ML20056G924
| ML20056G924 | |
| Person / Time | |
|---|---|
| Site: | 05000047 |
| Issue date: | 01/13/1971 |
| From: | Joe Gillespie ARMY, DEPT. OF |
| To: | US ATOMIC ENERGY COMMISSION (AEC) |
| Shared Package | |
| ML20056G923 | List: |
| References | |
| NUDOCS 9309070326 | |
| Download: ML20056G924 (1) | |
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U. S. Atomic Energy Cox.ission Division of Reactor Licensing Washington, D. C. 20545 Centlemen:
It is requested that our License No. R-65, USAEC Docket 50-47 be amended to authorize the Army Materials and }'echanics Research Center to possess, but not to operate, its nuclear reactor facility.
Inclosed is a Deactiva-tion Report including Technical Specifications for the facility in a deactivated condition. -
Operations were ceased on 1 April 1970. It is considered that such deactiva-tion vill not endanger the health and safety of the public.
Sincerely yours,
Incl J01Di V. CILLESPIE I
as (43 copies each)
LTC Cal C Deputy Director /Cor=anding Officer s
Subscribed and sworn to before i
me this __ day of 19 71 at Watertow, liiddlesex County, liassach us e t ts l
ECMAS M. SHESEK i
Notary Public I
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DEACTIVATION REPORT OF THE ARMY MATERIALS RESEARCH REACTOR December 8, 1970 Aruy Materials and Mechanics Research Center Watertown, Massachusetts 02172 4
1 9f091S=c)473
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i TABLE Or CONTE?TI'S i
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A.
Introduction 1
i M.
"emoval of Hazardous "aterials.
3 C.
Disposition of Non-Hazardous Items 3
D.
Containment Shell 5
i E.
Technical specifications 5
1.
Site 5
?.
Administrative and "rocedural Decuirements.
6 3,
Health and Safety 8
4.
"aintenance q
5.
Pecords o
T.
Safety Analvses 10 C.
Health Physics Survey 11 H.
Conclusion 13 r
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1 A.
INTPnD"CTION The U.S. Atomic Energy Conmission (USAEC) and the Army Reactors Conmittee j
i on Uealth and Safety (ARCllS) are requested to authorize the Army "aterials 1
and "echanics Desearch Center (A"MPC) to possess, but not to operate, the deactivated nuclear reactor facility, located at Uatertoirn,'tassnehusetts in accordance with the Technical Specifications presented herein.
i This report outlines the stens taken to put the nuclear reactor facilftv in a condition 90 that:
n.
there is no hazard due to accidental nuclear critica?ity, b.
there is a negligible probability of release of radioactive raterials, and f
I' c.
there are adenuate maintenanco and sirveillance programs.
A""PC currentiv holds the folleving licenses in addition to the "acility l
License " 65:
a.
Ev-product "aterials License, No. 20-01nin_n4 h.
Special Nuclear "aterial License, No. SPf-244.
n.
REMn"AL OF HAZARDOUS MATEPlALS l
1.
Disposition of Muclear ruel l
To insure no nossible nuclear criticality can occur all fuel j
elements containing special nuclear material have been removed and returned to i
the U. S. Atomic Energy Commission.
Irradiated fuel elements were handled under contract with National Lead Co.
The number of elements van RI.
Pn-irradiated fuel elenents and material were packaged and returned through nornal trar.nportation means to the National Lead Co.
This consisted of three 6
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elements and samples of Al-U allovs.
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Pisnosit'on of Radioactive "aterial Item a.
Beq Pcflector Elements These elements were disposed of as high activity waste under contract with the Nuclear Engineerine Co., Inc.
Item b.
Shim-Safety Pods and Armatures Shim-safety rods and armatures were disposed of as high activity waste.
Item c.
rission Chambers These chambers contain U-235 and will be transferred to another reactor facility and reported under SNM-244. Total U-235 contained is less than 5 Frans and is stored in a locked cabinet.
Item d.
Ionization Chambers These chambers were disposed of as lou level radio-active vaste.
Item c.
Magnets and Guide Tubes "arnets have been stored in rear of control roon.
Guide tubes have had the radioactive stainless steel pieces removed and the ruide tiihes stored. Stainless steel nieces were disposed of as high activity radioactive waste.
Item f.
Padioactive Sources The sources used for calibration and check of survev aeters have been transferred to the Padiation and occupa-tional Safety Branch (Posn).
2
item g.
Main Pool Portions of the stainless steel liner and items such as, the beam tubes, the nedestal, the grid plate, cad the in-strument rack are radioactive and have been left in the pool.
I The security of the containment shell and the erection of proper signs at the pool top prevent the exposure of personnel to any hazards. Radiation level on the pool top is less than 20 mr/hr at floor level.
j C.
DISPOSITION OF NON-MAZARDOUS ITEMS Item a.
Control Rod Drives j
These drives have been removed and stored with cre-servatives on all noving parts in the rear of the control room.
Item b.
Instrumentation and Monitoring Equipment This equipment has been left in place but not operating.
i All electrical equipment has been defused.
Item c.
Primary Coolant System i
All water has been drained and disposed of to the MDC sanitary sewaFe system. Preservatives have been put on all exposed ferrous metal moving parts of pumps and motors. All electrical equipment has been defused. All openings of motors have been taped.
f Item d.
Secondary Coolant System All water has been drained to MDC sanitary sewane.
Tan motors have been removed, preserved and stored in contain-ment shell.
3
4 o.
4 Item e.
Heating and Ventilating System of Containment Shell,
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This system will be kept in operation. The automatic i
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butterfly valves on the containment shell intake and exhaust lines have been left in a mechanically fixed open position.
l.
Item f.
Air locks l
The inflatable rubber gaskets on the doors of the airlocks have been removed. The south airlock doors have been taped to keep out the elements. The west airlock to Buildin; 97 l
f has been left as is without gaskets.
4 Item g.
Experimental Equipment Experimental equipment not required by the investigators
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l has been left in place. Electrical enuipment has been defused.
item h.
Overhead Crane Annual preventive maintenance by factorv representative i
vill be continued.
t Item i. Fuel Storage Tank Water has been drained and disposed of to MDC sanitary sewer.
i l
i Item j. Cathodic Protection System This cathodic protection system of the shell is cur-rently being replaced by the Post Engineer. This work will be f
completed and system maintained.
Item k.
Retention Tank This 40,000 gallon retention tank located between the shel3 and Building 47 has been drained and flushed clean to the MDC sanitary sewer.
4 j
h.
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Item 1.
Licuid Waste System, Eldg 97.
This system will be maintained to handle any waste
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from the work conducted in Building 97 authorized by the Byproduct Material License (20-01010-04).
l ltem m.
Pool Make-Up System.
System has been disconnected from servicing contain-i ment shell. May be operated for Buildings 97 and 292 as needed.
l D.
CONTAINMENT SHELL i
Areas of the containment shell will be secured in accordance with the requirements of 10 CFR 20.
Areas which require posting and control are the primary coolant area and the main pooltop.
E.
TECHUICAL SPECITICATIONS 1
1.
SITE i
a.
Plant Area The plant area includes only the reactor containment shell.
1 Personnel access shall be controlled by knowledgeable AMMRC personnel in accordance with written procedure. Personnel access in the immediate l
future shall be for maintenance and surveillance activities.
-l b.
Principle Activities The principal activities carried on within the niant area shall be the possession of the reactor facility and the maintenance and surve:111ance programs. Regulatory authorities will be notified of any other use in advance.
c.
Physical Security The only access to the containment shall is by the two airlocks.
4 5
<3 The outer doors of the airlocks will be locked and the key retain-I ed by the Intelligence and Security Branch (ISB). The inner i
doors will be monitored for opening and such opening will alarm j
at the main office of the ISB. The Facility Supervisor will 3
maintain a list of personnel, who are authorized access, at the ISB. When an authorized person desires to enter the shell he will-(1) Sign out a key at the ISB (2) Just prior to opening inner door, clear entry by telephone i
with ISB (ISB will log the entry).
l When the authorized person is leaving the shell he will, by telephone:
(1) Notify ISB after outer door has been secured.
(2) Return key promptly to ISB.
j l
Instructions for entry will be posted at the airlocks by the l
i racility Supervisor.
f Upon receipt of an alarm caused by an unauthoriced opening, the l
l Security Police will immediately investigate the case. "ersons f
aperchended will he held and the racility Sunervisor notified, 2.
ADMINISTRATIVE Ann "PnCEDURM. REOUIT!r"ENTS L
a.
General rigure 1 depicts the current line organization and the re-I sponcibilities as required.
Activities involving access to the pla7t area and use of any i
area or in-place equipment shall be conducted under the direction of the designated Facility Supervisor with functional responsibility 6
S SURVEIL LAN CE MANAGEMENT REVIEW AND AUDIT MAINTENANCE 8 SECURITY DIRECTOR ADMINISTRATIVE FACILITY REACTOR SAFEGUARDS DIVISION SUPERVISOR COMMITTEE RADIATION 8 OCCUPTIONAL SAFETY BRANCH POST ENGINEERING BRANCH INTELLIGENCE 8 SECURITY BRANCH
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i and commensurate authority to maintain the facility in a safe and secure condition at all times. The Facility Supervisor shall utilize j
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.k the resources of other AM'tPC personnel as necessarv to provide an i
effective safaty program.
i h.
Review and Audit t-(1) Hritten procedures for control of access to the niant area, use of plant area, facilities and enuipment and for periodic'insnection of the facility shall he established and approved by the Director.
1 (2) Uritten procedures specified in b. (1) above shall be reviewed hv technically qualified personnel responsible to a management position-other than the Facility Supervisor (the Peactor Fafeguards Committee)
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(PSC) in accordance with a written charter for that function.
(3) The P.SC shall semi-annually audit activities conducted in the
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plant area to verify that effective radiological control practices are maintained.
3.
HEALTH AND SAFETY a.
Padiation Monitoring Radiation monitoring instruments and dosimetry devices shall be available and used as appropriate to prevent exnosure of nersonnel 4
to radiation in accordance with the standards of 10 CFE " art 20.
A general radiation survey including smears shall be conducted month-IV by the EnSB.
h.
Removal of *faterials and Equipment j
As a radiation and contamination control measure, all materials and couinnent removed from the shcIl shall be monitored and 8
)i.
ATOMIC ENERGY COMMISSION
' 4 I
WASHINGTON, D.C. 20545
' rf, April 3, 1971 1
Docket No. 50-47 l
l U. S. Department of the Army Army Materials and Mechanics Research Center ATTN: John W. Gillespie, LTC, Cml C Deputy Director / Commanding Officer Watertown, Massachusetts 02172 i
Gentlemen:
In response to your application dated January 13, 1971 Amendment No. 9.
to Facility License No. R-65 is enclosed.
The amendment authorizes you to possess, but not to operate, your deactivated pool-type research i
reactor located in Watertown, Massachusetts.
A copy of the Notice of Issuance of Facility License Amendment, which has been submitted to the Office of the Federal Register for publication, and a copy of our related Safety Evaluation are also enclosed.
Sincerely,
,,ysh onald J.
vholt Assistant Director for Reactor Operations l
Division of Reactor Licensing
Enclosures:
1.
Amendment No. 9 2.
Federal Pagister Notice 3.
Safety Evaluation
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UNITED STATES
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8 ATOMIC ENERGY COMMISSION
'I WASHINGTON, D.C. 20545 "9,
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j U4tig ti ARMY MATERIALS AND MECHANICS RESEARCH CENTER 1
1 DOCKET NO. 50-47 AMENDED FACILITY LICENSE License No. R-65 Amendment No. 9 1.
The Atomic Energy Commission ("the Commission") has found that:
A.
The application for license amendment dated January 13, 1971, complies with the requirements of the Atomic Energy Act of 1954, as amended ("the Act"), and the regulations of the Commission set forth in 10 CFR Chapter I; i
B.
The facility will be possessed in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; C.
There is reasonable assurance (1) that the activities authorized by this license can be conducted without endangering the health and safety of the public, and (ii) that such activities will be i
conducted in compliance with the regulations of the Commission;
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D.
The applicant is technically and financially qualified to engage in the activities authorized by this license in accordance with the rules and regulations of the Commission; E.
The applicant is a Federal Agency which does not have to furnish j
proof of financial protection and has executed an indemnity agreement which satisfies the requirements of 10 CFR Part 140, and l
T.
The issuance of this license will not be inimical to the common I
defense and security or to the health and safety of the public.
2.
Facility License No. R-65, as amended, is hereby amended in its entirety to read as follows:
A.
Tnis license applies to the light water-moderated and cooled pool-type nuclear reactor (hereinaf ter " facility") owned by the Army Materials and Mechanics Research Center (hereinafter "AMMRC" i
T S-l- L D S O f O W Q,y
% or "the licensee") and located in Watertown, Massachusetts, and originally licensed as described in the licensee's application dated December 1,1956, and subsequent amendments thereto B.
Subject to the conditions and requirements incorporated herein the Commission hereby licenses the Army Materials and Mechanics Research Center:
(1)
Pursuant to Section 104c of the Act and 10 CFR Part 50,
" Licensing of Production and Utilization Facilities",
to possess, but not to operate, the deactivated facility as a utilization facility in accordance with the procedures and limitations described in the application dated January and in this license; and 13, 1971,
(2) Pursuant to the Act and 10 CFR Part 30, " Rules of General Applicability to Licensing of Byproduct Material", to possess but not to separate, such byproduct material as may have been produced by operation of the facility.
C.
This license shall be deemed to contain and be subject to the ditions specified in Part 20, Section 30.34 of Part 30, and Sections con-50.54 and 50.59 of Part 50 of the Commission's regulations; is subject to all applicable provisions of the Act and rules, regulations and orders of the Co= mission not; or hereaf ter in effect; and is subject to the additional conditions specified or incorporated below:
(1)
AMMRC shall not operate the facility unless the Commission has authorized such operation by further amendment to this license.
(2) 1echnical Specifienticns T. e Technical Specifications contained in Appendix A appended as Change No. 1 are hereby incorporated in this 11 cense.
AMMRC shall possess the reactor in accordance with these Tech-The nical Specifications.
No changes shall be made in the Technical Specifications unless authorized by the Commiseien as provided in Section 50.59 of 10 CFR Part 50.
i l
D.
This amended license is effective as of the date of issuance and shall expire at midnight, October 2, 1997.
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FOR E AT MIC ENTRGY COMMISSION
/
.s,yn
/'r' sonald Skovholt Assistant Director for Reactor Operations Division of Reactor Licensing
Attachment:
Appendix A - Technical Specifications (Change No. 1)
Date of Issuance: April 3, 1971
- - - - - - ~
5
4 APPENDIX A TO FACILITY LICENSE NO. R-65 I
TECHNICAL SPECIFICATIONS CHANGE NO. 1 ARMY MATERIALS AND MECHANICS RESEARCH CENTER i
DOCKET NO. 50-47 DATE: April 3, 1971 1.
SITE a.
Plant Area The plant area is defined as the area within the reactor containment shell.
i i
b.
Principal Activities The principal activities to be carried on within the plant area shall be maintenance and surveillance programs. 'The Atomic Energy Commission's Division of Reactor Licensing shall be notified in advance of any other l
use.
l c.
Physical Security l
Access to the plant area shall only be via the two airlocks.
The outer doors of the airlocks shall be locked and the key retained by the Intelligence and Security Branch (ISB).
The inner' doors shall be monitored continuously for opening by an alarm at the main office of the ISB.
The Facility Supervisor will maintain a list of personnel at the ISB office who are authorized access to the facility. When an authorized person desires to enter the plhnt area he must:
(1)
Sign out a key at the ISB office; and (2)
Clear entry by telephone with the ISB (ISB will log the entry) just prior to opening the inner door.
When the authorized person is leaving the plant area, he must:
(1) Notify the ISB, by telephone, after the oute door has been secured; and
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4
- (2)
Return the key promptly to the ISB of fice.
1 Instructions for entry shall be posted at the airlocks by the Facility i
Supervisor.
t Upon receipt of an alarm caused by an unauthorized opening, the Security
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Police shall immediately investigate the facility. Persons apprehended
~
will be held and the Facility Supervisor notified.
2.
ADMINISTRATIVE AND PROCEDURAL REQUIREMENTS a.
General Figure 1 depicts the line organization and the general responsibilities.
Activities involving access to the plant area and use of any area or installed equipment shall be performed under the direction of the designated Facility Supervisor who has the responsibility and commen-surate authority to maintain the facility in a safe and secure condition at all times. The Facility Supervisor shall utilize the i
resources of other AMMRC personnel as necessary to provide an effective safety program.
b.
Review and Audit (1) Written procedures for control or access to the plant area, use of plant area, facilities and equipment and periodic inspection of the facility shall be established and approved by the Director.
l (2) ' Written procedures specified in b(1) above shall be reviewed by the Reactor Safeguards Committee (RSC) in accordance with a written charter for that function.
(3)
The RSC shall semiannually audit activities performed in the plant area to verify that effective safety and radiological control practices are maintained.
3.
HEALTH AND SAFETY a.
Radiation Monitoring Radiation monitoring instruments and dosimetry devices shall be 1
available and used in accordance with procedural requirements.
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y t 3 A general radiation survey, including smears, shall be performed monthly by the Radiation and Occupationel Safety Branch (ROSB).
b.
Removal of Materials and Equipment i
As a radiation and contamination control measure, all materials a
and equipment removed from the plant area shall be monitored and released in accordance with AMMRC procedures and in compliance with the standards of 10 CFR Part 20, by the ROSB.
4.
MAINTENANCE a.
Heating and Ventilating System The Post Engineering Branch (PEB) shall perform the following activities:
(1) A weekly visual inspection.
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(2) A monthly check of all equipment in accordance with a written checklist.
b.
Cathodic Protection System i
The PEB shall read, record and evaluate voltage and current readings of the cathodic protection system quarterly.
The effectiveness of the system shall be checked, using a half-cell, semiannually.
c.
Fire Fighting Equipme.nt The PEB shall check and maintain fire extinguishers in the plant area monthly.
The PEB shall maintain the fire hoses.
d.
Fire Alarm System The PEB shall have an operability check of the fire alann system performed semiannually.
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5.
RECORDS
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In addition to those records required by applicable AEC regulations, I
including Section 20.401 of 10 CFR Part 20, the AMMRC shall keep the following records:
Records of principal maintenance activities and equipment sur-a.
veillance.
I b.
Records of inspections of the deactivated facility.
f c.
Records showing radioactive releases or discharges to the air or f
water beyond the effective control of the AMMRC as measured at the l
point of such release or discharge.
6.
REPORTS i
In addition to the reporting requirements of applicable AEC regulations, l
and in no way substituting therefor, reports shall be submitted to the l
AEC as follows:
}
A prompt report (by telephone or telegraph to the Director, AEC Region I Compliance Office) and a report within 10 days l
(in writing to the Director, Division of Reactor Licensing, USAEC, Washington, D. C.
20545) of any indication or occurrence of a possible unsafe condition relating to the facility or to facility personnel or the public.
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SURVEllLANCE MANAGEMENT REVIEW AND AUDIT MAINTENANCE 8 SECURITY DIRECTOR 4
ADMINISTRATIVE FACILITY REACTOR SAFEGUARDS
. DIVISION SUPERVISOR COMMITTEE C
RADIATION 8 OCCUPTIONAL SAFETY BRANCH I
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POST ENGINEERING BRANCH INTELLIGENCE 8 SECURITY
.BRANC H
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y UNITED STATES ATOMIC ENERGY COMMISSION DOCKET NO. 50-47 4
ARMY MATERIALS AND MECHANICS RESEARCH CENTER NOTICE OF ISSUANCE OF FACILITY LICENSE AMENDMENT i
i n
The Atomic Energy Commission ("the Commission") has issued, effective as of the date of issuance, Amendment No. 9 to Facility License No. R-65.
The j
license presently authorizes the Army Materials and Mechanics Research Center (AMMRC) of the U. S. Department of the Army to possess, use and operate its pool-type research reactor located in Watertown, Massachusetts, at power levels up to five megawatts (thermal). The amendment authorizes AMMRC to possess, but not to operate, the reactor in accordance with AMMRC's application l
dated January 13, 1971.
i The Commission has found that the application for the amendment complies with the requirements of the Atcmic Energy Act of 1954, as amended
("the Act"),
)
and the Commission's regulations published in 10 CFR Chapter I.
The Commission j
has made the findings required by the Act and the Commission's regulations, which are set forth in the amendment, and has concluded that the issuance of i
the amendment will not be inimical to the common defense and security or to the health and safety of the public.
The Commission has also found that prior public notice of proposed issuance of this amended license is not l
required since t.he possession of the facility in accordance with the terms j
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. of the amended license does not involve significant hazards considerations different from those previously evaluated.
Within fif teen days from the date of publication of the notice in the FEDERAL REGISTER, the applicant may file a request for a hearing and any person whose interest may be affected by this proceeding may file a petition i
for leave to intervene. Requests for a hearing and petitions to intervene shall be filed in accordance with the Commission's " Rules of Practice" in 10 CFR Part 2.
If a request for a hearing or a petition for leave to inter-vene is filed within the time prescribed in this notice, the Commission will issue a notice of hearing or an appropriate order.
For further details with respect to this amendment, see (1)
AMMRC's application dated January 13, 1971, (2) the amendment to the facility license, including revised Technical Specifications, and (3) a related Safety Evaluation by the Division of Reactor Licensing, all of which are available for public inspection at the Commission's Public Document Room at 1717 H Street, N. W.,
Washington, D. C.
Copies of items (2) and (3) above may be obtained upon request sent to the U. S. Atomic Energy Commission, Washington, D. C.
- 20545, Attention: Director, Division of Reactor Licensing.
Dated at Bethesda, Maryland, this 3rd day of April,1971.
FOR THE ATOMIC ENERGY COMMISSION
/
ald J kovholt Assistant Director for Reactor Operations Division of Reactor Licensing
UNITED STATES ATOMIC ENERGY COMMISSION 5AFETY EVALUATION BY THE DIVISION OF REACTOR LICENSING DOCKET No. 50-47 ARMY MATERIALS AND MECHANICS RESEARCH CENTER (AMMRC) REACTOR FACILITY 1
By application amendment dated January 13, 1971, the Army Materials and }kchanics Research Center submitted a report on the deactivation of tha Army Materials Research Reactor (AMRR) and requested authorization to possess, but not to operate, the reactor facility.
The submittal included proposed Technical Speci-fications for the facility in a deactivated condition.
Reactor operatiers ceased on April 1, 1970, and the reactor facility is presently in a deactivated condition.
i The deactivation report outlines the steps taken by the licensee to preclude nuclear criticslity or the inadvertent, release of radioactive materials and assure i
the establishment of adequate maintenance and surveillance programs.
The licensee utated thaa all readily accessible and/or removable materials, which emitted direct beta-gn=na radiation in excess of 2.5 mR/hc, were removed from the containment shell.
Two remainiag areas where the direct radiation field exceeda 2.5 mR/hr will be desienated radiation areas.
The licensee reported the disposition of hazardous materials as follows. All l
fuel elements containing special nuclear materials were shipped offsite. The r
beryllium-oxide elements, shim-safety rods and arnatures, ionization chambers, and radioactive sections of the control rod guide tubes were disposed of as radioactive vaste.
The fission chambers, which c >ntain small amounts of uranium 235, were transferred to another reactor facility and radioactive sources used for :alibrction and checking of radiation monitoring instruments were transferred to the Radiation and Occupational Safety Branch of ANMRC.
Portions of the pool liner, the beam tubes, the core pedestal and grid plate, the instrument rack, and the demineralizer resins, which are radioactive, will remain in place.
The licensee reported the disposition of non-hazardous items as follows.
The control rod drives were removed and stored in the control room.
Ins trumenta tion l
and monitoring equipa2nt will re=ain in place but not operating; the fuses were removed from all electrical equipment.
Both the primary and secondary coolant I
systems were drainei into the sanitary sewerage system.
The fuel storage pit t
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i
. i and the retention tank were drained and the water discharged into the sanitary sewerage system.
The reactor pool water makeup system was disconnected, but the aiquid waste i
rystem will te naintained to handle any radioactive vaste that may be generated i
in an adjacent building.
The containment shell heating and ventilating system, t
the overhead crane and the containment shell cathodic protection system will be f
maintained.
The two radiation areas within the containment shell are the reactor pool and the primary system piping area.
The dose rate at the top of the reaccor pool, due to the induced radioactivity in structural members within the pool, is less than 20 millirem per hour.
Earrier ropes were placed at the entrance to the top of the pool and signs designating it as a radiation area were posted.
The
(
top of the pool was covered with steel plates to prevent access to the interior of the pool.
Since access to the containment shell vill be limited and controlled, the licensee concludes, and we agree, that the radiation emanating ~f rom the interior of the reactor pool vill not constitute an ur. cue hazard to personnel.
The resins in the primary system demineralizers constitute the only radioactive 1
material remaining in the primary system piping area. The resins are contained in thick-walled, steel cylinders and, therefore, cannot escape from the primary system.
The dose rates at the surface of the demineralizer are less than 60 i
millirem per hour.
The primary system piping area was posted as a radiation area.
The licensee concludes, and we agree, that the existence of this controlled j
radiation area doe <. sot constitute an undue radiation hazard.
l Maintaining radiological safety within the containment shell will be the responsi-bility of the Radiation and Occupational Safety Branch at AMMRC. A general l
l radiation survey within the containment shell will be performed on a monthly f
basis.
Radiation monitoring instruments and dosimetry devices will be available i
and utilized in accordance with the requirements of 10 CFR Part 20.
i i
We have reviewed the Technical Specifications proposed for the deactivated facility and have concluded that they include those items important to the j
saf ety of the reactor f acility in its deactivated condition.
The licensee defines the plant area to be controlled as the area within the reactor containment shell.
i The principal activities to be carried on within this area are identified and physical security measures are outlined.
The administrative and procedural requirement identify the organization and its responsibilities to provide an effective safety program.
The review and audit function of management and the 4
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o.
! written procedures that will be in effect are also specified.
There will be.
written procedures for control of access to the plant area and for control of all activities within the plant area.
The radiation monitoring practices and procedures for governing the removal of materials and equipment from the plant area and the requirements for periodic maintenance of remaining systems and equipment are specified.
CONCLUSION Based on the above considerations, we have concluded that there is reasonable assurance that the health and safety of the public will not be endangered by the existence of the AMMRC reactor facility in the reported deactivated condition.
aid J. Skovholt 2
Assistant Director t
for Reactor Operations Division of Reactor Licensing Date: April 3, 1971 i
i I
.