ML19341A195: Difference between revisions

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o FARLEY UNIT 2 SPECIAL LOW-POWER TESTS SAFETY EVALUATION JANUARY, 1981 REVISION 2 8
o FARLEY UNIT 2 SPECIAL LOW-POWER TESTS SAFETY EVALUATION JANUARY, 1981 REVISION 2 8
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8101220 Gyy                              l l                                                \
8101220 Gyy                              l l                                                \


1
1 2.7    EFFECT OF STEAM GENERATOR SECONDARY SIDE ISOLATON                i DN NATURAL CIRCULATION (TEST 4) i l
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2.7    EFFECT OF STEAM GENERATOR SECONDARY SIDE ISOLATON                i DN NATURAL CIRCULATION (TEST 4) i l
Objective - To determine the effects of steam generator secondary side isolation on natural circulation.
Objective - To determine the effects of steam generator secondary side isolation on natural circulation.
Method - Establish natural circulation conditions as in Test 2a but at 1% power. Isolate the feedwater and steam line for one steam generator and establish equilibrium. Return the steam generators to service in reverse order.
Method - Establish natural circulation conditions as in Test 2a but at 1% power. Isolate the feedwater and steam line for one steam generator and establish equilibrium. Return the steam generators to service in reverse order.
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2.9    FORCED CIRCULATION COOLDOWN (TEST 5)
2.9    FORCED CIRCULATION COOLDOWN (TEST 5)
This test establishes the initial conditions necessary for Test 4,      .
This test establishes the initial conditions necessary for Test 4,      .
Effect of Steam Generator Secondary Side Isolation On Natural Circulation. Any evaluations, technical specification exceptions or analysis necessary to bound the consequences of this test are the same as Tes t 4. (Note: This test (5) is performed as part of test 4 above)
Effect of Steam Generator Secondary Side Isolation On Natural Circulation. Any evaluations, technical specification exceptions or analysis necessary to bound the consequences of this test are the same as Tes t 4. (Note: This test (5) is performed as part of test 4 above) 2.10 BORON MIIING AND COOLDOWN Westinghouse does not believe that it is advisable to perform this test utilizing core heat as noted in NS-TMA-2242, T. M. Anderson, Westinghouse, to H. Denton, NRC.
* 2.10 BORON MIIING AND COOLDOWN Westinghouse does not believe that it is advisable to perform this test utilizing core heat as noted in NS-TMA-2242, T. M. Anderson, Westinghouse, to H. Denton, NRC.
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TABLE 3-1 TECHNICAL SPECIFICATION IMPACT                ,
TABLE 3-1 TECHNICAL SPECIFICATION IMPACT                ,
Test Technical Specifiestion      1  2a  2b  2c  3      4 /6
Test Technical Specifiestion      1  2a  2b  2c  3      4 /6 2.1.1  Core Safety Limits              X      X  X    X    X    X      1 2.2.1  Various Reactor Trips Overtemperature AT                  X  X    X    X    X Overpower AT                        X  X    X    X    X Steam Generator Level              I  X    X    X    X 3.1.1.4 Moderator Temperature coef-                                X ficient 3.1.1.5 Minimum Temperature for                                    X Criticality 3.3.1  Various Reactor Trips Overtemperature AT                  X  X    X    X    X Overpower AT                        X  X    X    X    X Steam Generator Level              X  X    X    X    X 3.3.2  Safety Injection - All                  X  X    X    X    X  X -
                                                                          <-
automatic functions Auxiliary Feedwater Initiation                            X    X    X    X    X  X 3.4.4  Pressurizer                                I    X            X 3.7.1.2 Auxiliary Feedwater                  X              X        X 3.8.1.1 AC Power Sources                                      X        X AC Onsite Power Distribu-3.8.2.1                                                      X        X tion System 3.8.2.3 DC Distribution System                                X        X 3.10.3  Special Test Exceptions -                                  X Physics Tests 3-10 1}}
2.1.1  Core Safety Limits              X      X  X    X    X    X      1 2.2.1  Various Reactor Trips Overtemperature AT                  X  X    X    X    X Overpower AT                        X  X    X    X    X Steam Generator Level              I  X    X    X    X 3.1.1.4 Moderator Temperature coef-                                X ficient 3.1.1.5 Minimum Temperature for                                    X Criticality 3.3.1  Various Reactor Trips Overtemperature AT                  X  X    X    X    X Overpower AT                        X  X    X    X    X Steam Generator Level              X  X    X    X    X 3.3.2  Safety Injection - All                  X  X    X    X    X  X -
automatic functions Auxiliary Feedwater Initiation                            X    X    X    X    X  X 3.4.4  Pressurizer                                I    X            X 3.7.1.2 Auxiliary Feedwater                  X              X        X 3.8.1.1 AC Power Sources                                      X        X AC Onsite Power Distribu-
                                                                                    '
3.8.2.1                                                      X        X tion System 3.8.2.3 DC Distribution System                                X        X 3.10.3  Special Test Exceptions -                                  X Physics Tests 3-10 1}}

Latest revision as of 10:04, 31 January 2020

to Farley Unit 2 Special Low Power Tests,Safety Evaluation.
ML19341A195
Person / Time
Site: Farley Southern Nuclear icon.png
Issue date: 01/31/1981
From:
WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
To:
Shared Package
ML19341A194 List:
References
NUDOCS 8101220349
Download: ML19341A195 (3)
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o FARLEY UNIT 2 SPECIAL LOW-POWER TESTS SAFETY EVALUATION JANUARY, 1981 REVISION 2 8

8101220 Gyy l l \

1 2.7 EFFECT OF STEAM GENERATOR SECONDARY SIDE ISOLATON i DN NATURAL CIRCULATION (TEST 4) i l

Objective - To determine the effects of steam generator secondary side isolation on natural circulation.

Method - Establish natural circulation conditions as in Test 2a but at 1% power. Isolate the feedwater and steam line for one steam generator and establish equilibrium. Return the steam generators to service in reverse order.

2.8 ESTABLISHMENT OF NATURAL CIRCULATION FROM STAGNANT CONDITIONS Westinghouse does not believe that it is advisable to perform this test as noted in a letter from T. M. Anderson, Westinghouse, to H. Denton, NRC, NS-TMA-2242, April 29, 1980.

2.9 FORCED CIRCULATION COOLDOWN (TEST 5)

This test establishes the initial conditions necessary for Test 4, .

Effect of Steam Generator Secondary Side Isolation On Natural Circulation. Any evaluations, technical specification exceptions or analysis necessary to bound the consequences of this test are the same as Tes t 4. (Note: This test (5) is performed as part of test 4 above) 2.10 BORON MIIING AND COOLDOWN Westinghouse does not believe that it is advisable to perform this test utilizing core heat as noted in NS-TMA-2242, T. M. Anderson, Westinghouse, to H. Denton, NRC.

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TABLE 3-1 TECHNICAL SPECIFICATION IMPACT ,

Test Technical Specifiestion 1 2a 2b 2c 3 4 /6 2.1.1 Core Safety Limits X X X X X X 1 2.2.1 Various Reactor Trips Overtemperature AT X X X X X Overpower AT X X X X X Steam Generator Level I X X X X 3.1.1.4 Moderator Temperature coef- X ficient 3.1.1.5 Minimum Temperature for X Criticality 3.3.1 Various Reactor Trips Overtemperature AT X X X X X Overpower AT X X X X X Steam Generator Level X X X X X 3.3.2 Safety Injection - All X X X X X X -

automatic functions Auxiliary Feedwater Initiation X X X X X X 3.4.4 Pressurizer I X X 3.7.1.2 Auxiliary Feedwater X X X 3.8.1.1 AC Power Sources X X AC Onsite Power Distribu-3.8.2.1 X X tion System 3.8.2.3 DC Distribution System X X 3.10.3 Special Test Exceptions - X Physics Tests 3-10 1

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