Similar Documents at Byron |
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Category:CONSTRUCTION PERMITS-APPLICATION & AMENDMENTS TO APP
MONTHYEARML20154A3571986-02-27027 February 1986 Application to Amend CPPR-131,revising Latest Const Completion Date to 870601 Due to Extended Const & Turnover for Testing Periods.Fee Paid ML20138A0061985-09-25025 September 1985 Application for Amends to CPPR-131,CPPR-132 & CPPR-133, Incorporating Partial Exemption from GDC 4 to Allow Implementation of leak-before-break Concept on RCS Primary Loops.Fee Paid ML20094P2141984-08-13013 August 1984 Application to Amend CPPR-30,extending Permit to 850101 to Cover Time for OL Hearings & Issuance ML20027A9231982-09-0202 September 1982 Application for Amend to CPs & Ols,Consisting of Amend 39 to FSAR ML20054D6131982-04-19019 April 1982 Application for Amend of CPPR-130 & CPPR-131,extending Completion Date from 820601 to 841001 for Unit 1 & from 831101 to 860401 for Unit 2.EIA Supporting Extension Request Encl ML20050B8231982-03-31031 March 1982 Application to Amend CPs & OLs Consisting of Amend 37 to Fsar.Amend Consists of Responses to Questions from Various Branches within NRR ML20003D7451981-03-20020 March 1981 Amend 30 to FSAR Revising Chapters 4 & 15 & Sections 1.3,1.6 & 6.2.1.5 1986-02-27
[Table view] Category:CONSTRUCTION PERMITS-APPLICATION TO AMEND EXISTING CP
MONTHYEARML20154A3571986-02-27027 February 1986 Application to Amend CPPR-131,revising Latest Const Completion Date to 870601 Due to Extended Const & Turnover for Testing Periods.Fee Paid ML20138A0061985-09-25025 September 1985 Application for Amends to CPPR-131,CPPR-132 & CPPR-133, Incorporating Partial Exemption from GDC 4 to Allow Implementation of leak-before-break Concept on RCS Primary Loops.Fee Paid ML20094P2141984-08-13013 August 1984 Application to Amend CPPR-30,extending Permit to 850101 to Cover Time for OL Hearings & Issuance ML20027A9231982-09-0202 September 1982 Application for Amend to CPs & Ols,Consisting of Amend 39 to FSAR ML20054D6131982-04-19019 April 1982 Application for Amend of CPPR-130 & CPPR-131,extending Completion Date from 820601 to 841001 for Unit 1 & from 831101 to 860401 for Unit 2.EIA Supporting Extension Request Encl ML20050B8231982-03-31031 March 1982 Application to Amend CPs & OLs Consisting of Amend 37 to Fsar.Amend Consists of Responses to Questions from Various Branches within NRR 1986-02-27
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML20209B7301999-06-30030 June 1999 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,providing Correction to LCO Associated with TS Section 3.8.5, DC Sources - Shutdown & Deleting Various References to At&T Batteries in Braidwood TS Section 3.8 ML20204H9661999-03-23023 March 1999 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,revising TSs to Support Installation of New Boral high-density SFP Storage racks.Non-proprietary & Proprietary Info Encl.Proprietary Info Withheld.Per 10CFR2.790 ML20204H4211999-03-22022 March 1999 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,allowing Use of Gamma-Metrics post-accident Neutron Monitors to Provide Neutron Flux Info During Operational Mode 6 ML20198N3351998-12-29029 December 1998 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,revising Twelve RTS & ESFAS Allowable Values Contained in ITS Table 3.3.1-1 & Table 3.3.2-1 ML20195J4101998-11-19019 November 1998 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,revising App C,Addl License Conditions,By Deleting & Adding License Conditions as Stated.Marked Up App C Pages, Encl ML20155H9941998-10-30030 October 1998 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,revising TS Design Features Description Contained in Section 5.6.2 ML20248C5301998-05-29029 May 1998 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,revising TS Bases Section 3/4.4.4, Relief Valves to Credit Automatic Function of PORVs to Provide Mitigation for Inadvertent Operation of ECCS ML20217E1771998-03-24024 March 1998 Application for Amends to Licenses NPF-37 & NPF-66,revising TS Surveillance Sections & Bases to Allow Util to Defer 10CFR50,App J Type a Testing of Byron Unit 2 Containment Until Next Refuel Outage in 1999 ML20198C2961997-12-30030 December 1997 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,revising TS 3.7.1.3, Condensate Storage Tank & Associated Bases for Plants to Raise Min Allowable CST Level ML20198H7521997-12-29029 December 1997 Errata to Amend 94 & 94 to Licenses NPF-37 & NPF-66, Correcting Typo That Was Inadvertently Introduced on TS Page 5-5 ML20199A4651997-11-0707 November 1997 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,respectively.Amends Would Revise TS Surveillance Sections 4.6.1.1.c,4.6.1.2.a,4.6.1.2.b & Bases to Allow Performance of 10CFR50 App J,Type a Testing ML20198J9301997-10-16016 October 1997 Application for Amend to License NPF-37,requesting Exemption from Requirements of 10CFR70.24(a), Criticality Accident Requirements. Request Is Being Docketed to Reflect Units 1 & 2 So That Amend Numbers Remain Identical ML20202F4481997-10-10010 October 1997 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,requesting to Convert Byron & Braidwood Current Tech Specs to Byron & Braidwood Improved Tech Specs ML20211D9341997-09-24024 September 1997 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,respectively,revising Allowable Time Interval for Performing Turbine Throttle valve.Non-proprietary & Proprietary Trs,Encl.Proprietary Info Withheld ML20216G8341997-09-0808 September 1997 Application for Amend to TS 4.5.2.b & Associated Bases to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,respectively,to Bring Byron Unit 1 & Braidwood Unit 1 Requirement in Conformance W/Unit 2 Requirements Approved by NRC in ML20148P7041997-06-30030 June 1997 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,revising TS Section 3.9.11,5.6.1.1 & 6.9.10 to Allow Util to Take Credit for Soluble B in Spent Fuel Storage Pool Water to Maintain Acceptable Margin of Subcriticality ML20141F3041997-06-24024 June 1997 Suppl to 970524 Application for Amends to Licenses NPF-66 & NPF-77,revising TS 4.5.2.b Re Venting of ECCS Pump Casings & Discharge Piping High Points Outside of Containment.Proposed Changes to Bases Revised to Delete Ref to Pressure ML20141B7551997-06-17017 June 1997 Application for Amend to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,revising TS Sections 3/4.6.1.6,4.6.1.2,6.8.4 & 6.9.1.11 to Support New Requirements in 10CFR50.55a ML20148J3031997-06-0909 June 1997 Application for Amend to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,reflecting Latest Rev of Waste Gas Decay Accident Dose Calculation ML20140D0011997-05-31031 May 1997 Suppl to 970523 Application for Exigent Amend to License NPF-37,revising TS Surveillance Requirement Re ECCS Pump Casings & Discharge Piping High Points Outside of Containment ML20141K8961997-05-24024 May 1997 Application for Exigent Amends to Licenses NPF-37,NPF-66 & NPF-77,revising TS Surveillance Requirement 4.5.2.b to Encompass non-operating ECCS Pumps & Discharge Piping Which Are Provided W/High Point Vent Valves ML20141J9781997-05-21021 May 1997 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,requesting to Allow Licensee Control of RCS Pressure & Temp Limits for Heatup,Cooldown,Low Temp Operation & Hydrostatic Testing ML20148B6071997-05-0606 May 1997 Application for Amends to TS of Licenses NPF-37 & NPF-66, Revising TS 3/4.7.5, Ultimate Heat Sink & Associated Bases to Support SG Replacement & Incorporate Recent UHS Design Evaluations ML20196G0401997-04-25025 April 1997 Suppl to 970130 Application for Amends to Licenses NPF-37, NPF-66,NPF-72 & NPF-77,revising TS for Containment & RCS Vol.Encl marked-up Improved TS Pages Were Not Included in Original Submittal ML20137S5241997-04-0707 April 1997 Application for Amends to Licenses NPF-37 & NPF-66,revising TS 3/4.8.2 to Allow Replacement of 125 Volt Dc Gould Batteries W/New C&D Charter Power Systems Inc Batteries ML20137N9801997-03-24024 March 1997 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,removing Values of cycle-specific Core Operating Limits from TS & Relocating Values to Operating Limit Rept ML20137C5991997-03-14014 March 1997 Application for Amends to Licenses NPF-37 & NPF-66,reducing Allowable Unit 1 RCS Dose Equivalent I-131 from 0.35 Uci/ Gram to 0.20 Uci/Gram for Remainder of Cycle 8 ML20137C7911997-03-14014 March 1997 Application for Amends to Licenses NPF-37 & NPF-66,deleting 12 License Conditions from Unit 1 Operating License & Two License Conditions from Unit 2 Operating License ML20135E6791997-02-28028 February 1997 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,replacing Original Westinghouse D4 SG at Byron & Braidwood W/B&W International SGs ML20135B5571997-02-24024 February 1997 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,from Current TS to Improved TS Consistent w/NUREG-1431,Rev 1, STS - W Plants, Dtd Apr 1995 ML20134N8381997-02-18018 February 1997 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,requesting Rev to Support Steam Generator Replacement ML20134F3751997-01-31031 January 1997 Application for Amends to Licenses NPF-37 & NPF-66,revising TS Bases 3.4.8 to Reduce Allowable Reactor Coolant Sys Dose Equivalent I-131 from 0.35 Uci/G to 0.20 Uci for Remainder of Cycle 8 ML20134E8451997-01-30030 January 1997 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77 to Revised TS 1.0, Definitions, 3/4.6.1, Primary Containment & Associated Bases & 5.4.2, Reactor Coolant Sys Volume, for Bs & Bs to Support SG Replacement ML20134D0321997-01-20020 January 1997 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,revising TS Section 3.6.3 Containment Isolation Valves for Byron & Braidwood Unit 1 to Support Replacement of Original W Model D4 SGs W/Babcock & Wilcox Intl SGs ML20133B5851996-12-13013 December 1996 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77 Requesting Conversion to Improved Standard TSs ML20134N7661996-11-0505 November 1996 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,revising TS 3.9.11,5.6.1.1 & 6.9.1.10 to Allow Util to Take Credit for Soluble Boron in Spent Fuel Pool Water in Maintaining Acceptable Margin of Subcriticality ML20132A0241996-11-0404 November 1996 Application for Amends to Licenses NPF-37 & NPF-72,revising TS 3.6.1.6 to Allow one-time Exemption to Requirements of SR 4.6.1.6.1.e.1 ML20117D1451996-08-23023 August 1996 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77 Requesting Rev to Appendix a TS 3/4.7.7, Non-Accessible Area Exhaust Filter Plenum Ventilation Sys ML20117J0141996-08-19019 August 1996 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,respectively,renewing 3.0 Volt Bobbin Coil Probe,Sg TSP Interim Plugging Criteria Limit for Outside Diameter Stress Corrosion Cracking ML20116F0791996-08-0202 August 1996 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,eliminating Corrosion Testing Requirement for SG Tube Sleeving ML20108E7791996-04-29029 April 1996 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,revising TS Section 3/4.7.1, Turbine Cycle Safety Valves & Associated Bases ML20100L2271996-02-27027 February 1996 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,respectively,implementing 10CFR50,App J,Option B That Allows Use of Performance Based Surveillance Frequencies for Type A,B & C Tests Rather than Predetermined Intervals ML20100H8841996-02-21021 February 1996 Submits Suppl Info Re Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,respectively,proposing to Revise Ten of Line Item TS Improvements Recommended by GL 93-05 ML20096C0161996-01-11011 January 1996 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,respectively,revising TS 3.3.1, Rt Sys Instrumentation, Table 3.3-1,Functional Unit 6, Source Range,Neutron Flux, Consistent W/Improved STS ML20095J5081995-12-21021 December 1995 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,expanding Plant Operating Limits Rept to Include Limits Suggested by GL 88-16, Removal of Cycle-Specific Parameter Limits from Ts ML20095D6191995-12-0606 December 1995 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,revising TS Section 3/4.6.1, Primary Containment, to Incorporate Requirements of Revised 10CFR50,App J,Which Became Effective on 951026 ML20098C6751995-10-0303 October 1995 Application for Amends to Licenses NPF-37 & NPF-66,revising Allowable Time Intervals for Performing Certain TS Surveillance Requirements on Plant Components During Power Operation,Per GL 93-05 ML20098A3851995-09-20020 September 1995 Suppl Application for Amends to Licenses NPF-37,NPF-66, NPF-72 & NPF-77,modifying TS 3.6.1.7, Containment Purge Ventilation Sys ML20092H3151995-09-14014 September 1995 Application for Amends to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,revising TS 5.3.1, Fuel Assemblies to Allow Use of Alternate Zirconium Based Fuel Cladding,Zirlo & TS 5.4.1.a to Refer to UFSAR Rather than FSAR ML20087E2521995-08-11011 August 1995 Suppl to Application for Amends to Licenses NPF-37,NPF-66, NPF-72 & NPF-77,revising TS 3.6.1.7, Containment Purge Ventilation Sys 1999-06-30
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,- / N Commonwealth Edison l , on) First National Plata. Chicago. Illinois
( l Addr:ss R; ply to: Post O'fice Box 767
,- Chicago, Illinois 60690 April 19, 1982 N
O t Mr . Ha rold R . Denton, Director Of fice of Nuclear Reactor Regulation 8 9 U.S. Nuclear Regulatory Commission NECElVED Washington, DC 20555 p]
APR 221982m- b' mIky #
Subject:
Byron Station Units 1 and 2 Cons truction Permit Ex tensio n E 28 NRC Docket Nos. 50-454 ano 50-455
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9 References (a): December 31, 1975 letter from D. B. Vassallo to Byron Lee, Jr.
Dear Mr. Denton:
Pursuant to the provisions of 10 CFR 50.55(b), Commonwealth Edison hereby requests amendment of the Byron Station Construction Permits CPPR-130 and CPPR-131 issued by reference (a). For the reasons delineated below, we request that tne " latest completion date" be revised from June 1, 1982 to October 1, 1984 for Byron Unit 1 and from November 1, 1983 to April 1, 1986 for Byron Unit 2. Thi s amendment involves only a change to construction completion dates.
In our opinion it does not involve a significant hazard consideration.
The need for an extension of time oeyond the present construction permit completion dates is a result of an extended construction period, despite the fact that construction has continued without interruption since its inception. The longer period has resulted principally from the need to install larger quantities of material and equipment than originally contemplated as well as changes in NRC regulatory requirements, some o f which resulted from the NRC's response to the Three Mile Island incident.
The need for extension is also based upon improvements in the manner in which we are implementing NRC requirements. These changes have increased the amount of design work and installation labor required to complete the installation of each component, pipe, cable, and structural memoer. These additional measures have been and are being implemented a t a pace consistent with the Company 's need to spread financing requirements more evenly throughout the construction period in order to keep annual financing requirements within the Company's capabilities.
Although the requested revised completion dates extend beyond the dates by which Edison currently expects to load fuel at Byron Units 1 and 2, this letter does not represent a change to the current fuel load schedules. The revised completion dates reflect a conservative estimate of actual completion of the units. This has been done to avoid the necessity o f having to request another construction completion date extension at some future time should any unanticipater1 delays in construction actually occur.
i g(
g 82042306p
H. R. Denton April 19, 1982 r
i Attached is a proposed " Finding of No Significant Impact" prepared by Commonwealth Edison tc address the environmental impact of the extension of these construction permits.
Three (3) signed originals and thirty-seven (37) copies of this submittal are provided for your review and approval.
Enclosed is a check in the amount of $1600, submitted in -
accordance with the fee schedule defined in 10 CFR 170.22.
Very truly yours,
.d LJ L. O. DelGeo rg e Director of Nuclear Licensing
. Im !
SUBSCHIBED and SWOR to before me thish Jay of h ;* L , 1982
" ~ ~
& L 0- 4fr ) u Notary Public
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a ENV IRO NMENTA L IMPACT APPRAISAL SUPPORTING THE REQUEST FOR EXTENSION OF THE DATES FOR COMPLETION OF CONSTRUCTION OF BYRON STATION, UNITS 1 AND 2. COMMONWEALTH EDISON. UNIT 1, t CPPR-130 - UNIT 2, CPPR-131, DOCKET NOS . 50-454, 50-455
- 1. Description or Proposed Action The action requested is the issuance of an ORDER pertaining to Byron Station Units 1 and 2. The ORDER would extend the latest completion date of Unit 1 by 28 months and the latest completion date of Unit 2 by 28 months .
- 2. Summary Description of the Probable Impacts of the Proposed Action The environmental impacts associated with construction of Byron have been previously addressed in the NRC staff's final environmental statement, construction permit stage (FES-CP) issued February , 1974, and determined by the Atomic Safety and Licensing Board in their partial initial decision-Environmental and Site Suitability Matters dated December 6, 1974.
The Atomic Safety and Licensing Board identified in the Initial Decision the following major ef fects due to construction:
A. Station related construction will disturb 300 acres of the site. Of this, 150 acres would serve as an improved habitat for small mammals, deer and birds, owing to the exclusion of farmers and hunters.
B. Construction activities of the intake and discharge structures will have a temporary effect upon the Rock
] River due to siltation caused by dredging.
C. Construction of the station and development on the 300
< Ore site will generate noise and dust.
5 D. Dewatering of the construction site will have an
- effect on groundwater.
- E. Short-term traffic problems may occur due to construction activities.
F. Transmission line construction associated with station development will create minor impacts.
G. Impacts may occur to eight acres on the pipeline corridor due to construction which were tentatively identified to contain possible archeological artifacts.
It was recommended that these areas be tested for archeological significance prior to pipeline corridor construction.
H. Area surface runoff from the construction site may have an impact upon streams of the area.
With respect to Item A, the extension of construction activities on the site would delay the return of the 150 acres not used for station facilities back to agriculture productiveness or restoration to a natural state.
Construction related effects identified in Items B and D noted above have already occurred, were monitored and the effects were found to be localized. Therefore, the construction permit extensions would not add impacts in these areas.
In relation to construction e f fect C noted above: major excavations and structures, the make-up and blowdown pipelines, and ancillary structures are completed and additional noise and dust would not be generated as a result of extending the con-struction permit. The granting of the required construction permit extension would extend noise and dust from other sources such as parking lots for construction workers and construction roads. These sources are, however, continually treated for dust control.
With respect to Item E, listed above, the construction work force has already reached a maximum and is now declining.
With respect to Item F, three transmission lines are to be cons tructed for Byron Station. The Byron East transmission line is partially completed (the 6.5 mile portion extending east from the station to the Nelson-Cherry Valley transmission line is complete and the remaining 15.3 miles to the Cherry Valley Transmission Substation is scheduled to be constructed in 1983). The Byron South transmission line is under construction and will be completed in 1982. The Byron Wempleton transmission line construction has started and will be completed in 1983.
The extension of the construction schedule will delay the minor impacts of construction discussed in the Atomic Safety and Licensing Initial Decision. Less land will be committed due to the selection and use of single shaf t structures for tangent and light angles (up to 130) rather than the wide based lattice steel towers specified in the original environmental report, thus reducing the impact on farming activities.
Item G recommended testing of the eight identified archeological sites on the pipeline corridor. Further investigations of the sites showed that three were of archeological importance. These sites have been, and will continue to be, protected from construction impacts. The remaining five were found to consist of only scattered surf ace finds and the archeological consultant and the State Historic Preservation of ficer determined that protection from construction impact was not required. An exten-slon of the construction permit will not result in additional impacts to archeological resources.
With respect to Item H, area surface runof f due in part to
- construction is circulated through an oil separator to the wastewater collection basin where suspended solids settle out
! prior to discharge. A construction permit extension would extend the period that construction related runoff would be treated and released. Frequent discharges of water into the Woodland Creek have affected two landowners downstream from the plant. .These effects have been mitigated by installation of culverts in the motocross raceway area and a bridge over the creek in a subdivision. The quantity of water from precipita-tion discharged is no longer a fontion of construction activities.
- 3. Conclusion and Basis for Finding of No Significant Impact On the basis of the above, it is our opinion that there will be no significant impacts attributable to the requested action. ,
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