ML20036B222
| ML20036B222 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 05/10/1993 |
| From: | SOUTHERN NUCLEAR OPERATING CO. |
| To: | |
| Shared Package | |
| ML20036B217 | List: |
| References | |
| NUDOCS 9305180315 | |
| Download: ML20036B222 (32) | |
Text
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t' Proposed Changes 1
to the i
Farley Unit 1 and Unit 2 Technical Specifications k
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i 9305180315 930510 PDR ADOCK 05000348 P-PDR
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Proposed Changed Technical Specification Pages Farley Unit 1 Remove Page Insert Page XIX XIX*
l-4 1-4
- 6-17 6-17*
6-23 6-23 *
- Farley Unit 2 Remove Page Insen Page XIX XIX*
l-4 1 -4
- 6-17 6-17*
6-23 6-23 *
- l Supersedes proposed changed technical specification page submitted by Southern Nuclear Operating Company letter dated June 23,1992.
- Sup_ersedes proposed changed technical specification page submitted by Southern Nuclear Operating Company letter dated August 24,1992.
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t INDEX ADMINISTRATIVE CONTROLS j
SECTION EAGI Review.....................................................
6-10 Audits.....................................................
6-11 l
Authority..................................................
6-12 l
t Records....................................................
6-12 l
l 6.5.3 TECHNICAL REVIEW AND CONTROL i
Activities.................................................
6-12 1
Records....................................................
6-13 6.6 REPORTABLE EVENT ACTION......................................
6-14 r
6.7 SAFETY LIMIT VIOLATION.......................................
6-14
)
6.8 PROCEDURES AND PROGRAMS......................................
6-14
. i 6.9 REPORTING REOUIREMENTS t
6.9.1 ROUTINE REPORTS l.:
Startup Report.............................................
6-15c An n u al Repo r t..............................................
6-16
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Annual Radiological Environmental Operating Report.........
6-17.
[4rusual Sc i nnu:' Radioactive Effluent Release Report.............
6 j r
Monthly Operating Report...................................
6-19 s
Radi al Peaki ng Factor Limi t Report.........................
6 f Annual Diesel Generator Reliability Data Report.............
6-19 l
Annual Reactor Coolant System Specific Activity Report..... -
6-20
-j ll Annual Sealed Source Leakage Report........................
6-20 6
6.9.2 SPECIAL REPORTS...........................................
6-20
[
i 6.10 RECORD RETENTION............................................-
6-20 l
t 6.11 RADIATION PROTECTION PROGRAM................................
6-21a
-6.12 HIGH RADIATION AREA.........................................
6-22 i
v f
FARLEY-UNIT-1 XIX AMEN 0 MENT N0.
DEFINITIONS l
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.
l OFFSITE DOSE CALCULATION MANUAL (ODCM) i 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 i
liquid effluent monitoring alarm / trip setpoints, and in the conduct of the Radiological Environmental Monitoring Program. The ODCM shall also 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 kinnu:J Radioactive Effluent l
Release Reports required by Technical Specification
.9.1.6, 6.9.1.7, 6.9.1.8 and 6.9.1.9.
l Anmal OPERABLE - OPERABILITY 1.18 A system, subsystem, train, component or device shall be OPERABLE or have OPEPABILITY when it is capable of performing 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 i
their related support function (s).
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FARLEY-UNIT 1 1-4 AMENDMENT NO.
ADMINISTRATIVE CONTROLS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 4
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 i
Environmental Monitoring Program for the reporting period. The material provided shall be consistent with the objectives outlined in (1) the ODCM and (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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CakChdar pP i
ANHRAL SEMIT'P"Jf1 RADI0 ACTIVE EFFLUENT RELEASE REPORT before W y1 Annual 6.9.1.8 and 6.9.1.9 The Semiennuel-Radioactive Efflue Rele se Report 3 er eparetica coverire ths operation of the unit during the previous C men'5bf each year.
i shall be submitted within 0^ deye efter Jenuery I end Juij 1 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.B.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 common 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.
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l-FARLEY-UNIT 1 6-17 AMENDMENT NO.
F i
ADMINISTRATIVE CONTROLS 6.13 PROCESS CONTROL PROGRAM (PCPI 6.13.1 The PCP shall be approved by the Comission prior to implementation.
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 6.10.2.0.
This documentation shall contain:
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 conformance of the solidified waste product to existing requirements of Federal, State, or other applicable regulations.
2.
Shall become effective after review and acceptance by the PORC and the approval of the General Manager - Nuclear Plant.
6.14 0FFSITE DOSE CALCULATION MANUAL f0DCMI 6.14.1 The 00CM shall be approved by the Comission prior to implementation.
6.14.2 Licensee initiated changes to the ODCH:
1.
Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.2.o.
This documentation shall contain:
a.
Sufficient information to support the change together with the y
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 20.1302, 40 CFR Part 190, 10 CFR 50.36a, and Appendix 1 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 approval of the General Manager - Nuclear Plant.
Ql 3.
Shall be submitted to the Commission in the 3rm of a complete,flegible copy of the entire ODCM as a part of or cnncta rent with the Seektmuet Radioactive Effluent Release Report for the period of the report in which any change to the ODCM 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 implemented.
FARLEY-UNIT 1 6-23 AMENDMENT NO.
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f INDEX a
ADMINISTRATIVE CONTROLS i
l SECTION P. AGE Review.....................................................
6-10 l
Audits.....................................................
6-11 l
l Authority..................................................
6-12 Records....................................................
6-12 i
6.5.3 TECHNICAL REVIEW AND CONTROL t
Activities.................................................
6-12 l
1 Records....................................................
6-13 i;
I 6.6 REPORTABLE EVENT ACTION......................................
6-14 i
6.7 SAFETY LIMIT VIOLATION.........................................
6-14 6.8 PROCEDURES AND PROGRAMS......................................
6-14 I
i 6.9 REPORTING REOUIREMENTS i
l 6.9.1 ROUTINE REPORTS l
t Startup Report.............................................
6-15a An n u al Re p o r t..............................................
6-16
{
i Annual Radiological Environmental Operating Report.........
6-17 Annual Radioactive Effluent Release Report.................
6-17
}
Monthly Operating Report...................................
6-19 l
Radi al Peaki ng Factor Limi t Report.........................
6-19 i
Annual Diesel Generator Reliability Data Report............
6 t t
Annual Reactor Coolant System Specific Activity Report.....
6,
Annual Seal ed Source Leakage Report........................
6-20 6.9.2 SPECIAL REPORTS............................................
6 6.10 RECORD RETENTION............................................
6-20 3
t 6.11 RADIATION PR'TECTION PROGRAM................................
6-21a i
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6.12 HIGH RADIATION AREA.........................................
6-22 l
'FARLEY-UNIT-1.
XIX-AMENDMENT NO.
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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 l
and the Process Control Program.
l l
OFFSITF 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 alarm / trip setpoints, and in the conduct of the Radiological Environmental Monitoring Program. The ODCM shall also 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 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 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 AMENDMENT NO.
4 ADMINISTRATIVE CONTROLS 1
ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT
'1 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 (2) Sections IV.B.2, IV.B.3, and IV.C of Appendix I to 10 CFR Part 50. A l
single submittal may be made for a multiple unit station.
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ANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT i
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 j
i 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 i
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.B.1 of Appendix ! to 10 CFR Part 50. A single submittal may be made for a multiple unit station. The submittal should combine those sections that are common 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.
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FARLEY-UNIT 1 6-17 AMENDMENT NO.
l
i ADMINISTRATIVE CONTROLS i
6.13 PROCESS CONTROL PROGRAM (PCP) i 6.13.1 The PCP shall be approved by the Comission prior to implementation.
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 f
contain:
a.
Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change (s) and
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b.
A determination that the change will maintain the overall I
conformance of the solidified waste product to existing requirements of Federal, State, or other applicable regulations.
2.
Shall become effective after review and acceptance by the PORC and the approval of the General Manager - Nuclear Plant.
j 6.14 0FFSITE DOSE CALCULATION MANUAL (0DCM) 6.14.1 The ODCM shall be approved by the Comission prior to implementation.
}
6.14.2 Licensee initiated changes to the ODCH:
i 1.
Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.2.o.
This documentation shall contain:
j i
a.
Sufficient information to support the change together with the i
appropriate analyses or evaluations justifying the change (s) and l
b.
A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.106, 40 CFR Part-190, 10 CFR 50.36a, and Appendix I to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.
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2.
Shall become effective after review and acceptance by the PORC and the t
approval of the General Manager - Nuclear Plant.
3.
Shall be submitted to the Commission in the form of a complete, legible
}
copy of the entire ODCM as a part.of or concurrent with the Annual Radioactive Effluent Release Report for the period of the report in which any change to the ODCM was made.
Each change shall be identified
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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.,
i month / year) the change was implemented.
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i FARLEY-UNIT 1 6-23 AMENDMENT NO.
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INDEX ADMINISTRATIVE CONTROLS SECTION PA_GE Review.....................................................
6-10 Audits.....................................................
6-11 Authority..................................................
6-12 Records....................................................
6-12 6.5.3 TECHNICAL REVIEW AND CONTROL Activities.................................................
6-12 Records....................................................
5-13 i
6.6 REPORTABLE EVENT ACTION......................................
6-14 6.7 SAFETY LIMIT VIOLATION.......................................
6-14 6.8 PROCEDURES AND PROGRAMS......................................
6-14 6.9 REPORTING REOUIREMENTS 6.9.1 ROUTINE REPORTS Startup Report.............................................
6-15c An n u al R e p o r t..............................................
6-16 Annual Radiological Environmental Operating Report.........
6-17 Annual Semi unuel Radioactive Effluent Release Report.............
6-17 Monthl y Operati ng Repo rt...................................
6-19
.7adial Peaking Factor Limi t Report.........................
6-19 Annual Diesel Generator Reliability Data Report............
6-19 Annual Reactor Coolant System Specific Activity Report.....
6-20 Annual Seal ed Source Leakage Report........................
6-20 6.9.2 SPECIAL REPORTS............................................
6-20 l
6.10 RECORD RETENTION............................................
6-20 6.11 RADIATION PROTECTION PROGRAM................................
6-21a 6.12 HIGH RADIATION AREA.........................................
6-22 FARLEY-UNIT 2 XIX AMENDMENT NO.
1 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.
f 0FFSITE 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 alarm / trip setpoints, and in the conduct of the Radiological Environmental Monitoring Program. The ODCM shall also 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 bs included in the Annual Radiological Environmental Surveillance and Scaiannual Radioactive Effluent Release Reports required by Technical Specifications E.9.1.6, 6.9.1.7, 6.9.1.8 and 6.9.1.9.
Annual 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 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 2 1-4 AMENDMENT NO.
ADMINISTRATIVE CONTROLS ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 6.9.1.5 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 Environmental Monitoring Program for the reporting period. The material provided shall be consistent with the objectives outlined in (1) the ODCM and (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.
calmdar )4af NEAL SEN A'? UAL RADI0 ACTIVE EFFLUENT RELEASE REPORT Nott by1 Annual
/
6.9.1.8 and 6.9.1.9 The S;minna;l Radioactive Efflue t ReleJse Report covering the operation of the unit during the previous 5 acatt of si,tretian d
shall be submitted within 00 dejs eits Jennerj 1 end July i 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.B.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 common 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.
FARLEY-UNIT 2 6-17 AMENDMENT NO.
I ADMINISTRATIVE CONTROLS 4
6.13 PROCESS CONTROL PROGRAM fPCP)
{
6.13.1 The PCP shall be approved by the Commission prior to implementation.
}
6.13.2 Licensee initiated changes to the PCP:
1.
Shall be documented and records of reviews performed shall be retained f
as required by Specification 6.10.2.o.
This documentation shall contain:
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 conformance of the solidified waste product to existing requirements of Federal, State, or other applicable regulations.
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 CALCUtATION MANUAL (ODCM)
I 6.14.1 The ODCM shall be approved by the Commission prior to implementation.
l I
6.14.2 Licensee initiated changes to the ODCM:
[
1.
Shall be documented and records of reviews performed shall be retained l
as required by Specification 6.10.2.o.
This documentation shall contain:
f a.
Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change (s) and I
b.
A determination that the change will maintain the level of radioactive effluent control required by 10 CFR 20.1302, 40 CFR Part i
190, 10 CFR 50.36a, and Appendix I.to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.
~
i 2.
Shall become effective after review and acceptance by the PORC and the approval of the General Manager - Nuclear Plant.
}
3.
Shall be submitted to the Commission in the form of a complete,4 legible i
copy of the entire ODCM as a part of or concurrent with the k;iennual l
Radioactive Effluent Release Report for the period of the report in l
which any change to the ODCM was made.
Each change shall be identified by markings in the margin of the affected pages, clearly indicating the i
area of the page that was changed, and shall indicate the date (e.g.,
r month / year) the change was implemented.
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FARLEY-UNIT 2 6-23 AMENDMENT NO.
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INDEX ADMINISTRATIVE CONTROLS SECTION ELE Review.....................................................
6-10 Audits.....................................................
6-11 Authority..................................................
6-12 Records...................................................
6-12 6.S.3 TECHNICAL REVIEW AND CONTROL Activities.................................................
6-12 Records....................................................
6-13 i
5 6 REPORTABLE EVENT ACTION......................................
6-14 6.7 SAFETY LIMIT VIOLATION.......................................
6-14 6.8 PROCEDURES AND PROGRAMS......................................
6-14 6.9 REPORTING RE0VIREMENTS 6.9.1 ROUTINE REPORTS Startup Report.............................................
6-15a An n u a l R e p o r t..............................................
6-16 Annual Radiological Environmental Operating Report.........
6-17 Annual Radioactive Ef fluent Release Report.................
6-17 Morthly Operating Report...................................
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 Seal 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.........................................
6-22 FARLEY-UNIT 2 XIX AMENDMENT NO.
i i
DEFINITIONS LIOUID RADWAETE TREATMENT SYSTEM 1.15 This definition deleted. Refer to the Offsite Dose Calculation Manual.
4 MAJOR CHANGES TO RADIDACTIVE WASTE TREATMENT SYSTEMS 1.16.This definition deleted. Refer to the Offsite Dose Calculation Manual and the Process Control Program.
h 0FFSITE 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 alarm / trip setpoints, and in the conduct of the Radiological Environmental Monitoring Program. The ODCM shall also 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 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 l.18 A system, subsystem, train, component or device shall be OPERABLE or have OPEP. ABILITY when it is capable of performing 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 2 1-4 AMENDMENT NO.
ADMINISTRATIVE CONTROLS 4
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 1 of each year. The report shall include summaries, interpretations, and analysis of trends of the results of the Radiological i
Environmental Monitoring Program for the reporting period. The material provided shall be consistent with the objectives outlined in (1) the ODCM and (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.
I i
d 1
t ANNUAL RADI0 ACTIVE EFFLUENT RELEASE REPORT i
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 1
submitted beforc May 1 of each year. The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste l
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.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
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.
I i
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a FARLEY-UNIT 2 6-17 AMENDMENT NO.
I l
s ADMINISTRATIVE CONTROLS j
6.13 PROCESS CONTROL PROGRAM (PCP) 4 6.13.1 The PCP shall be approved by the Commission prior to implementation.
l 6.13.2 Licensee initiated changes to the PCP:
1.
Shall be documented and records of reviews performed shall be retained l
as required by Specification 6.10.2.0.
This documentation shall l
1 contain:
l a.
Sufficient information to support the change together with the l
appropriate analyses or evaluations justifying the change (s) and l
b.
A determination that the change will maintain the overall conformance of the solidified waste product to existing requirements l
of Federal, State, or other applicable regulations.
I 2.
Shall become effective after review and acceptance by the PORC and the l
approval of the General Manager - Nuclear Plant.
j 6.14 0FFSITE DOSE CALCULATION MANUAL (00CM) 4 6.14.1 The ODCM shall be approved by the Commission prior to implementation.
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6.14.2 Licensee initiated changes to the ODCM:
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Shall be documented and records of reviews performed shall be retained as required by Specification 6.10.2.o.
This documentation shall j
contain:
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a.
Sufficient information to support the change together with the appropriate analyses or evaluations justifying the change (s) and 4
b.
A determination that the change will maintain the level' of
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radioactive effluent control required by 10 CFR 20.106 40 CFR Part i
190, 10 CFR 50.36a, and Appendix 1 to 10 CFR Part 50 and not adversely impact the accuracy or reliability of effluent, dose, or setpoint calculations.
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2.
Shall become effective after review and acceptance 5y the PORC and the j
approval of the General Manager - Nuclear Plant.
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Shall be submitted to the Commission in the form of a complete, legible l
copy of the entire ODCM as a part of or concurrent with the Annual Radioactive Effluent Release Report for the period of the report in which any change to the ODCM was made.
Each change shall be identified by markings in the margin of the affected pages, clearly indicating the i
area of the page that was changed, and shall indicate the date (e.g.,
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month / year) the change was implemented.
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FARLEY-UNIT 2 6-23 AMENDMENT NO.
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l Joseph M. Farley Nuclear Plant Units 1 and 2 Technical Specification Changes Associated With Semiannual Radioactive Emuent Release Report j
t Safety Assessment Proposed Change 1 l
Revise proposed Farley Unit I and Unit 2 Technical Specification 1.17 submitted by
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Southern Nuclear Operating Company Letter dated June 23,1992, in response to Generic Letter 89-01, in order to change the frequency of submittal of the Semiannual Radioactive Emuent Release Report to an annual basis.
Safety Assessment I
Proposed Farley Unit I and Unit 2 Technical Specification 1.17 submitted by Southern b'uclear Operating Company letter dated June 23,1992, revised the definition of the Offsite Dose Calculation Manual in accordance with the requirements of Generic Letter 89-01. Contained in that definition was a reference to the Semiannual Radioactive Efiluent Release Report. Therefore, it is proposed that the definition be revised to change
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the reference to the Annual Radioactive EfIluent Release Report in order to implement the l
new 10 CFR 50.36a reponing requirements.
i This proposed change is administrative in nature in order to reduce an unnecessary burden of governmental regulation. This change will in no way will reduce the protection for the public health and safety.
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Proposed Change 2 i
Revise proposed Farley Unit I and Unit 2 Technical Specifications 6.9.1.8 and 6.9.1.9 and its index reference, submitted by Southern Nuclear Operating Company Letter dated l
June 23,1992, in response to Generic Letter 89-01, in order to change the frequency of submittal of the Semiannual Radioactive EfIluent Release Report to an annual basis. Also t
proposed is a change to the submittal date of the report from within 60 days after January 1 and July 1 of each year, to, prior to May 1 of each year.
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Safety Assessment l
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Proposed Technical Specifications 6.9.1.8 and 6.9.1.9 submitted by Southern Nuclear
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Operating Company letter dated June 23,1992, contained the Generic Letter 89-01 requirement for submitting a Semiannual Radioactive EfIluent Release Report within 60 days after January 1 and July 1 of each year. In accordance with the requirements of 9
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Safety Assessment i
Page 2 i
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l the new 10 CFR 50.36a, Southern Nuclear Operating Company proposes to change the l
frequency of submittal of the report to an annual basis thereby becoming the Annual i
Radioactive Emuent Release Repon. The corresponding index reference to the Semiannual Radioactive Emuent Release Repor1 has also been revised.
l Although a schedule for submi*tal of an annual repon is not stipulated in the new l
10 CFR 50.36a, it is proposca that the schedule be revised such that the repon is submitted prior to May I of each year. This change would then be consistent with the prior to May I reponing requirement for the Annual Radiological Emironmental Operating Repon which is currently contained in Farley Unit I and Unit 2 Technical j
Specification 6.9.1.6, and proposed Farley Unit I and Unit 2 Technical Specifications 6.9.1.6 and 6.9.1.7 submitted in Southern Nuclear Operating Company's response to Generic Letter 89-01 dated June 23,1997 i
Farley Unit I and Unit 2 Technical Specifications 6.9.1.8 and 6.9.1.9 also require that the
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quantity of radioactive solid wastes released be reported in the Semiannual Radioactive i
Emuent Release Report. However, the reponing requirement associated with solid i
e wastes is not addressed in either the old or new 10 CFR 50.36a. Therefore, to be consistent with the proposed reponing requirements for liquid and gaseous emuents it is proposed that the quantity of solid waste releases also be reported on an annual basis.
These proposed changes are administrative in nature in order to reduce an unnecessary burden of governmental regulation. This change will in no way will reduce the protection.
l for the public health and safety.
l Proposed Change 3 l
Revise proposed Farley Unit I and Unit 2 Technical Specification 6.14.2 submitted by
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Southern Nuclear Operating Company Letter dated June 23,1992, in response to Generic
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Letter 89-01, and later revised by SNC letter dated August 24,1992 regarding l
implementation of the new 10 CFR 20 requirements in order to change the frequency of
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submittal of the Semiannual Radioactive Emuent Release Report to an annual basis.
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Safety Assessment Proposed Farley Unit I and Unit 2 Technical Specification 6.14.2 submitted by Southern l
Nuclear Operating Company letters dated June 23 and August 24,1992, revised the
-l Administrative Controls Section requirements for the Offsite Dose Calculation Manual in accordance with the requirements _of Generic Letter 89-01 and the requirements of the i
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Safety Assessment Page 3 new 10 CFR 20, respectively. Contained in the proposed technical specification was a reference to the Semiannual Radioactive Efiluent Release Repon. Therefore, it is again proposed that the Administrative Controls Section requirements be revised to change the reference to the Annual Radioactive Effluent Release Repon in order to implement the new 10 CFR 50.36a reponing requirements..
This proposed change is administrative in nature in order to reduce an unnecessary burden of governmental regulation. This change will in no way will reduce the protection for the public health and safety.
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1 Pursuant to 10 CFR 50.92 i
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Joseph M. Farley Nuclear Plan: Units 1 and 2 l
Technical Specification Changes Associated With Semiannual Radioactive Emuent Release Repon i
10 CFR 50.92 Evaluation Proposed Changes f
The proposed changes to the Farley Unit I and 2 Technical Specifications are required to implement the new 10 CFR 50.36a reponing requirement related to the quantity of radioactive emuents released from nuclear power reactors. Currently, such reporting for j
Farley is made on a semiannual basis in the Semiannual Radioactive Emuent Release Report. The new 10 CFR 50.36a extends the reponing cycle to an annual basis.
Backcround j
On August 31,1992, the Nuclear Regulatory Commission (NRC) placed a notice in the Federal Register (57 FR 39353) regarding several amendments to their regulations.
Specifically,10 CFR 50.36a was one of the regulations revised whereby the frequency of l
reponing the quantity of each of the principal radionuclides released to unrestri:ted areas in liquid and in gaseous emuents was changed from semiannual to annual. Such action j
was taken by the NRC in response to a Presidential memorandum requesting that selected Federal agencies review and modify regulations that would eliminate any unnecessary burden of governmental regulation and insure that the regulated community is not subject 4
to duplicative or inconsistent regulation.
The reponing of the quantity of emuent releases is currently performed at Farley on a se.iannual basis in accordance with the Semiannual Radioactive Emuent Release Report l
requirement contained in the Farley Unit 1 and Unit 2 Technical Specifications. That reporting requirement continued to be maintained in Southern Nuclear Operating
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Company's (SNC's) response to Generic Letter 89-01 dated June 23,1992 and in SNC's submittal dated August 24,1992 regarding implementation of the new 10 CFR 20 l
requirements. Therefore,in accordance with 57 FR 39353, SNC proposes to satisfy the new 10 CFR 50.36a reporting requirement in an Annual Radioactive Emuent Release Report which will replace the current semiannual report.
The Farley Unit I and Unit 2 Technical Specifications also require that the quantity of radioactive solid wastes released be reported in the Semiannual Radioactive Emuent Release Report. Although the reponing requirement associated with solid wastes is not
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addressed in either the old or new 10 CFR 50.36a, SNC believes that the intent of the i
Presidential memorandum would be to allow for a change to the reporting requirement for l
solid wastes, similar to that being provided for liquid and gaseous emuents in order to more effectively reduce the burden of governmental regulation.
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10 CFR 50.92 Evaluation f
Pace 2 I
Analysis f
t The proposed changes to the technical specifications will allow for the implementation of the new 10 CFR 50.36a reporting requirement and fulfill the spirit of the Presidential memorandum. The proposed changes are administrative in nature and will not reduce the level of radiological control at Farley. Compliance with applicable regulatory requirements governing radioactive efiluents, radiological environmental monitoring, and solid wastes, including 10 CFR 20, Appendix 1 to 10 CFR 50,10 CFR 61,10 CFR 71, and 40 CFR 190, will continue to be maintained.
SNC has reviewed the requirements of 10 CFR 50.92 as they relate to the proposed l
changes and has made the following determination:
l 1.
The proposed changes do not involve a significant increase in the probability or consequences of an accident previously evaluated. The proposed changes are j
administrative in nature and do not involve any change to the configuration or i
method of operation of any plant equipment that is used to mitigate the consequences of an accident. Also, the proposed changes do not alter the coaditions or assumptions in any of the Final Safety Analysis Report (FSAR) accident analyses.
Since the FSAR_ accident analyses remain bounding, the radiological consequences previously evaluated are not adversely affected by the proposed changes. Therefore, it can be concluded that the proposed changes do not involve a significant increase in the probability or consequences of an accident previously evaluated.
2.
The proposed changes do not create the possibility of a new or different kind of accident from any accident previously evaluated. The proposed changes are administrative in nature and do not involve any change to the configuration or j
method of operation of any plant equipment that is used to mitigate the consequences l
l of an accident. Accordingly, no new failure modes have been defined for any plant system or component important to safety nor has any new limiting failure been
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identified as a result of the proposed changes. Also, there will be no change in the j
types or increase in the amount ofefiluents released offsite. Therefore,it can be f
concluded that the proposed changes do not create the possibility of a new or
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different kind of accident from any accident previously evaluated.
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3.
The proposed changes do not involve a significant reduction in a margin of safety.
I The proposed changes are administrative in nature and do not adversely impact the plant's ability to meet applicable regulatory requirements related to liquid and gaseous effluents, and solid waste releases. The proposed changes would also r
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4 10 CFR 50.92 Evaluation Page 3 eliminate an unnecessary burden of governmental regulation without reducing protection for public health and safety. Therefore,it can be concluded that the proposed changes do not involve a significant reduction in a margin of safety.
Conclusion Based on the preceding analysis, SNC has determined that the proposed changes to the
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technical specifications will not significantly increase the probability or consequences of an accident previously evaluated, create the possibility of a new or different kind of accident from any accident previously evaluated, or involve a significant reduction in a margin of safety. Therefore, SNC has determined that the proposed changes meet the requirements of 10 CFR 50.92(c) and do not involve a significant bazards consideration.
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,u-Joseph M. Farley Nuclear Plant Units 1 and 2 Technical Specification Changes Associated With j
Semiannual Radioactive Efiluent Release Report j
Emironmental Evaluation Southe n Nuclear Operating Company has determined that the proposed changes to the i
Farley Unit 1 and Unit 2 Technical Specifications are administrative in nature and will facilitate implementation of the new 10 CFR 50.36a requirements and fulfill the spirit of the Presidential memorandum. The proposed changes do not adversely affect plant safety since the probability of any accident is not affected nor is there any effect on the consequences of any accident No changes are being made in the types or amounts of any radiological or non radiological efIluents that may be released offsite. The proposed I
changes do not involve any other environmental impacts. No increase in individual or -
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cumulative occupational radiation exposure will result from these proposed changes.
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Additionally, these changes do not involve the use of any resources not previously considered in the Final Emironmental Statement related to the operation of Farley Nuclear Plant. Therefore, it can be concluded that the proposed changes to the technical I
specifications will not have a significant effect on the quality of the emironment.
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