ML20238E003
| ML20238E003 | |
| Person / Time | |
|---|---|
| Site: | Fort Calhoun  |
| Issue date: | 12/29/1987 |
| From: | OMAHA PUBLIC POWER DISTRICT |
| To: | |
| Shared Package | |
| ML20238D981 | List: |
| References | |
| NUDOCS 8801040576 | |
| Download: ML20238E003 (5) | |
Text
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2.0 LIMITING CONDITIONS FOR OPERATION J
2.1 Reactor Coolant System (Continued) y; 2.1.2
-Heatup and Cooldown Rate (Continued) s (a) The curve in Figure 2-3 shall be used to predict the 3
3 increase in transition temperature based on integrated fast neutron flux.
If measurements on the irradiation specimens indicate a deviation from this curve, a new curve shall be constructed.
j (b) The limit line on the figures shall be updated for a new integrated power period as follows:
the total integrated I
reactor thennal power from startup to the end of the new l
period shall be converted to'an equivalent integrated fast neutron exposure (E>l MeV).
For this plant, based upon l
surveillance materials tests, weld chemical composition crM l
data, and the effect of a reduced vessel fluence rate l
I providedbycoreloaddesignsbeginningdthgnactorvessel pel Cycle _8.,1 the predicted surface. fluence at the e itial beltline weld material for 40 years at 1500 MWt and an 80%
load factor is 2.9x1019 n/cm.
The flux reduction applied 2
to the fluence calculations was based on a Cycle 1-9 average azimuthal flux distribution plot generated using DOT 4.3.
The predicted transition temperature shift to the end of the new period shali. hen be obtained from Figure 2-3.
(c) The limit lines in Figures 2-1A and 2-1B shall be moved parallel to the. temperature axis (horizontal) in the direction of increasing temperature a distance equivalent to the transition temperature shift during the period since the curves were last constructed.
The boltup temperature limit line shall remain at '82*F as it is set by the NDTT of the reactor vessel flange and not subject to fast neutron fl ux. The lowest servict temperature shall remain at 182 F l
because components related to this temperature are also not subject to fast neutron flux.
(d) The Technical Specification 2,.3(3) shall be revised each time the curves of Figures 2-14 and 2 1B are revised.
4,
All components in the reactor coolant system are designed to withstand and pressure changes.(1 pads due to reactor ecclant system temperature the effects of cyclic
,e l>
These cyclic loads a m introduced by normal unit load transients, reactor trips and startup and shutdown operation.
. Dur;ing unit startup and shutdown, the rates of temperature and pressure
~
changes are limited. The design number of cycles for heatup and cool-down is based upon a rate of 100*F in any one hour period and for cyclic f
s! operation.
2-4 Amendment No. 22,47,64,74.77,100
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!$O 00h 5
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' 2. 0 LIMITING CONDITIONS FOR OPERATION (Continued) )
2.1 Reactor Coolant System (Continued 2.1.2 Heatuo and Cooldown Rate 1500 MWt and 80% load factor. The predicted shift at this location at the 1/4t depth from the inner surface is 332*F, including margin, and was calculated using the shift prediction equation of the proposed Regulatory Guide 1.99, Revision 2.
The actual shift in TNOT will be re-established periodically during the plant operation by testing of reactor vessel material samples which are irradiated cumulatively by securing them near the inside wall of the reactor vessel as described in Section 4.5.3 and Figure 4.5-1 of the USAR. To compensate for any increase in the TNDT caused by irradiation, limits on the pressure-temperature relationship are periodically changed to stay within the stress limits during heatup surveiAancq specimen (8)of the second removed irradiated reactor vess and cooldown.
Analysis pggts
, combined with weld chemical composition data and reduced 4 core loading designs initiated in Cycle 8, indicates that the fluence at the end of 15.0 Effective Full power Years (EFPY) at 1500 MWt will be 1.4x10 9 n/cm2 on the inside surface of the reactor 1
vessel. This results in a total shift of the RTNDT of 285 F, including margin, for the area of greatest sensitivity (weld metal) at the 1/4t location as determined from Figure 2-3.
Operation through fuel Cycle.16 will result in less than 15.0 EFpY.
The limit lines in Figures 2-1 A and 2-1B are based on the following:
A.
Heatup and Cooldown Curves - From Section III of the ASME Code, Appendix G-2215.
KIR = 2 KIM + XIT KIR = Alicwance stress intensity factor at temperatures related to RTNDT (ASME III Figure G-2110.l).
Stress intensity factor for membrane stress (pressure).
Kgg = The 2 rcpresents a safety facter of 2 on pressure.
l IT = Stress ir, tensity factor radial thermal gradient.
K 1hc above ecuation is applied tc the reactor vessel beltline.
For plant heatup the thermal str u s is opposite in sign frem the pressure stress eno consideration of a heatup rate would allow for a higher pressure. For. heatup it is therefore conservative to I
consider an 130 thermal heatup or KIT = 0.
For piant cooldown thermal and pressure stress are additive.
l 2-6 Amendment No. 22,f 7,M,7f,77,100
2.0 LIMITING CONDITIONS FOR OPERATION
- 2. 4 Containment Cooling (Continued) component cooling heat exchangers and shutdown heat exchangers.
A full-capacity diesel generator:is connected to each of the two engineered safeguards 4.16-kV buses.
Three engineered safeguards 480-Volt double-ended load centers are provided; of the six transformers, three are connected to each of the two 4.16-kV buses.
Two load centers are operated as two-bus-section units; the third is provided with a center bus manually. transferable to either associated end section. The center bus section supplies HPSI Pump SI-2C, CS Pump SI-3C and Charging Pump CH-1C any of which can thus be supplied from either 4.16-kV bus if required.
Three component cooling heat exch p egs_hava_ sufficient 402 to remove 4M-x 10 BTU /hr following a l
capacity (....
...g...mg) The containment sprays initially take loss-of-coolant accident.
coolantfromthesafetyinjectionandrefuelingwater(SIRW)tg.
Before this supply of water is exhausted (at least 24 minutes) the spray system is transferred to the recirculation mode and the pumps i
take suction from the containment sump.
One shutdcwn cooling heat ex-I changer is sufficient to satisfy the spra[33ystem requirements during the long-term containment cooling period In addition, in the un-likely event of the component cooling water supply being lost, raw water can be utilized for diregcooling of the shutdown heat exchangers and containment cooling coils.
The containment spray system is redundant with the containment air cooling function.gng and iodine removal system for the containment recirculation, co The spray system is sized such that two of the three spray pumps would limit the containment pressure to below the design value following a DBA without taking credit for g air coolers or the cooling creacity of the safety injection system.
Similarly, two cooling and filteHng units or one cooling and filtering unit and both cooling units have the capability of limiting thegntainment pressure under the same conditions as two spray pumps, Yhe redundant cooling equipment provided to limit the containment
}
pressure following a DEA is divided between i.he independen'. power i
supply systems.
The raw water and component cooling water pumps are
$imilarly distributed on the 4.16-kV and 480 Volt buses to serve the above ccoling groups.
Each cooling group has a design capacity ec,ual to that required to restrict the containment pressure to below the design values In the event of a DBA, loss of normal power sources and failure of one diesel generator to operate, better than one full z
group would be connected to the available diesel generator, thus i
providing more than ample reserve.
Any one unit removed from a given j
I bus does not restrict the groups which can be connected to one diesel-I generator from fulfilling their design function. The removal of two units from buses which can be connected to one diesel generator could limit the capability of the associated cooling groups; therefore, to ensure availability of the power supply to the redundant equipment in the event of loss of normal power sources, the diesel generator serving this redundant equipment is in standby condition.
During l
Amendment No.111 2-26 i
__ __ _____ A
l TABLE 2-10(Continued) i Post-Accident Monitoring Instrumentation Operating Limits beith (c) With channels inoperable, restore at least one channel to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> or be in at least HOT SHUTDOWN within the next l
12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
(d) With the number of OPERABLE channels less than required by the minimum channels operable requirements, operation may. continue until the next cold shutdown, at which time the required channel (s) shall be made 1
j
- operable, 1
(e) With the number of OPERABLE channels one less than the minimum channels operable requirement, either 1.
restore the inoperable channel (s) to OPERABLE status within 7 days, or 2.
initiate an alternate means of monitoring the subcooled margin, or 3.
be in at least HOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
(f) With both channels inoperable, 1.
restore the inoperable channel (s) to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br />, or 2.
initiate an alternate means of monitoring the subcooled margin, or 3.
be in at least HOT. SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
(g) Mith the number of OPERABLE channels one less than the minimum channels operable requiremer.t. either restora the inoperable channel to OPERABLE status within 7 days, or be in at least MOT SHUTDOWN within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.
(h) With both channels inoperable, either restore the inoperable enannel(s) to OPERABLE status within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> or be irs at least HOT SHUTDOWN within the next 12 hourt.
(1) With the number of OPERABLE Core Exit Thervoccuples lars than the four required by NUREG-0737, either restore to at least four OPERABLE channels within seven days of discovery of loss of operability, or p epare and submit a special report to the Comission pursuant to Specification 5.9.3 within 30 days, outlining the actions taken, the cause of the inoperability and the plans for restoring the inoperable channel to OPERABLE status.
(j) A channel is eight sensors in a probe. A channel is OPERABLE if four or more sensors, two or more in the upper four and two or more in the lower four, are OPERABLE.
2-98a Amendment No.110
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