ML15349A045
| ML15349A045 | |
| Person / Time | |
|---|---|
| Site: | Vallecitos File:GEH Hitachi icon.png |
| Issue date: | 12/15/2015 |
| From: | Murray S GE-Hitachi Nuclear Energy Americas |
| To: | Document Control Desk, Office of Nuclear Material Safety and Safeguards |
| References | |
| SPM 15-039 | |
| Download: ML15349A045 (3) | |
Text
GE Hitachi Nuclear Energy Scott P. Murray Manager, Facility Licensing 3901 Castle Hayne Road P.O. Box 780 SPM 15-039 Wilmington, NC 28402 USA December 15, 2015 T (910) 819-5950 scott.murray@ge.com Director, Office of Nuclear Material Safety and Safeguards U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 ATTN: Document Control Desk
Subject:
GEH Vallecitos Nuclear Center (VNC) Request for DR-10 and TR-1 License Continuation
References:
- 2) NRC License TR-1, General Electric Test Reactor (GETR), Docket 50-70
- 3) Letter, M. Mendonca (NRC) to G. Stimmell (GE), TR-1, General Electric Test Reactor (GETR), Issuance of Amendment 16, 9/30/92 (Accession
- 4) Letter, M. Masnik (NRC) to G. Stimmell (GE), DPR-1, Vallecitos Boiling Water Reactor (VBWR), License Remains in Effect, 11/3/97 (Accession
- 9711120128)
- 5) Letter, S.P. Murray to Director NMSS, GEH VNC Request for Alternate Decommissioning Schedules, 7/10/15
- 6) Letter, S.P. Murray to Director NMSS, Supplemental Information, GEH VNC Request for Alternate Decommissioning Schedules, 10/15/15
Dear Sir or Madam:
GE Hitachi Nuclear Energy Americas LLC (GEH) hereby requests license continuations for shut down reactor licenses DR-10 (EVESR) and TR-1 (GETR) (References 1 and 2) in accordance with 10 CFR 50.51(b). Both of these licenses currently expire on January 26, 2016. The continuations are similar to the one NRC granted for the DPR-1 (VBWR) facility on November 3, 1997 (Reference 4). License continuations for all three shutdown reactors will support the integrated approach to reactor facility decommissioning at the VNC site as described in References 3, 5 and 6.
GEH is the holder of NRC Licenses DPR-1 (VBWR), DR-10 (EVESR), TR-1 (GETR) and R-33 (NTR) licensed reactor facilities at the VNC site. The VBWR, EVESR and GETR facilities have permanently ceased operations and are being maintained and controlled in a possession only status.
DPR-1 The VBWR is a 50 MW thermal experimental research reactor initially licensed in 1957.
It was shut down on December 9, 1963 for an extended period of time and subsequently deactivated. All fuel has been removed from the reactor and shipped offsite. In addition, much of the equipment used to operate the reactor (nuclear instrumentation, control rod drives, pumps,
US NRC SPM-15-039 December 15, 2015 etc.) has been removed. On September 9, 1965, the AEC amended DPR-1 license to possess, but not operate, the facility in the condition described in the Final Report on Deactivation dated February 5, 1965. The NRC, in amendment 19, subsequently extended the license until May 14, 1996. The VBWR license expired on May 14, 1996 and, pursuant to 10 CFR 50.51(b), continues in effect authorizing ownership, possession, control and maintenance of the facility.
DR-10 The EVESR is a 17 MW thermal experimental research reactor initially licensed in 1963. It was shut down on February 1, 1967 and subsequently deactivated. All fuel and other special nuclear material for the EVESR has been removed and shipped offsite. In addition, much of the equipment used to operate the reactor (nuclear instrumentation, piping, pumps, valves, etc.) has been removed. On June 17, 1968, the AEC amended DR-10 license to possess, but not operate, the facility in the condition described in the EVESR Deactivation Report dated October 12, 1967. The current EVESR license expiration date is January 26, 2016.
TR-1 The GETR is a 50 MW thermal experimental test, development and isotope production reactor initially licensed to operate in 1959. It was shutdown in 1977 and subsequently deactivated. All fuel and isotope production targets containing special nuclear material have been removed from the facility and shipped offsite. The current GETR license expiration date is January 26, 2016.
When NRC extended the TR-1 (GETR) license with the issuance of amendment 16 on September 30, 1992 (Reference 3), the supporting NRC safety evaluation states in Section 3.0:
In response to an NRC staff request for additional information, the licensee, by letter dated August 7, 1992, requested that the expiration date for the GETR be changed to match the EVESR license expiration date from the originally requested 40 year license extension. This request is consistent with the factors to be considered in the delay of decommissioning for licenses other than electric utilities in 10 CFR 50.82 (b)(1)(ii) and (iii). That is, the reduced radiological impact (due to the decay of the residual radioactivity, and the associated reduction in (1) radiological exposure to site personnel, (2) radiological exposure to the public, and (3) the radiological waste) provides protection of the public health and safety in accordance with 10 CFR 50.82 (b)(1)(ii). The presence of other non-power reactor facilities, as well as other nuclear facilities (e.g. an NRC Special Nuclear Material license and a State license) at the site is another factor to be considered in the decommissioning process as specified in 10 CFR 50.82 (b)(1)(iii).
The delay time would also allow for an integrated approach to the decommissioning of at least the licensed non-power reactors under 10 CFR Part 50 at VNC. This integrated approach would also provide protection of the public health and safety.
GEH requests license continuance beyond the current expiration dates for shutdown reactor licenses DR-10 (EVESR), and TR-1 (GETR). This request is consistent with 10 CFR 50.51(b) that states each license for a facility that has permanently ceased operations continues in effect beyond the expiration date to authorize ownership and possession of the production or utilization facility until the Commission notifies the licensee in writing that the license is terminated. The EVESR and GETR licenses are requested to continue in effect authorizing ownership, possession, control and maintenance of these facilities.
US NRC SPM-15-039 December 15, 2015 Please contact me on (910) 819-5950, if you have any questions or would like to discuss this matter further.
Sincerely, x~P Scott P. Murray, Mana er.
Facility Licensing Commitments: None Attachments: None Cc: B. Watson, USNRC NMSS J. Parrott, USNRC NMSS
GE Hitachi Nuclear Energy Scott P. Murray Manager, Facility Licensing 3901 Castle Hayne Road P.O. Box 780 SPM 15-039 Wilmington, NC 28402 USA December 15, 2015 T (910) 819-5950 scott.murray@ge.com Director, Office of Nuclear Material Safety and Safeguards U.S. Nuclear Regulatory Commission Washington, D.C. 20555-0001 ATTN: Document Control Desk
Subject:
GEH Vallecitos Nuclear Center (VNC) Request for DR-10 and TR-1 License Continuation
References:
- 2) NRC License TR-1, General Electric Test Reactor (GETR), Docket 50-70
- 3) Letter, M. Mendonca (NRC) to G. Stimmell (GE), TR-1, General Electric Test Reactor (GETR), Issuance of Amendment 16, 9/30/92 (Accession
- 4) Letter, M. Masnik (NRC) to G. Stimmell (GE), DPR-1, Vallecitos Boiling Water Reactor (VBWR), License Remains in Effect, 11/3/97 (Accession
- 9711120128)
- 5) Letter, S.P. Murray to Director NMSS, GEH VNC Request for Alternate Decommissioning Schedules, 7/10/15
- 6) Letter, S.P. Murray to Director NMSS, Supplemental Information, GEH VNC Request for Alternate Decommissioning Schedules, 10/15/15
Dear Sir or Madam:
GE Hitachi Nuclear Energy Americas LLC (GEH) hereby requests license continuations for shut down reactor licenses DR-10 (EVESR) and TR-1 (GETR) (References 1 and 2) in accordance with 10 CFR 50.51(b). Both of these licenses currently expire on January 26, 2016. The continuations are similar to the one NRC granted for the DPR-1 (VBWR) facility on November 3, 1997 (Reference 4). License continuations for all three shutdown reactors will support the integrated approach to reactor facility decommissioning at the VNC site as described in References 3, 5 and 6.
GEH is the holder of NRC Licenses DPR-1 (VBWR), DR-10 (EVESR), TR-1 (GETR) and R-33 (NTR) licensed reactor facilities at the VNC site. The VBWR, EVESR and GETR facilities have permanently ceased operations and are being maintained and controlled in a possession only status.
DPR-1 The VBWR is a 50 MW thermal experimental research reactor initially licensed in 1957.
It was shut down on December 9, 1963 for an extended period of time and subsequently deactivated. All fuel has been removed from the reactor and shipped offsite. In addition, much of the equipment used to operate the reactor (nuclear instrumentation, control rod drives, pumps,
US NRC SPM-15-039 December 15, 2015 etc.) has been removed. On September 9, 1965, the AEC amended DPR-1 license to possess, but not operate, the facility in the condition described in the Final Report on Deactivation dated February 5, 1965. The NRC, in amendment 19, subsequently extended the license until May 14, 1996. The VBWR license expired on May 14, 1996 and, pursuant to 10 CFR 50.51(b), continues in effect authorizing ownership, possession, control and maintenance of the facility.
DR-10 The EVESR is a 17 MW thermal experimental research reactor initially licensed in 1963. It was shut down on February 1, 1967 and subsequently deactivated. All fuel and other special nuclear material for the EVESR has been removed and shipped offsite. In addition, much of the equipment used to operate the reactor (nuclear instrumentation, piping, pumps, valves, etc.) has been removed. On June 17, 1968, the AEC amended DR-10 license to possess, but not operate, the facility in the condition described in the EVESR Deactivation Report dated October 12, 1967. The current EVESR license expiration date is January 26, 2016.
TR-1 The GETR is a 50 MW thermal experimental test, development and isotope production reactor initially licensed to operate in 1959. It was shutdown in 1977 and subsequently deactivated. All fuel and isotope production targets containing special nuclear material have been removed from the facility and shipped offsite. The current GETR license expiration date is January 26, 2016.
When NRC extended the TR-1 (GETR) license with the issuance of amendment 16 on September 30, 1992 (Reference 3), the supporting NRC safety evaluation states in Section 3.0:
In response to an NRC staff request for additional information, the licensee, by letter dated August 7, 1992, requested that the expiration date for the GETR be changed to match the EVESR license expiration date from the originally requested 40 year license extension. This request is consistent with the factors to be considered in the delay of decommissioning for licenses other than electric utilities in 10 CFR 50.82 (b)(1)(ii) and (iii). That is, the reduced radiological impact (due to the decay of the residual radioactivity, and the associated reduction in (1) radiological exposure to site personnel, (2) radiological exposure to the public, and (3) the radiological waste) provides protection of the public health and safety in accordance with 10 CFR 50.82 (b)(1)(ii). The presence of other non-power reactor facilities, as well as other nuclear facilities (e.g. an NRC Special Nuclear Material license and a State license) at the site is another factor to be considered in the decommissioning process as specified in 10 CFR 50.82 (b)(1)(iii).
The delay time would also allow for an integrated approach to the decommissioning of at least the licensed non-power reactors under 10 CFR Part 50 at VNC. This integrated approach would also provide protection of the public health and safety.
GEH requests license continuance beyond the current expiration dates for shutdown reactor licenses DR-10 (EVESR), and TR-1 (GETR). This request is consistent with 10 CFR 50.51(b) that states each license for a facility that has permanently ceased operations continues in effect beyond the expiration date to authorize ownership and possession of the production or utilization facility until the Commission notifies the licensee in writing that the license is terminated. The EVESR and GETR licenses are requested to continue in effect authorizing ownership, possession, control and maintenance of these facilities.
US NRC SPM-15-039 December 15, 2015 Please contact me on (910) 819-5950, if you have any questions or would like to discuss this matter further.
Sincerely, x~P Scott P. Murray, Mana er.
Facility Licensing Commitments: None Attachments: None Cc: B. Watson, USNRC NMSS J. Parrott, USNRC NMSS