Letter Sequence Approval |
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Results
Other: A04104, Forwards Overview Re Appeal for Requested Mod of Hydrogen Purge Sys Valves to Close on Radiation Signal,Per Generic Ltr 84-08 & NUREG-0737,Item II.E.4.2.7, Containment Venting at Power. Addl Info Re Leakage Testing Expected by 840730, B11269, Forwards Figure 3.1,per Re NUREG-0737,Item II.E.4.2.7, Containment Venting at Power, Providing Justification That Isolation Logic for Hydrogen Purge Valves Adequate, ML20004B640, ML20008E564, ML20078N847, ML20134A587, ML20134A599, ML20137A490, ML20137B423, ML20137B442
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MONTHYEARML20008E5641981-02-27027 February 1981 Provides Justification for Min Containment Pressure Used to Initiate Containment Isolation for Facility,Per NRC 801231 Request Re NUREG-0737.Present Containment Isolation Setpoint Is Adequate & No Reduction in Setpoint Is Warranted Project stage: Other ML20004B6401981-05-20020 May 1981 Advises That No Mods Will Be Made to TMI Action Plan Item II.E.4.2 Re Containment Isolation Dependability.Signals Used for Containment Isolation Are Redundant & Diverse & Adequate to Ensure Safe Operation Project stage: Other A03035, Forwards Response to NRC Request for Addl Info Re Operability of 6-inch Butterfly Containment Purge & Vent Valves.Based on Analyses,Adequate Justification Does Not Exist to Warrant Mods to Equipment1983-03-28028 March 1983 Forwards Response to NRC Request for Addl Info Re Operability of 6-inch Butterfly Containment Purge & Vent Valves.Based on Analyses,Adequate Justification Does Not Exist to Warrant Mods to Equipment Project stage: Request ML20078N8471983-10-27027 October 1983 Forwards Response to NRC 830902 Comments on Unresolved Items Re Containment Purge/Vent Review.No Addl Tech Specs or Equipment Mods Warranted.Operability Requirement Met W/Compliance W/Tmi Item II.E.4.2 Project stage: Other A03992, Requests Informal Appeal Meeting W/Nrc to Review Requested Mod of Hydrogen Purge Valves to Close on High Radiation Signal,Per Generic Ltr 84-08 & NUREG-0737,Item II.E.4.2.71984-05-15015 May 1984 Requests Informal Appeal Meeting W/Nrc to Review Requested Mod of Hydrogen Purge Valves to Close on High Radiation Signal,Per Generic Ltr 84-08 & NUREG-0737,Item II.E.4.2.7 Project stage: Meeting A04104, Forwards Overview Re Appeal for Requested Mod of Hydrogen Purge Sys Valves to Close on Radiation Signal,Per Generic Ltr 84-08 & NUREG-0737,Item II.E.4.2.7, Containment Venting at Power. Addl Info Re Leakage Testing Expected by 8407301984-07-11011 July 1984 Forwards Overview Re Appeal for Requested Mod of Hydrogen Purge Sys Valves to Close on Radiation Signal,Per Generic Ltr 84-08 & NUREG-0737,Item II.E.4.2.7, Containment Venting at Power. Addl Info Re Leakage Testing Expected by 840730 Project stage: Other B11269, Forwards Figure 3.1,per Re NUREG-0737,Item II.E.4.2.7, Containment Venting at Power, Providing Justification That Isolation Logic for Hydrogen Purge Valves Adequate1984-07-13013 July 1984 Forwards Figure 3.1,per Re NUREG-0737,Item II.E.4.2.7, Containment Venting at Power, Providing Justification That Isolation Logic for Hydrogen Purge Valves Adequate Project stage: Other ML20133E7071985-10-0303 October 1985 Forwards Structural & Geotechnical Engineering Branch Request for Addl Info to Complete Review of 850724 Application to Modify Tech Specs Re Spent Fuel Storage Capacity Expansion Project stage: RAI B11777, Forwards Response to Request for Addl Info Re 850724 Application to Revise Tech Specs on Spent Fuel Storage Capacity1985-10-17017 October 1985 Forwards Response to Request for Addl Info Re 850724 Application to Revise Tech Specs on Spent Fuel Storage Capacity Project stage: Request ML20134A5991985-10-29029 October 1985 Notice of Consideration of Issuance of Amend to License DPR-65 & Proposed NSHC Determination & Opportunity for Hearing.Amend Authorizes Licensee to Increase Spent Fuel Pool Storage Capacity from 667 to 1,112 Storage Locations Project stage: Other ML20134A5871985-10-29029 October 1985 Forwards Notice of Consideration of Issuance of Amend to License DPR-65 & Proposed NSHC Determination & Opportunity for Hearing Re 850724 Application to Expand Spent Fuel Pool Storage Capacity Project stage: Other B11889, Forwards Confirmation of Resolution to Request for Addl Info Re Application for Increased Spent Fuel Storage Capacity Based on Series of Telcons1985-11-25025 November 1985 Forwards Confirmation of Resolution to Request for Addl Info Re Application for Increased Spent Fuel Storage Capacity Based on Series of Telcons Project stage: Request B11766, Submits Isap Topic 1.11, Post-Accident Hydrogen Monitor Per 850517 Commitment.Installation of Redundant Containment Hydrogen Monitor Unnecessary.Addl Info Will Be Provided by 8601311985-11-25025 November 1985 Submits Isap Topic 1.11, Post-Accident Hydrogen Monitor Per 850517 Commitment.Installation of Redundant Containment Hydrogen Monitor Unnecessary.Addl Info Will Be Provided by 860131 Project stage: Request B11893, Forwards Review of Spent Fuel Storage Capacity Expansion Request,Containing Proposed Mod to Tech Spec Re Decay Time Requirement,In Response to NRC 850826 Request for Addl Info1985-11-27027 November 1985 Forwards Review of Spent Fuel Storage Capacity Expansion Request,Containing Proposed Mod to Tech Spec Re Decay Time Requirement,In Response to NRC 850826 Request for Addl Info Project stage: Request B11910, Responds to Request for Addl Info Re Spent Fuel Storage Capacity.Analysis Showing That Adjacent Modules Do Not Contact During Seismic Event Inadvertently Omitted from1985-12-0303 December 1985 Responds to Request for Addl Info Re Spent Fuel Storage Capacity.Analysis Showing That Adjacent Modules Do Not Contact During Seismic Event Inadvertently Omitted from Project stage: Request ML20137B4421985-12-16016 December 1985 Environ Assessment & Finding of No Significant Impact Supporting Amend to License DPR-65,authorizing Increase of Spent Fuel Pool Storage Capacity Project stage: Other ML20137B4231985-12-16016 December 1985 Forwards Environ Assessment & Finding of No Significant Impact Re 850724 Request for Amend to License DPR-65 Concerning Spent Fuel Pool Expansion Project stage: Other ML20137B4321985-12-16016 December 1985 Notice of Environ Assessment & Finding of No Significant Impact Re Issuance of Amend to License DPR-65,changing Tech Specs to Increase Storage Capacity of Spent Fuel Pool Project stage: Approval ML20137A4901985-12-31031 December 1985 Forwards Addl Info Demonstrating Compliance w/NUREG-0737, Item II.E.4.2.7 Re Containment Venting Through Hydrogen Purge Valves,Per 840425,0902 & 1211 Requests Project stage: Other 1985-10-17
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1 7590-01
~ UNITED STATES NUCLEAR REGULATORY COPMISSION NORTHEAST NUCLEAR ENERGY COMPANY, ET AL.
MILLSTONE NUCLEAR POWER STATION, UNIT NO. 2 DOCKET NO. 50-336
-NOTICE OF ENVIRONMENTAL ASSESSMENT AND FINDING OF NO SIGNIFICANT IMPACT L
l The U. S. Nuclear Regulatory Connission (the Consnission) is considering
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issuance of an amendment to Operating License No. DPR-65 to Northeast Nuclear -
i Energy Company, et al., (the licensee) for Millstone Unit No. 2 located in Waterford, Connecticut.
Identification of Proposed Action: The amendment would consist of changes
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to the operating license and Technical Specifications (TS) and would i
authorize an increase of the storage capacity of the spent fuel pool (SFP)
I from 667 fuel assemblies to 1112 fuel assemblies with enrichments no greater j
f than 4.5 weight percent U-235.
The amendment to the TS is responsive to the licensee's application dated July 24, 1985. The NRC staff has prepared an Environmental Assessment l
of the proposed action, " Environmental Assessment By the Office of Nuclear i
Reactor Regulation Relating to the Modification of the Spent Fuel Storage i
Pool, Operating License No. DPR-65, Northeast Nuclear Energy Company, et al.,
Millstone Unit No. 2 Docket No. 50-336" dated Summary of Environmental Assessment: The Final Generic Environmental Impact 4
l Statement (FGEIS) on Handling and Storage of Spent Light Water Power Reactor Fuel (NUREG-0575) concluded that the environmental impact of interim storage i
of spent fuel was negligible and the cost of the various alternatives reflects P
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2 the advantage of continued generation of nuclear power with the accompanying spent fuel storage. Because of the differences in SFP designs, the FGEIS i
recommended licensing SFP expansion on a case-by-case basis.
j For Millstone Unit 2, the expansion of the storage capacity of the SFP will not create any significant additional radiological effects or measurable non-radiological environmental impacts. The additional total body dose that might be received by an individual at the site boundary is less than 0.1 millrem per year; the estimated dose to the population within an 80 kilometer radius of the plant is estimated to be less than 0.1 person-rem per year.
These doses are small compared to the fluctuations in the annual dose this population receives from exposure to the background radiation. The total occupational exposure for the reracking and the additional occupational exposure for the subsequent operation of the modified SFP is less than 2% of the average annual occupational dose of 500 person-rems for all plant operations at Millstone Unit 2.
Therefore, the staff concludes that the exposure to workers is as low as is reasonably achievable (ALARA) and is
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acceptable.
i Findino Of No Significant Impact: The staff has reviewed this proposed I
facility modification relative to the requirements set forth in 10 CFR Part 51.
Based upon the environmental assessment, the staff concluded that there are no significant radiological or non-radiological impacts associated with the proposed action and that the proposed license amendment will not have a significant effect on the quality of the human environment. Therefore, the Commission has determined, pursuant to 10 CFR 51.31, not to prepare an environmental impact statement for the proposed amendment.
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For further details with respect to this action, see (1) the application for amendment to the Technical Specifications dated July 24,1985,(2)the FGEIS on Handling and Storage of Spent Light Water Power Reactor Fuel (NUREG-0575), (3) the Final Environmental Statement for Millstone 2 issued June 1973, and (4) the Environmental Assessment dated December 16, 1985.
These documents are available for public inspection at the Commission's Public 4
Document Room, 1717 H Street, N.W., Washington, D. C., 20555 and at the Waterford Public Library, 49 Rope Ferry Road, Waterford, Connecticut.
Dated at Bethesda, Maryland this December 16, 1985.
FOR THE CLEAR REGU 7 9 ; _ LATORY COMMISS 4
1 Ashok
. Thadani, Director PWR P ject Directorate #8 i
Division of PWR Licensing-B e
d o
e
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