ML20108A628
| ML20108A628 | |
| Person / Time | |
|---|---|
| Site: | Mcguire |
| Issue date: | 04/29/1996 |
| From: | DUKE POWER CO. |
| To: | |
| Shared Package | |
| ML20108A620 | List: |
| References | |
| NUDOCS 9605020334 | |
| Download: ML20108A628 (2) | |
Text
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9 REACTOR COOLANT SYSTEM BASES OPERATIONAL LEAKAGE (continued) l The CONTROLLED LEAKAGE limitation restricts operation when the total flow supplied to the reactor coolant pump seals exceeds 40 gpm with the modulating valve in the supply line fully open at a nominal RCS pressure of 2235 psig.
This limitation ensures that in the event of a LOCA, the* Safety Injection flow will not be less than assumed in the accident analyses.
The total steam generator tube leakage limit of 0.27 gpm for all steam generators and the 135 g)d leakage limit per generator ensures that the dosage contribution from the tu)e leakage will be limited to the applicable fraction of 10 CFR Part 100 dose guideline values for all FSAR Chapter 15 transients.
The 0.27 gpm and the 135 gpd limits are consistent with the ass,umptions used in the analysis of these accidents.
The 135 gpd leakage limit per steam generator ensures that steam generator tube integrity is maintained in the event of a main steam line rupture or under LOCA conditions.
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PRESSURE BOUNDARY LEAKAGE of any magnitude is unacceptable since it may be indicative of an impending gross failure of the pressure boundary. There-fore, the presence of any PRESSURE BOUNDARY LEAKAGE requires the unit to be promptly placed in COLD SHUTDOWN.
l 3/4.4.7 CHEMISTRY The limitations on Reactor Coolant System chemistry ensure that corrosion of the Reactor Coolant System is minimized and reduces the potential for Reac-tor Coolant System leakage or failure'due to stress corrosion. Maintaining the chemistry within the Steady State Limits provides adequate corrosion protection to ensure the structural integrity of the Reactor Coolant System over the life i
of the plant. The associated effects of exceeding the oxygen, chloride, and fluoride limits are time and temperature dependent. Corrosion studies show that operation may be continued with contaminant concentration levels in excess of the Steady State Limits, up to the Transient Limits, for the specified limited I
t'ime intervals without having a significant effect on the structural integrity of the Reactor Coolant System.
The time interval permitting continued opera-tion within the restrictions of the Transient Limits provides time for taking corrective actions to restore the contaminant concentrations to within the Steady State Limits.
l l
The Surveillance Requirements provide adequate assurance that concentra-i tions in excess of the limits will be detected in sufficient time to take corrective ACTION.
3/4.4.8 SPECIFIC ACTIVITY
}
The limitations on the specific activity of the reactor coolant ensure i
that the resulting 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> doses at the site boundary will not exceed an appro-priately small fraction of Part 100 dose guideline values following a steam j
generator tube rupture accident in cc,njunction with an assumed steady state i
primary-to-secondary steam generator leakage rate of 0.27 gpm.
The values for j
l the limits on specific activity represent limits based upon a parametric 4
McGUIRE - UNIT 2 B 3/4 4-5 9605020334 960429 i.
PDR ADOCK 05000370 i
P PDR
a DESIGN TEATURES M,[
FUEL ASSEMBLIES Continued) to comply with all fuel safety design bases. A limited number of lead test assemblies that have not completed representative testing may be placed in non-limiting core regions.
CONTROL R0D ASSEMBLIES 5.3.2 The core shall contain 53 full-length and no part-length control rod assemblies. The full-length control rod assemblies shall contain a nominal 142 inches of absorber material. The nominal values of absorber material for Unit 2 control rods shall be 100% boron carbide (B C) for 102 inches and 80%
4 silver, 15% indium, and 5% cadmium for the 40-inch tip. All control rods shall be clad with stainless steel tubing.
5.4 REACTOR COOLANT SYSTEM OESIGN PRESSURE AND TEMPERATURE i
5.4.1 The Reactor Coolant System is designed and shall be maintained:
I a.
In accordance with the Code requirements specified in Section 5.2 of the FSAR, with allowance for normal degradation pursuant to the applicable Surveillance Requirements, b.
For a pressure of 2485 psig, and l
c.
For a temperature of 650 F, except for the pressurizer which is 680'F.
VOLUME
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l 5.4.2 The total water and steam volume of the Reactor Coolant System is 13,050 i 100 cubic feet at a nominal T of 525*F.
ag 5.5 METEOROLOGICAL TOWER LOCATION 5.5.1 The meteorological tower shall be located as shown on Figure 5.1-1.
5.6 FUEL STORAGE CRITICALITY 5.6.1 a.
The spent fuel storage racks are designed and shall be maintained with:
I 1) k ff 5 0.95 if fully flooded with unborated water as d,escribed in Section 9.1 of the FSAR; and l
2)
A nominal 10.4" center to center distance between fuel assemblies placed in Region 1; and s
3)
A nominal 9.125" center to center distance between fuel assemblies placed in Region 2.
i McGUIRE - UNIT 2 5-7 Amendment No.
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