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Category:SAFETY EVALUATION REPORT--LICENSING & RELATED ISSUES
MONTHYEARML20198R9321997-10-30030 October 1997 Safety Evaluation Supporting Amend 12 to License R-120 1997-10-30
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARML20211G6811999-06-30030 June 1999 Pulstar Reactor Annual Rept to Us NRC for Jul 1998 - June 1999. with ML20238E8731998-06-30030 June 1998 Pulstar Reactor Annual Rept for Period Jul 1997 - June 1998 ML20198R9321997-10-30030 October 1997 Safety Evaluation Supporting Amend 12 to License R-120 ML20210Q7941997-06-30030 June 1997 Pulstar Reactor Annual Rept for Jul 1996 - June 1997 ML20141J9391997-04-30030 April 1997 Safety Evaluation Report Related to the Renewal of the Operating License for the Research Reactor at North Carolina State University ML20133F8501996-12-11011 December 1996 Ro:On 961206,PULSTAR Surveillance Program Was Deficient in prestart-up Check Since It Did Not Verify Full Operation of Scram Logic Unit as Described in Ufsar.Caused by Deficient Surveillance procedures.Re-soldered Connection ML20148G2811996-06-30030 June 1996 Corrections to Pulstar Facility Annual Rept Section 6.7.5.f.1 for Periods 950701-960630,940701-950630 & 930701- 940630 ML20117E8881996-06-30030 June 1996 Pulstar Reactor Annual Report to NRC for Jul 1995 - June 1996 ML20091P4731995-06-30030 June 1995 Pulstar Reactor Annual Rept for Period Jul 1994 - June 1995 ML20072P2401994-06-30030 June 1994 Pulstar Reactor Annual Rept for Period Jul 1993 - June 1994 ML20056G0841993-06-30030 June 1993 Pulstar Reactor Annual Rept for Period Jul 1992 - June 1993 ML20127P8261992-11-27027 November 1992 Offsite Dose Calculation for Noble Gases ML20099K2691992-06-30030 June 1992 Pulstar Annual Rept to NRC for Jul 1991-June 1992 North Carolina State Univ Nuclear Reactor Program ML20082H8171991-06-30030 June 1991 Pulstar Annual Rept to NRC for Jul 1990 to June 1991 ML20082A3911991-06-27027 June 1991 Ro:On 910625,reactor Operator Logged That Reactor Key Turned Off & Removed from Reactor Control Console While Key Still Turned On.Operator Suspended for 24 H & Operating Procedures Will Be Changed Re Custody of Reactor Key ML20059D1451990-06-30030 June 1990 Pulstar Annual Rept to NRC for Jul 1989 - June 1990 ML20246N6781989-06-30030 June 1989 Pulstar Annual Rept to NRC for Jul 1988 - June 1989 ML20245B4451988-06-30030 June 1988 Financial Rept for Yr Ending 880630 ML20153E1691988-06-30030 June 1988 Pulstar Annual Rept to NRC for Jul 1987 - June 1988 ML20196G8881988-03-0303 March 1988 Headquarters Daily Rept for 880303 ML20237H3851987-06-30030 June 1987 Annual Rept for Jul 1986 - June 1987 ML20215K3521986-08-20020 August 1986 Ro:On 860813,console Key Left in Keyswitch & in on Position.Caused by Personnel Error.Reactor Operator & Duty Senior Operator Suspended from Licensed Duties for 1 Wk ML20214L4891986-06-30030 June 1986 Pulstar Annual Rept to NRC for Jul 1985 - June 1986 ML20134L7461985-06-30030 June 1985 Pulstar Annual Rept to NRC for Period Jul 1984 - June 1985 ML20096C8311984-06-30030 June 1984 Pulstar Annual Rept to NRC for Jul 1983 - June 1984 ML20063J4611982-08-27027 August 1982 Pulstar Annual Rept to Nrc,Jul 1981-June 1982 ML20069D7661982-08-20020 August 1982 Errata to Pulstar Annual Rept to Usnrc,Jul 1981-June 1982, Environ Radiation Surveillance Rept for 811005-820820 ML20042C0411982-03-22022 March 1982 Ro:On 820312,during Reactor Startup,Keyswitch Discovered in on Position.Caused by Failure of Reactor Operator to Follow Established Shutdown Procedure.Operator Interviewed & Guidance Issued for Performing Reactor Checklists ML20041E1841981-09-30030 September 1981 to QA Program for Shipping Radioactive Matl ML20004D8801981-06-0101 June 1981 Ro:On 810527,during Preoperational Checkout,Polarizing High Voltage Was Removed from Safety Channel Compensated Ion Chamber Neutron Detector.Caused by Operator Inadvertently Reducing High Voltage Power Supply Output to Zero ML19344E6071980-08-27027 August 1980 Annual Rept,Jul 1979 to Jul 1980. ML19310A4041980-03-15015 March 1980 Dismantling Plan for Facility ML19275A5611979-09-11011 September 1979 QA Plan for Shipment of R-3 Fuel. ML19254A7851979-06-30030 June 1979 Pulstar Annual Rept, 780701-790630 1999-06-30
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- f. +,t UNITED STATES
- 3 U S NUCLEAR REGULATORY COMMISSION D E WASHINGTON D.C. m f .
SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT NO.12 TO FACILITv LICENSE NO. R-120 NORTH CAROLINA STATE UNIVERSITY DOCKET NO. 50-297
1.0 INTRODUCTION
By letter dated September 10,1997, North Carolina State University (NC State or the licensee) submitted a request for an amendment to Appendix A of Facility License No. R 120. Technical Specifications (TS) for the North Carolina State University PULSTAR Reactor. The requested changes would update Figure 5.2-1 of the TS, PULSTAR Reactor Site Map, and remove reference to Region ll in TS 6.7, Reporting Requirements.
2.0 EVALUATION The licensee has requested changes to TS Figure 5.21, PULSTAR Reactor Site Map. NC State has changed the names of some streets surrounding the reactor site. The requested change to the TS keeps the street names up to date. The staff finds that these changes are administrative in nature and are therefore acceptable.
The licensee has requested changes to TS 6.7, Reporting Requirements. The requestod changes would remove reference to Region 11in the TS. On August 4,1997, the non-power reactor inspection program was transferred for licensees in Region ll from the region to the Office of Nuclear Reactor Regulation. A letter from the Region 11 Administrator to NC State dated August 1,1997, informed NC State of the change and instructed the' licensee to direct correspondence, reports, and inquiries to the Document Control Desk at NRC Headquarters. The staff finds that this change is administrative in nature, removes unneeded reporting requirements from the TS, and is therefore acceptable to the staff.
3.0 ENVIRONMENTAL CONSIDERATION
This amendment involves changes in recordkeeping, reporting, or administrative procedures or requirements. Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(10). Pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of this amendraent.
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ADOCK 05000297 PDR
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4.0 CONCLUSION
Tha staff has concluded, on the basis of the considerations discussed above, that -
(1) because the amendment does not involve a significant increase in the probability or consequences of accidents previously evaluated, or create the possibility of a new or different kind of accident from any accident previously evaluated, and does not involve a significant reduction in a margin of safety, the amendment does not involve a significant hazards consideration; (2) there is reasonable assurance that the health and safety of the public will not be endangered by the proposed activities; and (3) such activities will be conducted in compliance with the Commission's regulations and the issuance of this amendment will not be inimical to the common defense and security or the health and safety of the public.
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- Principai Contributor: A. Adams, Jr.
. Date: October 30, 1997 i
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