ML20045B339: Difference between revisions

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e ATTACHMENT II DUKE POWER COMPANY McGUIRE NUCLEAR STATION PROPOSED CHANGES TO TECHNICAL SPECIFICATIONS SUPPLEMENT 2 9306170207 930604 9 DR ADOCK 0500
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                                                                             PAGE       .
6.5.2 NUCLEAR SAFETY REVIEW BOARD (NSRB) 4 Function...................................................
1 6.5.2 NUCLEAR SAFETY REVIEW BOARD (NSRB)                                                         ;
6-9 i
4 Function...................................................               6-9         i i
i Organization..............................................
Organization..............................................               6-10'       l l
6-10' l
Review....................................................               6-11       !
l Review....................................................
Audits....................................................               6-11 Authority.................................................               6-12 Records...................................................               6-13,     I 6.6 REPORTABLE EVENT ACTI0N........................................                 6-13       !
6-11 Audits....................................................
7
6-11 Authority.................................................
: 6. 7 SAFETY LIMIT VIOLATION..........................................               6-13       e 6.8 PROCEDURES AND PR0 GRAMS. ......................................                 6-14     .!
6-12 Records...................................................
i 1
6-13, I
6.9 REPORTING RE0UIREMENTS                                                                     ;
6.6 REPORTABLE EVENT ACTI0N........................................
6.9.1 ROUTINE-REP 0RTS..............................................                 6-16b l   >
6-13 7
Startup Report....... .....................................              6-16~
: 6. 7 SAFETY LIMIT VIOLATION..........................................
Annual Reports.............................           ..............      6-17       !
6-13 e
i Annual Radiological Environmental Operating Report........               6     l 4
6.8 PROCEDURES AND PR0 GRAMS.......................................
femiennual Radioactive Effluent Release Report. . . . . . . . . . . ,
6-14 i
6-18       t i
1 6.9 REPORTING RE0UIREMENTS 6.9.1 ROUTINE-REP 0RTS..............................................
Monthly Operating Reports..................................               6-20       !
6-16b l
Core Operating Limits Report..............................               6-21
Startup Report.......
{5 l
6-16~
t McGUIRE - UNITS 1 and 2                                                           .
Annual Reports.............................
XXII            . Amendment No.14f(Unit 1)         1 Amendment No. JOr-(Unit 2)       i
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
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~
                        ' DEFINITIONS                                                                             .
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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         .
' DEFINITIONS l
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       :
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-     I   :
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             j have OPERABILITY when it is capable of performing its specified function (s),         (
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
and when all necessary attendant instrumentation, controls, electrical power, c7oling or seal water, lubrication or other auxiliary equipment that are i
,                        combination of core reactivity condition, power level, and average reactor             ,
required for the system, subsystem, train, component, or device to perform its function (s) are also capable of performing their related support functicn(s).
a                        coolant temperature specified in Table 1.2.                                           :,
'_ 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                                                                           i 1.21 PHYSICS TESTS shall be those tests performed to measure the fundamental           !
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             j 50.59, or (3) otherwise apprcved by the Commission,                                   j PRESSURE BOUNDARY LEAKAGE                                                               f 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.
(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-~       i ing and packaging of solid radioactive wastes based on demonstrated processing           '
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 1
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                   1-4           Amendment No.TT9, (Unit 1)
McGUIRE - UNITS 1 and 2 1-4 Amendment No.TT9, (Unit 1)
;                                                                                Amendment No. g (Unit 2)     -1
Amendment No. g (Unit 2)
-1


llflnl1menf 8 Setppin n m f L
llflnl1menf 8 Setppin n m f L l
                    .                                                                              l ADMINISTRATIVE CONTROLS f
f ADMINISTRATIVE CONTROLS I
I                                                                                                i ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT
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           i prior to May 1 of each year. The report shall include summaries, interpreta-           ,
: 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           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.                           -
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
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-5Ef4EANNUAL RADI0 ACTIVE EFFLUENT RELEASE fPORT*** calc.ulu ga <
            -5Ef4EANNUALp RADI0 ACTIVE EFFLUENT RELEASE fPORT*** calc.ulu ga < }
i The Semiannual Radioactive Effluep (t Release Report covering the}
: 6. 9.1. 7 The Semiannual Radioactive Effluep (t Release Report covering the _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
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                   18       Amendment No. JJS-(Unit 1)
McGUIRE - UNITS 1 and 2 18 Amendment No. JJS-(Unit 1)
Amendment. No. W-(Unit 2)         l
Amendment. No. W-(Unit 2) l
      ,                      __    _--        _        -}}
-}}

Latest revision as of 12:16, 19 December 2024

Proposed TS Revising Frequency of Radiological Effluent Rept
ML20045B339
Person / Time
Site: McGuire, Mcguire  Duke Energy icon.png
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

~

~

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' 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

PRESSURE BOUNDARY LEAKAGE f

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

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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

-