ML19317H259: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
 
(Created page by program invented by StriderTol)
 
Line 18: Line 18:
=Text=
=Text=
{{#Wiki_filter:.  .  . - _ .  . _ _ _ _ _ _ - _ _ _ _ _ _ _ _ .      _. _ _ _ _ _ _ _ _ _ _ .
{{#Wiki_filter:.  .  . - _ .  . _ _ _ _ _ _ - _ _ _ _ _ _ _ _ .      _. _ _ _ _ _ _ _ _ _ _ .
  ..
8005050 ATTACfDIENT II Proposed Technical Specification F
    ,    ,
        .
            *
      .
8005050 ATTACfDIENT II Proposed Technical Specification
                                                                                                                            .
                                                                                                                              %
F
                                                                                                                          -
>
                                                                                             /r -
                                                                                             /r -
i
i
!


                                                                                        .
TABLE OF CONTENTS SECTION                    TITLE                          PAGE 1.-      DEFINITIONS                                          1 1.1        RATED POWER                                        1 1.2        REACTOR OPERATING CONDITIONS                        1
  -                                                            __
.          .
            .
    . . . ..
              *
* TABLE OF CONTENTS SECTION                    TITLE                          PAGE 1.-      DEFINITIONS                                          1 1.1        RATED POWER                                        1 1.2        REACTOR OPERATING CONDITIONS                        1
                 '1.3        OPERABLE                                          2 1.4        PROTECTION INSTRQWENTATION LOGIC                  2 1.5        INSTRUMENTATION SURVEILLANCE                      3 1.6        QUADRANT POWER TILT                                4 1.7        REACTOR BUILDING                                  4
                 '1.3        OPERABLE                                          2 1.4        PROTECTION INSTRQWENTATION LOGIC                  2 1.5        INSTRUMENTATION SURVEILLANCE                      3 1.6        QUADRANT POWER TILT                                4 1.7        REACTOR BUILDING                                  4
: 2.      SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS    7 2.1        SAFETY LIMITS, REACTOR CORE                        7 2.2        SAFETY LIMITS, REACTOR SYSTEM PRESSURE            10 2.3        LIMITING SAFETY SYSTEM SETTINGS, PROTECTIVE INSTRUMENTATION                                  11
: 2.      SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS    7 2.1        SAFETY LIMITS, REACTOR CORE                        7 2.2        SAFETY LIMITS, REACTOR SYSTEM PRESSURE            10 2.3        LIMITING SAFETY SYSTEM SETTINGS, PROTECTIVE INSTRUMENTATION                                  11
: 3.      LIMITING CONDITIONS FOR OPERATION                  16 3.1        REACTOR COOLANT SYSTEM                            16 3.1.1        Operational Components                        16 3.1.2        Pressurization, Heatup and Cooldown
: 3.      LIMITING CONDITIONS FOR OPERATION                  16 3.1        REACTOR COOLANT SYSTEM                            16 3.1.1        Operational Components                        16 3.1.2        Pressurization, Heatup and Cooldown
                                -
: 8. imitations                              18 3.1.3        Minimuc Conditions for Criticality            21 3.1.4        Reactor Coolant System Acitivity              22 3.1. 5 -      Chemistry                                      25 3.1.6          Leakage                                      27 3.1.7        Moderator Temperature Coefficient of                      ,
: 8. imitations                              18 3.1.3        Minimuc Conditions for Criticality            21 3.1.4        Reactor Coolant System Acitivity              22 3.1. 5 -      Chemistry                                      25 3.1.6          Leakage                                      27 3.1.7        Moderator Temperature Coefficient of                      ,
Reactivity                                30 3.1. 8 -      Low Power Physics Testing Restrictions        31 3.1.9        Control Rod Operation-                        32 3.2        B0 RATION                                        34  l 3.3        EMERGENCY CORE COOLING REACTOR BUILDING COOLING, 10 AND REACTOR BUILDING SPRAY SYSTEMS                36 3.4        STEAM AND POWER CONVERSION SYSTEM                40 3.5        INSTRUMENTyriON SYSTEMS                          42 3.5.1        Operatioral Safety Instrumentation            42          -
Reactivity                                30 3.1. 8 -      Low Power Physics Testing Restrictions        31 3.1.9        Control Rod Operation-                        32 3.2        B0 RATION                                        34  l 3.3        EMERGENCY CORE COOLING REACTOR BUILDING COOLING, 10 AND REACTOR BUILDING SPRAY SYSTEMS                36 3.4        STEAM AND POWER CONVERSION SYSTEM                40 3.5        INSTRUMENTyriON SYSTEMS                          42 3.5.1        Operatioral Safety Instrumentation            42          -
Line 49: Line 31:
3.6        REACTOR BUILDING                                  54 3.7        AUXILIARY ELECTRICAL SYSTEM                      56
3.6        REACTOR BUILDING                                  54 3.7        AUXILIARY ELECTRICAL SYSTEM                      56
                 .3.8        FUEL LOADING AND REFUELING                        58 3.9        CONTROL ROOM EMERGENCY AIR CONDITIONING SYSTEM    60  l 10 3.10      SECONDARY SYSTEM ACTIVITY                        66 3.11      EMERGENCY COOLING POND-                          66a 3.12      MISCELLANE0US RADI0 ACTIVE MATERIALS SOURCES      66b 3.13      PENETRATION ROOM VENTILATION SYSTEM              66c 3.14'      HYDROGEN PURGE SYSTEM                            66e  10 3.15      FUEL HANDLING AREA VENTILATION SYSTEM            66g i                                          l
                 .3.8        FUEL LOADING AND REFUELING                        58 3.9        CONTROL ROOM EMERGENCY AIR CONDITIONING SYSTEM    60  l 10 3.10      SECONDARY SYSTEM ACTIVITY                        66 3.11      EMERGENCY COOLING POND-                          66a 3.12      MISCELLANE0US RADI0 ACTIVE MATERIALS SOURCES      66b 3.13      PENETRATION ROOM VENTILATION SYSTEM              66c 3.14'      HYDROGEN PURGE SYSTEM                            66e  10 3.15      FUEL HANDLING AREA VENTILATION SYSTEM            66g i                                          l
                                                    .


        .,
3.2 BORATION Applicability A ,. lies to the operational status of those systems which are capable of providing boration to the reactor coolant system.
  ...    .
            ,
          .
      ..
                  .
3.2 BORATION
                                                                              .
Applicability A ,. lies to the operational status of those systems which are capable of providing boration to the reactor coolant system.
Objective To provide for adequate boration under all operating conditions to assure ability to bring the reactor to a' cold shutdown condition.
Objective To provide for adequate boration under all operating conditions to assure ability to bring the reactor to a' cold shutdown condition.
Specification 3.2.1      The reactor shall not be heated or maintained above 200 F unless the fol1_: wing conditions are met:
Specification 3.2.1      The reactor shall not be heated or maintained above 200 F unless the fol1_: wing conditions are met:
Line 70: Line 43:
3.2.1.3    The boric acid addition tank and associated piping, valves and both pumps may be out of service for a maximum of 24 hours.
3.2.1.3    The boric acid addition tank and associated piping, valves and both pumps may be out of service for a maximum of 24 hours.
After the 24 hour period, if the system is not returned to service and operable, the reactor shall be brought te the hot shutdown condition within an additional 12 hours.
After the 24 hour period, if the system is not returned to service and operable, the reactor shall be brought te the hot shutdown condition within an additional 12 hours.
                                                                                                  .
Bases The makeup system and chemical addition system provide control of the reactor coolant system boron concentration.(1) This is normally accom-plished by using any of the three makeup pumps in series with a boric acid pump associated with the boric acid addition tank. The alternate method of boration will be the use of the makeup pump or DHR p;mp taking      l suction directly from the borated water storage tank. (2) C                    -
Bases The makeup system and chemical addition system provide control of the reactor coolant system boron concentration.(1) This is normally accom-plished by using any of the three makeup pumps in series with a boric acid pump associated with the boric acid addition tank. The alternate method of boration will be the use of the makeup pump or DHR p;mp taking      l suction directly from the borated water storage tank. (2) C                    -
The quantity of boric acid in storage from either of the two above mentioned sources is sufficient to borate the' reactor coolant system to a 1% subcritical margin in the cold condition at the worst time in core life with a-stuck control rod' assembly.
The quantity of boric acid in storage from either of the two above mentioned sources is sufficient to borate the' reactor coolant system to a 1% subcritical margin in the cold condition at the worst time in core life with a-stuck control rod' assembly.
i l
i l
                                                                                         --}}
                                                                                         --}}

Latest revision as of 07:38, 1 February 2020

Proposed Tech Specs Change Re Reactor Vessel Overpressurization
ML19317H259
Person / Time
Site: Arkansas Nuclear Entergy icon.png
Issue date: 12/03/1976
From:
ARKANSAS POWER & LIGHT CO.
To:
Shared Package
ML19317H256 List:
References
NUDOCS 8005050445
Download: ML19317H259 (3)


Text

. . . - _ . . _ _ _ _ _ _ - _ _ _ _ _ _ _ _ . _. _ _ _ _ _ _ _ _ _ _ .

8005050 ATTACfDIENT II Proposed Technical Specification F

/r -

i

TABLE OF CONTENTS SECTION TITLE PAGE 1.- DEFINITIONS 1 1.1 RATED POWER 1 1.2 REACTOR OPERATING CONDITIONS 1

'1.3 OPERABLE 2 1.4 PROTECTION INSTRQWENTATION LOGIC 2 1.5 INSTRUMENTATION SURVEILLANCE 3 1.6 QUADRANT POWER TILT 4 1.7 REACTOR BUILDING 4

2. SAFETY LIMITS AND LIMITING SAFETY SYSTEM SETTINGS 7 2.1 SAFETY LIMITS, REACTOR CORE 7 2.2 SAFETY LIMITS, REACTOR SYSTEM PRESSURE 10 2.3 LIMITING SAFETY SYSTEM SETTINGS, PROTECTIVE INSTRUMENTATION 11
3. LIMITING CONDITIONS FOR OPERATION 16 3.1 REACTOR COOLANT SYSTEM 16 3.1.1 Operational Components 16 3.1.2 Pressurization, Heatup and Cooldown
8. imitations 18 3.1.3 Minimuc Conditions for Criticality 21 3.1.4 Reactor Coolant System Acitivity 22 3.1. 5 - Chemistry 25 3.1.6 Leakage 27 3.1.7 Moderator Temperature Coefficient of ,

Reactivity 30 3.1. 8 - Low Power Physics Testing Restrictions 31 3.1.9 Control Rod Operation- 32 3.2 B0 RATION 34 l 3.3 EMERGENCY CORE COOLING REACTOR BUILDING COOLING, 10 AND REACTOR BUILDING SPRAY SYSTEMS 36 3.4 STEAM AND POWER CONVERSION SYSTEM 40 3.5 INSTRUMENTyriON SYSTEMS 42 3.5.1 Operatioral Safety Instrumentation 42 -

3.5.2 . Control Rod Group and Power Distribution Limits 46 3.5.3 Safety Features Actuation System Setpoints 49 3.5.4 In-Core Instrumentation 51 .

3.6 REACTOR BUILDING 54 3.7 AUXILIARY ELECTRICAL SYSTEM 56

.3.8 FUEL LOADING AND REFUELING 58 3.9 CONTROL ROOM EMERGENCY AIR CONDITIONING SYSTEM 60 l 10 3.10 SECONDARY SYSTEM ACTIVITY 66 3.11 EMERGENCY COOLING POND- 66a 3.12 MISCELLANE0US RADI0 ACTIVE MATERIALS SOURCES 66b 3.13 PENETRATION ROOM VENTILATION SYSTEM 66c 3.14' HYDROGEN PURGE SYSTEM 66e 10 3.15 FUEL HANDLING AREA VENTILATION SYSTEM 66g i l

3.2 BORATION Applicability A ,. lies to the operational status of those systems which are capable of providing boration to the reactor coolant system.

Objective To provide for adequate boration under all operating conditions to assure ability to bring the reactor to a' cold shutdown condition.

Specification 3.2.1 The reactor shall not be heated or maintained above 200 F unless the fol1_: wing conditions are met:

I 3.2.1.2 One makeup pump and one Decay Heat Removal pump are operable.

3.2.1.2 A source of concentrated boric acid solution in addition to that is the borated water storage tank is available and operable.

This requirement is fulfilled by the boric acid addition tank.

This tank shall contain at least the equivalent of 47 inches (550ft ) of 8700 ppm boron as boric acid solution with a temper-ature of at least 10 F above the crystallization temperature.

System piping and valves necessary to establish a flow path from the tank t- the makeup system shall also be operable and .

shall have at 1 cast the same temperature as the boric acid addi-tion tank. One associated boric acid pump is operable.

3.2.1.3 The boric acid addition tank and associated piping, valves and both pumps may be out of service for a maximum of 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

After the 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period, if the system is not returned to service and operable, the reactor shall be brought te the hot shutdown condition within an additional 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

Bases The makeup system and chemical addition system provide control of the reactor coolant system boron concentration.(1) This is normally accom-plished by using any of the three makeup pumps in series with a boric acid pump associated with the boric acid addition tank. The alternate method of boration will be the use of the makeup pump or DHR p;mp taking l suction directly from the borated water storage tank. (2) C -

The quantity of boric acid in storage from either of the two above mentioned sources is sufficient to borate the' reactor coolant system to a 1% subcritical margin in the cold condition at the worst time in core life with a-stuck control rod' assembly.

i l

--