ML20059J202
| ML20059J202 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 10/29/1993 |
| From: | Bajwa S Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20059J206 | List: |
| References | |
| NUDOCS 9311120089 | |
| Download: ML20059J202 (14) | |
Text
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'o UNITED STATES j
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NUCLEAR REGULATORY COMMISSION g
- y WASmGTON. D. C. 20555 e
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i SOUTHERN NUCLEAR OPERATING COMPANY. INC.
DOCKET NO. 50-348 i
JOSEPH M. FARLEY NUCLEAR PLANT. UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No.102 License No. NPF-2 1.
The Nuclear Regulatory Commission (the Commission) has found that:
i A.
The application for amendment by Southern Nuclear Operating I
Company, Inc. (Southern Nuclear), dated May 10, 1993, 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; 8.
The facility will operate in conformity with the application, the provisions of the Act, and the rules and regulations of the Commission; i
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 license amendment will not be inimical to the common defense and security or to the health and safety of the l
public; and E.
The issuance of this amendment is in accordance with 10 CFR Part t
51 of the Commission's regulations and all applicable requirements have been satisfied.
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.
NPF-2 is hereby amended to read as follows:
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9311120089 931029 PDR ADOCK 05000348 P
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(2)
Technical Specifications' The Technical Specifications contained in Appendices A and B, as.
revised through Amendment No.102, are hereby incorporated in the license. Southern Nuclear shall operate the facility in 4
accordance with the Technical Specifications.
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3.
This license amendment is effective as of its date of issuance and shall be implemented within 30 days of issuance.
l FOR THE NUCLEAR REGULATORY COMMISSION 1
S. Singh Bajwa, Acting Director Project Directorate II-I i
Division of Reactor Projects - I/II i
Office of Nuclear Reactor Regulation i
Attachment:
Changes to the Technical Specifications j
Date of Issuance:
October 29, 1993 i
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e ATTACHMENT TO LICENSE AMENDMENT NO.102 TO FACILITY OPERATING LICENSE NO. NPF-2 DOCKET NO. 50-348 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages.
The revised areas are indicated by marginal lines.
I Remove Paces Insert Paoes XIX XIX l-4 1-4 6-17 6-17 6-23 6-23 l
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ADMINISTRATIVE CONTROLS l
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SECTIDN f.&E Review.....................................................
6-10 Audits.....................................................
6-11 Authority..................................................
6-12 Records....................................................
6-12 6.5.3 TECHNICAL REVIEW AND CONTROL
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Activities.................................................
6-12 Records....................................................
6-13
... re m m e r m T Aal.......................................
6-i.
6.7 SAFETY LIMIT VIOLATION.......................................
6-14 6.8 PROCEDURES AND PROGRAMS......................................
6-14 6.9 REPORTING RE0UIREMENTS 6.9.1 ROUTINE REPORTS Startup Report.............................................
6-15a Ann u al Repo rt..............................................
6-16 Annual Radiological Environmental Operating Report.........
6-17 Annual Radioactive Effluent Release Report.................
6-17 Monthly Operati ng Report...................................
6-19 Radi al Pe aking Factor Limi t Report.........................
6-19 Annual Diesel Generator Reliability Data Report............
6-19 Annual Reactor Coolant Systen Specific Activity Report.....
6-20 Annual Se al ed Source Leakage Report........................
6-20 6.9.2 SPECIAL REPORTS............................................
6-20 6.10 RECORD RETENTION............................................
6-20 6.11 RADIATION PROTECTION PROGRAM................................
6-21a 6.12 HIGH RADIATION AREA.........................................
5-22 FARLEY-UNIT 1 Xg ANDOWIT NO.57,99,102
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DEFINITIONS LIOUID RADWASTE TREATMENT SYSTEM 1.15 This definition deleted. Refer to the Offsite Dose Calculation Manual.
MAJOR CHANGES TO RADI0 ACTIVE WASTE TREATMENT SYSTEMS 1.16 This definition deleted. Refer to the Offsite Dose Calculation Manual and the Process Control Program.
OFFSITE DOSE CALCULATION MANUAL (ODCM) 1.17 The OFFSITE DOSE CALCULATION MANUAL shall contain the methodology and parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitoring alam/ trip setpoints, and in the conduct of the Radiological Environmental Monitoring Program. The ODCM shall also contain (1) the Radioactive Effluent Controls and Radiological Environner.tal Monitoring Programs required by Technical Specification 6.8.3 and (2) descriptions of the infomation that should be included in the Annual Radiological Environmental Surveillance and Annual Radioactive Effluent Release Reports required by Technical Specifications 6.9.1.6, 6.9.1.7, 6.9.1.8 and 6.9.1.9.
OPERABLE - OPERABILITY 1.18 A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of perfoming its specified function (s), and when all necessary attendant instrumentation, controls, a normal and an emer-gency electrical power sources, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, com-ponent or device to perform its function (s) are also capable of performing their related support function (s).
FARLEY-UNIT 1 1-4 AMEENDIT NO. 26,99,102 v
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ADMINISTRATIVE CONTROLS
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ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT I
6.9.1.6 and 6.9.1.7 The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted before May 1 of each year. The report shall include summaries, interpretations, and analysis of trends of the results of the Radiological 1
Environmental Monitoring Program for the reporting period. The material provided shall be consistent with the objectives outlined in (1) the ODCM and i
(2) Sections IV.B.2, IV.B.3, and IV.C of Appendix I to 10 CFR Part 50. A single submittal may be made for a multiple unit station.
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-l ANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT 6.9.1.8 and 6.9.1.9 The Annual Radioactive Effluent Release Report covering j
the operation of the unit during the previous calendar year shall be submitted before May 1 of each year. The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit. The material provided shall be (1) consistent with the objectives outlined in the ODCM and PCP and (2) in conformance with 10 CFR 50.36a and Section IV.8.1 of Appendix I to 10 CFR Part 50. A single submittal may be made for a multiple unit station. The submittal should combine those sections that are cosmon to all units at the station; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit.
s FARLEY-UNIT 1 6-17 AMElWMENT NO. 26,99,102 c - --
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ADMINISTRATIVE CONTROLS 6.13 PROCESS CONTROL PROGRAM (PCP) 6.13.1 The PCP shall be approved by the Commission prior to implementation.
t 6.13.2 Licensee initiated changes to the PCP:
1.
Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.2.o.
This documentation shall contain:
i a.
Sufficient infomation to support the change together with the appropriate analyses or evaluations justifying W change (s) and b.
A determination that the change will maintain the overall confomance of the solidified waste product to existing requirements of Federal, State, or other applicable regulations.
j 2.
Shall become effective after review and acceptance by the PORC and the I
approval of the General Manager - Nuclear Plant.
6.14 0FFSITE DOSE CALCULATION MANUAL (00CM) 6.14.1 The 00CM shall be approved by the Commission prior to implementation.
6.14.2 Licensee initiated changes to the CDCM:
1.
Shall be documented and records of reviews perfomed shall be retained as required by Specification 6.10.2.o.
This documentation shall i
contain:
a.
Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change (s) and b.
A detemination that the change will maintain the level of radioactive affluent control required by 10 CFR 20.106, 40 CFR Part 190, 10 CFR 50.36a, and Appendix ! to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.
2.
Shall become effective after review and acceptance by the PORC and the i
approval of the General Manager - Nuclear Plant.
3.
Shall be submitted to the Commission in the fem of a complete, legible copy of the entire 00CM as a part of or concurrent with the Annual i
Radioactive Effluent Release Report for the period of the report in which any change to the ODCM was made. Each chan by markings in the margin of the affected pages, ge shall be identified clearly indicating the area of the page that was changed, and shall indicate the date (e.g.,
month / year) the change was implemented.
FARLEY-UNIT 1 6-23 AfEIDENT NO 57,I00,102
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'o UNITED STATES
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NUCLEAR REGULATORY COMMISSION I
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SOUTHERN NUCLEAR OPERATING COMPANY. INC.
DOCKET NO. 50-364 i
i JOSEPH M. EARLEY NUCLEAR PLANT. UNIT 2 l
4 AMENDMENT TO FACILITY OPERATING LICENSE f
Amendment No. 95
-License No. NPF-8 l
1.
The Nuclear Regulatory Commission (the Commission) has found that:
A.
The application for amendment by Southern Nuclear Operating I
Company, Inc. (Southern Nuclear), dated May 10, 1993, 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
)
l provisions of the Act, and the rules and regulations of the Commission; j
C.
There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health l
and safety of the public, and (ii) that such activities will be conducted in compliance with the Commission's regulations;
- j D.
The issuance of this license amendment will not be inimical to the common defense and security or to the health and safety of the public; and
)
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E.
The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied.
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. NPF-8 is hereby amended to read as follows:
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(2)
Technical Soecifications l
The Technical Specifications contained in Appendices A and B, as revised through Amendment No. 95, are hereby incorporated in the license. Southern Nuclear shall operate the facility in accordance with the Technical Specifications.
3.
This license amendment is effective as of its date of issuance and shall be implemented within 30 days of issuance.
FOR THE NUCLEAR REGULATORY COMMISSION 4
i i
S. Singh Bajwa, Acting Director J
Project Directorate 11-1 i
Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Attachment:
Changes to the Technical Specifications i
Date of Issuance: October 29, 1993 a
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ATTACHMENT TO LICENSE AMENDMENT NO, 95 TO FACILITY OPERATING LICENSE NO. NPF-8 DOCKET NO. 50-364 Replace the following pages of the Appendix A Technical Specifications with the enclosed pages. The revised areas are indicated by marginal lines.
Remove Paoes Insert Paaes XIX XIX 1-4 1-4 6-17 6-17 6-23 6-23 e
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ADMINISTRATIVE CONTROLS SECTION E&E Review.....................................................
6-10 Audits.....................................................
6-11 Authority..................................................
6-12 Records....................................................
6-12 6.5.3 TECHNICAL REVIEW AND CONTROL Activities.................................................
6-12 R e c o rd s....................................................
6-13 6.6 REPORTABLE EVENT ACTION......................................
6-14 6.7 SAFETY LIMIT VIOLATION.......................................
6-14 6.8 PROCEDURES AND PROGRAMS......................................
6-14 6.9 REPORTING REQUIREMENTS 6.9.1 ROUTINE REPORTS Startup Report.............................................
6-15a An n u al Re p o r t..............................................
6-16 Annual Radiological Environmental Operating Report.........
6-17 Annual Radioactive Effluent Release Report.................
6-17 Monthly Ope rat i ng Repo rt...................................
6-19 Radi al Peaking Factor Limit Report.........................
6-19 Annual Diesel Generator Reliability Data Report............
6-19 Annual Reactor Coolant System Specific Activity Report.....
6-20 Annual Se al ed Source Le akage Report........................
6-20 6.9.2 SPECIAL REPORTS............................................
6-20 6.10 RECORD RETENTION............................................
6-20 6.11 RADIATION PROTECTION PROGRAM................................
E-21a 6.12 HIGH RADIATION AREA.........................................
6-22 FARLEY-UNIT 2 XIX AMDEMENT HD. 49,91,95
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DEFINITIONS LIOUID RADWASTE TREATMENT SYSTEM 1.15 This definition deleted. Refer to the Offsite Dose Calculation Manual.
1 MAJOR CHANGES TO RADI0 ACTIVE WASTE TREATMENT SYSTEMS l
1.16 This definition deleted. Refer to the Offsite Dose Calculation Manual and the Process Control Program.
4 i
l 0FFSITE DOSE CALCULATION MANUAL (0DCM) 1.17 The OFFSITE DOSE CALCULATION MANUAL shall contain the methodology and
[
parameters used in the calculation of offsite doses resulting from radioactive gaseous and liquid affluents, in the calculation of gaseous and liquid effluent monitoring alarsVtrip setpoints, and in the conduct of the Radiological Environmental Monitoring Program. The CDCM shall aise contain (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs required by Technical Specification 6.8.3 and (2) descriptions of the information that should be included in the Annual
~
Radiological Environmental Surveillance and Annual Radioactive Effluent i
Release Reports required by Technical Specifications 6.9.1.6, 6.9.1.7 6.9.1.8 and 6.9.1.9.
OPERABLE - OPERABILITY 1.18 A system, subsystem, train, component or device shall be OPERABLE or have OPERABILITY when it is capable of performing its specified function (s), and when all necessary attendant instrumentation, controls, a normal and an amer-gency electrical power sources, cooling or seal water, lubrication or other auxiliary equipment that are required for the system, subsystem, train, com-ponent or device to perform its function (s) are also capable of performing theirrelatedsupportfunction(s).
1 FARLEY-UNIT 2 1-4 AMDDENT ND. 9I,95 I
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ADMINISTRATIVE CONTROLS I
ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 6.9.1.6 and 6.9.1.7 The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted before May I of each year. The reart shall include summaries, l
interpretations, and analysis of trends of tse results of the Radiological Environmental Monitoring Program for the reporting period. The material l
provided shall be consistent with the objectives outlined in (1) the 00CM and i
(2) Sections IV.B.2 IV.B.3, and IV.C of Appendix I to 10 CFR Part 50. L A single submittal may be made for a multiple unit station.
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i ANNUAL RADIQACTIVE EFFLUENT RELEASE REPORT l
6.9.1.8 and 6.9.1.9 The Annual Radioactive Effluent Release. Report covering the operation of the unit during the previous calendar year shall be submitted before May 1 of each year. The report shall include a summary of I
the quantities of radioactive 11guld and gaseous affluents and solid waste released from the unit. The material provided shall be (1) consistent with the objectives outlined in the ODCM and PCP and (2) in conformance with 10 1
CFR 50.36a and Section IV.B.1 of Appendix I to 10 CFR Part 50. A single submittal may be made for a multiple unit station. The submittal should i
combine those sections that are common to all units at the station; however, l
for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit.
1 l
s FARLEY-UNIT 2 6-17 N G D W ND. fl,95 w.
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i ADMINISTRATIVE CONTROLS 6.13 PROCESS CONTROL PROGRAM (PCP) 6.13.1 The PCP shall be approved by the Consission prior to implementation.
6.13.2 Licensee initiated changes to the PCP:
)
1.
Shall be documented and records of reviews perfomed shall be retained as required by Specification 6.10.2.o.
This documentation shall J
contain:
l l
a.
Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change (s) and b.
A determination that the change will maintain the overall confomance of the solidified waste product to existing requirements of Federal, State, or other applicable regulations.
j 2.
Shall become effective after review and acceptance by the PORC and the approval of the General Manager - Nuclear Plant.
l 6.14 0FFSITE DOSE CALCULATION MANUAL (0DCM) i 6.14.1 The ODCM shall be approved by the Commission prior to implementation.
l 6.14.2 Licensee initiated changes to the ODCM:
1.
Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.2.o.
This documentation shall contain:
i a.
Sufficient infomation to support the change together with the appropriate analyses or evaluations justifying the change (s) and b.
A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.106, 40 CFR Part i
190, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and not l
adversely impact the accuracy or reliability of effluent, dose, or j
setpoint calculations.
2.
Shall become effective after review and acceptance by the PORC and the approval of the General Manager - Nuclear Plant.
l 3.
Shall be submitted to the Commission in the form of a complete, legible copy of the entire 00CM as a part of or concurrent with the Annual a
Radioactive Effluent Release Report for the period of the report in which any change to the 00CM was made.
Each change shall be identified by markings in the margin of the affected pages, clearly indicating the area of the page that was changed, and shall indicate the date (e.g.,
month / year) the change was imp,emented.
i FARLEY-UNIT 2 6-23 MOpelT ND. H,92,95
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