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e ATTACHMENT II DUKE POWER COMPANY McGUIRE NUCLEAR STATION PROPOSED CHANGES TO TECHNICAL SPECIFICATIONS SUPPLEMENT 2 9306170207 930604 | e ATTACHMENT II DUKE POWER COMPANY McGUIRE NUCLEAR STATION PROPOSED CHANGES TO TECHNICAL SPECIFICATIONS SUPPLEMENT 2 9306170207 930604 DR ADOCK 0500 9 | ||
b ANachmen+ E | b ANachmen+ E 67plemen + L INDEX ADMINISTRATIVE CONTROLS SECTION PAGE 1 | ||
67plemen + L INDEX ADMINISTRATIVE CONTROLS SECTION | 6.5.2 NUCLEAR SAFETY REVIEW BOARD (NSRB) 4 Function................................................... | ||
6-9 i | |||
4 Function................................................... | i Organization.............................................. | ||
Organization.............................................. | 6-10' l | ||
Review.................................................... | l Review.................................................... | ||
Audits.................................................... | 6-11 Audits.................................................... | ||
7 | 6-11 Authority................................................. | ||
: 6. 7 SAFETY LIMIT VIOLATION.......................................... | 6-12 Records................................................... | ||
6-13, I | |||
6.9 REPORTING RE0UIREMENTS | 6.6 REPORTABLE EVENT ACTI0N........................................ | ||
6.9.1 ROUTINE-REP 0RTS.............................................. | 6-13 7 | ||
Startup Report....... | : 6. 7 SAFETY LIMIT VIOLATION.......................................... | ||
Annual Reports............................. | 6-13 e | ||
6.8 PROCEDURES AND PR0 GRAMS....................................... | |||
femiennual Radioactive Effluent Release Report. . . . . . . . . . . , | 6-14 i | ||
6-18 | 1 6.9 REPORTING RE0UIREMENTS 6.9.1 ROUTINE-REP 0RTS.............................................. | ||
Monthly Operating Reports.................................. | 6-16b l | ||
Core Operating Limits Report.............................. | Startup Report....... | ||
{5 l | 6-16~ | ||
t McGUIRE - UNITS 1 and 2 | Annual Reports............................. | ||
6-17 i | |||
Annual Radiological Environmental Operating Report........ | |||
6 l 4 | |||
femiennual Radioactive Effluent Release Report..........., | |||
6-18 t | |||
i Monthly Operating Reports.................................. | |||
6-20 Core Operating Limits Report.............................. | |||
6-21 | |||
{ | |||
5 l | |||
t McGUIRE - UNITS 1 and 2 XXII | |||
. Amendment No.14f(Unit 1) 1 Amendment No. JOr-(Unit 2) i | |||
/]hhmea + 1T l | |||
~ | |||
~ | |||
&pk<sz | |||
' DEFINITIONS l | |||
and liquid effluents, in the calculation of gaseous and liquid effluent monitor- | 0FFSITE DOSE CALCULATION MANUAL (ODCM) e 1.18 The OFFSITE DOSE CALCULATION MANUAL shall contain the methodology and l | ||
Controls and Radiological Environmental Monitoring Programs required by Sec- | parameters used in the calculation of offsite doses due to racioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitor-l ing Alarm / Trip Setpoints, and in the. conduct of the Environmental Radiological l | ||
tion 6.8.4 and (2) descriptions of the information that should be included | Monitoring Program. The ODCM shall also contain (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs required by Sec-I tion 6.8.4 and (2) descriptions of the information that should be included in the Annual Radiological Environmental Operating and4eaifnnual Radioactive Effluent Release Reports required by FSAR Chapter 16. | ||
in the Annual Radiological Environmental Operating and4eaifnnual Radioactive Effluent Release Reports required by FSAR Chapter 16. | t OPERABLE - OPERABILITY | ||
t OPERABLE - OPERABILITY | ] | ||
1.19 A system, subsystem, train, component or device shall be OPERABLE or j | |||
1.19 A system, subsystem, train, component or device shall be OPERABLE or | have OPERABILITY when it is capable of performing its specified function (s), | ||
) | ( | ||
c7oling or seal water, lubrication or other auxiliary equipment that are | ) | ||
and when all necessary attendant instrumentation, controls, electrical power, c7oling or seal water, lubrication or other auxiliary equipment that are i | |||
required for the system, subsystem, train, component, or device to perform its function (s) are also capable of performing their related support functicn(s). | |||
'_ ERATIONAL MODE - MODE 1.20 An CPERATIONAL MODE (i.e., MODE) shall correspond to any one inclusive combination of core reactivity condition, power level, and average reactor coolant temperature specified in Table 1.2. | |||
PHYSICS TESTS | a PHYSICS TESTS i | ||
nuclear characteristics of the core and related instrumentation: (1) describec | 1.21 PHYSICS TESTS shall be those tests performed to measure the fundamental nuclear characteristics of the core and related instrumentation: | ||
in Chapter 14.0 of the FSAP, (2) authorized under the provisicns of~10 CFR | (1) describec in Chapter 14.0 of the FSAP, (2) authorized under the provisicns of~10 CFR j | ||
50.59, or (3) otherwise apprcved by the Commission, j | |||
PROCESS CONTPOL PROGRAM (PCP) 1.23 The PROCESS-C0t.~TOL-PROGRAM (PCP) shall contain'the current formulas, sampling, analyses, test,-and determinations to be made to ensure that process-~ | PRESSURE BOUNDARY LEAKAGE f | ||
of actual or simulated wet solid wastes will be-accomplished in such a way-as | 1.22 PRESSURE BOUNDARY LEAKAGE shall be leakage (except steam generator tube l | ||
to assure compliance with 10 CFR Parts 20, 61, and 71, State regulations, burial | leakage) through a nonisolable fault in a Reactor. Coolant System component body, pipe wall, or vessel wall. | ||
ground requirements, ar.d other requirements governing the disposal of solid radioactive waste. | } | ||
PROCESS CONTPOL PROGRAM (PCP) 1.23 The PROCESS-C0t.~TOL-PROGRAM (PCP) shall contain'the current formulas, sampling, analyses, test,-and determinations to be made to ensure that process-~ | |||
i ing and packaging of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes will be-accomplished in such a way-as to assure compliance with 10 CFR Parts 20, 61, and 71, State regulations, burial ground requirements, ar.d other requirements governing the disposal of solid radioactive waste. | |||
j. | j. | ||
McGUIRE - UNITS 1 and 2 | McGUIRE - UNITS 1 and 2 1-4 Amendment No.TT9, (Unit 1) | ||
Amendment No. g (Unit 2) | |||
-1 | |||
llflnl1menf 8 Setppin n m f L | llflnl1menf 8 Setppin n m f L l | ||
f ADMINISTRATIVE CONTROLS I | |||
i ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT | |||
* i | * i | ||
: 6. 9.1. 6 Routine Radiological Environmental Operating Reports covering the operation of the unit during the previous calendar year shall be submitted | : 6. 9.1. 6 Routine Radiological Environmental Operating Reports covering the operation of the unit during the previous calendar year shall be submitted i | ||
tions, and analysis of trends of the results of the ram ological Environmental | prior to May 1 of each year. | ||
Monitoring Program for the reporting period. The material provided shall be | The report shall include summaries, interpreta-tions, and analysis of trends of the results of the ram ological Environmental Monitoring Program for the reporting period. | ||
The material provided shall be l | |||
consistent with the objectives outlined in (1) the ODCM and (2) Sections l | |||
IV.B.2, IV.B.3, and IV.C of Appendix I to 10 CFR Part 50. | |||
i i | i i | ||
{ | { | ||
4 t | 4 t | ||
4 | 4 | ||
-5Ef4EANNUAL RADI0 ACTIVE EFFLUENT RELEASE fPORT*** calc.ulu ga < | |||
i The Semiannual Radioactive Effluep (t Release Report covering the} | |||
p | |||
MW t NM \ o b cc ch egg e, | : 6. 9.1. 7 | ||
A single submittal may be made for a multiple unit station. | _j operation of the unit during the previousv6-month 5 Of ugeration shall be sub-i mitted,within_5G day +-af ter-January +and-July L44-eachyou. | ||
l' A single submittal may be made for a multiple unit station. _The submittal | -l MW t NM \\ o b cc ch egg e, A | ||
should combine those sections that are common to all units at-the station; | A single submittal may be made for a multiple unit station. | ||
however, for units with separate Radwaste Systems, the submittal shall-specify the releases of radioactive material from each unit. | l' 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. | ||
McGUIRE - UNITS 1 and 2 | McGUIRE - UNITS 1 and 2 18 Amendment No. JJS-(Unit 1) | ||
Amendment. No. W-(Unit 2) | Amendment. No. W-(Unit 2) l | ||
-}} | |||
Latest revision as of 12:16, 19 December 2024
| ML20045B339 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire |
| Issue date: | 06/04/1993 |
| From: | DUKE POWER CO. |
| To: | |
| Shared Package | |
| ML20045B332 | List: |
| References | |
| NUDOCS 9306170207 | |
| Download: ML20045B339 (4) | |
Text
y i
l I
e ATTACHMENT II DUKE POWER COMPANY McGUIRE NUCLEAR STATION PROPOSED CHANGES TO TECHNICAL SPECIFICATIONS SUPPLEMENT 2 9306170207 930604 DR ADOCK 0500 9
b ANachmen+ E 67plemen + L INDEX ADMINISTRATIVE CONTROLS SECTION PAGE 1
6.5.2 NUCLEAR SAFETY REVIEW BOARD (NSRB) 4 Function...................................................
6-9 i
i Organization..............................................
6-10' l
l Review....................................................
6-11 Audits....................................................
6-11 Authority.................................................
6-12 Records...................................................
6-13, I
6.6 REPORTABLE EVENT ACTI0N........................................
6-13 7
- 6. 7 SAFETY LIMIT VIOLATION..........................................
6-13 e
6.8 PROCEDURES AND PR0 GRAMS.......................................
6-14 i
1 6.9 REPORTING RE0UIREMENTS 6.9.1 ROUTINE-REP 0RTS..............................................
6-16b l
Startup Report.......
6-16~
Annual Reports.............................
6-17 i
Annual Radiological Environmental Operating Report........
6 l 4
femiennual Radioactive Effluent Release Report...........,
6-18 t
i Monthly Operating Reports..................................
6-20 Core Operating Limits Report..............................
6-21
{
5 l
t McGUIRE - UNITS 1 and 2 XXII
. Amendment No.14f(Unit 1) 1 Amendment No. JOr-(Unit 2) i
/]hhmea + 1T l
~
~
&pk<sz
' DEFINITIONS l
0FFSITE DOSE CALCULATION MANUAL (ODCM) e 1.18 The OFFSITE DOSE CALCULATION MANUAL shall contain the methodology and l
parameters used in the calculation of offsite doses due to racioactive gaseous and liquid effluents, in the calculation of gaseous and liquid effluent monitor-l ing Alarm / Trip Setpoints, and in the. conduct of the Environmental Radiological l
Monitoring Program. The ODCM shall also contain (1) the Radioactive Effluent Controls and Radiological Environmental Monitoring Programs required by Sec-I tion 6.8.4 and (2) descriptions of the information that should be included in the Annual Radiological Environmental Operating and4eaifnnual Radioactive Effluent Release Reports required by FSAR Chapter 16.
t OPERABLE - OPERABILITY
]
1.19 A system, subsystem, train, component or device shall be OPERABLE or j
have OPERABILITY when it is capable of performing its specified function (s),
(
)
and when all necessary attendant instrumentation, controls, electrical power, c7oling or seal water, lubrication or other auxiliary equipment that are i
required for the system, subsystem, train, component, or device to perform its function (s) are also capable of performing their related support functicn(s).
'_ ERATIONAL MODE - MODE 1.20 An CPERATIONAL MODE (i.e., MODE) shall correspond to any one inclusive combination of core reactivity condition, power level, and average reactor coolant temperature specified in Table 1.2.
a PHYSICS TESTS i
1.21 PHYSICS TESTS shall be those tests performed to measure the fundamental nuclear characteristics of the core and related instrumentation:
(1) describec in Chapter 14.0 of the FSAP, (2) authorized under the provisicns of~10 CFR j
50.59, or (3) otherwise apprcved by the Commission, j
1.22 PRESSURE BOUNDARY LEAKAGE shall be leakage (except steam generator tube l
leakage) through a nonisolable fault in a Reactor. Coolant System component body, pipe wall, or vessel wall.
}
PROCESS CONTPOL PROGRAM (PCP) 1.23 The PROCESS-C0t.~TOL-PROGRAM (PCP) shall contain'the current formulas, sampling, analyses, test,-and determinations to be made to ensure that process-~
i ing and packaging of solid radioactive wastes based on demonstrated processing of actual or simulated wet solid wastes will be-accomplished in such a way-as to assure compliance with 10 CFR Parts 20, 61, and 71, State regulations, burial ground requirements, ar.d other requirements governing the disposal of solid radioactive waste.
j.
McGUIRE - UNITS 1 and 2 1-4 Amendment No.TT9, (Unit 1)
Amendment No. g (Unit 2)
-1
llflnl1menf 8 Setppin n m f L l
f ADMINISTRATIVE CONTROLS I
i ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT
- i
- 6. 9.1. 6 Routine Radiological Environmental Operating Reports covering the operation of the unit during the previous calendar year shall be submitted i
prior to May 1 of each year.
The report shall include summaries, interpreta-tions, and analysis of trends of the results of the ram ological Environmental Monitoring Program for the reporting period.
The material provided shall be l
consistent with the objectives outlined in (1) the ODCM and (2) Sections l
IV.B.2, IV.B.3, and IV.C of Appendix I to 10 CFR Part 50.
i i
{
4 t
4
-5Ef4EANNUAL RADI0 ACTIVE EFFLUENT RELEASE fPORT*** calc.ulu ga <
i The Semiannual Radioactive Effluep (t Release Report covering the}
p
- 6. 9.1. 7
_j operation of the unit during the previousv6-month 5 Of ugeration shall be sub-i mitted,within_5G day +-af ter-January +and-July L44-eachyou.
-l MW t NM \\ o b cc ch egg e, A
A single submittal may be made for a multiple unit station.
l' 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.
McGUIRE - UNITS 1 and 2 18 Amendment No. JJS-(Unit 1)
Amendment. No. W-(Unit 2) l
-