ML20097A286
| ML20097A286 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 02/02/1996 |
| From: | SOUTHERN CALIFORNIA EDISON CO. |
| To: | |
| Shared Package | |
| ML20097A267 | List: |
| References | |
| NUDOCS 9602050237 | |
| Download: ML20097A286 (10) | |
Text
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RCS P/T Limits 3.4.3 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.3 RCS Pressure and Temperature (P/T) Limits LC0 3.4.3 With the reactor vessel head bolts tensioned *, the Reactor Coolant System (except the pressurizer) temperature and pressure shall be limited in accordance with the limit lines shown on Figures 3.4.3-1, 3.4.3-2, 3.4.3-3, 3.4.3-4, 3.4.3-5, and Table 3.4.3-1 during heatup, cooldown, and inservice leak and hydrostatic testing with:
a.
A maximum heatup of 60*F in any 1-hour period with RCS cold leg temperature greater than or equal to 86*F.
b.
A maximum cooldown as specified by Figure 3.4.3-3 in any 1-hour period with RCS cold leg temperature less than or equal to 160 F.
A maximum cooldown of 100*F in any 1-hour period with RCS cold leg temperature greater than 160* F.
c.
A maximum temperature change of 10 F in any 1-hour period during inservice hydrostatic and leak testing operations above the heatup and cooldown limit curves, d.
A minimum temperature of 86 F to tension reactor vessel head bolts.
With the reactor vessel head bolts detensioned, the Reactor Coolant System (except the pressurizer) temperature shall be limited to a maximum heatup or cooldown of 60 F in any 1-hour period.
- With the reactor vessel head bolts detensioned, RCS cold leg temperature may be less than 86'F.
SAN ON0FRE--UNIT 2 3.4-5 Amendment No.
11/03/95 9602050237 960202 PDR ADOCK 05000361 p
RCS P/T Limits 3.4.3 1
APPLICABILITY:
At all times.
ACTIONS i
CONDITION REQUIRED ACTION COMPLETION TIME A.
NOTE---------
A.1 Restoreparameter(s) 30 minutes Required Action A.2 to within limits.
shall be completed whenever this AND Condition is entered.
A.2 Determine RCS is 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> acceptable for Requirements of LC0 continued operation.
not met in MODE 1, 2, 3, or 4.
i B.
Required Action and B.1 Be in MODE 3.
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time of Condition A AND not met.
B.2 Be in MODE 5 with 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> RCS pressure
< 500 psia.
C.
NOTE---------
C.1 Initiate action to Immediately Required Action C.2 restore parameter (s) shall be completed to within limits.
whenever this Condition is entered.
AND C.2 Determine RCS is Prior to Requirements of LC0 acceptable for entering MODE 4 not met any time in continued operation.
other than MODE 1, 2, 3, or 4.
i SAN ON0FRE--UNIT 2 3.4-6 Amendment No.
11/03/95
RCS P/T Limits 3.4.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.4.3.1
NOTE--------------------
Only required to be performed during RCS heatup and cooldown operations and RCS inservice leak and hydrostatic testing.
Verify RCS pressure, RCS temperature, and 30 minutes RCS heatup and cooldown rates within limits specified in Figure 3.4.3-1, Figure 3.4.3-2, Figure 3.4.3-3, Figure 3.4.3-4, Figure 3.4.3-5, and Table 3.4.3-1.
SR 3.4.3.2 The reactor vessel material irradiation In accordance surveillance specimens shall be removed and with examined, to determine changes in material requirements of properties, as required by 10 CFR 50 10CFR 50 Appendix H.
The results of these Appendix H examinations shall be used to update figures 3.4.3-1 through 3.4.3-5.
Recalculate the Adjusted Reference Temperature in accordance with Regulatory Guide 1.99, Revision 2, " Radiation Embrittlement of Reactor Vessel Materials,"
May 1988.
SAN ON0FRE--UNIT 2 3.4-6a Amendment No.
11/03/95
RCS P/T Limits B 3.4.3 BASES SURVEILLANCE SR 3.4.3.2 REQUIREMENTS (continued)
This SR verifies that the reactor vessel material irradiation surveillance specimens will be removed and examined, to determine changes in material properties, as required by 10 CFR 50 Appendix H.
The results of these i
examinations will be used to update Figures 3.4.3-1 through 3.4.3-5.
Also, the Adjusted Reference Temperature will be recalculated in accordance with Regulatory Guide 1.99, Revision 2, " Radiation Embrittlenent of Reactor Vessel Materials," May 1988.
REFERENCES 1.
Deleted.
2.
3.
ASME, Boiler and Pressure Vessel Code,Section III, I
Appendix G.
4.
ASTM E185-73.
5.
6.
ASME, Boiler and Pressure Vessel Code,Section XI, Appendix E.
7.
UFSAR, Chapter 5.
1 i
i i
SAN ONOFRE--UNIT 2 B 3.4-16 Amendment No.
11/03/95
MSSVs 3.7.1 Table 3.7.1-2 (page 1 of 1)
Main Steam Safety Valves (Lift Settings)
VALVE NUMBER LIFT SETTING
- Steam Generator Steam Generator (psig)
- 1
- 2 2PSV-8401 2PSV-8410 1085**
2PSV-8402 2PSV-8411 1092 2PSV-8403 2PSV-8412 1099 2PSV-8404 2PSV-8413 1106 2PSV-8405 2PSV-8414 1113 2PSV-8406 2PSV-8415 1120 2PSV-8407 2PSV-8416 1127 2PSV-8408 2PSV-8417 1134 2PSV-8409 2PSV-8418 1140 The lift setting pressure shall correspond to ambient conditions of the valve at nominal operating temperature and pressure.
Each MSSV has an as-found tolerance of +2%/-3%.
Following testing according to LC0 5.5.2.10, MSSVs will be set within +/-1% of the specified lift setpoint.
Valves 2PSV-8401 and 2PSV-8410 have an as-found lift setting of 1085 psig with a tolerance of +1%/-3%.
SAN ON0FRE--UNIT 2 3.7-4 Amendment No.
11/03/95
. _ _ _ _ - ~
RCS P/T Limits 3.4.3 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.3 RCS Pressure and Temperature (P/T) Limits LC0 3.4.3 With the reactor vessel head bolts tensioned *, the Reactor Coolant System (except the pressurizer) temperature and pressure shall be limited in accordance with the limit lines shown on Figures 3.4.3-1, 3.4.3-2, 3.4.3-3, 3.4.3-4, 3.4.3-5, and Table 3.4.3-1 during heatup, cooldown, and inservice leak and hydrostatic testing with:
a.
A maximum heatup of 60 F in any 1-hour period with RCS cold leg temperature greater than or equal to 86*F.
b.
A maximum cooldown as specified by Figure 3.4.3-3 in any 1-hour period with RCS cold leg temperature less than or equal to 147 F.
A maximum cooldown of 100 F in any 1-hour period with RCS cold leg temperature greater than 147* F.
c.
A maximum temperature change of 10 F in any 1-hour period during inservice hydrostatic and leak testing operations above the heatup and cooldown limit cur:es.
d.
A minimum temperature of 86 F to tension reactor vessel head bolts.
With the reactor vessel head bolts detensioned, the Reactor Coolant System (except the pressurizer) temperature shall be limited to a maximum heatup or cooldown of 60*F in any 1-hour period.
- With the reactor vessel head bolts detensioned, RCS cold leg temperature may be less than 86*F.
SAN ONOFRE--UNIT 3 3.4-5 Amendment No.
11/03/95
=
RCS P/T Limits 3.4.3 i
APPLICABILITY:
At all times.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
NOTE---------
A.1 Restore parameter (s) 30 minutes Required Action A.2 to within limits.
shall be completed whenever this AND Condition is entered.
A.2 Determine RCS is 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> acceptable for Requirements of LC0 continued operation.
not met in MODE 1, 2, i
3, or 4.
B.
Required Action and B.1 Be in MODE 3.
6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time of Condition A AND not met.
B.2 Be in MODE 5 with 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> RCS pressure
< 500 psia.
C.
NOTE---------
C.1 Initiate action to Immediately Required Action C.2 restore parameter (s) shall be completed to within limits.
whenever this Condition is entered.
AND C.2 Determine RCS is Prior to Requirements of LC0 acceptable for entering MODE 4 not met any time in continued operation.
other than MODE 1, 2, 3, or 4.
SAN ON0FRE--UNIT 3 3.4-6 Amendment No.
11/03/95
RCS P/T Limits 3.4.3 SURVEILLANCE REQUIREMENTS SURVEILLANCE
. FREQUENCY SR 3.4.3.1
NOTE--------------------
Only required to be performed during RCS heatup and cooldown operations and RCS inservice leak and hydrostatic testing.
Verify RCS pressure, RCS temperature, and 30 minutes RCS heatup.and cooldown rates within limits i
specified in Figure 3.4.3-1, Figure 3.4.3-l 2, Figure 3.4.3-3, Figure 3.4.3-4, Figure 3.4.3-5, and Table 3.4.3-1.
SR 3.4.3.2 The reactor vessel material irradiation In accordance surveillance specimens shall be removed and with examined, to determine changes in material requirements of properties, as required by 10 CFR 50 10CFR 50 Appendix H.
The results of these Appendix H examinations shall be used to update Figures 3.4.3-1 through 3.4.3-5.
Recalculate the Adjusted Reference Temperature in accordance with Regulatory Guide 1.99, Revision 2, " Radiation Embrittlement of Reactor Vessel Materials,"
May 1988.
i SAN ON0FRE--UNIT 3 3.4-6a Amendment No.
11/03/95
RCS P/T Limits B 3.4.3 BASES SURVEILLANCE SR 3.4.3.2 REQUIREMENTS (continued)
This SR verifies that the reactor vessel material
)
irradiation' surveillance specimens will be removed and i
examined, to determine changes in material properties, as required by 10 CFR 50 Appendix H.
The results of these examinations will be used to update Figures 3.4.3-1 through 3.4.3-5.
Also, the Adjusted Reference Temperature will be recalculated in accordance with Regulatory Guide 1.99, Revision 2, " Radiation Embrittlement of Reactor Vessel Materials," May 1988.
REFERENCES 1.
Deleted.
2.
3.
ASME, Boiler and Pressure Vessel Code,Section III, Appendix G.
4.
ASTM E185-73.
5.
6.
ASME, Boiler and Pressure Vessel Code,Section XI, Appendix E.
7.
UFSAR, Chapter 5.
SAN ON0FRE--UNIT 3 B 3.4-16 Amendment No.
11/03/95
MSSVs 3.7.1 Table 3.7.1-2 (page 1 of 1)
Main Steam Safety Valves (Lift Settings)
VALVE NUMBER LIFT SETTING
- Steam Generator Steam Generator (psig)
- 1
'#2 3PSV-8401 3PSV-8410 1085**
3PSV-8402 3PSV-8411 1092 3PSV-8403 3PSV-8412 1099 3PSV-8404 3PSV-8413 1106 3PSV-8405 3PSV-8414 1113 3PSV-8406 3PSV-8415 1120 3PSV-8407 3PSV-8416 1127 3PSV-8408 3PSV-8417 1134 1
3PSV-8409 3PSV-8418 1140 The-lift setting pressure shall correspond to ambient conditions of the i
valve at nominal operating temperature and pressure.
Each MSSV has an as-found tolerance of +2%/-3%.
Following testing according to LC0 1
5.5.2.10, MSSVs will be set within +/-1% of the specified lift setpoint.
Valves 3PSV-8401 and 3PSV-8410 have an as-found lift setting of 1085 psig with a tolerance of +1%/-3%.
i SAN ON0FRE--UNIT 3 3.7-4 Amendment No.
11/03/95
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