ML20216F724
| ML20216F724 | |
| Person / Time | |
|---|---|
| Site: | Waltz Mill |
| Issue date: | 03/25/1963 |
| From: | Lowenstein R US ATOMIC ENERGY COMMISSION (AEC) |
| To: | |
| Shared Package | |
| ML20216F225 | List:
|
| References | |
| FOIA-98-100 TR-02-A-002, TR-2-A-2, NUDOCS 9804170224 | |
| Download: ML20216F724 (5) | |
Text
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UNITED STATES I
- > ATOMIC ENERGY COMMISSION O WASHINGTON 25. D.C.
d *sQ'"" ' f DOCKET NO. 50-22 WESTINQ10llSE ELECTRIC CORPORATIGN i 1 C_ g !! S,, E,
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t License No. TR-2
. Amendment No. 2 License No. TR-2 is amended in its entirety to mad as follows: _,
- 1. '
This licenso applies to the utilization facility known as the I Westinghouse Testing Reactor which is owned by the Westinghouse j Electric Corporation and located near Waltz Mill, in Westmoreland l County, Pennsylvania, described in Westinghouse's application , i i attested February 29, 1952 and amendments thereto, and for which Construction July 3, 1957. Pormit No. CPTR-1 was issued by the Commission on
- 2. '
Subject to the conditions and requirements incorporated herein ,
the Commission hereby licenses Westinghouse Electric C6rporation:
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- a. 4 l Pursuant to Section 104(c) of the Atomic Energy Act of 1954 ,
CFR, Chapter 1, Part 50, " Licensing of Production and Uti zation Facilitics," to possess, but not to operate, the facility i as a utilir.ation facility in the condition described in the
" FinalJanuary dated Shutdown Report for' Westinghouse Testing Reactor, WTR-172" 25,1963,[ky WQ23 dtp y 2 - 70 .)
b.
Pursuant to the Act and Title 10, CFR, Chapter 1, Part 30,
" Licensing of B) product Material," to possess, but not to separate, such byproduct material as 'may be contained in the structural parts of the facility.
3.
Pursuant Part 20, to the Act and Section 20.501 of Title 10, CFR, Chapter 1 ,
is exempt from the requirements of Section 20.203(c)(2" Standa for a visi-ble or audibicTest Westinghouse control device in high radiation areas )of the ing Reactor. _
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This license shall be deemed to contain and be subject to all applicable provisions of the Act and rules, regulations and orders of the Commission now or hereafter in effect; and is subject to any additional ccnditions specified or incorporated below:
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- a. Westinghouse shall not reactivate the facility without prior approval of the Commission,
- b. Westinghouse shall not dispose of the facility or the property occupied by the facility without prior approval of the Commission.
- c. Westinghouse shall keep the following records:
(1) Records of annual inspections of the retired facility, including results of surveys of radioactivity levels. -
(2) Records showing radioactivity released or discharged into the air or water beyond the effective control of Westinghouse as measured at the point of such release or discharge.
- d. Westinghouse shall submit the following reports in writing to the Commission:
(1) An immediate report of any indication or occurnnee of a possible unsafe condition relating to the facility or the public.
(2) An annual report of the status of the retired facility t including results of surveys of radioactivity levels.
- 5. This license is effectivo as of the date of issuance and shall expire at midnight July 3,1967. f FOR Ti!E ATOMIC ENERGY C0bNISSIm Origial Sigud by
& Lonnfein i
Director l Division of Licensing and Regulation .
Date of Issuance: MAR 2 51963
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HAZARDS ANALYSIS BY THE TEST & POWER RE ACTOR SAFETY BRANCH DIVISION OF LICENSING AND REGULATION s,yp WESTINGHOUSE ELECTRIC CORPORATION RETIREMENT OF WESTINGHOUSE TESTING REACTOR DOCKET NO. 50-22 Introduction and Background j i
on May 8,1962, the Westinghouse Electric Corporation advised the Commission !
that the Westinghouse Testing Reactor, then operating under AEC Facility !
License TR-2, had been shut down and was to be permanently retired. Westing- l house filed an amendment to its application including a Shutdoun Report (RIR-170) describing a two-phase program for the shutdown and retirement of the facility.
The first phase involved the removal of fuel, decontamination of certain areas, and measures for restricting access to the facility. The second phase involving the safeguarding of the shutdown facility was to begin upon completion of Phase 1.
The Commission advised Westinghouse that Phase 1 of the shutdown progran could be conducted under the terms of License No. TR-2 and that upon notification that Phase 1 had been completed along with any necessary amendment to the Shutdown Report, AEC would consider issuance of an amendment to the license which would authorize possession only of the facility, siace the structure itself was not to be totally dismantled.
l On January 25, 1963, Westinghouse informed the Commission that the shutdown and permanent retirement of the WTR facility had been completed and submitted " Final Shutdown Report for Westinghouse Testing Reactor" (RTR-172). This report de-scribes the action taken and conditions now prevailing at the facility.
Description of Deactivation and Retirement The retired WTR is located on a large site owned by the Westinghouse Electric Corporation near Waltz Mill, Pennsylvania. The site will continue to be used in connection with other operations, some of which are licensed by AEC.
The following sunnarizes the steps taken by Westinghouse to retire the WTR:
- 1. The irradiated fuel elements in the reactor have been removed and returned to the AEC in accordance with licensed procedures. All nonirradiated fuel elements have been returned to the supplier or other licensees for reprocess-ing and recovery.of special nuclear material.
(f2. All experimental material was returned to the original supplier or dis-posed of as waste material.
- 3. The reactor vessel has been drained and the head assembly replaced and bolted down. All other openings have been secured.
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- 4. The primary coolant system, pipes and tanks have been drained and openings secured to prevent escape of any airborne activity, g g ,5:!P ic o v i r - - - = - ~ - - ,mww mm- e s...- w .- -.-7mm-m.
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w 5. The subpile room has been cleaned and the doors locked. I l
6.
All irradiated materials have been removed from the canal. The canal itself has been carefully cleaned and covered with polyethylene sheeting i
and a heavy wire mesh screen. Access to the canal area in the reactor !
building is restricted by a heavy screen placed in the canal at the build- ,
ing wall.
- 7. The contaminated pipe tunnels have been cleaned of gross contamination and access is restricted by locked gates, doors, and concrete slabs as appro-pria te.
- 8. Loop No. 4 has been removed and concrete shielding slabs replaced on the I shielding cubicle to prevent access. Loop Nos. 1 to 3 have been posted {
with appropriate signs.
- 9. The Reactor Building itself has been cleaned and all doors have been locked.
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- 10. In the Process Building, entrances to retired areas have been locked and, '
in addition, gates or doors to the pump rooms and other internal areas have been locked. Since some of these retired areas are radioactive, they have been posted as restricted areas.
_ Analysis of Hazard to Public from Retired Condition As a nonoperating reactor, the only radiation danger to the public would be from i direct radiation from contaminated surfaces or by the dispersal of residual con-tamination. During the deactivation of the facility, irradiated materials and/or !
equipment have been removed and areas decontaminated, where practical. A radia-tion survey was made of all retired areas on December 31, 1962, to establish the radiation levels after these measures. The results of this survey (Appendix A to the Final Shutdown Report) indicate that some contamination still exists in certain areas. The highest levels were found in the Process Bu'.1 ding, where con-tact readings on certain primary system components are in the range specified for a "High. Radiation Area" as defined in 10 CFR 20. All of these areas have been posted, and access to any radiation or contamination area is restricted by locked doors and gates, and, in addition, the entire facility is surrounded by a chain link fence. A twenty-four hour guard is to be maintained at the site to dis-courage trespassing and unlawful entry.
In view of physical security features and administrative procedures limiting cntry to the retired area, it is believed that the requirement in 20.203(c)(2) for a visible or audible control device in high radiation area's of the WTR may be waived. In addition, we believe that the procedures proposed for controlling cnd restricting access to the WTR provide adequate protection against any direct radiation hazard to the public.
All combustible material, such as the cooling tower, is being removed from the site. Further, there are no sources of explosive gases or dust in the retireo creas. Therefore, it does not appear that dispersal of residual contamination to the atmosphere from the WTR constitutes a significant public hazard.
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3 Personnel trained in handling contaminated materials, radiation instruments, l and fighting fires are available in the event of an emergency at the WTR.
Further, Westinghouse proposes to conduct annual inspections of the retired l t
facilities to determine if either nucient or non nuclear hazards have developed.
Conclusion It is the opinion of the Staff that Westinghouse has taken all practical steps to decontaminate, deactivate, and secure the Westinghouse Testing Reactor, and that there is reasonable assurance that the retired facility will be maintained in such a manner that the health and safety of the public will not be endangered.
FOR THE ATOMIC ENERGY CO)911SSION '
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/Saul Levine, Chief l Test & Power Reactor Safety Branch Division of Licensing and Regulation i
Date: MAR 2 51963 4 t
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