ML19254D928: Difference between revisions
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SAFETY EVALUATION FOR CHANGES TO TECHNICAL SPECIFICATION TABLE 3.3-5 | SAFETY EVALUATION FOR CHANGES TO TECHNICAL SPECIFICATION TABLE 3.3-5 | ||
==Background:== | ==Background:== | ||
bkddi Maintaining steem generator water level automatically during periods of low power operation will reduce the control room operator attention required and provide better assurance of plant availability by resucing reactor trips. The present piping and valve arrangement in the feedwater system does not provide a means of automatic steam generator level control at low reactor power levels. | |||
Bypass valves will be installed around the main feedwater control valves as part of a system modification to provide this capability. ' Closure time requirements associated with the feedwater control valves (FCV) should also be specified for the feedwater bypass valves and incorporated into the technical specifications. | |||
Maintaining steem generator water level automatically during periods of low power operation will reduce the control room operator attention required and provide better assurance of plant availability by resucing reactor trips. The present piping and valve arrangement in the feedwater system does not provide a means of automatic steam generator level control at low reactor power levels. Bypass valves will be installed around the main feedwater control valves as part of a system modification to provide this capability. ' Closure time requirements associated with the feedwater control | '*o C | ||
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6 e ., , | ^ | ||
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a. | |||
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==References:== | ==References:== | ||
(1) Technical Specification 3.3.2.1, Table 3.3-5. | (1) Technical Specification 3.3.2.1, Table 3.3-5. | ||
(2) | (2) | ||
FSAR Sections 6.2.1.3.11,10.4.7, and 15.4.2.1. | |||
Bases: | Bases: | ||
The feedwater bypass valves are ASME III, Nuclear Class 3 valves which are designed to close within 5 seconds. The closure time of s 5 seconds is consistent with the assumptions used in the accident analysis for FCV feedwater isolation in the event of a main steam line break inside contain-ment. Therefore, this closure time should be specified for the feedwater bypass valves in the technici.1 specifications. | The feedwater bypass valves are ASME III, Nuclear Class 3 valves which are designed to close within 5 seconds. | ||
The closure time of s 5 seconds is consistent with the assumptions used in the accident analysis for FCV feedwater isolation in the event of a main steam line break inside contain-ment. | |||
Therefore, this closure time should be specified for the feedwater bypass valves in the technici.1 specifications. | |||
Concl u ion: | Concl u ion: | ||
The proposed changes to Technical Specification Table 3.3-5 do not involve an unreviewed safety question as defined by 10CFR50.59. | The proposed changes to Technical Specification Table 3.3-5 do not involve an unreviewed safety question as defined by 10CFR50.59. | ||
1 | 1 | ||
#') | |||
4.' | |||
-] 3 7 910 30 03R 3 | |||
TABLE 3.3-5 (Continued) | TABLE 3.3-5 (Continued) | ||
| Line 49: | Line 56: | ||
~ | ~ | ||
pumps and RHR pumps. | pumps and RHR pumps. | ||
# Diecel generator starting and sequence loading delays not included. | |||
Of f.-lte power available. Pc onse time limit includes opening of valves to establish SI path and attainment of discharge pressure for centrifugal charging pumps. | Of f.-lte power available. | ||
Pc onse time limit includes opening of valves to establish SI path and attainment of discharge pressure for centrifugal charging pumps. | |||
## Diesel generator starting and sequence loading delays included. | |||
Response time limit includes opening of valves to establish SI path and attainment of discharge pressure for centrifugal charging pumps. | Response time limit includes opening of valves to establish SI path and attainment of discharge pressure for centrifugal charging pumps. | ||
### Verification shall include testing of all instrumentation, the | |||
~ | |||
nad hypass volves | isolation valves (MOV-3232A, 3232B, 3232C)3en+ the control valves CV-478, 488, 498)F The isolation valves must function within 30 seconds and the control valves within 5 seconds. | ||
4 nad hypass volves | |||
~ | ~ | ||
oxd %e bypass valves | oxd %e bypass valves (Fcv-479,189,199) | ||
;qa s | |||
s | |||
(. | (. | ||
C\nLEY - UNIT 1 | C\\nLEY - UNIT 1 3/4 3-30}} | ||
Latest revision as of 06:41, 4 January 2025
| ML19254D928 | |
| Person / Time | |
|---|---|
| Site: | Farley |
| Issue date: | 10/23/1979 |
| From: | ALABAMA POWER CO. |
| To: | |
| Shared Package | |
| ML19254D924 | List: |
| References | |
| NUDOCS 7910300323 | |
| Download: ML19254D928 (1) | |
Text
..
SAFETY EVALUATION FOR CHANGES TO TECHNICAL SPECIFICATION TABLE 3.3-5
Background:
bkddi Maintaining steem generator water level automatically during periods of low power operation will reduce the control room operator attention required and provide better assurance of plant availability by resucing reactor trips. The present piping and valve arrangement in the feedwater system does not provide a means of automatic steam generator level control at low reactor power levels.
Bypass valves will be installed around the main feedwater control valves as part of a system modification to provide this capability. ' Closure time requirements associated with the feedwater control valves (FCV) should also be specified for the feedwater bypass valves and incorporated into the technical specifications.
'*o C
6 e.,,
l
,[ c ho t
^
2,.
J',<
-(,, b.c c.,,,
a.
- m
'a
References:
(1) Technical Specification 3.3.2.1, Table 3.3-5.
(2)
FSAR Sections 6.2.1.3.11,10.4.7, and 15.4.2.1.
Bases:
The feedwater bypass valves are ASME III, Nuclear Class 3 valves which are designed to close within 5 seconds.
The closure time of s 5 seconds is consistent with the assumptions used in the accident analysis for FCV feedwater isolation in the event of a main steam line break inside contain-ment.
Therefore, this closure time should be specified for the feedwater bypass valves in the technici.1 specifications.
Concl u ion:
The proposed changes to Technical Specification Table 3.3-5 do not involve an unreviewed safety question as defined by 10CFR50.59.
1
- ')
4.'
-] 3 7 910 30 03R 3
TABLE 3.3-5 (Continued)
TABLE NOTATION
- Diesel generator starting and sequence loading delays included.
Response time limit includes opening of valves to establish SI path and attainment of discharge pressure for centrifugal charging
~
pumps and RHR pumps.
- Diecel generator starting and sequence loading delays not included.
Of f.-lte power available.
Pc onse time limit includes opening of valves to establish SI path and attainment of discharge pressure for centrifugal charging pumps.
- Diesel generator starting and sequence loading delays included.
Response time limit includes opening of valves to establish SI path and attainment of discharge pressure for centrifugal charging pumps.
- Verification shall include testing of all instrumentation, the
~
isolation valves (MOV-3232A, 3232B, 3232C)3en+ the control valves CV-478, 488, 498)F The isolation valves must function within 30 seconds and the control valves within 5 seconds.
4 nad hypass volves
~
oxd %e bypass valves (Fcv-479,189,199)
- qa s
(.
C\\nLEY - UNIT 1 3/4 3-30