ML20136G486
| ML20136G486 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 03/10/1997 |
| From: | ENTERGY OPERATIONS, INC. |
| To: | |
| Shared Package | |
| ML20136G483 | List: |
| References | |
| NUDOCS 9703180056 | |
| Download: ML20136G486 (5) | |
Text
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3.1.2.7 Prior to reaching thirty ons effectiva full powar years of l
operation, Figures 3.1.2-1, 3.1.2-2 cnd 3.1.2-3 shall be updated for the next service period in accordance with 10CFR50, Appendix G.
The service period shall be of sufficient duration l
to permit the scheduled evaluation of a portion of the surveillance data scheduled in accordance with the latest revision of Topical Report BAW-1543 (5). The highest predicted adjusted reference temperature of all the beltline region materials shall be used to determine the adjusted reference temperature at the end of the service period. The basis for this prediction shall be submitted for NRC staff review in accordance with Specification 3.1.2.8.
The provisions of Specification 3.0.3 are not applicable, j
3.1.2.8 The-updated proposed technical specifications referred to in 3.1.2.7 shall be submitted for NRC review at least 90 days prior to the end of the service period.
l 3
3.1.2.9 With the exception of ASME Section XI testing and when the core flood tank is depressurized, during a plant cooldown the core flood tank discharge valves shall be closed and the circuit breakers for the motor operators opened before depressurizing the reactor coolant system below 600 psig.
3.1.2.10 With the exception of ASME Section XI testing, fill and vent of the reactor coolant system, emergency RCS makeup and to allow naintenance of the valves, when the reactor coolant temperature is less than 262*F, the High Pressure Injection motor operated l
l valves shall be closed with their opening control circuits for the motor operators disabled.
3.1.2.11 The plant shall not be operated in a water solid condition when the RCS pressure boundary is intact except as allowed by i
Emergency Operating Procedures and during System Hydrotest.
9703180056 970310 PDR ADOCK 05000313 P
PDR Amendment No. M,M,M,MB,MG, 18a M4, M1,
BASES
,All reactor coolant system components are designed to withstand the effects of cyclic loads due to system temperature and pressure changes. (1) These cyclic loads are introduced by unit load transients, reactor trips, and unit heatup and cooldown operations. The number of thermal and loading cycles used for design purposes are shown in Table 4-8 of the FSAR.
The maximum unit heatup and cooldown rates satisfy stress limits for cyclic operation. (2)
The 200 psig pressure limit for the secondary side of the steam generator at a temperature less than 100*F satisfies stress levels for temperatures below the DTT. (3)
The major components of the reactor coolant pressure boundary have been analyzed in accordance with Appendix G to 10CFR50. Results of this analysis, including the actual pressure-temperature limitations of the reactor coolant pressure boundary, are given in FTI Document 77-1258569-01 (4). The limiting weld l
material is being irradiated as part of the B&W Owners Group Integrated Reactor Vessel Material Surveillance Program and the identification and locations of the capsules containing the limiting weld material is discussed in the latest revision to B&W report, BAW-1543. (5)
The chemical composition of the limiting weld material is reported in the B&W Report, BAW-2121P (6). The effect of neutron irradiation on the RTNDT of the limiting weld material is reported in FTI Calculations 32-1245917-00 and 32-1257716-00 (7).
Figures 3.1.2-1, 3.1.2-2, and 3.1.2-3 present the pressure-temperature limit curves for hydrostatic test, normal heatup, and normal cooldown respectively.
The limit curves are applicable through the thirty first effective full power year of operation. The service period was reduced by one effective full power year from that assumed in FTI Document 77-1258569-01 to be conservative with respect to independent calculations performed by the NRC staff. The pressure limit is also adjusted for the pressure differential between the point of system pressure measurement and the limiting component for all allowed operating reacter l coolant pump combinations.
The pressure-temperature limit lines shown on Figure 3.1.2-2 for reactor criticality and on Figure 3.1.2-1 for hydrostatic testing have been provided to assure compliance with the minimum temperature requirements of Appendix G to 10CFR50 for reactor criticality and for inservice hydrostatic testing.
The actual shift in RTNDT of the beltline region material will be established
)
periodically during operation by removing and evaluating, in accordance with Appendix H to 10CFR50, reactor vessel material irradiation surveillance specimens which are installed near the inside wall of this or a similar reactor vessel in the core region.
The spray temperature difference restriction based on a stress analysis of the spray line nozzle is imposed to maintain the thermal stresses at the pressurizer spray line nozzle below the design limit. Temperature requirements for the steam generator correspond with the measured NDTT for the shell.
Amendment No. 3G,G4,M,83,464, 19
FIGURE 3.1.21 RCS INSERVICE HYDROSTATIC TEST H/U & C/D LIMITS TO 31 EFPY 2400 2200 1
l i
f 2000 i
61800 t
w 6 1600 31400 J
H ACCEPTABLE
@1200 REGION 9
< 1000 g
l D
E 800
/
Y A
y 600 f
a:
400 l
200 0
0 50 100 150 200 250 300 350 400 450 500 550 600 RCS COLD LEG TEMPERATURE (*F)
Notes:
1.
This curve is not adjusted for instrument error and shall not be used for operation.
2.
All Notes on Figure 3.1.2-2 are applicable for heatups. This curve is based on a heatup rate of < 90*F/HR.
3.
All Notes on Figure 3.1.2-3 are applicable for cooldowns.
Amendment No. G8,83,M4, 20a
FIGURE 3.1.2-2 RCS HEATUP LIMITATIONS TO 31 EFPY 2400 2200 I
2000 f
f
< 50'F/HR g 1800.
f f
Non-Critical O
^
Curve h
f
< 90*F/HR I:
Critical
$1600 Curv.
)7 H
0 l
i j 1400 H
J O
l 2 1200 7
H<
y1000 JIl 7
o 800 ACCEPTABLE m
< 70'F/HR
)
REGION Non-Critical y j
/
g curve w
g
[
400
/
-9/
\\
A t
200
< 90 F/HR Non-Critical Curve 0
i I
0 50 100 150 200 250 300 350 400 450 500 550 600 RCS COLD LEG TEMPERATURE (*F)
Notes:
1.
These curves are not adjusted for instrument error and shall not be used for operation.
2.
When DHR is in operation with no RCPs operating, the DHR system return temperature shall be used.
3.
RCP Operating Restrictions:
RCS TEMP RCP RESTRICTIONS T > 300*F None 300*F 2 T 2 225*F s3 l
225*F > T 2 84*F s2 T < 84*F No RCPs operating 4.
Allowable Heatup Rates:
RCS TEMP H/U RATE 60*F < T 5 84*F 5 15'F/HR T > 84*F As allowed by applicable curve Amendment No. GB,M,-144, 20b l
FIGURE 3.1.2-3 RCS COOLDOWN LIMITS TO 31 EFPY 2400 J
1 2200 2000 6
g1800
/
j$ 1600 4
0WJ 1400 H
k ACCEPTABLE g< 1200 f
ggazog f
$1000 D
800 4
b b@
>/
400 200 0
0 50 100 150 200 250 300 350 400 450 500 550 600 RCS COLD LEG TEMPERATURE ('F)
Notes:
- 1. This curve is not adjusted for instrument error and shall not be used for operation.
- 2. A maximum step temperature change of 25*F is allowable when securing all RCPs with the DHR system in operation. This change is defined as the RCS temperature prior to securing all the RCPs minus the DHR return temperature after the RCPs are secured. When DHR is in operation with no RCPs operating, the DHR system return temperature shall be used.
- 3. RCP Operating Restrictions:
RCS TEMP RCP RESTRICTIONS T > 255'F None 150*F s T s 255*F 52 (See Note 5)
T < 150*F No RCPs operating
- 4. Allowable Cooldown Rates:
RCS TEMP C/D RATE STEP CHANGE T 2 280*F 100*F/HR s 50*F in any 1/2 HR 280*F > T 2 150*F 50*F/HR (See Note 5) s 25*F in any 1/2 HR T < 150*F 25*F/HR s 25'F in any 1 HR
- 5. If RCPs are operated < 200*F, then the RCS cooldown rate from 150*F s T s 180*F is reduced to 30*F in 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br />.
Amendment No M,84, M4, 20c