ML20034C004
| ML20034C004 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 04/23/1990 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | GPU Nuclear Corp, Jersey Central Power & Light Co |
| Shared Package | |
| ML20034C005 | List: |
| References | |
| DPR-16-A-138 NUDOCS 9005010298 | |
| Download: ML20034C004 (6) | |
Text
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f NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20695 t
GPU NtJCLEAR CORPOPATION
$0 JERSEY CEllTRAL POWER & LIGHT COPPANY DOCKET NO. 50-219 OYSTER CREEK NtlCLEAR GENERAT_IllG STATION, Al'ENDMENT TO PROVISIONAL OPERATING LICENSE, Amendment No.138 License No. DPR-16 1.
The Ituelear Regulatory Comission (the Comission) has found that:
A.
The application for amendment by GPU Nuclear Corporation, et al.,
(thelicensee),datedFebruary 23, 1990, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Comission's rules and regulations set forth in 10 CFR Chapter I; D.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Comission; C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations; D.
The issuance of this amendment will rot be inimical to the comon i
defense and security or to the health and safety of the public; and E.
The issuance of this amendment-is in accordance with 10 CFR Part 51 of the Comission's regulations and all applicable requirements have been satisfied, i
9005010298 900423 ADOCK0500gj9 DR
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2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, l
and paragraph 2.C.(2) of Provisional Operating License No. DPR-16 is hereby amended to read as follows.
(2) Technical Specifications The Technical Specifications conta(ned in Appendices A and B, as revised through Amendment No.138, are hereby incorporated in the license. GPU Nuclear Corporation shall operate the facility in accordance with the Technical Specifications.
3.
This license amendrent is effective as of the date of issuance. to be imple'ented within 30 days of issuance.
m FOR THE NUCLEAR REGULATORY COMMISSION L
o sf. Stolz, Directo
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P oject Directorate 4 4 i
bivision of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of Issuance: April 23, 1990 i
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F ATTACHPENT TO LICENSE AMENDMENT fl0.138 PROVISIONAL OPEPATING LICENSE NO. DPR-16 DOCKET 110. 50-219 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages as indicated.
The revised pages are identified by amendment number and contain vertical lines indicating the areas of chr nge.
a Remove Insert Page 1.0-5 Page 1.0-5 Page 1.0-6 Page 1.0-6 Page 1.0-7 Page 1.0 7 l
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l the testing of one system, subsystem, train er other designated
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component at the beginning of each subinterval.
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1.24 sURvrf t t ner REcuf trurwTs surveillance requirements are requiremente relating to test, i
calibration, or inspection to assure that the necessary quality of systems and components is maintained, that facility operation will be within the safety limits, and that the limiting conditions of operation will be met.
Each surveillance requirsment shall be performed within the specified time intervai with a maximum allowable extension not to exceed 25% of the surveillance interval.
- Surveillance requirements for sys.tems and components are applicable only during the modes of operation for which the system or components are required to be operable, unless otherwise stated in the specification.
)
This definition establishes the limit for which the specified time interval for surveillance Requirements may be extended.
It permits an allowable extension of the normal surveillance interval to facilitate surveillance scheduling and consideration of plant operating conditions that may not be suitable for conducting the surveillance, eg., transient conditions or other ongoing surveillance or maintenance e.ctivities.
It also provides flexibility to accommodate the length of a funi cycle for surveillances that are performed at each refuelAng outage and aru specified with a fuel cycle length surveillance interval.
It is not intended that this provision be used j
s repeatedly as a convenience to extend surveillance intervals beyond that specified for surveillances that are not performed during refueling outages.
The limitation of this definition is based on engineering judgement and the recognition that the most probable result of any particular surveillance being performad is the verification of conformance with the survelliance Requirements.
This provision is sufficient to ensure that the reliability ensured through surveillance activities is not significantly degraded beyond l
that obtained from the specified surveillance interval.
1.2$
FIRE SUPPRESSION WATER SYSTEM A FIRE SUPPRESS!oN WATER SYSTEM shall consist of t a water source; pump; and distribution piping with associated sectioniaing control or isolation valves.
Such valves shall include yard hydrant curb valves, and the first valve ahead of the water flow alarm device on each sprinkler, hose stand-up or spray system riser.
1.26 FRACTION OF LIMITINC POWER DENSITY fFLPD)
The fraction of limiting power density is the ratio of the linear heat generation rate (LHGR) existing at a given location to the design LHCR for that bundle type.
1.27 KAXIMUM FRACTION OF LIMITING POWER DENSITY f MPLPD)
P The maximum fraction of limiting power density it the highest value existing in the core of the fraction of limiting pcwer density (FLPD).
- Not applicable to containment leak rate test.
OYSTER CAEEK 1.0-5 Amendment No.: '14, h, Q, h, af,
s, 138 Correction: 10-10-7s
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1.28 raieTrow or mAtre Powra m yi The fraction of rated power is the ratio of eore thermal power to I
rated thermal power.
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i 1.29 Top er AerrVr runt teken - 353.3 inches above vessel sero.
1.30 REPORTABLE EVENT A REPORTABLE EVENT shall be any of those conditions specified La i
Section 80.73 to 10 CFR Part 80.
i 1.31 IDENTIr!ED 12ARASE l
IDENTIFIED LEAKAGE is that leakage which is collected in the l
primary containment equipment drain tank and eventually transferred to radwaste for processing.
3.32 UNIDENTIFIED trark,rr l,
UNIDENTIFIED LEAKAGE is all measured leakage that is other than identified leakage.
1.33 PROCESS CONTROL PLAN The PROCESS CONTROL PLAN shall generally describe the essential operational controls and surveillance checks for processing wet radioactive waste in order to provide reasonable assurance of compliance with class 3 or C i
stability requirements of 10 CFR Part 61.56 (b) before disposal.
1.34 AUGMEt4TED OFFCAs SYSTEM fhoc)
The AUGMENTED OFFCAs SYSTEM is a system designed and installed to holdup and/or process radioactive gases from the main condenser offgas system for the purpose of reducing the radioactive material content of the gases before release to the environs.
1.35 PJ3iRER OF THE PUBLIC A MEMBER OF TNE PUBLIC is a person who is not occupationally associated with GPU Nuclear and who does not normally frequent the Oyster Creek Nuclear Cenerating Station site.
The category does not. include l
contractors, contractor employees, vendors, or persons who enter the site to make deliveries, to service equipment, work on the site, or for other purposes associated with plant functions.
1.36 ortsITE boSE CALCULATION MANUAL An CFFS1TE DOSE CALCULATION MANUAI,(ODCM) states the methodology and parameters to be used in the calculation of radiation doses offsite due to radioactive gaseous and liquid effluents and in the calculation of radioactive gaseous and liquid offluent monitoring instrumentation alarm / trip setpoints.
1 OYSTER CREEK 1.0-6 Amendment No.t10k,7420 k, k *ki ke 8,138 Correction
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o 1.37,ggggg PURGE OR PURGING is the controlled process of discharging air er gas from a confinement and replacing it with air or gas.
1.34 Exettston amma EXCLUSION AREA is defined in 10 CFR part 100.3(3). As used in these technical specification, the Raelusten Area boundary is the perimeter line around the OCN08 beyond which the land is neither owned, letood, mer otherwise subject to control by GPU (ref. CDcN Pipure 1-1).
the Exclusion Area is termed 0FF81TE.
The area eutside 1.39 makeTom vansrt emmanuar traTInsa System pressure testing required by ASME Code Section XIe Article IWA-5000, including system leakage and hydrostatic tests, with reaeter vessel completely water solid, core not critical and section 3.3.A satisfied.
1.40
$UlsTANTIVE CKkNers SUBSTANTIVE CRANGts are those which affect the activities associated with a document or the document's maahing or intent.
Raamples of non-substantive changes aret (1) correcting spelling, (2) adding (but not deleting) sign-off spaces, (3) blocking in notes, cautions, etc, (4) changes in corporate and personnel titles which do not reassign responsibilities and which are not referenced in the Appendia A Technical Specifications, and (5) changes in nomenclature or editorial changes which clearly do not change function, meaning or intent.
1.41 Dost tourvAtrNT f=131 DoSt EQU2 VALENT 2-131 shall be that concentration of I-131 microcuries per gram which alone would produce the same thyroid does as the quantity and isotopic mixture of I-131, I-132, 1-133, 1-134, and 1-135 actually present.
The thyroid dose conversion factors used for this calculation shall be those listed in Table R-7 or Regulatory Guide 1.109,
" Calculation of Annual Doses to Man from Routine Releases of Reactor Effluences for the Purpose of Evaluating compliance with 10 CFR Par 40 Appendia 2*.
CYSTER CRttK 1.0-7 Amendment No.: h,
,h correction 10-10-78 12 i 12D, 1 6.