown in Table 3.3-6.

The provisions of Specitications 3.0.3 anc 3.0.4 are not applicable.

c.

SURVEILLANCE REQUIREMENTS 4.3.3.1 Each radiation monitoring instrumentation channel for plant operations shall be demonstrated OPERABLE by the performance of the CHANNEL CHECK, CHANNEL CALIBRATION and 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 4

4,-

~

~

.-y.-

~--i -

.-c-

TABL2 3.3-6 Yg RADIATION MONITORING INSTRUMENTATION FOR PLANT OFERATIONS E

MINIMUM H

CHANNELS CHANNELS APPLICABLE ALARM / TRIP

['

FUNCTIONAL UNIT TO TRIP / ALARM OPERABLE MODES SETPOINT ACTION

[

1.

Fuel Building Isolation-Radioactivity-High and Criticality (ORE-AR055/56) 1 2

<5 mR/h 29 2.

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

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

All 26 Y

3.

Gaseous Radioactivity-RCS Leakage Detection Y

a) Unit 1 (IRE-PR0118)

N.A.

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

28 b) Unit 2 (2RE-PR011B)

N.A.

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

28 4.

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

N,A.

1 1,2,3,4 R. A.

28 b) Unit 2 (2RE-PR011A)

H.A.

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

28 5.

Main Control Room.Isolatien-Outside Air Intake-Gaseous Radioactivity-High a) Train A (ORE-PRGJ.3/328) 1 2

All

< 2 mR/h 27 b) Train B (CRE-PR0338/348) 1 2

All 32mR/h 27 5$

8 CD

TABLE NOTATIONS

• With new fuel or irradiated fuel in the-fuel storage areas or fuel building.

• • Trip Setpoint is to be established such that the actual submersion dose rate would not exceed 10 mR/hr in the containment-building.

For containment purge 4

or vent the Setpoint value may be increased up to twi e the maximum concentra-l tion activity in the containment determined by the sample analysis performed prior to each release in ac',ordance with Table 4.11-2 provided the value does not exceed 10% of the eouivalent limits of Specification 3.11.2.1.a in accord-ance with the methodology and parameters in the ODCM.

l ACTION STATEMENTS ACTION 26 With less than the Minimum Channels OPERABLE requirement, operation may_ continue provided the containment purge valves are maintained closed.

ACTION 27 With the number of OPERABLE channels less-than the Minimum Channels OPERABLE requirement, within I hour switch to the redundant train of Control Room Ventilation, provided the redundant train meets the Minimum Channels OPERABLE requirement or isolate the Control Room Ventilation Systen and initiate opere.M an of the Control Room Make-up System.

Restore the inoperable momtors to OPERABLE status within 30 days or submit a Special Report to the Commission pursuant to Specification 6.9.2 within the following 30 days that provides the cause of the inoperability and the plans for restoration.

4 ACTION 28

- Must satisfy the ACTION requirement for Specificat,'on 3.4.6.1.

i ACTION 29 With the number of OPERABLE channels one less than the Minimum i

Channels OPERABLE requirement, ACTI0li a. of Spccification 3.9.12 I

must be satisfied.

With both channels inoperable, provide an appropriate portable continuous monitor with the-same Alarm Set-f point in the fuel pool crea with one Fuel Handling Building Exhaust filter plenum in operation.

Otherwise satisfy ACTION b.

of Specification 3.9.12.

l I

2

)

BYRON - UNITS 1 & 2 3/4 3-41 AMENDMENT NO.48

.~

co TABLE 4.3-3 5

RADIATION MON _ITORING INSTRUMENTATION FOR PLANT OPERATIONS SURVEILLANCE REQUIREMENTS C5d DIGITAL g

CHANNEL e.

CHANNEL CHANNEL OPERATIGNAL MODES FOR WHICH FUNCTIONAL UNIT CHECK CALIBRATION, TEST SURVEILLANCE IS REQUIRED m

1.

Fuel Building Isolation-Radioactivity-High and Criticality (ORE-AR055/56)

S R

M 2.

Containment Isolation-Containment Radioactivity-High R

a) Unit 1 (1RE-AR011/12)

S R

M All b) Unit 2 (2RE-AR011/12)

R M

All Y

9t 3.

Gaseous Radioactivity-RCS Leakage Detectico a) Unit 1 (IRE-PRO 11B)

S R

H 1,2,3,4 b) Unit 2 (2RE-PR0118)

S R

H 1,2,3,4 4.

Particulate Radioactiv;tv-RCS t.eakage Detection s) Unit 1 (IRE-PRO 11A)'

S R

M 1,2,3,4 b) Unit 2 (2RE-PR011A)

S R

M 1,'.2, 3, 4 5.

M..in Control Roon Isolation-E

-Outside Air Intake-Gaseous 5

Radioactivity-High M

a) Train A (ORE-PR031B/328)

S R

M All 5:

b) Train B (ORE-PR033B/348)

S R

M All g

^With new fuel or irradiated fuel in the fuel storage areas or fuel building.

mcq?g o

8 gg UNITED STATES

),

r-c NUCLEAR REGULATORY COMMISSION

d t s ~ [+p f

WASHINGTON, D.C. 20665

+...

COMMONWEALTH EDISON COMPANY DOCKET N0. STN 50-456 BRAIDWOOD STATION. UNIT NO. 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 37 License No. NPF-72 1.

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

A.

The spplication for amendnent by Commonwealth Edison Company (the licensee) dated November 6, 1987, as supplemerted by letters dated February 8, 1991, January 13 and February 6, 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 conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (1) 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 epplicable 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 hereby amended to read as follows:

i

. (2)

Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment no. 37 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

l t )MA Richa'ld

. 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 5, 1992 4

39htCg -

[

\\

o UNITED STATES-5

.E NUClf.AR REGULATORY COMMISSION o

WASHINGTON, D.C. 20066 COMMONWEAtTH EDISON COMPANY:

DOCKET NO. STN 50-457 BRA 10 WOOD STATION. UNIT NO. 2 AMENDMENT TO FACILITY OPERATING LICENSE

-Amendment No.37 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.6, 1987,.as_ supplemented by letters dated February 8, 1991, January 13 and February 6,.1992, complies with-

'he 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 a'pplication, 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 amendn.ent 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;.

o

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

2.

Accordingly, the-licensezis amendcd by changes to the Technical-Specifi-cations as indicated in the attachment to this license. amendment, and.

1 paragraph 2.C.(2) of Facility Operating License No..NPF-77fis hereby amended to read as follows:

__m

..J

_ _ _ _ _ - _ _ - _ (2)

Technical Soecifications The Technical Specifications contained in Appendix A as revised through Amendment No. 37 and the Environmental Prctection 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 Plan.

3.

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

FOR THE NUCLEAR REGULATOR,Y COMMISSION cg) fpa.

=

Richard 4 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 5, 1992 i

ATTACHMENT TO LICENSE AMENDMENT NOS. 37 AND 37 FACillTY OPERATING LICENSE NOS. NPF-72 AND NPF-77 DOCKET NOS. 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 by amendment number and contain vertical lines indicating the area of change.

Remove Paoes Insert Paoes 3/4 3-39 3/4 3-39 3/4 3-40 3/4 3-40 3/4 3-41 3/4 3-41 3/4 3-42 3/4 3-42 B

i i

p I

1 r

INSTRUMENTATIONL i

3/4.3.3' MONITORING INSTRUMENTATION 1

j RADIATION MONITORING FOR PLANT OPERATIONS LIMITING CONDITION FOR OPERATION 3.3.3.1 -The radiation monitoring instrumentation channels for plant operations l

shown in-Table 3.3-6 shall be OPERABLE with their Alarm / Trip.Setpoints within i

the specified limits.

I i.

APPLICABILITY:

As-shown in-Table 3s3-6.

l ACTION:

i h

With a radiation monitoring channel-Alarm / Trip Setpoint for planti a.

operations exceeding the value shown in Table 3.3-6, adjust the-t l

Setpoint to within c.s limit within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> 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.

1 i

The provisions of Specification 3.0.3 and 3.0.4 are not applicable.

c.

i I

l SURVEILLANCE REQUIREMENTS-I 4.3.3.1 Each radiation monitoring instrumentatio channel ~for plant operations; L

shall be: demonstrated 0PERABLE by the performance.of the: CHANNEL CHECK,1 CHANNEL-1 CALIBRATION'and DIGITAL CHANNEL OPERATIONAL TEST for the MODES and at the-d frequencies shown in Table 4.3-3.

j BRAIDWOOD - UNITS 1 & 2 3/4 3-39 AMENDMENT NO. 37

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

R 1

TABLE 3.3-6 cn5g-RAOIATION MONITORING INSTRUMENTATION FOR PLANT OPERATIONS 6'8 MINIMUM CHANNELS CNANNELS APPLICABLE ALARM / TRIP c5 FUNCTIONAL UNIT TO TRIP /. ARM GPERABLE-MODES SETPOINT ACTION

--e

[

1.

Fuel Building Isolation-Radioactivity-High and 3

Criticality (ORE-AR055/56) 1 2

<5 mR/h 29 m

2.

Containment Isolation-Containment Radioactivity-

.High a) Unit 1 (1RE-AR011/12) 1 2

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

All 26

$. 3.

Gaseous Radioactivity-RCS Leakage Detection

{

a) Unit 1 (1RE-PR0118)

N.A.

1 1.2,3,4 N. A.

28 b) Unit 2 (2RE-PR011B)

N.A.

1~

., 2, 3, 4 N.A.

28 o

4.

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

N.A.

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

28 l

b) Unit 2 (2RE-PR011A)

N.A.

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

28 5.

Main Control Room Isolation--

Outside Air Intake-Gaseous Radioactivity-High a) Train A-(0RE-PR0318/328) 1 2

All

< 2 mR/h 27 b) Train B (ORE-PR033B/348) 1-2

'All 7 2 mR/h g

27

=

.O U

l t

E

. g..

h l'

TABLE NOTATIONS-1 I

• With new fuel or irradiated fuel in th'e fuel storage areas.or ~ fuel building.

• • Trip Setpoint is to be established such that the actual submersion Ldose rate in

-would not exceed'10 mR/hr in the. containment building.

For containment purge.

or vent the Setpoint value may be increased up to twice the maximum concentra-tion _ activity.in the containment determined by the' sample analysis performed.

prior to_each release in accordance with Table 4.11-2 provided the value does not exceed 10% of the' equivalent-limits of Specification-3.11.-2.1.a'in accord-ance with the methodology and parameters _in the ODCM.

ACTION STATEMENTS ACTION 26 With less than the Minimum Channels 0PERABLE requi") ment, operation may continue provided-the containment purge valves are maintained-i closed.

ACTION 27 With the number of OPERABLE-channels less than the Minimum i-Channels OPERABLE requirement, within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> switch to the i

redundant train of Control Room Ventilation, provided the redundant train meets the Minimum Channels.0PERABLE requirement i

or isolate the Cont ol _ Room; Ventilation _ System and initiate operation of the Control Room Make up System.

Restore the inoperable monitors to OPERABLE--status within 30 days or. submit a Special Report;to the Commission pursuant to_ Specification 6.9.2_within-the following130 days that'provides the cause of the inoperability and the plans for: restoration.

}

ACTION 28 Must satisfy the ACTION requirement for Specification 3.4.6.1.

1 ACTION 29 With the number of OPERABLE channels one less than-the Minimum Channels OPERABLE. requirement, ACTION a.-of_ Specification 3;9.12 l

must be satisfied.

Witi both channels inoperable, provide an appropriate portable. continuous monitor with the'same: Alarm Set-i point in the fuel poollarea with one Fuel' Handling Building i

Exhaust filter plenum'in operation.

Otherwise: satisfy: ACTION b.

l of Specification 3.9.12.

I a

b k

i 1

1 BRAIDWOOD - UNITS 1 & 2 3/4 3-41 AMENDMENT NO. 37 i

,-....c.

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

a, TABLE 4.3-3 9;g RADIATION MONITORING INSTRUMENTATION FOR PLANT OPERATIONS SURVEILLANCE REQUIREMENTS 8

h DIGITAL 5

CHANNEL d

CHANNEL CHANNEL OPERATIONAL MODES FOR WHICH FUNCTIONAL UNIT CHECK CALIBRATION TEST SURVEILLANCE IS REQUIRED g

1.

Fuel Building Isolation-y Radioactivity-High and Criticality-(ORE-AR055/56)

S R

I' 2.

Containment Isolation-Containment Radioactivity-High a) Unit ~1 (IRE-AR011/12)

S R

M All

,g b) Unit 2 (2RE-AR011/12)

S R

M All

{

3.

Gaseous Radioactivity-RCS Leakage Detection m

a) Unit 1 (1RE-PR011B)

S R

M 1,2,3,4 b) Unit 2 (2RE-PR0118)

S R

H 1,2,3,4 4.

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

S R

M 1,2,3,4 b) Unit-2'(2RE-PR011A) 5 R

M 1,2,3,4 5.

Main Control Room Isolation-Outside Air Intake-Gaseous Radioactivity-High 3E a) Train A-(ORE-PR0318/328)

S R

M All b) Train B (ORE-PR033B/348)

S R

M All h

w g *With' new fuel or irradiated' fuel in the fuel storage areas or. fuel building.

O