ML20037D657
| ML20037D657 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 08/19/1981 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20037D654 | List: |
| References | |
| NUDOCS 8108280050 | |
| Download: ML20037D657 (4) | |
Text
.y REACTOR COOLANT SYSTEM BASES The actual shift in RT of the vessel material will be established periodically during operati by removing and evaluating, in accordance with ASTM E185-73, reactor vessel material irradiation surveillance speci-mens installed near the inside wall of the reactor vessel in the core a rea.
Since the neutron spectra at the irradiation samples and vessel inside radius are essentially identical, the measured transition shift fnr a sample can ce applied with confidence to the adjacent section of the reacter vessel.
The heatup and cooldewn curves must be recalculated when the ART from the cal b determined from the surveillance capsule is different iated ART for the equivalent capsule radiation exposure.
NDT The pressure-temperature limit lines shown on Figure 3.4-2 for reactor criticality and for inservice leak and hydrostatic testing have.
been provided to assure compliance with the minimum temperature require-ments of Appendix G to 10 CFR 50.
The maximum RT materials,withtheh.forallreactorcoolantsystempressure-retaining N xception of the reactor pressure vessel, has been determined to be 50'F.
The Lowest Service Temperature limit line shown on Fi'gure 3.4-2 is based upon this RT since Article NB-2332 (Sumer Addenda of 1972) of Section III of b ASME Boiler and Pressure Vessel Code requires the Lowest Service Temperature to be RT for piping, pumps and valves.
Belowthistemperature,theshem+100*F pressure must be limited to a maximum of 20% of the system's hydrostatic test pres'sure of 3125 psia.
The number of reactor vessel irradiation surveillance specimens and the f requencies for removing and testing these specimen; are provided in Table 4.4-5 to assure compliance with the requirements of Ap;:endix H to 10 CFR Part 50.
The limitations imposed on the pressurizer heatup and cooldown rates and spray water temperature differential are provided to assure that the pressurizer is operated within the design criteria assumed for the fati-gue analysis performed in accordance with the ASME Code requirements.
The OPERABILITY of two PORVs or an RCS vent opening of greater than 1.3 square inches ensures that the RCS will be protected from pressure transients which could exceed the limits of Appendix G to 10 CFR Part 50 when on or more of the RCS cold legs are 1 275'F.
Either PORV has adequate relieving capability to protect the RCS from overpressurization when the transient is limited to either (1) the start of an idle RCP with the secondary water temperature of the steam generator 1 6'F (34'F when 4
measured by a surface contact instrument) above the coolant temperature in the reactor vessel or (2) the start of a HPSI pump and its injection into a water solid RCS.
CALVERT CLIFFS - UNIT I B 3/4 4-11 Amendment No. 34 0108280050 810819 DR ADOCK 05000
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3/4.4.10 STRUCTURAL INTEGRITY The inspection programs for the ASt1E Code Class 1, 2 and 3 components ensure that the structural integrity of these components will be maintained at an acceptable level throughout the life of the plant. To the extent a',plicable, the inspection program for these components is in compliance with Section XI of i
the ASME Boiler and Pressure Vessel Code.
3/4.4.11 CORE BARREL MOVEMENT This specification is provided to ensure early detection of excessive core barrel movement if it should occur.
Core barrel movement will be detected by using four excore neutron detectors to obtain Amplitude Probability Distribu-tion (APD) and Spectral Analysis (SA).
Baseline core barrel movement Alert Levels and Action Levels will be confirmed ourina each reactor startup ~ ~
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' test progr'am fol' lowing a core reload. '
Data from these detectors is to be reduced in two forms.
Root mean square (RMS) values are computed from the APD of the signal amplitude.
These RMS magnitudes include variations due both to various neutronic effects and internals l
motion.
Consequently, these signals alone can only orovide a gross measure of j, core barrel motion.
A more accurate assessment of core barrel motion is obtained from the Auto and Cross Power Spectral Densities (PSD, XPSD), phase e
( ) and conerence (COH) of these signals.
These data result from the SA of j
the excore detector signals.
1 A modification to the required monitoring program may be justified by an analysis of the data obtained and by an examination of the affected parts during the plant shutdown at the end of any fuel cycle.
3/4.4.12 LETDOWN LINE EXCESS FLOW This specification is provided to ensure that the bypass valve for the excess flow check valve in the letdown line will be maintained closed during plant operation.
This bypass valve is required to be closed to ensure that the effects of a pipe rupture downstreara of this valve will not exceed the accident analyses assumptions.
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1 CALVERT CLIFFS - UNIT 1 33/44-12 Amendment No. 57
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CORE BARP.EL MOVEMENT LIMITING CONDITION FOR OPERATION 1
3.4.11 Core barrel movement shall be limited to less than the Amplitude Probability Distribution (APD) and Spectral Analysis (SA) Alert Levels for the applicable THERTiAL POWER level.
APPLICABILITY: MODE 1.
ACTION:
With the APD and/or SA exceeding their applicable Alert Levels, a.
POWER OPERATION may proceed provided the following actions are taken:
1.
APC shall be mensured and processed at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, j
2.
SA shall be measured at least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and shall be procesied at least once per 7 days, and 3.'
A Special Report, identifying the cause(s) for exceeding the applicable Alert _ Level, shall be prepared and sub-mitted to the Comm:ssion pursuant to Specification 6.9.2 within 30 days of detection.
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b.
With the APD and/or SA exceeding their applicable Action Levels, t
measure and process APD and SA data sithin 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to determine if the core barrel motion is exceed'ng its limits. With the i
core barrel motion exceeding its limits, reduce the core barrel motion to within its Action Levels within the next 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or be in HOT STANDBY within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
c.
The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.
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CALVERT CLIFFS - UNIT 1 3/4 4-29 Amendment No. 57 9 9 r
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SURVEILLANCE REQUIREMENTS 4.4.11 Routine tionitocing Core barrel movement shall be determined to be l
less than tne APD and'5A Alert Levels by using the excore neutron detectors to measure APD and SA at the fellowing frequencies:
a.
APD data shall be measured and processed at least once l
per 7 days.
b.
SA data shall be measured and processed at least once per 31 days.
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d CALVERT CL @FS - UNIT 1 3/4 4-30 Amendment No. 57
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