ML19296C478
| ML19296C478 | |
| Person / Time | |
|---|---|
| Site: | Plum Brook File:National Aeronautics and Space Administration icon.png |
| Issue date: | 02/20/1980 |
| From: | NATIONAL AERONAUTICS & SPACE ADMINISTRATION |
| To: | |
| Shared Package | |
| ML19296C476 | List: |
| References | |
| TR-3, NUDOCS 8002260247 | |
| Download: ML19296C478 (8) | |
Text
4-REPORT OF REACTOR STANDBY CONDITION FOR THE NASA PLUM BROOK REACTOR Reporting Period:
January 1, 1979 - December 31, 1979 ANNUAL REPORT License No. TR-3 Docket No. 50-30 February 20, 1980 NASA-Lewis Research Center Plum Brook Station Sandusky, Ohio 8002260
f.
REPORT OF REACTOR STANDBY CONDITION FOR THE NASA PLUM BROOK REACTOR Reporting Period:
January 1, 1979 - December 31, 1979 The following report has been prepared pursuant to Section 20.l(2) of Attach-ment A, Change No. 32, Amendment No. 6 to Amended Facility License No. TR-3 This report covers the 1979 Calendar Year period of the possess, but not op-erate license.
1.
Condition of Systems and Components:
The condition of all systems and components vital to the maintenance of a safe standby condition has been carefully reviewed. This includes all systems and components specifically noted in the Technical Specifications, plus some others considered of importance for maintaining the Facility in a safe standby con-dition. The Containment Vessel Cathodic Protection System remains energized, but is providing less than the recommended level of cathodic protection for a portion of the Containment Vessel wall.
Since NASA plans to dismantle the Plum Brook Reactor in the very near future (see item 6c, below), no renovation of this system is intended. All other systems and components are in the condition specified in the Technical Specifications and/or PBRF Standby Proce-dures.
2.
Assessment of Security and Surveillance Measures:
Security inspections are conducted at the Plum Brook Reactor Facility once each shift, i.e., three times per day, and each of the major buildings at the Facility is inspected by a guard once each day.
In addition, other security checks such as checks of fences and locks are being conducted monthly as specified in Section 18.2 of the Technical Specifications.
Surveillance of operating systems and components, absolute filters, and radiological surveys is being performed as specified in the Technical Specifications and/or Standby Procedures.
In addition, surveillance inspections are being performed for some nonoperating systems and components to assure that the standby condition is maintained in accordance with the Technical Specifications and/or Standby Procedures.
ll of the security and surveillance inspections are accomplished with the A
use of Inspection and Test Report (ITR) checksheets to insure that they are completed properly and in a timely manner.
Completed ITR's are reviewed and approved by the Plum Brook Reactor Facility (PBRF) Manager and/or the PBRF Radiation Protection Officer and filed as part of the PBRF Vital Records.
Equipment Maintenence Records (EMR's) are completed to document maintenance on vital components, equipment, systems and facilities which are not otherwise covered under the routine ITR system.
. The security and surveillance program in effect at the Plum Brook Reactor Facility is more than adequate to maintain the Facility in a safe standby condition.
3 Changes in Procedures:
There were no significant changes in procedures during the reporting period.
4.
PBRF and Environmental Radiological Surveys:
The following is a summary of the results of radiological surveys performed at the Plum Brook Reactor Facility and the surrounding environs.
4.1 Facility Monitoring a.
Direct Radiation Surveys (1)
Surveys of direct radiation levels using portable survey instruments are routinely performed at the tra6: :lons between the adiological control zones.
2 Alpha: Maximum level (d/m/100cm )
E, White to Magenta-Yellow Zones 0
Magenta-Yellow to Magenta Zones 0
Beta-Gammb: Maximum level (c/m)
White to Magenta-Yellow Zones 350 Magenta-Yellow to Magenta Zones 70,000 (2)
Surveys of general area direct radiation levels using TLD's are made at 11 locations.
A packet containing two TLD discs is positioned at each location.
Dose rates, in mr/hr, are computed from time of installation to time of readout.
One disc is ex-changed and processed quarterly, and the other on an annual basis.
Maximum Quarterly Maximum Dose Rate Single Annual TLD readout (Quarterly)
TLD readout (mr)
Loca+ Ion (mr)
(mr/hr) 1/1/79-12/31/79 PBRF Fenceline N 5.4
.002 14.6 PBRF Fenceline S 6.7
.003 18.4 PBRF Fenceline E 9.2
.004 37.3 PBRF Fenceline W 8.3
. 004 31.4 Reactor Building N 18.6
.009 69.9 Reactor Building S 17.7
.008 66.4 Reactor Building E 26.7
.012 45.0 Reactor Building W 15.7
.007 60.5 Hot Laboratory S 8.1
.004 32.5 Hot Laboratory E 62.7
.029 300.4 Hot Laboratory W 6.7
.003 84.3
. b.
Transferabit Contamination Surveys Representative smear surveys of surfaces at the transitions be-tween radiological control zones are performed routinely.
Listed below are the maximum contamination levels detected at any time during the report period.
2 Alpha: Maximum level (d/m/100cm )
White to Magenta-Yellow Zones 0
Magenta-Yellow to Hagenta Zones 0
2 Beta Gamma: Maximum level (d/m/100cm )
White to Magenta-Yellow Zones 134 Magenta-Yellow to Magenta Zones 925 c.
Air Sample Surveys Air samples are collected by drawing air successively through an HV 70 filter paper or equivalent, and a Whatman 41 charcoal cartridge or equivalent.
Samples e obtained over a 24-hour period at a flow rate of approximately two cfm.
(1)
Particulate - HV 70.
ALPHA BETA-GAMMA Number Average Maximum Average Maximum Location of Samples uCi/cc uCI/cc uCi/cc uCi/cc
~IS
~I4
-12
-12 PBRF Stack 4
6.9x10 2.08x10 0.11x10 0.17x10
-15
-I4
-12
-12 CV 0' Elevation 4
10.4x10 2.08x10 0.62x10-0.92x10j2 1.01x10 1.39x10 If 0.64x10_I2 CV-40' Elevation 4
5.2x10 j
j2 Hot Laboratory 4
9.5x10 3.15x10 0.18x10 0.73x10 (2)
Charcoal Cartridge.
GAMMA Number Average Maximum Location of Samples uCi/cc uCi/cc 0.05x10jl PBRF Stack 4
0.01x10 CV 0' Elevation 4
0.55x10.jj 0.97x10.jy CV-40' Elevation 4
0.45x10 Hot Laboratory 4
0.20x10~
0.11x10 I
0.33x10 d.
Water Samples Water samples are collected from the Emergency Retention Basin (ERB), the Cold Retention Area Tanks (CRA), the PBRF liquid effluent stream, and any one of the three deep wells.
The gross alpha and gross beta-gamma activity in 500 mi evaporated to dryness is measured, and reported in uti/mi of sample.
. ALPHA BETA-GAMMA Number Average Maximum Average Maximum Location of Samples uCi/ml uCi/ml uCi/mi uCi/mi
~7
-7
-7 ERB 4
0.008x10'7 0.027x10 0.456x10 0.627x10
-7
~7
~7
~7 CRA #1 4
0.006x10 0.016x10 0.262x10 0.276x10
-7
~7
-7
-7 CRA #2 4
0.016x10 0.039x10 0.303x10 0.449x10
~7
~7
-7
-7 Deep Wells 4
0.012x10 0.017x10 0.120x10 0.153x10
~7
~7
-7
-7 PBRF Eifluent 4
0.038x10 0.090x10 0.225x10 0.506x10 4.2 Environmental Monitoring Representative samples of airborne activity are routinely collected at four locations at a distance of approximately 1000 yards from the PBRF.
Direct radiation levels are monitored using TLD's at the same four locations.
Stream silt and water samples are collected from Plum Brook stream and the PBRF efflu-ent ditch external to PBRF.
a.
Air Sample Surveys Air samples are collected in the same manner as in item 4.lc above, except the sampling duration is five to seven days.
ALPHA BETA-GAMMA Type of Number of Average Maximum Average Maximum Sample Samples uCi/cc uCi/cc uCi/cc uCi/cc
-15
-15 2
Charcoal 16 0.02x10_ ] 0.09x10[j2 Particulate 16 1.35x10 3.47x10 0.31x10 0.58x10 b.
Water Samples ALPHA BETA-GAMMA Number of Average Maximum Average Maximum Location Samples uCi/ml uCi/mi uCi/ml uC1/ml
-7
-7
-7
-7 Plum Brook 4
0.02x10 0.04x10 0.096xlo 0.126x10 stream-upstream Plum Brook 4
0.028x10-7
~7
~7
-7 0.044x10 0.147x10 0.21x10 stream-downstream c.
Silt Samples ALPHA BETA-GAMMA Number of Average Maximum Average Maximum Location Samples uCi/gm uCi/gm uCi/gm uCi/gm
-6
-5
~
PBRF Effluent 16 7.77x10 1.2x10 0.34x10 0.78x10" Ditch Plum Brook 8
6.66x10-6 1.0x10-5 0.19xlo-5 0.25x10-4 Stream
. 5 Changes to the PBRF Facility:
One Facility Change was implemented during the reporting period. The change was as follows:
Facility Change #79-001 - New Standby Heating System This Facility Change provided for the installation of natural gas fired unit heaters and electric unit heaters. The new installation complements existing natural gas fired and electric unit heaters used for standby heating and provides minimum heating in areas previously heated via the SEB Steam Boilers. The new system thus eliminates the need for costly operation of the Boilers and the grossly inefficient steam heating system. The Steam Bollers and system were secured, drained, and placed in standby, and may be used as a backup system, if needed. The new installation / mode of operation does not constitute an unre-viewed safety question.
The only other changes consisted of one-for-one or equivalent replacements of components such as sump pumps, piping, relays, switches, etc., and other minor repairs.
Significant maintenance tasks included:
a.
Repair of the RB deepwell pumps, piping and control circuits.
b.
Periodic maintenance for sump pumps, alarms and controls, c.
R.T. nitrogen purge system component replacements.
d.
C.V. cathodic protection system replacements / repairs.
e.
Emergency big beam light servicing and repairs.
f.
C.V. dome insulation rework.
g.
Replacemert of roof vent caps h.
Natural gas line repair in SEB valve pit.
i.
Repair of leak in natural gas line north of SEB.
j.
SEB boiler annual inspection and maintenance.
k.
Seasonal and other maintcaance on heating system components.
1.
Repair of leak in Raw Water line along Centerline Road, m.
Leak isolation and water cleanup in Fan House, n.
Repair of shorted circuit :n substation "E" lights control.
o.
Repairs to Plum Brook Station flood gates at Pipe Creek boundary (security barrier).
,, 6.
Other:
a.
TR-3 License Change - On December 17, 1976, the NRC issued Amendment No. 6 to the Amended License TR-3 for the Plum Brook Reactor. This amendment revised the License and Technical Specification to exclude Building 1121, the Assembly, Test and Storage (ATS) Building; Building 1142, the Reactor Office Building, Structure 1156, the ATS Water Storage Tank; and the grounds adjacent thereto from the controlled area of the Plum Brook Reactor Facility (PBRF) and from licensing requirements. The revisions to the Technical Specifications were designed to take effect when the above buildings, water tank and grounds arc are shown to be free of radioactive contamination and separated from the PBRF by security barriers and isolation of the process piping.
In the previous reporting period (1978 Annual Report), it was reported that due to indecision by the EPA (for whom the buildings and area were to be excluded for use) ex-clusion had not been accomplished and the aforementioned buildings and area continued under licensing control.
In 1979, the EPA decideJ to forego plans to utilize the ATS Building, hence, the buildings and areo,were not isolated from the PBRF and therefore, remain under licensing control.
b.
Disposal of Excess Plum Brook Station Property - In the previous report-ing period (1978 Annual Report), it was reported that NASA had deeded 43 acres (actually 45 acres) of property within the Plum Brook Station (PBS) fenced area to Perkins School system and was anticipating transferring 561 (actually 604 acres) additional acres of excess property wi min the PBS fenced area to the EPA via GSA. The 45-acre site deeded to Perkins School system continues under NASA control until the NASA facilities located on the site, including the PBS Communications Center, are relocated to a new site on Plum Brook station property (new facilities are currently under construction) and the security fence is relocated.
NASA has not yet transferred the 604-acre plot to EPA, but the transfer is expected to be consummated via GSA in the near future.
This property will continue to be owned by the U.S. Government.
In addition, NASA will continue to control access to Plum Brook Station, inspect and maintain the PBS perimeter fence, and provide security surveillance for the entire PBS perimeter fence.
The nearest point of the property affected ir more than 4,000 feet from the fenced site of the Plum Brook Reactor Facility.
Standby conditions at the PBRF site will be unaffected.
c.
Future Disposition of the Plum Brook Reactor Facility - In the previous reporting period (1978 Annual Report), it was reported that a study had been performed under NASA contract to evaluate options considered appropriate for further decommissioning of the Plum Brook Reactor Facility (PBRF).
It was also re-ported that the results of this study had been reviewed by the NASA ad hoc committee (chartered to consider future disposition of the PBRF) in November 1978 and that recommendations of the committee had been submitted to NASA Management.
In April 1979, NASA decided to proceed with plans to dismantle the radioactive portions of PBRF. This would consist of the dismantlement and removal of all detectable reactor-originateo adioactivity above permissible limits so that the PBRF licenses may be terminated.
Since June 1979, NASA has been actively engaged in developing plans and compiling and formulating requi-site information and documentation for submission to the NRC to obtain Dismantl-ing Orders for the Plum Brook Reactor (PBR) and the Mockup Reactor (MUR), and revision to the PBRF Byproduct Materials License.
In addition, NASA has es-tablished a PBRF Dismant1ing Safety Committee with specific responsibi1ity to
. conduct safety review of all matters having safety implication relative to dismantling the PBRF, which includes review of all documentation relative to dismantiing prior to submittal to the NRC.
It is anticipated that submittal of documentation packages to the NRC for obtaining the Dismantling Orders and for revising the PBRF Byproduct Materials License will occur in late February or early March 1980.
d.
PBRF Audit - The annual Plum Brook Reactor Facility audit by the Lewis Research Center Audit Team was conducted on March 21, 1979 The Audit Team noted no items of ncacompliance with either the license conditions or standby procedures.
e.
Unusual Occurrences - There were no unusual occurrences during the reporting period.