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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217R2911997-08-28028 August 1997
Informs That Pg Boyle License SOP-70072 No Longer Working as Licensed SRO W/Penn State Univ Breazeale Reactor Effective 970630
ML20198E9811997-08-0505 August 1997
Informs That Responsibility for Non-Power Reactor Insp Program Has Been Transferred from Regional Ofc to Nrr. Addresses Listed
ML20237H4851987-08-28028 August 1987
Forward Safety Insp Rept 50-005/87-03 on 870720-21.No Violations Noted
ML20198E5291985-10-18018 October 1985
Forwards Ltr of Transmittal for Rev to Security Plan Which Will Be Mailed on or About 851025.W/o Encl
ML20098C8421984-09-21021 September 1984
Informs That Copies of NRC Approved Penn State Breazeale Nuclear Reactor Emergency Preparedness Plan Mailed to All Members of Emergency Organization & State of PA Emergency Mgt Agency.Plan Fully Implemented
ML20039C4901981-12-18018 December 1981
Informs of Violation of Administrative Policy Which Requires Senior Reactor Operator at Control Console for All Power Level Changes.Reactor Shutdown on 811211 W/Only Licensed Operator Present.Procedures Will Be Discussed W/Operators
ML19289F6651979-06-11011 June 1979
Forwards Executed Amend 14 to Indemnity Agreement E-10
1997-08-05
[Table view]
Category:EDUCATIONAL INSTITUTION TO NRC
MONTHYEARML20198E5291985-10-18018 October 1985
Forwards Ltr of Transmittal for Rev to Security Plan Which Will Be Mailed on or About 851025.W/o Encl
ML20098C8421984-09-21021 September 1984
Informs That Copies of NRC Approved Penn State Breazeale Nuclear Reactor Emergency Preparedness Plan Mailed to All Members of Emergency Organization & State of PA Emergency Mgt Agency.Plan Fully Implemented
ML20039C4901981-12-18018 December 1981
Informs of Violation of Administrative Policy Which Requires Senior Reactor Operator at Control Console for All Power Level Changes.Reactor Shutdown on 811211 W/Only Licensed Operator Present.Procedures Will Be Discussed W/Operators
ML19289F6651979-06-11011 June 1979
Forwards Executed Amend 14 to Indemnity Agreement E-10
1985-10-18
[Table view]
Category:INCOMING CORRESPONDENCE
MONTHYEARML20217R2911997-08-28028 August 1997
Informs That Pg Boyle License SOP-70072 No Longer Working as Licensed SRO W/Penn State Univ Breazeale Reactor Effective 970630
ML20198E5291985-10-18018 October 1985
Forwards Ltr of Transmittal for Rev to Security Plan Which Will Be Mailed on or About 851025.W/o Encl
ML20098C8421984-09-21021 September 1984
Informs That Copies of NRC Approved Penn State Breazeale Nuclear Reactor Emergency Preparedness Plan Mailed to All Members of Emergency Organization & State of PA Emergency Mgt Agency.Plan Fully Implemented
ML20039C4901981-12-18018 December 1981
Informs of Violation of Administrative Policy Which Requires Senior Reactor Operator at Control Console for All Power Level Changes.Reactor Shutdown on 811211 W/Only Licensed Operator Present.Procedures Will Be Discussed W/Operators
ML19289F6651979-06-11011 June 1979
Forwards Executed Amend 14 to Indemnity Agreement E-10
1997-08-28
[Table view] |
Text
Tile PENNSYLVANI A ST ATE U NIVERSITY 207 01 D MAIN llUll DING UNIVI RSITY PARK. PLNNSY1 VANIA 16502 Yke PicssJcm her Aic.a( W $14 Rewarth anJ (n Juale StuJics hb5 6H2 25 June 1979 Operating Reactors Division of Reactor Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Reference:
License R-2, Docket 50-05 Gentlemen:
On June 8, 1979, during a routine daily checkout of the reactor instru-mentation, it was discovered that the percent power meter stuck at 98% full scale and would not have scranmied had the power exceeded 98%. Amendment 16 to our license requires us to inform the Commission of any incident or condi-tion relating to the operation of the reactor which prevented or could have prevented the nuclear system from performing its safety function as described in the Technical Specifications. llence , the problem was immediately reported to Region I by a phone call from Dr. S . 11 . Levine to Mr. Larry Briggs, 10:30 A.M.,
June 8, 1979.
Disassembly of the percent power meter revealed a collection of dust in-side the meter movement which increased the internal friction in the meter preventing proper operation at the upper end of its scale. The meter move-ment was cleaned and checked for proper operation and returned to service. No further deficiency with this system has been observed.
The discovery was made during checkout of the instrumentation; therefore, the reactor was not operated with this condition. It was operated again only after the repair was effected and the system checked to assure proper operation.
Sincerely yours, m '
J
, ' > f[ <... ~ A e. ..Q l U < V,7 R. G. Cunningham Vice President for Research and Graduate Studies RGC:hml cc: I. B. McMaster 7908260 %~/ f