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
MONTHYEARML20217N3631999-10-13013 October 1999 Amends 111,111,104 & 104 to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,respectively,revising Requirements Related to cross- Tie DC Power Buses Between Units & Removing Refs to At&T Batteries Which Have Been Replaced at Braidwood Station ML20212A6801999-09-0909 September 1999 Corrected Tech Spec Pages 4 to Amends 110 & 110 to Licenses NPF-37 & NPF-66,correcting License Conditions 2.C(17) & 2.C(6) ML20211A8071999-08-10010 August 1999 Amends 110 & 110 to Licenses NPF-37 & NPF-66,respectively, Deleting License Conditions Which Have Been Satisfied, Revising Others to Delete Parts No Longer Applicable or to Revise References & Making Editorial Changes ML20209B7301999-06-30030 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 ML20207F1181999-06-0202 June 1999 Amend 102 to Licenses NPF-72 & NPF-77,revising TS 3.9.3 Re Use of Gamma-Metrics post-accident Source Range Neutron Flux Monitors as Alternative to Westinghouse Source Range Neutron Flux Monitors During Mode 6 Operations (Refueling) ML20206G5961999-05-0303 May 1999 Amends 108,108,101 & 101 to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,respectively,revising TS Requirements for Spent Fuel Pool Inadvertent Draindown Elevation ML20206B5451999-04-23023 April 1999 Amends 107 & 107 to Licenses NPF-37 & NPF-66,respectively, Changing TS Tables 3.3.1-1 & 3.3.2-1,to Revise Allowable Values for 12 Functions of RTS & ESFAS ML20206B6841999-04-23023 April 1999 Amends 100 & 100 to Licenses NFP-72 & NPF-77,respectively, Changing TS Tables 3.3.1-1 & 3.3.2-1,to Revise Allowable Values for 12 Functions of RTS & Efsas 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 ML20195D5081998-11-0404 November 1998 Errata to Amends 96 & 96 to Licenses NPF-72 & NPF-77, Respectively,Correcting TS Page 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 ML20154P1571998-10-15015 October 1998 Amends 97 & 97 to Licenses NPF-72 & NPF-77,respectively, Revising TS Re non-accessible Area Exhaust Filter Plenum Ventilation Sys to Reflect Design Lineup 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 ML20248E0221998-05-26026 May 1998 Amends 103 & 103 to Licenses NPF-37 & NPF-66,respectively, Revising Surveillance Frequency for Turbine Throttle Valves & Turbine Govern Valves from Monthly to Quarterly ML20248F4521998-05-26026 May 1998 Amends 93 & 93 to Licenses NPF-72 & NPF-77,respectively, Revising Surveillance Frequency for Turbine Throttle Valves & Turbine Governor Valves from Monthly to Quarterly ML20216C1161998-05-0808 May 1998 Amends 102 & 102 to Licenses NPF-37 & NPF-66,respectively, Deferring Next Scheduled Type a Containment Integrated Leak Rate Test for Plant,Unit 2,until Next Refueling Outage in 1999 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 ML20203A2751998-02-0303 February 1998 Amends 101 & 101 to Licenses NPF-37 & NPF-66,respectively, Reflect Forthcoming Replacement of Original Steam Generators ML20203B7231998-02-0303 February 1998 Amends 92 & 92 to Licenses NPF-72 & NPF-77,respectively, Revise TS to Reflect Forthcoming Replacement of Original Steam Generators ML20199E6871998-01-29029 January 1998 Amends 99,99,90 & 90 to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,respectively,revising TSs to Update Containment Vessel Structural Integrity to Meet Provisions of Recent Rev to 10CFR50.55a ML20199K4681998-01-23023 January 1998 Amends 89 & 89 to Licenses NPF-72 & NPF-77,respectively, Relocating RCS Pressure & Temperature Limits for Heatup, Cooldown,Low Temperature Operation & Hydrostatic Testing & Associated LTOP Sys Setpoint Curves ML20199J0281998-01-23023 January 1998 Amends 98 & 98 to Licenses NPF-37 & NPF-66,respectively, Relocating,Rcs Pressure & Temperature Limits for Heatup, Cooldown,Low Temperature Operation & Hydrostatic Testing & LTOP Sys Setpoint Curves ML20199F3631998-01-22022 January 1998 Amends 97 & 97 to Licenses NPF-37 & NPF-66,respectively. Amends Revise TS & Associated Bases Re Primary Containment Pressure & Reactor Coolant Sys Volume ML20199H7861998-01-22022 January 1998 Amends 88 & 88 to Licenses NPF-72 & NPF-77,respectively, Revising TS & Associated Bases Re Primary Containment Pressure & RCS Vol ML20199D2441998-01-15015 January 1998 Amends 87 & 87 to Licenses NPF-72 & NPF-77,respectively, Changing TS Requirements for SG Water Level to Support SG Replacement ML20199C1651998-01-15015 January 1998 Amends 96 & 96 to Licenses NPF-37 & NPF-66,respectively, Changing TS Requirements for SG Water Level to Support SG Replacement at Plant 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 ML20198B5691997-12-12012 December 1997 Amends 95 & 95 to Licenses NPF-37 & NPF-66,respectively, Changing TS 3/4.7.5, UHS & Associated Bases to Support SG Replacement & Incorporate Recent UHS Design Evaluations ML20203F6511997-12-0404 December 1997 Amends 86 & 86 to Licenses NPF-72 & NPF-77,respectively, Granting Partial Credit for Boron in Spent Fuel Pools to Maintain Subcriticality ML20203D3581997-12-0404 December 1997 Amends 94 & 94 to Licenses NPF-37 & NPF-66,respectively, Granting Partial Credit for Boron in Spent Fuel Pools to Maintain Subcriticality ML20202E5711997-11-25025 November 1997 Amends 93 & 93 to Licenses NPF-37 & NPF-66,respectively, Revising TS to Permit Installation & Use of C&D Charter Power Sys,Inc,Batteries 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 ML20210K4051997-08-13013 August 1997 Amends 92 & 92 to Licenses NPF-37 & NPF-66,respectively, Authorizing Change to Realistic Dose Values for Process Gas Sys Rupture in Section 15.0 of Plant UFSAR ML20210M6581997-08-13013 August 1997 Amend 84 to License NPF-77,revising TS 4.5.2.b.1 to Clarify That Venting Only Required on ECCS Subsystems That Are Idle or Stagnant ML20210K7021997-08-13013 August 1997 Amend 91 to License NPF-66,revising TS 4.5.2.b.1 to Clarify That Venting Only Required on ECCS Subsystems That Are Idle or Stagnant ML20210K9661997-08-13013 August 1997 Amends 85 & 85 to Licenses NPF-72 & NPF-77,respectively, Authorizing Change to Realistic Dose Values for Process Gas Sys Rupture in Section 15.0 of Plant UFSAR ML20149B7561997-07-10010 July 1997 Amends 91,90,84 & 83 to Licenses NPF-37,NPF-66,NPF-72 & NPF-77,respectively,revising TS 3.6.3, Containment Isolation Valves, to Reflect Mods Associated W/Sg Replacement for Unit 1 of Each Station 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 ML20148F6661997-06-0101 June 1997 Amend 90 to License NPF-37,revises TS 4.5.2.b.1 to Include Use of UT to Verify That ECCS Completely Filled W/Water 1999-09-09
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Commonwealth Edison N
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, 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 8
9 Of fice of Nuclear Reactor Regulation U.S.
Nuclear Regulatory Commission NECElVED p]
APR 221982m-b' Washington, DC 20555 mIky #
Subject:
Byron Station Units 1 and 2 28 Cons truction Permit Ex tensio n E
NRC Docket Nos. 50-454 ano 50-455 9
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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 shouldg(
any unanticipater1 delays in construction actually occur.
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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, L
.d J 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
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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, CPPR-130 - UNIT 2, CPPR-131, DOCKET NOS. 50-454, 50-455 t
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
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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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