Letter Sequence Other |
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Results
Other: ML19327A527, ML19327A533, ML19330B521, ML19330B523, ML19331B934, ML19336A759, ML19340B179, ML19344B508, ML19347C984, ML19347C997, ML19350A630, ML20053A188, ML20080J137, ML20080P638, ML20085B165, ML20244B663, ML20244B666
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MONTHYEARML19330B5211980-07-25025 July 1980 Responds to IE Bulletin 80-17,Suppl 2, Failure of 76 of 185 Control Rods to Fully Insert During Scram at Bwr. No Mod Required for Units 1 & 2 Vent Sys Since as-built Sys Satisfies Requirements of Bulletin Project stage: Other ML19330B5231980-07-25025 July 1980 Responds to IE Bulletin 80-14, Degradation of BWR Scram Discharge Vol Capability. Investigation to Determine How Frequently Scram Discharge Vol Vent & Drain Valves Should Be Tested Underway Project stage: Other ML19327A5331980-07-28028 July 1980 Responds to IE Bulletin 80-17.Provides Manual & Automatic Scram Test Results.Scram Discharge Vol Vent Lines Verified & Emergency Operating Procedure Changes Completed Project stage: Other ML19327A5271980-07-31031 July 1980 Responds to IE Bulletin 80-17 & Provides Manual Scram Test Results.Scram Discharge Vol Vents Lines Verified as Functional & Full Operator Training to Be Completed as of 800802.Recirculation Pump Trip Installed Project stage: Other ML19331B9341980-08-0505 August 1980 Responds to IE Bulletin 80-17, Failure of Control Rods to Insert During Scram at Bwr. Automatic Scram Performed & Scram Discharge Vol Responded Properly.Automatic Scram Test Results Enncl Project stage: Other ML19340B1791980-10-10010 October 1980 Responds to NRC Requesting Tech Spec Mods Re Scram Discharge Vol.Present Tech Specs Assume Control Drive Sys Operability & Scram Discharge Vol Piping Is Sized to Assure Complete Scram.Mods Will Not Increase Reliability Project stage: Other ML19344B5081980-10-14014 October 1980 Responds to Mar 1980 Comments Made at White House Issues Briefing session.NUREG-0625 Is Not Intended to Be Sole Basis for Judging Sites.Evacuation Plans Considered in Licensing Actions Leading to Cp.Foundation Will Be Evaluated Project stage: Other ML19336A7591980-10-24024 October 1980 Responds to 801001 Request Re Participation in Development of Scram Sys Design & Performance Criteria.Not Active Member in Subgroup Considering Criteria.Plans to Consolidate Reviews of Design Rather than Performing Separate Reviews Project stage: Other ML19347C9811981-02-26026 February 1981 Application for Amend to Licenses NPF-5 & DPR-57,submitted as Proposed Changes to Tech Specs Re BWR Scram Sys Design Project stage: Request ML19341C7971981-02-26026 February 1981 Semiannual Rept,Plant Radioactive Effluent Releases,Jul-Dec 1980 Project stage: Request ML19347C9841981-02-26026 February 1981 Tech Spec Tables 3.6.3-1,3.7-1 & Page 3.7-20 for Primary Containment Isolation Valves Project stage: Other ML19347C9971981-03-0404 March 1981 Submits Addl Info Re BWR Scram Discharge Sys Mods,Per 801001 Request.Mods Will Be Implemented as Needed to Result in Conformance to Owners Group Criteria by End of 1982 Provided Qualified Equipment Is Commercially Available Project stage: Other ML19350A6301981-03-0606 March 1981 Notifies That Util 801010 Commitments to BWR Scram Discharge Sys long-term Mods Do Not Satisfy NRC Criteria.Revised Tech Specs Must Be Proposed at Least 3 Months in Advance of Mod Completion Dates Project stage: Other ML20010E8921981-09-0101 September 1981 Forwards Franklin Research Ctr Request for Addl Info Re BWR Scram Discharge Vol long-term Mods.Info Requested within 45 Days of Receipt of Ltr Project stage: RAI ML19280B1321981-10-0101 October 1981 Responds to 810901 Request for Addl Info from Franklin Research Ctr Re Util 810226 Proposed Tech Spec Mods for Scram Discharge Vol.Util Will Submit Amend to Unit 1 Rod Block Setpoint & Surveillance Requirements Project stage: Request ML20244B6631982-01-13013 January 1982 BWR Scram Discharge Vol Long-Term Mods, Technical Evaluation Rept Project stage: Other ML20244B6661982-01-13013 January 1982 BWR Scram Discharge Vol Long-Term Mods,Ga Power Co,Hatch Nuclear Plant,Unit 1, Technical Evaluation Rept Project stage: Other ML20053A1881982-05-18018 May 1982 Requests Extension of 821231 Commitment Date for Installation of Qualified Level Transmitters in Scram Discharge Sys to 831231 Project stage: Other ML20085B1651983-06-24024 June 1983 Order Confirming Licensee Commitments to Install Mods to Scram Discharge Sys by 831231 Project stage: Other ML20080J1161983-09-19019 September 1983 Application to Amend Licenses DPR-57 & NPF-5,changing Tech Specs to Reflect Mods to Scram Discharge Sys,As Required by NRC Project stage: Request ML20080J1371983-09-19019 September 1983 Proposed Tech Spec Changes Re Scram Discharge Sys Project stage: Other ML20080P6381983-10-0303 October 1983 Requests That Re Proposed Tech Spec Changes Concerning Scram Discharge Sys Be Superseded by 830919 Submittal Project stage: Other ML20083E0871983-12-14014 December 1983 Proposed Tech Spec Changes Re Scram Discharge Vol Closure Times Project stage: Other ML20083E0061983-12-14014 December 1983 Suppl to 830919 Application to Amend Licenses DPR-57 & NPF-5,changing Tech Specs Re Scram Discharge Vol Closure Times Project stage: Request ML20083D8561983-12-20020 December 1983 Corrects Changing Tech Specs Re Scram Discharge Sys Operability.Outboard Scram Discharge Vol Vent & Drain Valves Close Vs Open within 5 After Closure of Inboard Valves Project stage: Other ML20083H7761983-12-22022 December 1983 Forwards Addl Info Re Requesting Substitution of Longer Values for Scram Discharge Vol Vent & Drain Valve Closure Times.Closure Times Proposed in Do Not Meet Acceptance Criteria in SER Project stage: Other ML20084D3391984-04-23023 April 1984 Submits Results of GE Review of 831222 Analysis of Scram Discharge Vol Vent & Drain Valve Closure Times in Excess of 30 S.Ge Does Not Concur W/Analysis.Closure Times Should Be Accepted as Is.Continued Plant Operation Justified Project stage: Other ML20092A4271984-06-14014 June 1984 Submits Schedule Requested in Re Implementation of Mods Resulting in Scram Discharge Vol Vent & Drain Valve Closure Times Which Meet GE Requirements of 30 S.Tests Will Be Performed to Determine Extent of Mods Project stage: Other ML20135G5101985-09-13013 September 1985 Application for Amends to Licenses DPR-57 & NPF-5,adding 60 Scram Discharge Vol Vent & Drain Valve Closure Time Requirement to Tech Specs.Fee Paid Project stage: Request ML20135G5191985-09-13013 September 1985 Proposed Tech Spec,Adding 60 Scram Discharge Vol Vent & Drain Valve Closure Time Requirement Project stage: Other ML20136J4051985-11-18018 November 1985 Responds to Request for Addl Info Re 850913 Application for Amends to Licenses DPR-57 & NPF-5,allowing 60 Closure Time Limit for Scram Discharge Vol Vent & Drain Valves.Figure 6.2.2 from GE NEDO-24342 Re Scram Sys Pipe Breaks Encl Project stage: Request ML20137F7721986-01-0606 January 1986 Proposed Tech Spec Changes Providing Value of 45 Closure Time Requirement for Scram Discharge Vol Vent & Drain Valves Project stage: Other ML20137F3011986-01-0606 January 1986 Rev to 850913 Application for Amend to Licenses DPR-57 & NPF-5,revising Tech Spec to Provide Value of 45 Closure Time Requirement for Scram Discharge Vol Vent & Drain Valves for Unit 1 Project stage: Request ML20204A2781986-04-28028 April 1986 Forwards Request for Addl Info Re Request for Rev to Tech Specs to Reflect Addition of Closure of Containment Purge & Vent Valves on High Containment Radiation Signal.Response Requested within 60 Days Project stage: RAI ML20211G6301986-06-12012 June 1986 Forwards Request for Addl Info Re Util Listed Requests to Amend Tech Specs to Provide Closure Time Requirements for Scram Discharge Vol Vent & Drain Valves.Info Requested within 45 Days of Ltr Receipt Project stage: RAI ML20210T7521986-09-23023 September 1986 Responds to NRC 860612 Request for Addl Info Re Scram Discharge Vol Vent & Drain Valve Closure Times Project stage: Request ML20213G7521986-11-11011 November 1986 Forwards Bechtel Calculation Sheets Re CRD Scram Discharge Header Drain Piping Project stage: Other ML20214F3901987-05-13013 May 1987 Amends 136 & 75 to Licenses DPR-57 & NPF-5,respectively, Providing Closure Time Requirements for Scram Discharge Vol Vent & Drain Valves Project stage: Other ML20214F3951987-05-13013 May 1987 Safety Evaluation Supporting Amends 136 & 75 to Licenses DPR-57 & NPF-5,respectively Project stage: Approval 1983-10-03
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Dear Ms. Seed:
1 As indicated in Mr. Folsom's letter of June 20, 1980, your comments regarding the Bailly facility, which you made at the issues briefing session held in March 1980 at the White House, have been forwarded to the Nuclear Regulatory Commission for our consideration.
Your comments on the Bailly plant fall into three basic areas; i.e., site suitability with emphasis on the population density, the feasibility of evacuating the adjacent steelmill and national park in the event of a severe accident at Bailly and the capability of the foundation of this plant.
Each of ne:;e areas is discussed below.
Your comment that the Bailly site, "... scored worst of all the country's sites
" undoubtedly refers to the proposed guidelines for siting of future nuclear power plants contained in NUREG-0625, " Report of the Siting Policy Task Force,"
August 1979.
That document proposed new siting criteria, including surrounding population, which would be considered by the NRC staff in evaluating sites for nuclear powr plants.
It should be noted that the basic intent of the NRC in issuing F.s dccument was to reemphasize the importance of icw population as one of tne factors to be considered when evaluating a proposed site.
- However, NUREG-0625 does not consider any of the other equally important siting consid-i erations such as the availability of cooling water, the proximity of a site to existing transmission corridors, the geology and seismology of a site and the environmental impact of a plant.
Since all of these factors must be considered in establishing acceptability of a site, NUREG-0625 is not intended to be the sole basis for judging sites.
Public comment on this document has been invited.
With respect to your comment characterizing the Bailly site as the worst of all
, the country's sites, we have revewed all of the presently licensed sites for their potential to cause significant radiation exposure to the surrounding population in the event of a severe accident. We found that when the distribution of population, the potential source.of fission products and a typical " worst case' meteorological dispersion is considered, the Bailly site ranks eighth to nin:.5 in terms of potential radiation dosage for distances between 30 miles and 50 nd i's away from the site.
(At these distances, the population centered about Chicago, Illinois is included.) However, Bailly is far dcwn the list for distances up to ten miles from the plant.
This reflects the relatively small population in a ten mile radius around the Bailly facility as well as its relativel, small power level in comparison with cther nuclear power plants.
If only SM 0 5 8o1021030/
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Ms. Jane Seed !
the total population around a facility is considered, the Bailly plant ranks eighth at a distance of 10 miles from the site. This is relevant to the evacuation of the total population within a 10-mile emergency planning zone (EPZ).
We have also determined on various other population criteria that the Bailly facility does not rate as one of the worst of the country's sites.
With respect to your concern regarding the feasibility of e'vacuating Bethlehem Steel in the event of a serious accident at Bailly, this was considered prior to issuance of the Bailly construction permit.
You may wish to refer to Chapter 13 of the Bailly Preliminary Safety Analysis Report, a copy of which is available in the West Chester Public Library,125 South Second Street, Chesterton, Indiana, d6304.
This local i
Public Document Room contains all information pertaining to the, Bailly facility.
Basically it was determined that only a small number of people would be required to shutdown the critical steel facilities and that adequate protection could be provided for these steel workers.
In a similar vein, during the construction permit stage, it was detemined that there wc'ild be a limited number of par,k visitors in the westernmost portion of the Indiana Danes National Park adjacent to the Bailly facility. Our position with respect to tese visitors is that they would receive prompt notification in the event that an evacuation of that area was required and that this evacuation could be readily accompli:hed.
Both of the above topics were censidered in the licensin0 actions leading up to the issuance of the Bailly con-struction pemit.
The evacuation of all people within the 10-mile EPE around Bailly was recently consideced in a study by a consultant to the Federal Emergency Management Agency.
This FEMA funded study indicated that the 10-mile EPZ could t e evacuated in about three hours under nomal conditions and in five hours during peak attendance at the nearby State Park' Beach.
Both of these estimates place the Bailly site as ranking about fifth or sixth in tems of the time required to evacuate the 10-mile EPZ.
While we are continuing our review of the evacuation feasibility of various nuclear power plants, we can state that Bailly has no fundamental impediment unduly restricting evacuation and that the Bailly site is not the worst site in this regard.
The environmental impact of the construction and operation of the Ee:lly facility on the flora and fauna in the Indiana Dunes was considered during the 65 hearing days before the Atomic Licensing and Safety Board and was not foune.. to be significant.
s Finally, we recognize thet the soils in the upper strata at the Bailly site consist of a compressible clay layer of varying thickness overlain by low density dune sand.
This material is not suitable as a foundation for a nuclear power plant.
- However, NIPSLO has excavated the dune sand and proposes to drive piles through the compressible clay layer into the underlying, dense interbedded layers of sand and clay. All the field investigations, to date have indicated that piles driven in this manner can
6 3-Ms. Jane Seed carry loads far in excess of the actual loads which could occur under extreme environmental conditions (i.e., a severe earthquake) in combination with the design basis accident. While we have not yet completed our evaluation of NIPSCO's present proposal for installing the foundation piles, we intend to assure that the piles provide a proper foundation for the plant.
Thank you for expressing your concerns regarding the Bailly site.
Sincerely, hN$
Harold R. Denton, Director Office of Nuclear Reactor Regulation d
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