ML20206P073
| ML20206P073 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 05/12/1999 |
| From: | Clifford J NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20206P079 | List: |
| References | |
| NUDOCS 9905180140 | |
| Download: ML20206P073 (8) | |
Text
s 4A8 MO p-
-t UNITED STATES g
j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2055MX)01
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- %4.....,o GPU NUCLEAR. INC.
AND JERSEY CENTRAL POWER & LIGHT COMPANY DOCKET NO. 50-219
,0YSTER CREEK NUCLEAR GENERATING STATION AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 205 License No. DPR-16 I
i 1.
The Nuclear Regulatory Commission (the Commission) has found that:
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A.
The application for amendment by GPU Nuclear, Inc. et al., (the licensee), dated November 10,1998, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations set forth in 10 CFR Chapter I;
' B.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission 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 Commission's regulations; D.
The issuance of this amendment will not be inimical to the common 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 1
Commission's regulations and all applicable requirements have been satisfied.
9905190140 990512 PDR ADOCK 05000219 P
PDR w.
e' 2.
Accordingly, the license is amended by changes to the Technical Specifications as indicated in the attachment to this license amendment, and paragraph 2.C.(2) of Facility Operating License No. DPR-16 is hereby amended to read as follows:
(2)
Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 205, are hereby incorporated in the license. GPU Nuclear, Inc. shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of the date of issuance, to be implemented within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION Q
J mes W. Clifford, Chief, Section 2 Project Directorate i Division of Licensing Project Management Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications Date of issuance: May 12,1999
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ATTACHMENT TO LICENSE AMENDMENT NO. 205 FACILITY OPERATING LICENSE NO. OPR-16 DOCKET NO. 50-219 Replace the following pages of the Appendix A, Technical Specifications, with the attached pages as indicated. The revised pages are identified by amendment number and contain vertical lines indicating the areas of change.
Remove Insert i
i 1.0-7 1.0-7 5.1-1 5.1-1 5.1-2 6-12 6-12
TABLE bF CONTENTS Section 1 Definitions Page i.!
Operable - Operability 1.0-1 1.2 Operating -
1.0-1 1.3 Power Operation 1.0 1 1.4 Startup Mode 1.0-1 1.5 Run Mode 1.0-1 1.6
- Shutdown Condition 1.0-1 1.7 '
Cold Shutdown 1.0-2 1.8 Place in Shutdown Condition 1.0-2 1.9 Place in Cold Shutdown Condition 1.0-2 1.10 Place in isolation Condition 1.0-2
' l.I1 - Refuel Mode -
1.0-2 1.12 : Refueling Outage 1.0-2 1.13 = Primary Containment Integrity 1.0-2 1.14 Secondary Contamment Integrity 1.0-3 l
1.15 Deleted 1.0-3 1.16. Rated Flux 1.0-3 1.17 Reactor Thennal Power-To-Water 1.0-3 1.18 Protective Instrumentation Logic Defmitions 1.0-3 1.19 Instrumentation Surveillance Defmitions 1.0-4 1.20.FDSAR 1.0-4 1.21' Core Alteration 1.0-4 1.22 Critical Power Ratio 1.0-4 1.23 Staggered Test Basis 1.0-4 1.24 Surveillance Requirenwnts.
1.0-5 1.25 Appendix J Test Pressure l.0-5 1.26 Fraction of Limiting Power Density (FLPD) 1.0-5 1.27 Maximum Fraction of Limiting Power Density (MFLPD) 1.0-5 1.28-Fraction of Rated Power (FRP) 1.0-6 1.29 Top of Active Fuel (TAF) 1.0-6
- 1.30 Reportable Event 1.0-6 1.31 Identified Leakage 1.0 1.32 Unidentified Leakage 1.0-6 1.33: Process Control Plan 1.0-6 1.34 - Augmented Ofigas System (AOG) 1.0-6 1.35 Member of the Public 1.0-6 1.36 Of%e Dose Calculation Manual 1.0-6 i
1.37' Purge 1.0-7 1.38 Site Boundary 1.0-7 1.39 Reactor Vessel Pressure Testing.
1.0-7 1.40. Substantive Changes 1.0-7 1.4 I. Dose Equivalent 1-131 1.0-7 1.42 ~ Average Planar Linear Heat Generation Rate 1.0-8 l
1.43' Core Operating Limits Report 1.0-8 1.44 Local Linear Heat Generation Rate '
l.0-8 1.45' Shutdown Margin (SDM) 1.0-8 l
' OYSTER CREEK -
i Amendment Noc:-16+, t96, 2(6 q
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' parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluent, in the calculation ofgaseous and liquid effluent monitoring Alarmffrip Setpoints, and in the conduct of the Environmental Radiological Monitoring Program. The ODCM shall also contain (1) the Radioactive Effluent Controls and Radiological Ensironmental Monitoring Programs required by Section 6.8.4; and (2) descriptions of the i
information that should be included in the Annual Radioactive Efiluent Release Report AND Annual Radiological Environmental Operating Report required by Specifications 6.9.1.d and 6.9.1.e, respectively.
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1.37 PURGE PURGE OR PURGING is the controlled process ofdischarging air or gas from a confinement I
and replacing it with air or gas.
1.38 SITE BOUNDARY The SITE BOUNDARY is the perimeter line around the OCNGS beyond which the land is neither owned, leased, nor otherwise subject to control by GPU (ref. ODCM). The area outside the SITE BOUNDARY is termed OFFSITE or UNRESTRICTED AREA.
1,39 REACTOR VESSEL PRESSURE TESTING System pressure testmg required by ASME Code Section XI, Article IWA-5000, including system leakage and hydrostatic test, with reactor vessel completely water solid, core not critical and section 3.2.A satisfied.
1.40 SUBSTANTIVE CHANGES SUBSTANTIVE CHANGES are those which affect the activities associated with a document or the document's meamng or intent. Exan'ples of non-substantive changes are: (1) correcting spelling, (2) adding (but not deleting) sign off spaces, (30 blocking in notes, cautions, etc, (4) changes in corporate and personnel titles which do not reassign responsibilities and which are not referenced in the Appendix A Technical Specifications, and (5) changes in nomenclature or editorial changes which cler.rly do not change function, meamng or intent.
1.41 DOSE EOUIVALENT l-131 DOSE EQUIVALENT l-131 shall be that concentration ofI-131 microcuries per gram which alone would produce the same thyroid dose as the quantity and isotopic mixture ofI-131, 1-132,1-133,1-134, and 1 135 actually present. He thyroid dose conversion factors used for this calculation shall be those listed in Table E-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 Appendix 1."
OYSTER CREEK 1.0-7 Amendment No.:-tM,42&, RS, tt6,+M,t49,19t, 205
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SECTION 5 DESIGN _ FEATURES I
5.1 SJT_E A.
The reactor (center line) is located 1,358 feet west of the east boundary of New Jersey State Highway Route 9 which is the minimum exclusion distance as defined in 10 CFR 100.3. The licensee will at all times retain the complete authority to determine and maintain sufficient control of all activities through ownership, easement, contract and/or other legal instmments on property which is closer to the reactor (center line) than 1,358 feet. This includes the authority to exclude or remove personnel and property within the minimum exclusion distance.
I B.
The reactor building, standby gas treatment system and stack shall comprise a j
secondary containment in such fashion to enclose the primary containment in order j
to provide for controlled elevated release of the reactor building atmosphere under
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accident conditions.
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1 OYSTER CREEK 5.1-1 AmendTnt No. 205
BMet Exclusion area means that area surrounding the reactor, in which the reactor licensee has the authority to determine all activities including exclusion or removal of personnel and property from the area. This area may be traversed by a highway, railroad, or waterway, provided these are not so close to the facility as to interfere with normal operations of the facility and provided appropriate and effective arrangements are made to control traffic on the highway, railroad, or waterway, in case of emergency, to protect the public health and safety. Residence within the exclusion area shall normally be prohibited. In any event, residents shall be subject to ready removal in case of necessity. Activities unrelated to operation of the reactor may be permitted in an exclusion area under appropriate limitations, provided that no significant hazards to the public health and safety will result.
Activities unrelated to plant operation within the exclusion area are acceptable provided:
(a)
Such activities, including accidents associated with such activities, represent no haztrd to the plant or have been shown to be accommodated as part of the plant design basis (b)
The licensee is aware of such activities and has made appropriate arrangements to evacuate persons engaged in such activities, in the event of an accident, and (c)
There is reasonable assurance that persons engaged in such activities can be evacuated without receiving radiation doses in excess of the guideline values given in 10 CFR Part 100.
Contract provisions for property agreements in the exclusion area must ensure that the licensee retains sufficient control of all activities in the exclusion area including the authority to exclude or remove personnel and property, thereby (1) maintaining compliance with 10 CFR Part 100 radiological limits for the exclusion area, including evacuation when necessary, and (2) ensuring that any activities, now or in the future, in the exclusion area would not negatively affect nuclear safety, safe plant operations or violate current plant design or licensing bases.
Any property transactions in the " exclusion area", as is the case for any activity which has the potential to adversely affect nuclear safety or safe plant operations, requires a specific safety evaluation and 50.59 review.
References:
(1)-
10 CFR Pan 100, " Reactor Site Criteria".
(2)
NRC Standard Review Plan, NUREG-0800 (Formerly NUREG-75/087), Chapter 2.1.2, " Exclusion Area Authority and Control", Rev. 2, July 1981.
OYSTER CREEK 5.1-2 kenchent tb. 205
9.
Limitations on the annual and quarterly doses to a MEMBER OF THE PUBLIC from 1-131,1 133, tritium, and all radionuclides in particulate form with half-lives greater than 8 days in gaseous effluent released beyond the SITE BOUNDARY conforming to Appendix I of l
10 CFR 50, 10.
Limitations on the annual dose or dose commitment to any MEMBER OF THE PUBLIC due to releases of radioactivity and to radiation from Uranium fuel cycle sources conforming to 40 CFR Part 190.
b.
bdiological Environmental Monitoring Program A program shall be provided to monitor the radiation and radionuclides in the environs of the plant. The program shall provide (1) representative measurements of radioactivity in the highest potential exposure pathways, and (2) verification of the accuracy of the effluent monitoring program and modeling of environmental exposure pathways. The program shall (1) be contained in the ODCM, (2) conform to the guidance of Appendix 1 to 10 CFR Part 50, and (3) include the following:
1 1.
Monitoring, sampling, analysis, and reporting of radiation and radionuclides in the environment in accordance with the methodology and parameters in the ODCM, j
2.
A Land Use Census to ensure that changes in the use of areas at and beyond the SITE BOUNDARY are identified and that modifications to the monitoring program are made if required by the re 'Jts of this census, and 3.
Participation in an Interlaboratory Comparison Program to ensure that mdependent checks on the precision and accuracy of the measurements of radioactive materials in environmental sample matrices are performed as part of the quality assurance program for environmental monitoring.
1 OYSTER CREEK 6-12 Amendment No.:e,48, 84,-w8, +M, +M, %6, 205