ML20199D279
| ML20199D279 | |
| Person / Time | |
|---|---|
| Site: | Lynchburg Research Center |
| Issue date: | 11/17/1997 |
| From: | Brown S NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| To: | Johnson T NRC OFFICE OF NUCLEAR MATERIAL SAFETY & SAFEGUARDS (NMSS) |
| References | |
| SECY-91-096-C, SECY-91-96-C, NUDOCS 9711200299 | |
| Download: ML20199D279 (4) | |
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November 17, 1997
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' MEMORANDUM TO: Timothy C; Johnson, Section Leader Facilities Decommissioning Section, LLDP/D MS
- FROM:.
Stewart W. Brown, Project Manager -.
r" Facilities Decommissioning Section, LLDP/DWM/NMSS I
SUBJECT:
OAK RIDGE INSTITUTE FOR SCIENCE AND EDUCATION SURVEY OF TERMINATED NON-POWER REACTOR LICENSE, BABCOCK &
WILCOX LICENS3 R-47 (DOCKET NO 50 99)
The " Updated Report on Site Decommissioning Management Plan", SECY-91-096, required the review of docket files associated with terminated non-power reactors (NPR) licenses. The purpose of this review was to ensure that no contamination in excess p the current U.S. Nuclear Regulatory Commission unrestricted release guidelines exists atthe previously 4
liconsed facilities. In a report dated June 18,1991, Oak RMs Institute for Science and EducatL.n (ORISE), formerly Oak Ridge Associated Universtis, forwarded the results of their
' review of 60 terminated NPR licenses. Their review indicated that the docimt files associated 1
with 30 of the licenses did not contain sufficient information to support unrestncted release.
Further review of these licenses by the Office of Nuclear Reactor Regulation (NRR),
documented in a report dated July 31,1992, halved this number.
i in the absence of complete information, the following conditions, taken from the July 31,1992, NRR review, would be sufficient to conclude that the operations associated with a terminated license would pose no hazard for future site occupants:
l
- 1) The former site has been completely demolished. Either a field, parking lot, or completely new structure currently existo at the old NP1 site;
- 2) the building housing the reactor still exists, but the building has been remodeled to the extent that there is nothing left of the reactor facility to survey; 3)1 this site is currently used for some other purpose involving radioactive material; or
- 4) the reactor authorized was either an AGN-201, AGN-211, or L-77 type research reactor.
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Contact:
S. Brown, DWM!NMSS
- (301)415-6605
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97112 r," ^00299 971117,,= = = = =.. ~
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T. C. Johnson 2-l i
If the above conditions are not met and complete information concerning decommissioning and decontamination cannot be found, then both reviews generally called for confirmatory surveys j
to fillin any information voids.-
ORISE, based on its review of the Babcock & Wilcox License R-47 docket file, noted the -
following:
The Docket File does not contain specific procedures or survey results other than those noted in this report. The only areas surveyed were the heat exchanger room, pool, pool reactor basement, upper pool area, storage deck, control room, and staircases: but -
there were no radiation exposure measurements performed by the Licensee in the pool reactor basement, storage deck, control room, office, stair, or roof and smears were not taken in the office or roof. Additionally, the Licensee did not address the upper walls and ceilings. No other areas were surveyed such as the pump room, office, laboratories, counting rooms, roof, etc. Also, direct measurements for residual contamination were not performed.
Based on ORISE's review, the predominate isotopes were Zn-65 and Co-60 with half lives of 244 days and 6.3 years, respectively. Other isotopes that were found by sampling were Eu 152, Na-22, and Co-57 with half-lives of 15.3 years,2.6 years, and 272 days, respectively.
Since the facility ceased operations over 25 years ago, any isotope with a half-life less than 3.6 years has decayed to less than one percent of its original amount. Based on the small amounts of these isotopes present 25 years ago, isotopes Zn-65, Na-22, and CoJ7 have virtually decayed away. Leaving the only two isotopes Co-60 and Eu 152. Isotope Co-60 has decayed to less than three percent of its or;ginal amount and the amount present 25 years ago was not considered a hcalth risk. Thus, Eu 152 is the only isotope that has not decayed away. The original amount of Eu-152 has only decreased by one-half. However, the original amount of Eu-152 was negligible, as noted in the ORISE report.
In addition NRC Region ll, as part of its routine inspection program of the Naval Nuclear Fuel Division facility located in Lynchburg, Virginia, has twice inspected the site where the reactor formerly licensed as R-47 was located. The first inspection (Inspection Report No. 70-27/95-20, dated December 1,1995) (Attachment 1) found that radiation levels were essentially background nased on area exposure measuren nts. A second inspection of thN area was conducted (Inspection Report No. 70-27/97-10, dated October 27,1997) (Attachment 2) wnes e contact readings were taken. Again, the results were essentially background.
Based on the originai Iow-levels of residual contamination, the levels of residual contamination that would be remaining as a result of iatural decay, and the results of those inspections, I have concluded that the concerns originally raised by ORISE havo been aodressed, and i
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T, C. Johnson -- _..
- residual contamination at this site is below current NRC guidelines. This information should be placed in the docket files associated with the terminated licenses to avert any future duplication of effort.-
Attachment:
As stated cc: w/att: S. Weiss, NRR TICKET:LLDP-71ES
- DISTRlBUTION: ; Cintral Filel '
. RJohnson LBell
- DOCUMENT NAME:6.1 - s:\\dwm\\ildp\\swb\\npr.b&w
- See previous concurrence j
,OFC LLDP M LLDP' LLDP LLM d
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JCopeland*
TJohnson*
JHbey DATE 11'd4/97 11/14//97 11/12/97 11/i/97
_ OFFICIAL RECORD COPY LSS:
YES _X_ NO ACNW:
YES NO.
_X_
IG:
YES NO
_X_
Delete file after distribution YES NO
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e T.C, Johnson.
Based on the original low-levels of residual contamination, the levels of resi I contamination that would be remaining as a result of natural decay, and the results of thpse inspections, I have concluded that the concerns originally raised by ORISE have beery sddressed, and residual contamination at this site is below current NRC guidelines. T) fs information should be placed in the docket files associated with the terminated licenses t vert any future duplication of effort.
cc: w/att: S. Weiss, NRR
Attachment:
As stated
-TICKET:LLDP-7196 DISTRIBUTION:
Central File LLDP r/f f WM r/f NMSS r/f PDR RNelson RJohnsory/ Madams MW;ber 6.1 - s:\\dwm\\lldp\\swb\\n/
pr.b&w DOCUMENT NAME:
OFC LLDP A LLDPvb LLDP,/1 LLDP
,o SBrkhv JCopda TJhMn' JHickey NAME DATE i !) /f407
[$/97
// h/97
/ /97
/ /94 OFFICIAL RECORD COPY l.SS: YES _XfNO ACNW:
YES' NO
_X_
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YES/
NO
_X_
Delete file after distribution YES NO I-
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