ML20126D252
| ML20126D252 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 05/30/1985 |
| From: | Zwolinski J Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20126D255 | List: |
| References | |
| NUDOCS 8506140689 | |
| Download: ML20126D252 (8) | |
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UNITED $TATES NUCLEAR REGULATORY COMMISSION a
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WASHINGTON, D C. 20555
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t GPU NUCLEAR CORPORATION l
AN9 JERSEY CENTRAL POWER & LIGHT COMPANY OYSTER CREEK NUCLEAR GENERATING STATION AMENDMENT TO PROVISIONAL OPERATING LICENSE j
Amendment No. 84 License No. DPR-16 1.
The Nuclear Regulatory Commission (the Commission) has found that:
The application for amendment by(GPU Nuclear Corporation and Jersey A.
Central Power and Light Company the licensees) dated October 22, Energy Act of 1954, as amended (the Act)quirements of the Atomic 1984, complies with the standards and re
, 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 (1) 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 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 Commission'c regulations and all applicable requirements have bec.n satisfied.
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Accordingly, the license is amended by chances to the Technical Specifications as indicated in the attachment to this license amendment and Paragraph 2.C(2) of Provisional Operating License No. DPR-16 is hereby amended to read er follows:
(2) Technical Specifications The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 84, are hereby incorporated in the license. GPU Nuclear Corporation shall operate the facility in accordance with the Technical Specifications.
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This license amendment is effective as of the date of its issuance.
FOR THE NUCLEAR REGULATORY COMMISSION t/
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. John A. Zwolinski, Chief Operating Reactors Branch #5 I
Division of Licensing
Attachment:
Changes to the Technical Specifications Date of Issuance: May 30,1985 t
ATTACHPENT TO LICENSE AMENDMENT NO. 84 PROVISIONAL OPERATING LICENSE NO. DPR-16 DOCKET NO. 50-219 Revise Appendix A Technical Specifications by removing the pages identified below and inserting the enclosed pages. The revised pages are identified by the captioned amendment number and contain vertical lines indicating the area of change.
REMOVE INSERT i
i 11 11 1.0-6 1.0-6 6-14 6-14 6-17 6-17 6-18 6-19
TABLE OF CONTENTS I
Section 1 Definitions Page i.
1.1 Operable 1.0-1 l
1.2 Operating 1.0-1 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 1.0-1 1.8 Place in Shutdown Condition
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l 1.9 Place in Cold Shutdown Condition 1.0-2 1.10 Place in Isolated Condition 1.0-2 1.11 Refuel Mode 1.0-2 l
1.12 Refueling Outage 1.0-2 i
i 1.13 Primary Containment Integrity 1.0-2 l
1.14 Secondary Containment Integrity 1.0-2 1.15 Deleted 1.0-3 1.16 Rated Flux 1.0-3 1.17 Reactor Thermal Power-to-Water 1.0-3 1.18 Protective Instrumentation Logic Definitions 1.0-4 1.19 Instrumentation Surveillance Definitions 1.0-4 1.20 FDSAR 1.0-4 1.21 Core Alteration 1.0-5 1.22 Minimum Critical Power Ratio 1.0-5 1.23 Staggered Test Basis 1.0-5 1.24 Surveillance Requirements 1.0-5 1.25 Fire Suppression Water System 1.0-5 1.26 Fraction of Limiting Power Denisty (FLPD) 1.0-6 1.27 Maximum Fraction of Limiting Power Density (MFLPD) 1.0-6 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 l
Section 2 Safety Limits and Limiting Safety System Settings 2.1 Safety Limit - Fuel Cladding Integrity 2.1-1 2.2 Safety Limit - Reactor Coolant System Pressure 2.2-1 2.3 Limiting Safety System Settings 2.2-3 Safety 3 Limiting Conditions for Operation 3.0 Limiting Conditions for Operation (General) 3.0-1 3.1 Protective Instrumentation 3.1-1 3.2 Reactivity Control 3.2-1 3.3 Reactor Coolant 3.3.1 3.4 Emergency Cooling 3.4-1 3.5 Containment 3.5-1 3.6 Radioactive Effluents 3.6 1 3.7 Auxiliary Electrical Power 3.7-1 l
3.8 Isolation Condenser 3.8-1 3.9 Refueling 3.9-1 3.10 Core Limits 3.10-1 3.11 (Not Used) 3.11-1 3.12 Fire Protection 3.12-1 3.13 Accident Monitoring Instrumentation 3.13-1 Amendment No. [, g, p, f,
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Section 4-. surveillance Requirements.
1 4.1 Protective Instrumentation 4.1-1 4.2 Reactivity Control 4.2-1 4.3 Reactor Coolant 4.3,.....
4.4 Emergency Cooling 4. L. * * -
4.5 Containment 4.5-1 4.6 Radioactive Efflue%s 4.6-1 4.7 Auxiliary Electricek Power 4.7-1 4.8 Iso 11 tion Condenser 4.8-1 4.9 Refueling 4.9-1 4.10 ECCS Related Core Limits 4.10-1 4.11 Sealed Scurce Contamination 4.11-1 4.12 Fire Protection 4.12-1 4.13 Accident Monitoring Instrumentation 4.13-1 Section 5 Design Features 5.1 Site 5.1-1 5.2 Containment 5.2-1 5.3 Auxiliary Ecuipment 5.3-1 Section 6' Administrative Ccntrols 6.1 Res;onsibilit 6-1 Organi:atien'y 6.2 6-1 6.3 Facility Staff Qualifications 6-5 6.4
. Training 6-7 6.5 Review anc Audit 6-8 6.6 Rebortable Event Action 6-14 6.7 Safety Limit Violation 6-15 6.8 Procedgres 6-15 6.9 Reporting Require.ents 6-16 6.10 Record Retention 6-22 6.11 Radiation Drotection Procram 6-23 E.12 (Deleted) 6.13 Hich Radiatinn Area 6-24 6.14 Environmental Qualification 6 24
- 6.15 Integrity of Systems Outside Containment 6-25 6.16 Iodine Monitoring 6-25
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!ssued by NRC Order dated 10-2'4'-80.
mna.entno.g,g,g,%,84 u
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1,0 6 1.26 Fraction of-Limitino Power Density (FLPD) - The fraction of limiting power density is tne ratio of the linear heat generation rate (LHGR) existing at a given location to the design LEGR for that bundle type.
1.27 Maximum Fraction of Limitina Power Density (MFLPD) - The
. maximum fraction of limiting power density is tne
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highest value existing in the core of the fraction of o
limiting power density.(FLPD).
1.28 Fraction of Rated Power (FRP) - The fraction of rated power is the ratio of core thermal power to rated thermal p'ower.
1.29 Too of Active Fuel (TAF) - 353.3 inches above vessel zero.
J 1.30 REPORTA8LE EYDff j
A REPORTA8LE EVENT shall be any of those conditions specified in Section 50.73 to 10 CFR Part 50.
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Amendment No.
, 84
r5guirements relcted ta saf ty.
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Any other matter, involving safe operati.on of the nuclear power plant that the Manager - Nuclear Safety t eens appropriate for j
consideration.
AUIlloRITY 6.5.4.4 The 105tG'shall have access to the facility and facility records as 1
necessary to perform its evaluations' and assessments. Based on its l
reviews, the 10SRG shall provide reconnendations to the management positions responsible for the areas reviewed.
I QUALIFICATIONS 6.5.4.5 10SRG engineers shall have either (1) a Bachelor's Degree in.
Engineering or appropriate Physical Science and three years of professional level esperience in the nuclear power field which may' include technical supporting functions"or (2) eight years of appropriate esperience in suc* mar power plant operations and/or technology.
Credit toward experience will be given for advance degrees on a one-to-one basis up to a maximum of two years.
RECORDS 6.5.4.6 Reports of evaluations and assessments encompassed in Section 4
.6.5.4.3 shall be prepared, approved, and transmitted to the Wualear Safety Assessment Director Oyster Creek and Nuclear Assarance t
division Vice Presidents, and the management positions responsible '.
for the areas reviewed.
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6.6 REPORTABLE EVENT ACTION 6.6.1 1
The following actions shall be taken for REPORTA8LE EVENTS:
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a.
The Count'ssion shall be notified and'a report submitted pursuant to tne requirements of Section 50.73 to 10 CFR Part 50; and b.
Each REPORTABLE EVENT shall be reported to the cognizant manager and the cognizant division Vice President and the Vice President a Director Dyster Creek. The functionally cognizant division staff shall prepare a Licensee Event Report (LER) in accordance with the guidance outlined in 10 CFR 50.73(c). Copies of all such reports shall be submitted to the functionally co'gnizant division Vice President and the Vice President a Director Oyster Creek.
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, basis which will include a narrative of operating experience, to the Director, Office of Management and Program control, U.S.. Nuclear Regulatory Cousiasion,. Washington, D.C. 2055), with a copy. to the Regional Office of I&E, so later than the 15th of each month
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following the calendar monith covered by the report.
6.9.2 REPORTA8LE EVENTS' The submittal of Licensee Event Reports shall be accomplished in accordance with the requirements set forth in 10 C.:R 50.73.
6.9.3 UNIQUE REPORTING REQUIREMENTS Special reports shall be submitt'ed to the Director of Regulatory Operations Regional Office within the time period specified for each report.
These reports shall be submitted covering the activities identified below pursuant to the requirements of the applicable.
reference specification.
Materials Radiation Surveillance Specimen Reports (4.3A) a.
b.
Integrated Primary containment Leakage Tests (4.5)-
c.
Semi-annual reports specifying effluent release shall be submitted to the NRC.
These reports shall include the following (1) Radioactive Effluent Releases l
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6-17 Amendment No. /,84 (Pages 6-18 &'6-19 deleted; next page is 6-20) 4
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