ML19263C539
| ML19263C539 | |
| Person / Time | |
|---|---|
| Site: | Plum Brook |
| Issue date: | 02/17/1979 |
| From: | NATIONAL AERONAUTICS & SPACE ADMINISTRATION |
| To: | |
| Shared Package | |
| ML19263C537 | List: |
| References | |
| NUDOCS 7902260459 | |
| Download: ML19263C539 (8) | |
Text
REPORT OF REACTOR STANDBY CONDITION FOR THE NASA PLUM BROOK REACTOR Reporting Period: January 1,1978 - December 31, 1978 ANNUAL REPORT License No. TR-3 Docket No. 50-30 February 17, 1979 f:ASA-Lewis Research Center Plum Brook Station Sandusdy, Ohio 790226o di
REPORT OF REACTOR STANDBY CONDITION FOR THE NASA PLUM BROOK REACTOR Reporting Period: January 1,1978 - December 31, 1978 The following report has been prepared pursuant to Section 20.l(2) of Attachment A Change rh.
32, Amendment No. 6 to Amended Facility License No. TR-3.
This report covers the 1978 Calendar Year period of the possess, but not operate 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 Specifica-tions, plus some other considered of importance for maintaining the Facility in a safe standby condition. The Containment Vessel cathodic protection remains energized, but is providing less than the recommended level of cathodic protection for a portion of the Containment Vessel wall. The need to renovate this system is under study. All other systems and components are in the condition specified in the Technical Specifications and/or PBRF Standby Procedures.
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 build-ings atthe Facility is inspected by a guard once each day.
In addition, other security checks such as checks of fences and locks are being con-ducted 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 com-ponents to assure that the standby condition is maintained in accordance with the Technical Specifications and/or Standby Procedures.
All of the security and surveillance inspections are accomplished with the 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) I%ager and/or the PBRF Radiation Protection Officer and filed as part of the PBRF Vital Records. Equipment Maintenance 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 transitions between the radiological control zones.
Al pha : Maximum level (d/m/100cm )
White to Magenta-Yellow Zones 0
Magenta-Yellow to Magenta Zones 0
Beta-Gamma : Maximum level (c/m)
White to Magenta-Yellow Zones 700 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 co :taining two TLD discs is positioned at each locatior.
lx,7 rates, in mr/hr, are computed from time of installation to time of readout. One disc is exchanged and processed quarterly, and the other on an annual basis.
Maximum Quarterly Maximum Dose Rate Single Annual TLD readout (Quarterly)
TLD readout (mr)
Location (mr)
(mr/hr) 1/1/78-12/31/78 PBRF Fenceline N 11.8
.005 67.4 PBRF Fenceline S 12.5
.006 13.7 PBRF Fenceline E 14.5
.007 30.0 PBRF Fenceline W 13.5
.006 18.5 Reactor Building N 28.4
.01 3 73.5 Reactor Building S 26.9
.01 2 64.5 Reactor Building E 25.2
.01 2 50.1 Reactor Building W 26.2
.01 2 52.3 Hot Laboratory S 17.5
.008 32.1 Hot Laboratory E 91.0
.042 209.9 Hot Laboratory W 15.3
.007 26.5
. b.
Transferable Contamination Surveys Representative smear surveys of surfaces at the transitions between radiolocigal control zones are performed routinely. Listed below are the maximum contamination levels detected at any time during the report period.
2 Al pha : Maximum level (d/m/100cm )
White to Magenta-Yellow Zones 0
Magenta-Yellow to Magenta Zones 0
2 Beta Gamma: Maximum level (d/m/100cm )
White to Magenta-Yellow Zones 658 Magenta-Yellow to Magenta Zones 2,830 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 are obtained over a 24-hour period at a flow rate of approximately two cfm.
(1)
Particulate - HV 70.
ALPHA BETA-Gate 1A Number Average Maximum Average Maximum Location of Samples uCi/cc uCi/cc uCi/cc uCi/cc PBRF Stack 4
1.7x10-15 0.69x10-I4 0.41x10 1.26x10-12
-12 CV 0' Elevation 4
19.1x10 15 2.08x10-I4 0.79x10-12 1.37x10-12 15 CV-40' Elevation 4 14.8x1015 2.08x10 1.02x10 1.81 x10-12
-I4
-12 Hot Laboratory 4
13.9x10-2.78x10 3.40x10 5.06x10-12
-I4
-12 (2) Charcoal Cartridge.
GAMMA Number Average Maximum Location of Samples uCi/cc uCi/cc PBRF Stack 4
0.29x10 "
0.08x10-"
0.06x10 "'
0.18x10-
CV 0' Elevation 4
CV-40' Elevation 4 0.05x10 "
0.13x10 '
Hot Laboratory 4
0.08x10-0.16x10-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 ml evaporated to dryness is measured, and reported in uCi/ml of sample.
. ALPHA BETA-GAMMA Number Average Maximum Average Maximum Location of Samples UCi/ml uCi/ml uCi/ml uCi/ml ERB 4
0.004x10-7 0.009x10-7 0.82x10-7 1.024x10 7
CRA #1 4
NS0 NSO 0.33x10 7 0.441x10 7 CRA #2 4
0.008x10-7 0.023x10-7 0.44x10 7 0.627x10 7 Dee: Wells 4
0.004x10-7 0.011x10 7 0.10x10-0.170x10 PBLF Effluent 4
0.005x10 ~ 7 0.010x10-0.005x10-7 0.127x10-7 NOTE: Where "NS0" appears it indicates the counting results were so low as to be statistically not significantly different than zero.
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 loca-tions. Stream silt and water samples are collected from Plum Brook stream and the PBRF effluent 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 Sampl es uCi/cc uCi/cc uCi/cc uCi/cc Particulate 16 1.91 x10-15 11.11x10-15 0.13x10-12 0.53x10-12
-12 0.19x10-12 0.38x10 Charcoal 16 b.
Water Samples ALPHA BETA-GAMPA Number of Average Maximum Average Maximum Location Samples uCi/ml uCi/ml uCi/ml uCi/ml Plum Brook 4
0.03x10-7 0.08x10-7 0.17x10-7 0.27x10-7 stream-upstream
-7 Plum Brook 4
0.005x10-7 0.0lx10-0.08x10-7 0.13x10 stream-downstream c.
Silt Samples ALPHA BETA-GAMMA Number of Average Maximum Average Maximum Location Sampl es uCi/gm uCi/gm uCi/gm uCi/gm
-6
-5
-4
-4 PBRF Effluent 16 9.84x10 1.3x10 0.56x10 3.2x10 Ditch Plum Brook 8
7.52x10-6 1.3x10-5 0.24x10-5 0.31 x10-4 Stream
. 5.
Changes to the PBRF Facility:
There were no Facility changes during the reporting period.
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.
Signiiicant 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 leak test and repairs.
d.
C.V. cathodic protection system checks.
e.
Emergency big beam light servicing and repairs.
f.
C.V. dome insulation repairs.
g.
Replacement of roof vent caps h.
Spray coating of ROLB and ATS building with plastic preservative.
i.
Door lock repairs (periodic maintenance).
J.
SEB boiler annual inspection and maintenance.
k.
Seasonal and other maintenance on heating system components.
1.
Leak isolation and water cleanup in SPR.
m.
Leak repair and water cleanup in HPT.
n.
Repair of reactor substation voltage regulator.
6.
_0ther:
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 Specifications to ex-clude 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 require-ments. The revisions to the Technical Specifications were designed to take effect when the above buildings, water tank and grounds area are
. shown t-be free of radioactive contamination and separated from the PBRF by security barriers and isolation of the process piping.
In the previous reporting period (1977 Annual Report), it was reported that NASA expected to complete activities to effect this exclusion by the Fall of 1978.
Ex-clusion, however, has not yet been accomplished and the aforementioned buildings and area remain under licensing control.
Indecision by the EPA (for whom the buildings and area were to be excluded for use) continues to delay the exclusion activity. Effort on this activity was suspended in the Spring of 1978. To date, the equipment that was stored in the buildings and area to be excluded from the PBRF has been removed, but implementation of isolation has been held in abeyance pending decision for use by the EPA.
b.
Disposal of Excess Plum Brook Station Property - In the previous reporting period (1977 Annual Report), it was reported that NASA intended to excess about 550 acres of the approximate 6,000 acre fenced area of Plum Brook Station. The excess area has since been surveyed and consists of 604 acres, 43 acres of which has been deeded to Perkins School System.
The 43-acre site, however, remains under NASA control until the facilities, including the PBS Communications Center, are relocated to a new site on Plum Brook Station property and the security fence is relocated.
It is anticipated that the remaining 561 acres of excess property within the Plum Brook Station fenced area will be transferred to the EPA via GSA.
This property would continue to be owned by the U.S. Government.
In addition, NASA will continue to control access to Plum Brock Station, inspect and maintain the PBS perimeter fence, and provide security sur-veillance for the entire PBS perimeter fence. The nearest point of the property affected is 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 (1977 Annual Report), it was reported that NASA had decided to forego plans for any future operation of the Plum Brook Reactor Facility and NASA had established an ad hoc committee to consider future disposition of the Facility.
In addition, it was raported that, based on infomation obtained from the NRC and others, NASA had identified a number of options available for further decommissioning of the Facility.
During this reporting period a study was performed under NASA contract to evaluate options considered appropriate for further decommissioning of the Plum Brook Reactor Facility. Review of the results of this study was com-pleted by the NASA ad hoc committee in November 1978 and recommendations of the committee have been submitted to NASA management.
d.
PBRF Audit - The annual Plum Brook Reactor Facility audit by the Lewis Research Center Audit Team was conducted on February 28, 1978. The Audit Team noted no items of noncompliance with either the license condi-tions or standby procedures-
, f[RC Inspection - An NRC compliance inspection was performed on e.
December 13, 1978. No items of noncompliance or deviations were iden-tified in any of the areas inspected.
f.
Unusual Occurrences - There were no unusual occurrences during the reporting period.