ML20071F434
| ML20071F434 | |
| Person / Time | |
|---|---|
| Site: | Byron, Braidwood  |
| Issue date: | 06/30/1994 |
| From: | Capra R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20071F436 | List: |
| References | |
| NPF-37-A-062, NPF-66-A-062, NPF-72-A-052, NPF-77-A-052 NUDOCS 9407080219 | |
| Download: ML20071F434 (14) | |
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umTED STATES it,,gg,f l NUCLEAR REGULATORY COMMISSION
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-1 W A SHINoT ON D C 2M5 Mom COMMONWEALTH EDISON COMPA_!jl DOCKET NO. STN 50-454 BYRON STATION. UNIT NO. 1 AMENDMENT TO FACillTY OPERATING _ LICENSE Amendment No. 62 License No. NPF-37 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the licensee) dated March 7, 1994, as superceeded on March 24, 1994, 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 confornity with the application, the provisioos 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 shfety of the public, and (ii) that such activities will be conducted in conliance 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 r.hanges 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:
9407080219 940630 PDR ADOCK 050004541 P
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(2)
Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment No. 62 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 3 O 0.( Q Robert A. Capra, Director Project Directorate 111-2 Division of Reactor Projects - lil/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical-Specifications Date of issuance:
June 30, 1994 l
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UN11MD STATES t,,(1(0.
NUCLEAR REGULATORY COMMISSION
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COMMONWEALTH EDISDN COMPANY DOCKET NO. STN 50-455 BYRON STATION. UNIT t{L_l AMEN 0 MENT TO FAtl.LITY OPERATING LICENSE Amendment No. 62 License No. NPT-66 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Commonwealth Edison Company (the licensee) dated March 7, 1994, as superceeded on March 24, 1994, 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; E.
loe facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations; D.
The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Cominhsion'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:
. _. - _. (2)
Technical Specificjtions The Technical Specifications contained in Appendix A (NUREG-lll3),
as revised through Amendment No. 62 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. 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 NUCLEAR REGULATORY COMMISSION T U CL, Cc-f j Robert A. Capra, Director Project Directorate III-2 Division of Reactor Projects - Ill/IV Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance:
June 30, 1994
t ATTACHMENT TO LICENSE AMENDMENT NOS. 62 AND 62 i
FACILITY OPERATING LICENSE N05. NPF-37 AND NPF-66 CKET 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 captioned amendment number and contain marginal lines indicating the area of change.
Femove Paaes Insert Paaes-3/4 6-2 3/4 6-2 3/4 6-3 3/4 6-3 0
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CONTAINM{NT SYSTEMS CONTAINMENT LEAKAGE LIMITING CONDITION FOR OPERATION 3.6.1.2 Containment leakage rates shall be linited to:
a.
An overall integrated leakage rate of:
Less than or equal to L,44.4 psig, or,b.10%byweightofthecon 1) air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at P,,
2)
Less than or equal to L, 0.07% by weight of the containment air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for U-!41 (0.07% by weight of the containment air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for Urdt 2) at P,, 22.2 psig.
b.
A combined leakage rate of less than 0.60 L for all penetrations andvalvessubjecttoTypeBandCtests,whenpressurizedtoP,.
APPLICABILITY:
MODES 1, 2, 3, and 4.
ACTinN:
With either the measured overall integrated containment leakage rate exceeding 0.75 L, or 0.75 L,, as applicable, or the measured combined leakage rate for all penetrations and valves subject to Types B and C tests exceeding 0.60 L,,
restore the overall integrated leakage rate to less than 0.75 L, or less than 0.75 L, as applicable, and the mbined leakage rate for all penetrations subjecktolypeBandCteststoless than 0.60 L, prior to increasing the Peactor Coolant System temperature above 200*F.
SURVElllANCE RE0VIREMENU _ _
4.6.1.2 The containment leakage rates shall be demonstrated at the following test schedule and shall be determined in conformance with the criteria speci-fied in Appendix J of 10 CFR Part 50 using the methods and provisions of ANSI N45.4-1972:
a.
Type A (Overall Integrated Containment Leakage Rate) testing shall be conducted in accordance with the requirements specified in Appendix J to 10 CFR 50, as modified by approved exemptions; BYRON - UNITS 1 & 2 3/4 6-2 AMENDMENT NO. 62
I CONTAINMENT SYSTEMS SVRVEILLANCE RE0VIREMENTS (Continued) b.
If any periodic Type A test fails to meet either 0.75 L or 0.75 L,
the test scheQ1e for subsequent Type A tests shall be, reviewed an'd approved by the Commission.
If two consecutive Type A tests fail to meet 0.75 L a Type A test shall be performed at least every 18 months until, two consecutive Type A tests meet 0.75 L,;
c.
The accuracy of each Type A test shall be verified by a supplemental test which:
1)
Confirms the accuracy of the test by verifying that the supplemental test result, L, minus the sum of the Type A and the superimposed leak, L, Is equal to or less than 0.25 L, or 0.25 L,;
2)
Has a duration sufficient to stablish accurately the change in leakage rate between the Type A test and the supplemental test; and 3)
Requires that the rate at which gas is injected into the con-tainment or bled from the containment during the supplemental test is between 0.75 L, and 1.25 L,.
d.
Type B and C tests shall be conducted with gas at a pressure not less than P, 44.4 psig, at intervals no greater than 24 months except for testslnvolving:
1)
Air locks, and 2)
Purge supply u;d exhaust isolation valves with resilient material seals, e.
Air locks shall be tested and demonstrated OPERABLE by the require-ments of Specification 4.6.1.3; f.
Purge supply and exhaust isolation valves with resilient material seals shall be tested and demonstrated OPERABLE by the requirements of Specification 4.6.1.7.3 or 4.6.1.7.4, as applicable; and g.
The provisions of Specification 4.0.2 are not applicable.
BYROW - UNITS 1 & 2 3/4 6-3 AMENDMENT NO. 62 v
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UNITED STATES
( 5, jjg[. J NUCLEAR REGULATORY COMMISSION WAsHINGIOf 4 0 C. 2055MW1 COMMONWEALTH EDISON COMPAN1 DOCKET NO. STN 50-456 i
BRAIDWOOD STATION. 041T NO.l AMENDMENT TO FACIllTY OPERATING LICENSE Amendment No. 52 1.icense No. NFF-72 1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amer.dment by Ccmmonwealth Edison Company (the licensee) dated March 7,1994, as superceeded on March 24, 1994, 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 tne rules and regulations of the Commissicn; C.
There is reasonable assurance (i) that the activities authorized by this amendment car 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 amendaent will not l'e 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 chan0its to the Technical Specifi-cations as indicated in the attachment to this licenst amendment, and paragraph 2.C.(2) of facility Operating License No. NS-72 is heraby amended to read as follows:
= (2)
Technical Specifications The Technical Specifications contained in Appendix l, at revised through Amendment No. 52 and the Environmental Protec tion Plan contained in Appendix B, both of which are attached tireto, are hereby incorporated into this license.
The licensee sie,:1 eperate the far41D y in accordance with the Technical Specifica irnt and the Environmental Protection Plan.
3.
This iense amendment is effective as of the date of its issuance.
FOR T'IE NUCLEAR REGULATORY COMMISSION lH I 1 (p i
Robert A. Capra, Director
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Projec Directorate 11'-2 Divis* o nf Reactor Projects - lil/IV
- Offi, if 0,. lear Reactor Regulation
Attachment:
Changes to the Ttchnical Specifications Dat. of Issuance:
June 30, 1994 s
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WASHINGTON D C. ?Mn-ex t COMMONWEALTH EDISON COMPANY DOCKET NO. STN 50-457 BRAIDWOOD STATION. UNIT NO. 2 AMENDMENT TO FACILITf OPERATING LICENSE Amendment No. 52 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 March 7, 1994, as superceeded on March 24, 1994, 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 witt 'he application, the provisions of the Act, and the rules and regui.tions of the Commission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and saf ety of the public, and (ii) that such activities will be conducted in compliance with the Ccmn 5sion's regulations; 4
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:
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(2)
Technical Specifications The Technical Specifications contained in Appendix A as revised through Amendment tio. 52 and the Environmental Protection Plan contained in Appendix B, both of which were attached to License in, f1Pf-72, dated July 2,1987, are hereby incorporated into this l uense.
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 if its issuance.
FOR THE fiUCLEAR REGULATORY COMMISS10f4 7Ca. Cp Robert A. Capra, Director Project Directorate 111-2 Division of Reactor Projects - Ill/IV Office of flutlear Reactor Regulation
Attachment:
Changes to the Technical Spec 1fications Datt of 1ssuance: June 30. 1994
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ATTACHMENT TO LICENSE AMENDMENT NOS. 52 AND 52 t
FACILITY OPERATING LICENSE NOS. NPF-72 AND NPF-77 DOCKET NOS. STN 50-45E_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 6-2 3/4 6-2 3/4 6-3 3/4 6-3
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RDNTAINMENT SYSTEMS g
CONTAINMENT LEAKAGE LIMITING CONDITION FOR OPERATION 3.6.1.2 Containment leakage rates shall be limited to:
a.
An overall integrated leakage rate of:
, 0.10% by weight of the containment Less than or equal to L 41.4 psig, or 1) air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> at P,,
2)
Less than or equal to L, 0.07% by weight of the containment airper24hoursforUnIt1(0.07%byweightofthecontainment l
air per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> for Unit 2) at P,, 22.2 psig, b.
A combined leakage rate of less than 0.60 L for all penetrations andvalvessubjecttoTypeBandCtests,whenpressurizedtoP,.
APPLICABIllTY: MODES 1, 2, 3, and 4.
ACT10fj:
With either the measured overall integrated containment leakage rate exceeding 0.75 L, or 0.75 L, as applicable, or the measured combined leakage rate for i
all penetrations and vahes subject to Types B and C tests exceeding 0.60 L,,
restore the overall integrated leakage rate to less than 0.75 L, or less than 0.75 L, as applicable and the combined leakage rate for all penetrations subjeck to Type B and L tests to less than 0.60 L, prior to increasing the Reactor Coolant System temperature a'ove 200*F.
SURVElitANCE Rf001REMENTS 4.6.1.2 The containment leakage rates shall be demonstrated at the following test schedule and shall be determined in conformance with the criteria speci-fled in Appendix J of 10 CFR Part 50 using the methods and provisions of ANSI N45.4-1972:
a.
Type A (Overall Integrated Containment Leakage Rate) testing shall be conducted in accordance with the requirements specified in Appendix J to 10 CFR 50, as radified by approved exemptions; 1
BRAIDWOOD - UNITS 1 & 2 3/4 6-2 AMENDMENT NO. 52 1
_ _ _ _ _ _ _ _ _ _ ~ _ _
CONTAINMENT-SVSTEMS y
SURVEILLANCE RE0VIREMENTS (Continued) b.
If any periodic Type A test fails to meet either 0.75 L or 0.75 L,
the test schedule for subsequent Type A tests shall be, reviewed an*d approved by the Commission.
If two consecutive Type A tests fail to meet either 0.75 L or 0.75 L, a Type A test shall be performed at leastevery18monthsuntilt,woconsecutiveTypeAtestsmeeteither 0.75 L, or 0.75 L,;
l c.
The accuracy of each Type A test shall be verified by a supplemental test which:
1)
Confirms the accuracy of the test by verifying that the supplemental test result, L, is in accordance with the appropriatefollowingequation:
~
l L, - ( L,, + L,) l s 0. 25 L, or l L, - ( L,, + L,) l 1 0. 2 5 L, where L,, impose,d leak;is the measured Type A test leakage and L, is or L i the super 2)
Has a duration sufficient to establish accurately the change in leakage rate between the Type A test and tha supplemental test; and 3)
Requires that the rate at which gas is injected into the con-tainment or bled from the containment during the supplemental test is between 0.75 L, and 1.25 L, or 0.75 L, and 1.25 L,.
d.
Type B and C tests shall be conducted with gas at a pressure not less than P,, 44.4 psig, at intervals no greater than 24 months except for tests involving:
1)_
Air _ locks, and 2)
Purge supply and exhaust isolation valves with resilient material seals, e.
Air locks shall be tested and demonstrated OPERABLE by the require-ments of Specification 4 6.1.3; f.
Purge supply and exhaust isolation valves with resilient material seals shall be tested and demonstrated OPERABLE by the requirements J Specification 4.6.1.7.3 or 4.6.1.7.4, as applicable; and g.
The pavisions of Specification 4.0.2 are not applicable.
BRAIDWOOD - UNITS 1 & 2 3/4 6-3 AMENDMENT N0. 52 l
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