ML20072U894
| ML20072U894 | |
| Person / Time | |
|---|---|
| Site: | Saxton File:GPU Nuclear icon.png |
| Issue date: | 01/28/1964 |
| From: | Price E US ATOMIC ENERGY COMMISSION (AEC) |
| To: | |
| Shared Package | |
| ML20072T843 | List:
|
| References | |
| FOIA-91-17 NUDOCS 9104190342 | |
| Download: ML20072U894 (12) | |
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UNITED STATES ATOMIC ENERGY COWISSION DOCKET NO. 50-146-SAXTON NUCLEAR EXPERIENTAL CORPORATION NOTICE OF PROPOSED ISSUANCE-OF OPERATING LICENSE-
-l Notice is hereby given pursuant to.Section 189 of the Atomic i
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 l
1s 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 Commission proposes to issue an-operating-license 1 1
substantially as set 'forth below, ~ to Saxton authorizing operation.
. of the 23.5-megawatt (thermal) light. water moderated and cooled, nressurized water reactor located near the Borough of Saxton in
' 4 Sownship, Bedfc~i' wu,,
ivania.
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Const ndinrd oL'the! reactor was authorbud of Construction Permit :
- No'. CPPR-6 -issued February -.11, 1960. The reactor has been-operated
_under Provisional Operating _ License No. DPR-4 issued to Saxton q
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; 9104190342 910314 PDR FOIA DEKOK91-17 PDRi (2) There is reasonable assurance that (i) the activities authorized by this license can be conducted at the desig.
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-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 details with respect to this proposed license, see
'l) the license application amendment dated May 28, 1963, and supplement o
wrt of the Advisory Committe1 hted January 8,19W r i
<m keweter M
- guard-sa: i scpearatc r 12, i. fM a relate <* 1 s.
analysis prepared by the Research and Power Reactor Safety tiranch of the Division of Licensing and Regulation; and (4) the Technical Specifica-tions which are incorporated in the license and designated as Appendix.
A thereto; all of which availabic for public inspection at the
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3 Commission's Public Document Room,1717 H St reet, N, W., Washington, fi) above may be obtained at the D
C, Copies of items (2) ans Commission's Public Document Room, or upon request addressed to the Direc.
Atomic Energy Comission, Washington, D. C. 20545, Attention:
tor, Division of Licensing and Regulation.
FOR THE ATOMIC ENERGY COhMISSION Oririntil shmed by ELc n. ?ce.a Aunt Director Division of Licens' :g 6 Regulation Dated at Bethesda, Maryland this day of January,1964 JAN 2 81954 d
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l SAXTON NUCLEAR EXPERIMEttrAL C0dPhTION DOCKET NO. 50 14(t PROPOSED OPERATING LICENSE License No. DPR-4 This license applies to the pressurized water reactor (hereinaf ter referred 1.
to as the " reactor") owned by Saxton Nuclear Experimental Corporation (hereinaf ter referred to as "Saxton"), located north of the Borough of Saxton in Liberty Township, Bedford County, Pennsylvania, and described in and Amendment No. 7 dated June 30, Amendment No. 5 dated April 19, 1961, 1961, to Saxton's license application.
Subject to the conditions and requirements incorporated herein, the Atom 2.
Energy Consmission (hereinaf ter referred to as the " Commission") hereby Licenses.Saxton Pursuant to Section 104(b) of the Atomic Energy Act of 1954, as A.
- CFR, amor.ded. (hereinaf ter referred to as the "Act") and Title los Chapter 1. Part 50, " Licensing of Production and Utilization Facilities to possess, use and operate the reactor as a utilization facility;
' aunt to the Act and Title 10 CFR, Chapter 1. Part 70, "Special B.
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,a-i me at any one time 130 41 r.
Wial," to rece?7 4 m ation N w k.tiogrm di <.onta.N Uranium 235 as fuel for the c.
j" 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 material as may be produced by operation of the reactor, and to receive, possess, and use at any one time not to exceed 120 curies of polonium-beryllium as core neutros sources.
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2-ditions This license } hall be deemed to contain and be subject to the con 3.
70, and specified in Section 30.54 of Part 50, section 70.32 of Part Section 30.32 of Part 30 of the Commission's regulctionu, d rules, and is subject to all applicable provisions of the Act anin effect; and regulations and orders of the Commission now or heraaf ter is subject to the additional conditions specified below:
Maximum Power LeSei A.
f Saxton shall not operate the reactor at power levels in excess o 23.5 megawatts (thermal).
Technical Specific'ations_
B.
The Technical Specifications contained in Appendix A to this license b
(hereinaf ter referred to as the " Technical Specifications") are Saxton shall operate the facilityonly incorporated in this license.
No changes shall be in accordance with the Technical Specifications.
by the Coemis-made in the Technical Specifications unless authorized sks as provided in 10 CFR 50.59.
wnts ration of Changes. Teste sne Er j
titn.s described in the 4
, the saxtw uj b.
makes che # #
4 (2) rche changes in the procednes s
hasesde.uumasy repost, described in the hazards summary report, and (3) conduct tests or l is experiments not described in the hazards sumnary report on y h comaission's accordance with the novisions of Section 50.59 of t e re5ulations.
- b. Records under this license and 4
In addition to those otherwise requiret,'
llowing records:
applicable regulations, Saxton shall keep the fo
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i Reactor operating records, including power levels and period (1) of operations at each power level.
Records showing the radioactivity released or discharged into (2) f Saxton as the air or water beyond the effective control o discharge.
measured at or prior to the point of such release or Records of scrams, including reasons therefor.
(3) b ti-Records of principal maintenance operations involving su s (4) ts and tution or replacement of f acility equipment or componen the reasons therefor.
i Records of radioactivity measurements at on-site and off-s te (5) monitoring stations.
t Records of facility tests and measurements performed pursuan (6) to the requirements of the Technical Specifications.
E.
Reports d
In addition to reports otherwise required under this license an a-licable regulations:
in writing to the shall make an immedirtc p 4
w of a possible a.r>.
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- m., o m, o unmt ntw, of anv Jac;,9tv, unsate concitton relatis.g to the operation of th.
implied limitation, any possible unsafe including, without condition arising out of:
Any substantial variance disclosed by operation of (a) t the facility from the performance specifications se and forth in the hazards summary report,
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4 (b)
Any accidental release of radioactivity, whether or not resulting in property damage or personal injury or exposure above permissible limits.
(2)
Saxton shall report to the Commission in writing significant changes in plant organization, and transient or accident i
analyses, as described in the hasards summary report.
(3) Saxton shall submit to the Commission, on at 1 cast a semi.
annual basis, a written report of operating experience i
including:
(a)
A brief explanation of the cause of each,nplanned shut-down of the reactor.
(b) The amount of radioactive material removad 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 changea, tests, and n periments performed
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m nission's Rules to Paragraph ' ,
and Ro gu i at i : *
(e)
A description of the principal maintenance performed.
(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.B. of the Technical Specifications.
5 Such reports shall be due within 60 days after the end of each reporting period.
F.
De finit ions _
As used in Section 3 in this license, the term " facility" (1) means the following systems and components as described in the hazards summary report:
The containment vessel which houses the reactor, steam (a) generator, main coolant system, other miscellaneous auxiliary systems, and the fuel storage well.
The reactor core including the control rods, control rod (b) 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.
The pressure control and relief system which consists of N'
1ve, safety valves.
mriter, discharon w1 s.
e lect rt e arm t r.=
anti t iist rument at ivn am, we I
The charging system consisting of high pressure pumps and (e) instruments and controls.
The purification system consisting of heat exchangers, (f) flow control valve, demineralizers, and instrumentation and controls.
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6-The chemical addition system consisting of a steam heated (g) boric acid tank, boric acid pump, and a chemical addition tank.
The sampling and leak detection system consisting of high (h) pressure and low pressure sampling and leak detection lines, sample coolers, sample bombs, and instruments and controls.
The shutdown cooling system consisting of a low pressure (i) heat exchanger, pumps and instrumentation and controls.
The safety injection system consisting of two high pressure (j) pumps arranged in series, a high pressure and low pressure piping system, and instrumentation and controls.
The station service electrical system consisting of a (k) normal and emergency power supply, 440-volt feeder busses, pressurizer heater control center, motor control centers, battery and battery charger, safety injection pumps supply,
.i main coolant pump
-~4rter bus and vital bue supply -
mpp :
a, The radioact.t';e waste disposal facility consistint af o (1) solid waste disposal system, a liquid waste disposal system, and a gaseous wasto disposal system.
The radiation monitoring system consisting of plant (m) process monitoring, plant effluents monitoring, site monitoring ano plant area monitoring.
7 Shielding-inside and immediately outside the containment (n) l vessel, in the walls of and inside the containment vesse,
in the walls of sad inside of the control and auxiliary building, and in the waste treatment building.
The fuel handling system consisting of special tools, (o) hoists, and fuel storage rack.
The secondary coolant system inside the containment (p) l up vessel 'and the piping outside the containment vossa essure to the feedwater regulating valve and the steam pr regulating valve.
(q).The component cooling system consisting of circula pumps, heat exchangers, a surge tank, piping, valving and instrumentation.
The storage well system consisting of circulating pumps, (r) heat exchanger, dominera11ser, filters, storage tank, tation-
- the necessary piping, valving,-fittings,:instrumen 4-e.ontrols.
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(s) The cooling, tasting, and ventilation 1,pi~re consis
-y e
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- of the three systems provided to ventilate potent a radioactive areas of the plant (containment vessel, wast ding) and -
treatment plant, and control and auxiliary buil their common exhaust system.
i The Unit No. 2 turbine and main condenser in the exist (t) d to Pennsylvania Electric Company plant which will be use utilize the steam produced by the Saxton reactor plant.
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, (u) The spent fuel stortge rack consisting of a rectangular stainless steel crate type structure which is located in the storage well.
(2) As used in this license, the term " hazards suammary report" means the report designated by Saxton as the Final Sefaguards Report and submitted by Amendment No. $ to Saxton's license application, including the supplemental information submitted by Saxton in Amendment No. 7 the report designated by Saxton as the Phase 1 Safeguards Report submitted by Amendment No.10, including the supplemental information submitted by Saxton in Supplement No. I to Amendment No. 10.
4.
The license is effective as of the date of issuance and shall expire April 13, 1967, unless extended for good cause shown.
FOR, TdE ATOKlc ENERGY COMMISSION Director Regulation Divistor e,
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7 Att wlanauLa Appendix A Date of Issuance:
DATE:
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I M 6 Bog. Saxtes TO:
FROM AIO 799/8 ** S1120E PLUTONItM P100 RAM To somsider a proposal for the irradiation of plutonium
SUMMARY
a It is sariched fuel elements in the Sarton Reantor.
recommended that a contract be negotiated with Westinghouse to conduet the program which vill be under the Joint Euratom US Research & Devel. Progres.
FILED: Im 6 Westingw.m.
m oexcR.
date of paper:
4-9 4 REMARKSs s
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1 U. S. ATOMIC ENERGY COMMIS2ilON o
CORRESPONDENCE REFERENCE FORM
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