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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20078S4721995-02-15015 February 1995 Provides Update to Status of WNP-3 Project ML20069D0021994-05-17017 May 1994 Informs Board & Parties of Recent Developments Re WNP-3 Project ML20235B3621987-08-25025 August 1987 FOIA Request for Listed Documents for Specified Dockets ML20141D3441986-03-31031 March 1986 Concludes That Financial Info Submitted in Util Satisfies Requirements of 10CFR140.21 Re Licensee Maint of Approved Guarantee of Payment of Deferred Premiums ML20010H3481981-08-14014 August 1981 Responds to IE Bulletin 80-20, Failures of Westinghouse Type W-2 Spring Return to Neutral Control Switches. No Subj Switches Have Been Identified at Facilities.Util Awaits Info from GE for Final Resolution.Next Response by 811030 ML19260E0371980-01-28028 January 1980 Forwards Util 800123 News Releases.Utils Have Decided to Terminate Const Plans for Units.Reduced Load Growth Projections,Financial Constraints & Overregulation Cited as Contributing Factors ML19260E0101980-01-23023 January 1980 Forwards Util 800123 Press Release Re Termination of Plans to Build Four Addl Nuclear Units Presently in Design Stage. Const Will Continue on Two Units Near North Perry,Oh & One Near Shippingport,Pa ML20125D5911980-01-0808 January 1980 Discusses Recent Util Reorganization.Cw Frederickson Is Authorized Officer Responsible for Receipt & Transmittal of NRC Official Correspondence Re Facility.Bm Miller Authorized to Review & Approve Documents Re Licensing Application ML19253C9121979-12-0505 December 1979 Forwards 10-yr Forecast Rept to Be Used in Updating Plants Final Environ Statement.W/O Encl ML19254E1981979-10-24024 October 1979 Responds to 791010 Ltr Re Threatened & Endangered Species in Vicinity of Proposed Facility.Federal Law Requires Biological Assessment.Lists Info for Inclusion in Assessment ML19254D6791979-10-23023 October 1979 Responds to 791010 Ltr Re Followup Actions Resulting from NRC Reviews Re Tmi.Study of Scheduled Inservice Dates Continues.Licensing Manpower Reduced.Dates Cannot Now Be Amended to Include Six Items Noted in Ltr ML19289F5281979-06-0505 June 1979 Forwards PSAR Amend 22 Re Qa,In Response to NRC 790430 Ltr.Affidavit Encl ML19273B3991979-03-0707 March 1979 Applicants Request ASLB Attention to Recent & Subsequent Order of Aslab Which Bears Directly on Issue Presented in Order.Certificate of Svc Encl ML19276F5341979-03-0505 March 1979 Requests Convening of Radiological Health & Safety Phase of Const Permit Hearing.Related SER Suppl Was Issued in Jan. Certificate of Svc Encl ML19283B5751979-02-16016 February 1979 Ack Receipt of NRC 790131 Ltr.Util Feels Any Design & Initial Const Scheduled to Occur Between Now & 791101 Can Proceed W/O Precluding Possible Addition of ATWS Mitigating Equipment ML19256B1761979-01-0808 January 1979 Responds to NRC Request for Addl Info Re Tornado Missile Protection of Main Steam Lines.Info Deals W/Analysis of Automobile Impact on Main Steam Line Piping & Calculation of Restraint Barrier Stiffness ML19263A8921978-12-21021 December 1978 Discusses Schedule Changes in Const & Planning Studies.After Review,Util Concluded That Licensing Activities Re Pending Const Permit Application Should Continue Concurrently W/The Planning Studies ML20147H3541978-12-15015 December 1978 Responds to 781027 NRC Ltr by Forwarding Oec Commitment to Conform W/Nrc Cold Shutdown Design Requirements for Subj Facils. W/Encl Affidavit ML20148T4521978-12-0101 December 1978 Manager,Quality Assurance Dept Has Assumed the Duties of Previous Chief Nuc Qual Assurance Engineer & Responsibility for All non-nuc Quality Assurance.Forwards Clarification of Main Steam Valve Leak Rate Analysis ML20197C5201978-11-0707 November 1978 Forwards 780928 NRC Memo Discussing Results of Recent Underwriters Lab Fire Protec Res Test.W/Encl ANO:7811050359, 7811160004,7811060106,7811050373 ML20150C1721978-11-0606 November 1978 Proposes Steps Util Will Take to Resolve Areas of Discord Re 2nd Analysis of Probability of Unacceptable Conditions Occurring in Control Room as Result of Toxic Chem Spill Near Facil,Including Facil Design & Hazard Analysis ML20148H0621978-11-0303 November 1978 Responds to Expressing Concern Re Proposed Location of Subj Facil.Describes Lic Process ML20058A1431978-10-27027 October 1978 Forwards Util Responses to NRC Questions Re Financial Qualifications.Affidavit Requesting Withholding of Info Per 10CFR2.790 Also Encl ML20150B7411978-10-27027 October 1978 Forwards Requirements for Subj Facil Cold Shutdown.Req Comment Prior to Issuance of SER ML20197B6401978-10-18018 October 1978 Requests Viable Geographic Alternatives to Subj Facil & Any Info Re Evaluation Studies of Proposed Pwr Plant Sites ML20148H0691978-10-18018 October 1978 Believes There Must Be Viable Alternatives to Proposed Plant Location in Northern Oh ML20148A7631978-10-18018 October 1978 Advises That Const Schedules Currently Undergoing Review. Review Expected to Be Completed in Approx 30 Days. Certificate of Svc Encl ML20147E0791978-10-0909 October 1978 Forwards Addl Info for Sser Re Major Reorganization of Util. Senior Vice-President for Engineering & Const Responsible Fr All Engineering & Const Activities.Organizational Chart Encl ML20147C8781978-10-0606 October 1978 Forwards Info Which Is 780828 Suppl Testimony of L.Firestone Describing the Rev Capco Load Forecast as Submitted to Oh Pwr Siting Comm During State Cert Hearings for Subj Facil. Matl Was Previously Submitted Informally to Singh Bajwa,Nrc ML20204C7661978-08-17017 August 1978 Reports on 220th ACRS Meeting Held on 780803-05.Items Considered Incl:Review of Facils Requests for Constr Permit RESAR-414,CRAC Code Use ML19329C4541977-12-0808 December 1977 Requests Final Rept Re Davis Besse Shutdown Resulting from Release Valve Failure & NUREG 0337,DES for Erie Units 1 & 2 ML19329C6801974-11-0404 November 1974 Responds to AEC Notice Calling for Comment Re Anticompetitive Effects of CP on Behalf of City of Cleveland 1995-02-15
[Table view] Category:INTERNAL OR EXTERNAL MEMORANDUM
MONTHYEARML20197C5201978-11-0707 November 1978 Forwards 780928 NRC Memo Discussing Results of Recent Underwriters Lab Fire Protec Res Test.W/Encl ANO:7811050359, 7811160004,7811060106,7811050373 ML20204C7661978-08-17017 August 1978 Reports on 220th ACRS Meeting Held on 780803-05.Items Considered Incl:Review of Facils Requests for Constr Permit RESAR-414,CRAC Code Use 1978-08-17
[Table view] Category:MEMORANDUMS-CORRESPONDENCE
MONTHYEARML20197C5201978-11-0707 November 1978 Forwards 780928 NRC Memo Discussing Results of Recent Underwriters Lab Fire Protec Res Test.W/Encl ANO:7811050359, 7811160004,7811060106,7811050373 ML20204C7661978-08-17017 August 1978 Reports on 220th ACRS Meeting Held on 780803-05.Items Considered Incl:Review of Facils Requests for Constr Permit RESAR-414,CRAC Code Use 1978-08-17
[Table view] Category:NRC TO ASLP
MONTHYEARML20197C5201978-11-0707 November 1978 Forwards 780928 NRC Memo Discussing Results of Recent Underwriters Lab Fire Protec Res Test.W/Encl ANO:7811050359, 7811160004,7811060106,7811050373 1978-11-07
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Text
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0 NUCLEAH REGULATORY v.Asmrao109 o. c. 2cca
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%f ' ,.# h November 7,1978 Do Il#!g u e Elizabeth S. Bowers, Esq. , Chairman Dr. Frederick P. Cowan Atomic Safety and Licensing Board Apt. B-125 U.S. Nuclear Regulatory Commission 6152 N. Verde Trail Washington, D.C. 20555 Boca Rator, Florida 33433 Mr. Frederick J. Shon Atomic Safety and Licensing Board 7 .
U.S. Nuclear Regulatory Commission f Washington, D.C. 20555 g
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In the Matter of c) --
Ohio Edison Company, et al. -
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' (Erie Nuclear Plant, Units 1 and 2)
Docket Nos. STN_50-580 and STN 50-581 %
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Dear Members of the Board:
The SEh has been issued and no safety hearings have been held. In accord with our notification procedures we are sendirg you a memorandum from the Director of the Office of Nuclear Reactor Regulation to the Cornissioners dated September 29, 1978 discussing the results of a recently conducted fire protection research test by the Undentriters Laboratory for the Comission as part of the NRC's fire protection research program.
If the Board or the parties wish any additional information, please let us know.
Sincerely,
& A$g Charles A. Barth Counsel for NRC Staff,
Enclosure:
As Stated cc: (w/ enclosure)
Thomas A. Kayuha, Esq.
Jay Silberg, Esq. 7 81] 2]O ll4 Mrs. Evelyn Stebbins Mr. Robert W. Tufts Mr. Richard E. Febb Atomic Safety and Licensing Appeal Board Atomic Safety'and Licensing Board Panel '
Docketing and Service Section
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.. e NUCLEAR REGULATORY COMMisslON
. j .gZ% 3 WASHINGTON, D. C. 205% .
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%ghi September 29, 1978
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MEMORANDUM FOR: Chaiman Hendrie Commissioner Gilinsky Comissioner Kennedy '
Commissioner Bradford N Comissioner Ahearne , ,,
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THRU: Executive' Director for Operations (J FROM: Harold R. Denton, Director Office of Nuclear Reactor Regulation
SUBJECT:
NRC FIRE PROTECTION RESEARCH TEST 1
i On September 15, 1978, a fire test of a full-scale vertical cable tray -
l array was conducted at the Underwriters' Laboratory near Chicago, Illinois. It was part of the NRC-expedited fire protection research l program requested in the Comission's Order of April 13, 1978. The purpose of the test was to demonstrate the effectiveness of area sprinklers and mineral wool blanket type cable tray fire barriers in preventing damage to cables as a result of an exposure fire created by igniting two gallons of heptane. ,
The configuration of cables and fire protection features in the test ,
did not si alate any particular nuclear power plant. There are plants in operation and under construction for which the electrical cable tray configuration of the test was typical. However, based on the staff's ongoing fire protection reviews, we know of no operating plants with the configuration of fire protection features used in the test, although features of this type have been proposed for .
installation and are currently under review by the staff.
The test resulted in damage to some of the electrical cables. Prelim-inary analysis (see Enclosure 1) indicates that the configuration of fire protection features used in the test would not be acceptable for application in nuclear power plants. In particular, it appears that fire barriers for vertical trays in soce configurations may need to be designed to prevent entry of flamable fluids. A wick effect may also need to be considered in the design of fire barriers. The m- pnnnse of the_ fusible link sprinklers used in the test is also under s~ + w ~ m w,fgg 4.,
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