ML20076D705
| ML20076D705 | |
| Person / Time | |
|---|---|
| Site: | Saxton File:GPU Nuclear icon.png |
| Issue date: | 12/12/1963 |
| From: | Layman W SAXTON NUCLEAR EXPERIMENTAL CORP. |
| To: | US ATOMIC ENERGY COMMISSION (AEC) |
| Shared Package | |
| ML20071H103 | List: |
| References | |
| FOIA-91-17 NUDOCS 9107300178 | |
| Download: ML20076D705 (2) | |
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50-145 D?2-4 11 1 1 12/11/63 SMF.C 1 3 ITI M 5( 3) ;33 9.5 15 215203-13416/S3.
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UNITED STATES ATOMIC ENERGY COMMISSION
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DOCKET NO. 50-146-SAXTON NUCLEAR EXPERIMENTAL CORPORATION NOTICE OF PROPOSED ISSUANCE OF OPERATING LICENSE i
4 Notice is hereby given pursuant to Section 189 of the Atomic f
Energy Act of 1954, as amended, and Section 50.58 of 10 CFR 50, that unless within thirty days after publication of this notice in the Federal Register a request for a hearing is filed with the.U. S.
Atomic Energy Commission (the " Commission") by Saxton Nuclear Experi-mental Corporation ("Saxton"), or a petition for leave to intervene is filed by any person whose interest may be affected, as provided by and in accordance with the Commission's " Rules of Practice,"
10 CFR 2, the Commi~ssion proposes to issue an operating license, substantially as set forth below, to Saxton authorizing operation of the 23.5-megawatt (thermal) light water moderated and cooled, pressurized water reactor located near the Borough of Saxton in Liberty Township, Bedford County, Pennsylvania.
Construction of the reactor was authorized by Construction Permit No. CPPR-6 issued February 11, 1960. The reactor has been operated under Provisional Operating License No. DPR-4 issued to Saxton November 15, 1961.
The Commission has found that:
(1) The application complies with the requirements of the Atomic Energy Act of 1954, as amended, and the Commis-sion's regulations set forth in Title 10, Chapter 1, CFR;
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g 2-t (2) There is reasonable assurance that (i) the activities authorized by this license can be conducted at the desig-
's nated location without endangering the health and safety of the public, and (ii) such activities will be conducted in compliance with the rules and regulations of the Com-(
mission; (3) Saxton is technically and financially qualified to engage in the proposed activities in accordance with the Commis-i sion's regulations and to assume financial responsibility for payment of Commission charges for special nuclear material; (4) The issuance of this license will not be inimical to the common defense and security or to the health and safety of the public.
For further det&ils with respect to this proposed license, see (1) the license application amendment dated May 28, 1963, and supplement thereto dated January 8, 1964; (2) the report of the Advisory Committee on Reactor Safeguards dated September 12, 1963; (3) a related hazards analysis prepared by the Research and Power Reactor Safety Branch of the Division of hicensing and Regulation; and (4) the Technical Specifica-tions which are incorporated in the license and designated as Appendix S/. il b o A thereto; all of which use available for public inspection at the
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Commission's Public Document Room, 1717 H Street, N. W., Washington,
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Copies of items (2) and (3) above may be obtained at the D. ' C.
Consission's Public Document Room, or.upon request addressed to the Direc.
Atomic; Energy. Commission, Washington, D. C. 20545, Attention:_ _ _ _
___ ;j ter, Division of Licensing and Regulation.
FOR THE ATOMIC ENERGY COMMISSION Original signed by,
- Eber R. Price Maulut Director Division of Licensing 6 Regulation f
i Dated at Bethesda, Maryland this day of January,1964 JAN 2 81964 1
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gAXTON l1UCf 2Am EXPant==TAL CEP'DEATION 4
Durat 30. 50-146
.f v.w IgpFOSED OP m T14G~LICEMSE License No. OPE-4 This license applies to the pressurised water reactor (hereinaf ter referred 1.
Ii to as the " reactor") owned by Saxton Nuclear Experimental Corporation J;
(hereinaf ter referred to as "Saxton"), located north of the Borough of Saxton in Liberty Township, Bedford County, Pennsylvania, and described in b
A=aad===t No.'5 dated April 19 -1961, and Amendment No. 7 dated June 30, 1961, to Santon's license application.
2.
Subject to the conditions and requirements incorporated herein, the Atomic Energy Cossaission (hereinaf ter referred to as the "Coenf.ssion") hereby licenses.Saxton.
Pursuant to Section 104(b) of the Atomic Energy Act of 1954, as '
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amended, (hereinaf ter referred to as the "Act") and Title 10, CFR, Chapter 1. Part 50, " Licensing of Production and Utilization Facilities,"
to possess; use and operate the reacter as a utilisation facility; Pursuant to the Act and Title 10 CFR, Chapter 1. Part 70, '"Sp'ecial 5.
Nuclear Material," to receive, possess and use at any one ties 130
.g ;k kilogress of contained Uranian 235 as fuel for the operation of the reactor; and Pursuant to the Act 'and Title 10 CFR, Chapter 1, Part 30, " Licensing C.
of Byproduct Material," to possess, but not to separate, such by-product natorial as may be produced by operation of the reacter, and to receive, possess, and use at any one time not to exceed 120 curies of polonium-beryllium as core neutron sources.
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This license 'aball be deemed to contain and be subject to the conditions
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specified in Section 50.54 of Part 50, Section 70.32 of part 70, and Section 30.32 of Part 30 of the commission's regulations, and is subject to all applicable provisions of the Act and rules, regulations and orderer ~of the Commission now or hereafter in effect; and
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is subject to the additional conditions specified belows I
A.
W ri -- Power Level Saxton shall not operate the reactor at power levels in excLes of j
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23.5 megawatts (thermal).
i S.
Tschaical Specific'ations i
The Technical Specifications contained in Appendix A to this license (hereinafter referred to as the " Technical Specifications") are hereby incorporated in this license. Saxton shall operate the facilityonly in accordance with the Technical Specifications. No changes shall be made in the Technical Specifications unless authorised by the Commis-sion as provided in 10 CFR 50.59.
C.
Authorisation of Changes. Tests and Experiments Saxtoa may (1) makes changes in the Cv!!;'
described in the hasards surmary report (2) make changes in the procedures as describr.d in the hasards summary report, and (3) conduct tests or experiments not described in the hasards summary report only in accordance with the provisions of Sectica 50.59 of the Commission's r[gulations.
1,.
Records 4
In addition to those otherwise required under this license and applicable regulations, Saxtoa shall keep the following records:
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Reactor operating records, including power levels and period cf operations at each power level.
(2)
Records' showing the radioactivity released or discharged into the air or water beyond the effective control of Saxton as j
s' measured at or prior to the point of such release or discharge.
(3)
Records of scrams, including :easons therefor.
.(4)
Records of principal maintenance operations involving substi-tution or replacement of facility equipment or components and the reasons therefor.
(5)
Records of radioactivity measurements at on-site and off-site monitoring stations.
(6)- Records of facility tests and measurements performed pursuant to the requirements of the Tecimical Specifications.
E.
Reports In addition to reports otherwise required under this license and s
applicable regulations:
(1) Saxton shall make an imediate report in writing to the
- Commission of any indication or occurrence _of a possible unsafe condition relating to the operation of the facility,
. including, without implied limitation, any possible unsafe condition arising out-of:
_(a) Any substantial variance disclosed' by operation of the facility from the performance specifications set forth in the. hazards summary report, and 9
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4 (b)
Any accidental release of radioactivity, whether or not resulting in pro'perty damage or personal injury or exposure above permissible limits.
(2)
Saxton shall report to the Commission in writing significant
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changes in plant organization, and transient or accident analyses, as described in the hazards summary report, (3) Saxton shall submit to the Commission, on at least a semi.
\\ g v-annual basis, a written report of operatitg experience including:
(a)
A brief explanation of the cause of each unplanned shut-down of the reactor.
(b) The amount of radioactive material removed from the reactor by releases, discharges, and shipments of radioactive waste material.
(c) The levels of radioactivity in the principal fluid systems.
(d) A description of changes, tests, and experiments performed pursuant to Paragraph 50.59(a) of the Commission's Rules and Regulations.
(e)
A description of the principal maintenance perforned.
(f) A summary of reactor operation performed during the period including: Operations performed pursuant to the Research and Development program; an explanation of mal-functions of any equipment important to safety; periodic testing performed as required in section N.8 of the Technical Specifications.
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Such reports shp11 be due within 60 days after the end of each reporting period.
F.
De finit ions (1) As used in Section 3 in this license, the tem " facility" means the following systems and components as described in the hazards summary report:
(a)
The containment vessel which houses the reactor, steam generator, main coolant system, other miscellaneous auxiliary systems, and the fuel ' torage well.
(b) The reactor core including the control rods, control rod drives, support structure, and normal operation instru-mentation and controls.
(c) The main coolant loop including the piping, steam gener-ator, main coolant pump, reactor vessel, and normal operation instrumentation and controls.
(d)
The pressure control and relief system which consists of a pressurizer, discharge tank, relief valve, safety valves, electric heaters, and instrumentation and controls.
(e) The charging system consisting of high pressure pumps and' instruments and controls.
(f) The purification system consisting of heat exchangers, flow control valve, demineralizers, and instrumentation and controls.
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(g) The chemical addition system consisting of a steam heated boric acid tank, borJc acid pump, and a chemical addition tank.
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(h) The sampling and lesk detection system consisting of high pressure and low pressure sampling and Isak detection lines, sample coolers, sample bombs, and instruments and controls.
(1) The shutdown cooling system consisting of a low pressure hast exchanger, puispa sad instrumentation and controls.
(j) The safety injection system consisting of two high pressure pumps arranged in series, a high pressure and low pressure piping system, and instrumentation and controls.
(k) The station service electrical system consisting of a normal and emergency power supply, 440-voit feeder busses, pressurizer bester control center, motor control centers, battery and battery charger, safety injection pumps supply, inverter bus and vital bus supply, and main coolant pump supplies.
(1) The radioactive vasta disposal facility consist.ing of a solid wasta disposal system, a liquid waste disposal system, and a gaseous waste disposal system.
(a) The radiation monitoring system consisting of plant
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process monitoring, plant affluents monitoring, site monitoring and plant area monitoring.
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Shielding inside and immediately outside the containment (n) vessel, in the valls of and inside the containment vessel, in the walls'of and inside of the control and auxiliary building, and in the vaste treatment building.
j The fuel handling system consisting of special tools, (o) hoists, and fuel storage rack.
The secondary coolant system inside the containment (p) vessel and the piping outside the containment vessel uk to the feedvater regulating valve and the steam pressure regulating valve.
The component cooling system consisting of circulating (q) pumps, hast exchangers, a surge tank, piping, valving, and instrumantation.
The storage well system consisting of circulating pumps, (r) heat exchanger, domineralizer, filters, storage tank, and
's the necessary piping, valving, fittings, instrumentation and controls.
The cooling, heattag, and ventilation systems consisting (s) of the three systems provided to vantilate potentially radioactive areas of the plant (containmant vessel, waste treatment plant, and control and auxiliary building) and their common exhaust system.
The Unit No. 2 turbine and main condenser in the existing (t)
Pennsylvania glectric Company pleat which will be used to utilize the steam produced by the Saxton reactor plant.
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(u), The speac fuel storage rock consisting of a rectangular stainless steel crate type struc Nre which is located in the storage well.
(2) As used in this license, the term "hasards susumary report" means the report designated by Saxton as the Final Safeguards Report
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and submitted by Amendment No. 5 to Saxton's license application, including the supplemental information submitted by Saxton in Amendment No. 7, the report designated by Saxton as the phase I Safeguards Report submitted by Amenhut No.10, including the supplemental informatwn submitted by Saxton in Supplement No.1 to Amendment No. 10.
4.
The license is effective as of the date of issuance and shall expire April 13, 1967, unisse exten$ed for good causs shown.
- 01 THE ATONIC ENERGi CC00CSSION Director Division of Licensing and Reguistion Attachment Appendix A Date of. Issuance:
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