ML19341C510
| ML19341C510 | |
| Person / Time | |
|---|---|
| Site: | Plum Brook File:National Aeronautics and Space Administration icon.png |
| Issue date: | 02/17/1981 |
| From: | NATIONAL AERONAUTICS & SPACE ADMINISTRATION |
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| NUDOCS 8103030666 | |
| Download: ML19341C510 (12) | |
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4 REPORP OF REACIOR STANDBY OWDITICN FOR THE NASA, PIIM BIOOK REACIOR Reporting Period: January 1, 1980 - M r 31, 1980 AN?RRL REPORP
.t License No. TR-3 Docket No. 50-30 1
s i
1 February 17, 1981 NASA, Lewis Research Center Plum Brook Station Sandusky, Ohio e
81osoa"666
REPORP OF RFJCIOR STANDBY CCNDITICN FOR 'IIIE l
I NASA, PLUM BROOK RE/CIOR Reporting Period: January 1, 198'O - Decenber 31, 1980 The following report has been prepared pursuant to Section 20.1(2) of Attachmnt A, Gange No. 32, Arendnent No. 6 to Amended Facility License No. TR-3.
'Ihis report covers the 1980 Calendar Year period of the possess, but not operate, license.
1.
Condition of Systens and Conponents:
'Ihe condition of all systens and cmponents vital to the naintenance of a safe standby omdition has been carefully reviewed. 'Ihis includes all systenu and components specifically noted in the Tecnical Specifications plus sono others ccnsidered of inportance for naintaining the Facility in a safe standby conditicn. As reported in previous years, the Containrent Vessel Cathodic Protection System rennins energized, but is providing less than the recormended level of cathodic protection for a portion of the Containment Ves-sel wall. Since NASA plans to disunntle the Plum Brook Reactor Facility (PBRF) in the very near future (see Item 6c below) no renovation of this system is intendad. All other systens and conponents are in the condition specified in the Technical Specification and/or PBRF Standby Procedures.
2.
Assessannt of Security and Surwillance Measures:
Security inspections are cmducted at the Plum Brook Reactor Facility once each shift, i.e., three tines per day, and each of the najor buildings at the Facility is inspected by a guard cnce each day.
In addition, other security checks such as checks of fences and locks are being conducted nonthly as specified in Section 18.2 of the Technical Specifications. Surveillance of operating systens and contonents, absolute filters, and radiological surveys is being perfornud as specified in the Technical Specifications and/or Standby Procedures. In addition, surveillance inspections are being perforned for sone nonoperating systems and emponents 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 accorplished with the use of Inspection and Test Report (ITR) checksheets to insure that they are conpleted properly and in a tinely manner. Concleted ITR's are reviewed and approvad by the Plum Brook Ibactor Facility (PBRF) Manager and/or the PERF Radiation Protection Officer and filed as part of the PBRF Vital Records.
l Any ITR's requiring correctim action are reviewed as well by the Plum Brook Manage: rent Office. Dquipnent maintenance Iboords (EMR's) are coupleted to document maintenance on vital conponents, equipnent, systems and facilities which are not otherwise covered under the routine ITR system.
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2-The security and surveillance program in effect at the Plum Brook Reactor Facility is more than adegmte to maintain the Facility in a safe standby condition.
3.
Omnaes in Procedures:
During the reporting period, the following changes to Standby Procedures.
were inplenented:
Procedure Qianae No._
Description 80-1 Revision to procedures necessary for operation of new natural gas fired unit heaters which eliminated the need to operate the nore costly SLB Steam Boilers.
'Ihe Steam Boilers have been placed in standby and nny be used as a backup system, if needed. This heating system change was describcd in the previous
., reporting period (1979 Annual Ibport).
80-2 Additim of new procedures describing the scope of training and qualificatims of successor personnel for assignnnnt as Standby Manager or Alternate Standby Ibnager, Plum Brook Peactor Facility.
80-3 Revision to procedures reflecting operation of the redesigr.ed pressure reducing station for the continuous reactor tank nitrogen gas purge system. 'Ihis activity is described below in Paragraph 5, Facility 01ange No. FC 80-06.
4.
PERF and I:nvironmental Radiological Surveys:
The following is a suntary of the results of radiological surveys perforned at the Plum Brook Reactor Facility and the surrounding envirms.
4.1 Facility hbnitoring a.
Direct Radiation Surveys (1) Surveys of direct radiation levels using portable survey instrunents are routinely performed at the transitions between the radiological control zones.
2 Alpha: Manmum level (d/nt 100am )
/
c White to Magenta-Yellow Zones 0
Magenta-Yellow to Magenta Zones 0
i Beta-Ganma: Mmmum level (c/m)
Nhite to Magenta-Yellow Zmes 300 Magenta-Yellow to Magenta Zones 70,000 e
e w
(2) Surveys of general area direct radiation levels using TID' are rode at 11 locations.
A, packet ccntaining two TID's is positioned at each location. Dose rates, in mr/hr, are conputed from time of installation to tine of readout.
One TID is exchanged and processed quarterly, and the other on an annual basis.
Maximum Quarterly Maximum Dose Rate Single Annual TID Readout (Quarterly)
TID Readout (mr)
Iocation (mr)
(mr/hr) 1/1/80-12/31/80_
PBRP Fenwline N 11.0 0.005 13.1 PBRF Penceline S 6.2 0.003 14.4 PBRF Fenceline E 12.3 0.006 22.0 PBRF Fenmline W 15.0 0.007 22.0 Reactor Building N 18.2 0.008 54.6 Reactor Building S 17.4 0.008 43.9 Reactor Building E 12.1 0.006 38.7 Peactor Building W 17.9 0.008 54.6 IIot Iaboratory S 9.0 0.004 24.9 Hot Iaboratory E 69.3 0.032 199.0 Hot Iaboratory W 8.9 0.004 20.7 b.
Transferable Contamination Surveys Ibpresentative snear surveys of surfaces at the transitions between radiological control zones are performed routinely. Listed below are the maximum contamination levels detected at any time during the reporting period.
2 Alpha:
Maximum level (d/ny'100cn )
hhite to Magenta-Yellow Zones 0
Magenta-Yellow to Magenta Zones 0
2 Beta Gantna: Mmmum lesel (d/ml00cm )
h'hite to Magenta-Yellow Zones 123 Magenta-Yellow to Magenta Zones 4177 c.
Air Sanple Surveys Air sanples are collected by drawing air successively through an HV70 filter paper or equivalent, and a Whatman 41 charcoal cartridge or equivalent. Sanples are obtained over a 24-hour period at a flow rate of approximate 19 two cfm.
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(1) Particulate - IN 70.
AIPHA
,B EA-CA %
Number Average Maxirtri Average Maxiraum Iocaticn of Sanples uCi/cc uCi/cc tCi/cc tCi/cc
-15
-14
-12
-12 PBRF Stack 4
7.79x10 2.08x10 0.14x10
- 0. 36:d0
-15
-14 12
-12 CV 0' Elev. 4 14.7x10 3.45x10 0.88x10 1.84x10
-15
-14
-12
-12 CV-40' Elev 4 12.9x10 3.45x10 0.66x10 2.04x10
-15
-14
-12
-12 Hot Lab 4
8.7x10 1.74x10 1.26x10 4.3x10 (2). 01arocal Cartridge.
cA %
Ntuber Average
&xirun Iocation of Sanple uCi/cc tCi/cc PBRF Stack 4
- NSO USO-
-11
-11 CV 0' Elev.
4 0.03x10 0.09x10
-11
-11 CV-40' Elev.
4 0.03x10 0.10x10
-11
-11 Hot Laboratory 4
0.06x10 0.12x10 d.
Water Sanples Water sanples are collected from the Emergency Betention, Basin (ERB), the Cold Retention Area Tanks (CPA), the PBRF liquid effltymt strean
]
and any one of the three deep wells. ' Die gross alpha and gross beta gantra activity in 500 ml evaporated to dryness is neasured, and reported in tCi/ml of sanple.
ALPHA BETA-GN4%
Nunber Average Maxuun Average Maxirtra location of Sanoles uCi/ml tCi/ml uCi/ntl uCi/ml
-7
-7
-7
-7 ERB 4
0.009x10 0.03x10 0.34x10 0.46x10
-7
-7
-7
-7 CRA#1 4
0.017x10 0.04x10 0.179x10 0.27x10
-7
-7
-7
-7 CRA#2 4
0.055x10 0.075x10 0.22x10 0.28x10
-7
-7
-7
-7 Ibep Wells 4
0.004x10 0.009x10 0.07x10 0.12x10.
-7
-7
-7
-7 PBRF Effluent 4.
0.036x10 0.066x10 0.063x10 0.095x10
- NOIE:
Where "NSO" appears it indicates the counting results were so low as to be statistically not significantly different than zero.
4.2 Envirorcental bbnitoring - On-Sit _e Bepresentative sanples of airborne activity are routinely collected at four locations at a distance of approximately 1000 yards frun the PBRF, within the Plun Brook Station. Direct radiation lewls are nmitored using TID's at the sann four locaticns. Stream silt and water sanples are collected from Plu:n Brook stream and the PBRF effluent ditch external to PBRP.
a.
Air Sanple Surveys t
Air sanples are collected in the sane runner as in Item 4.lc
$1bove, execpt the sanpling duration is five to seven days.
ALPHA BETA-GNA Type of Nurrber of Average Maxinum Average
~ Maximum
~
Sanple Sanples uCi/cc uCi/cc uCi/cc uCi/_cc _-12
.r
-15
-15
-12 Particulate 16 2.87x10 11.96x10 0.03x10 0.12x10
-12
-12 Cnarcoal 16 0.22x10 0.50x10 b.
Water Sanples ALPHA BL%-GVta Ntrber of Average Max 1run Average Maximum Incation Sannles uCi/ml uCi/ml uCifm_l uCi/ml
-7
-7
-7
-7 Plum Brook 4
0.03x10 0,05x10 0.llx10 0.14x10 stream-upstream
-7
-7
-7
-7 Plum Brook 4
0.015x10 0.05x10 0.08x10 0.18x10 strean-downstream l '
c.
Silt Sanples ALPHA
~BLTA-GWA Nunber of Average Maxinun Average' btiximum Incation Sanples uCi/ml uCi/ml uCi/m_1 uCi/ml
-6
-5
-4
-4 PBRF Effluent 16 7.18x10 1.2x10 0.36x10 0.97x10
-6
-5
-5
-4 Plum Brcok 8
6.3 x10 0.9x10 0.21x10~~
0.25x10 Stream l
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. I.
d.
Direct Radiation Direct radiaticn levels are determined by using TLD's at the four
]
n air sa pling staticns.
A packet containing two TID's is positioned at
')
each location. Ibse rates, in mr/hr, are 'cotiputed from tine of installation h
to tinn of readout.
One TID is exchanged and processed quarterly, and the 4
other cn an annual basis.
J i
Maximum Quarterly Maximum Dose Rate Single Annual Sector TID Readout (quarterly)
TID Readout (mr)-
)
Incation (mr)
(mr/hr) 1-1-80-12-31-80.
North 8.6 0.004 &
East 20.1 0.009 22.2 South 6.6 0.003 27.0 West 13.7 0.006 22.2 4.3 Cnvironnentalftpitoring - Off-Site _
An of f-site environnental monitoring program was reinstituted, beginning April 1,1930, for the purpose of obtaining current radiation background data in anticipati.on of future use during further PBRF decomnissionine activities.
Weekly airborne particulate and fallout / precipitation sanples cre collected from four off-site sectors at distances of 3 to 10 miles from PRBF.
Quarterly silt /
soil, vegetation, and monthly direct radiation (TID) sanpling are also obtained at these same four locations.
A total of 8 weekly water samles are also obtained from the above four locations plus four additicnal locaticns.
a.
Air Sanple Surwys Particulate air sanples are collected over a five to seven day period in the aane manner as described in Item 4.1.c., except charcoal cartridges are excluded.
ALPIR BETA-GMea Nuitxar of Average Maximum Average Maximum I.ocation Sa: roles uCi/cc uCi/cc uCi/cc uCi/pc
-15
-15
-14
-14 Sandusky 1-C 40
< 5X10 8x10 7x10 20x10
-15
-15
-14
-14 durcn 3-B 40
< 5x10 7x10
< 5x10 15x10
-15
-15
-14
-14 Milan 4 40
< 5x10 9x10
< 5x10 9x10
-15
-15
-14
-14 N=*= H a 7 40
<5x10 lix10 6x10 30x10 f
1 1
b.
Water Sanples AIPHA BETA-GA M Nurter of Average Maxinun Average Maximum Iocation Sanples uCi/cc uCi/cc uC1/cc uCi/cc
-8
-8
-8
-8 Sandusky 1-B 40
< 1x10
<1x10
< 2x10 3x10
-8
-8
-8
-8 Sandusky 1-C 40
<1x10
<lx10
< 2x10
-3x10
-8
-8
-8
-8' Sandusky 2-A 40
< 1x10 2x10
< 2x10 2x10
-8
-8
-8
-8 Sandusky 2-B 40
< 1x10
<1x10
< 2x10
< 2x10
-8
-8
-8
-8 Huron 3-B 40
< 1x10
<lx10
< 2x10 5x10
-8
-8
-8
-8 Milan 4 40
< 1x10
<1x10
< 2x10 4x10
-8
-8
-8
-8 Castalia 7 40
< 1x10 2x10
< 2x10
'2x10
-8
-8
-8
-8 Sandusky 8 40
< 1x10
<1x10
< 2x10 3x10 c.
Fallout / Precipitation Total radioactivity from fallout and precipitation is determined by collection in hi-walled stainless steel pots mounted 6 feet above the surface of the ground.
ALPHA BUPA-GL%
Number of Average Maximum Average Maximum Incation Samples uCi/cc uCi/cc uCi/cc uCi/cc
-6
-6
-5
-5 Sandusky 1-C 39 3x10 10x10 3x10 12x10
-6
-6
-5
-5 Huron 3-B 39 2x10 4x10 3x10 12x10
-6
-6
-5
-5 Milan 4 39 2x10 10x10 3x10 9x10
-6
-6
-5
-5 Castalia 7 39 3x10 20x10 3x10 8x10 O
t
d.
Silt / Soil Sanples ALPHA BETA-CA%%
lb. of
~
Iocation Samples Averaoe uCi/gm Maxunum uCi/gm Average uCi/gm MayimM1 UCi/cm -6
-5
-5 Sandusky 1-C 3 7x10 10x10 2x10 2x10
-6
-6
-5
-5 I!urcn 3-B 3
5x10 6x10 1x10 lx10
-6
-6
-5
-5 Milan 4 3
4x10 6x10 2x10 2x10
-6
-6
-5
-5 Castalia 7 3
7x10 8x10 lx10 2x10 e.
Vegetation Sanples No. of
_ BETA-CATR Iocation Sannles Average uCi/am Maxuum uCi/gm
-5
-5 Sandusky 1-C 3
2x10 13x10
-5
-5 Hurcn 3-B 3
3x10 5x10
-5
-5 Milan 4 3
4x10 6x10
-5
-5 Castalia 7 3
4x10 5x10 f.
Direct Radiation Direct background envircnnental radiaticn levels are determined by use of TLD's at the four off-site air sanple locations. A packet containing two TLD's is positioned at each location. Ole TID is exchanged and processed monthly and the second is exchanged and processed annually.
Muunum 'Ibtal Dose (mr)
Maximum Dose Rate Single
- Iccation Monthly Annual Manthly_ (mr/hr)
Sandusky 1-C 3.5 14.8 0.002 Huron 3-B 2.4 7.4 0.001 Milan 4 2.5 12.6 0.001 Castalia 7 1.8 7.3 0.0008
- The envircnnental ntnitoring program was instituted April 1,1980.
Therefore, this " annual" data covers cnly nine ntxiths of this reporting period.
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5.
01anges to the PBRF Facility:
Six Facility changes were inplanented during* the reporting period as follows:
Facility Changa No.
Description 80-01*
Cut process piping and erect barrier wall in ATS/RB tunnel.
80-02*
Iblocate perineter security fence.
80-03*
Cut and cap sanitary discharge headers.
80-04*
Ctnstruct new ATS/ ROB area storm drainage system.
80-05*
Abandon ATS Building east electrical feed.
I$difications to continuous Reactor Tank (Rr) nitrogen 80-06 purge system. Redesign of pressure reducing station allows inprovenent in regulation and operating characteristics of N2 gas purge.
Relocation of station from outdoors to indoors eliminates periodic weather-related operating difficulties.
Flow rates through RP and test facilities and alarm setpoints rennin unchanged.
i The only other changes ccnsisted of one-for-one or equivalent replacenents of conponents such as stmp punps, piping, relays,. switches, etc., and other Irinor repairs.
Significant unintenance tasks included:
Unit heater system installation, including new vent screens.
a.
b.
(bntainnent Vessel (CV) cathodic protection maintenance.
Peplacenunt of security cable cn Primary Punp House roof jib cranes.
c.
d.
Abdification to Reactor Tank N2 purge system.
Installed weather protection cover cn Assenbly, Test and Storage (ATS) e.
Building power transformer.
i f.
Ibpairs to Reactor Building, -25 foot, deepwell punps.
Denotes facility changes brought about by inplerenting the PBRF site area exclusion described in Anendment No. 6 to Amended License TR-3. (See Para-graph 6.a. below) b
. g.
Ibpair of leak in Itra Water line (fire hydrant supply) east of the Waste liandling Building.
h.
Ibpairs to big beam emrgency lights for CV and Service Equipnent Building.
- i. Ibpairs to building lighting transforner terminal board necessitated by a lightning strike.
j.
Ibpairs to vibrating sunp punp, Fan House baserent.
6.
Other:
TR-3 License Chang - On Decenber 17, 1976, the NRC issued Amendnent j
a.
No. 6 to the Anended License TR-3 for the Plum Brook Ibactor. Wis amendnunt revised the License and Technical specification to exclude Building 16. 1121.
the Assenbly, Test and Storage (ATS) Building; Building Ib.1142, the Reactor Office Building, Structure No.1156, the ATS Water Storage Tank; and the grounds adjacent thereto from the controlled area of the Plum Bmok Reactor Facility l
(PBRF) and fran licensing requirenents. We revisions to the Technical Speci-fications were designed to take effect when the above buildings, water tank and l
grounds area are shown to be free of radioactive contamination and separated from the PBRF by security barriers and isolation of the process piping.
In a previous reporting period (1978 Annual Ibport), it was reported that due to l
indecision by the EPA (for whom the buildings and area were to be excitxled for use) exclusion had not been acconplished and the aforementioned buildings and area castinued under licensing control. In 1979, the EPA decided to forego plms to utilize the ATS Building.
In 1980, NASA designated futum use of the ATS Building by the Wind Energy Project Office, Inwis Ibsearch Center, for the purpose of establishing a structural testing facility called the wind Turbine Structures Laboratory (WPSL). The WrSL is envisioned to be a centralized, unique national test l
facility for conducting tests supporting the development and manufacture of snnll and large wind turbines as an alternate energy source. A safety l
analysis pf the new proposed use of Building No.1121 as a structural test I
laboratory and Building No.1142 as future office space was performed and found to pose no hazard to PBRF nor existence of an unmviewed safety ques-tion as defined in Section 50.59, 10CFR50.
All field work associated with exclusion of these buildings and the three-acre area fran PBRP was perforned during the Septerber-Noverrber 1980 tine period in accordance with the requirunents of Amendment No. 6 to Anended License TR-3.
A final radiological survey was conducted and documented in i
Report dated November 28, 1980. This report confirms the absence of reactor-originated radioactim traterial in the excluded area. As the reporting period 3
drew to a close, NASA plans were underway to distribute this Ibport to appropri-ate NRC offices in ocmpliance with Amendment No. 6.
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1 l b.
Discosal of Exmss Plum Brook Station Pronerty In the 1978 Annual Ibport, it was reported that WGA 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 acms of excess property within the PBS fenced area to the EPA via CSA. The 45-acre site deeded to Perkins School system continues under NASA control until the NASA facilities located on the site, including the PBS Conmunication Center, are relocated to a new site on Plum Brook Station property (new facilities are currently under construction) and the security fence is relocated.,All construction and relocation requirenents associated with the property transfer should be cortpleted in the first quarter of Calendar i
Year 1981. 'Ihe 604 acre plot to be transferred from NASA to the USEPA, via GSA, should be acccrnplished during the second quarter of Calendar Year 1981. This property will ccntinue to be owned by the U.S. Government.
In addition,IMSA will continue to ccntrol access to Plum Brook Station, inspect and maintain the PBS perimeter fence, and provide security surveillance for the entire PBS perineter fencn. The nearest point of the property affected is nore than 4,000 feet from the fenced site of the Plum Brook Reactor Facility. Standby ccnditions at the PBRF site will be unaffected.
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c.
Mure Disoodition of the Plum Brook Peactor Facility -
In the pmvious reporting period (1979 Annual Report), it was reported that NASA decided to proceed with plans to disnantle and decontaminate the radioactive portions of the PBRF. In march 1930 NASA submitted to NRC a mquest for permission to dismantle the radiological portions of PBRF. Included with this regtest were the following five documents:
Dismantling Plan-Plum Brook Reactor Dismantling Envircnnuntal Ibport-Plum Brook Ibactor Dismantling Dismantling Plan-Plum Brook Mock-Up Ibactor Disruntling Environmental Report-Plum Brook Mock-Up Reactor Dismantling ~
Application for revision to No.
34-06706-03 By-Product Materials License In May 1980 NBC issued Anendnent No. 02 to License No. 34-06706-03 as a partial response to this NASA request. As this reporting period ends, re-ceipt of a Dismantling Order from NRC is still pending.
d.
PBRF Administrative Channels -
Effective Septenber 3,1980 Mr. E. C. Boitel, Jr. was assigned as Manager, Plun Brook Paactor Facility replacing Mr. R. C. Didelot who elected to retire from NASA.
Included in this change was the appointnent of Mr. E. J. Minderman as first alternate PBRF Manager and Mr. T. L. Junod as second alternate PBRF
- Manager, Mr. Junod ccntinues to serve as the PBRF Radiaticn Protecticn Officer. 'Ihe Area 8 Safaty Conmittee continues to be the organization having safety responsibility at the PBRF. Mr. R. J. Koch ocntinues as Manager of the Pitan Brook Station.
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. c.
PIlltF Atriit -
'Iho annual Plum Brook Peactor Facility audit by the Icwis Pescarch Center Audit 'Ibam was conducted m April 30,1980. 'The Audit 'Iban noted no item of ncnccrpliance with either the license ocnditions or standbf procedures.
f.
Unusual Occurrences -
Thorn were no unusual occurrences during the reporting period.
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