ML20003D497

Proposed Tech Spec 3.4.11,reducing Core Barrel Movement Monitoring & Reporting Requirements

ML20003D497
Person / Time
Site:	Calvert Cliffs
Issue date:	03/23/1981
From:	BALTIMORE GAS & ELECTRIC CO.
To:
Shared Package
ML20003D495	List: ML20003D494 ML20003D497
References
NUDOCS 8103270433
Download: ML20003D497 (3)

Text

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j REACTOR COOLANT SYSTEM CORE BARREL MOVEMENT LIMITING CONDITION FOR OPERATION 3.4.11 Core barrel movement shall be limited to less than the Amplitude P obability Distribution (APD) and Spectral Analysis (SA) Alert Levels for the applicable THERMAL POWER level.

I APPLICABILITY: MODE 1.

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ACTION:

a. With the APD and/or SA exceeding their applicable Alert Levels, POWER OPERATION may proceed provided the following actions are f takea:

1. APD shall be measured 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 />,

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 prucc. sed at least once per 7 days, and l

, 3. A Special Report, identifying the cause(s) for exceeding the applicable Alert Level, shall be prepared ant sub-

- mitted to the Comission pursuant to specification b_

6.9.2 within gdays of detection.

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b.'. ~l 4 Levels, within I hour reduce THERMAt r+WER RMAL POWER and within the next 2 ii

_ o% of RATED emonstrate, through mani 'nn n# +ho eseneo noistenn cetnee that ADn and Ra

b. With the APD and/or SA exceeding their applicable Action Levels, measure and process APD and SA data within 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 exceeding its limits. With the 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 STANDSY within the following 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.

U 11 C. The provisions of Specifications 3.0.3 and 3.0.4 are not applicable.

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SURVEILLANCE RE0"._.MENTS

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4.4.11.1 Ba rline Monitoring Core barrel movement Alert Levels and :T Z-E-Z Action Le E . as determined by APD and SA monitoring of the excore neutron detectors, shall be determined at nominal THERPAL POWER levels of g=215 25%, 50%, 75% and 100% of RATED THERMAL POWER during the reactor startup j%L test program; these Alert Levels and Action Levels shall be reported in a s1Ei:=

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Special Report pursuant to Specification 6.9.2 within 31 days af ter initially reaching 100% of RATED THERMAL POWER. W.5[5

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4.4.11.2 Routine Monitoring Core barrel movement shall be determined Z_.T to be less than the APD and SA Alert levels by usino the excore neutron ' - - -

detectors to measure APD and SA at the following frequencies-

a. APD data shall be measured at ':::: :n:: p:- 'r e : ad d =_=-2

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b. SA data shall be measured and processed at least once per %I.I2f 31 days. 5@--

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REACTOR 30LANT SYSTEM BASES 3/4.4.10 STRUCTURAL INTEGR]TY The inspection programs for the ASME Code Class 1, 2 and 3 components <

ensure that the structural integrity of these components w.ill be maintained '

at an acceptable level throughout the life of the plant. To the extent applicable, the inspection program for these components is in compliance with Section XI of the ASME Boiler and Pressure Vessel Code.

3/4.4.11 CORE BARREL MVEMENT ' ' ~ '

T: S specification is provided to ensure early detection of excessive core bari 1 movement if it should occur. Core barrel movement will be detected by using four excore neutron detectors to obtain Amplitude Probability Distribution (APD) and Spectral Analysis (SA). Baseline core barrel movement Alert Levels and Action Levels at nominal THEFRAL POWER Jevels of 250, 50%, 75% and 100% of RATED THEPXAL POWER will be deteg ined during the reactor startup test procram. ..

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A modification to the recuired 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 the first fuel cycle.

3/4.4.12 LEiD0Wi; lit:E EXCESS iLOW This specification is provided to ensure that the bypass valve for l during plantflow the excess check valve in the letdown line will be r4aintained closed operation. This bypass valve is required to be closed to ensure that the effects of a pipe ructure downstream of this valve will not exceed the accident analyses assumptions. ,{

Data from these detectors is to be reduced in the forms.

I RMS values are computed from the Amplitude Probability Density (APD) of the signal arslitude. Tnese RMS magnitudes include p variations due both to various neutronic effects and internals i i i motion. Consequently, these signals alone can only provide a gross measure of CSB motion. A more accurate assessment of

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CSB motion is obtained from the Auto and Cross Power Spectral Densities (PSD, XPSD), phase (f) and coherence (COH) of these signal s. These data result from a Spectral Analysis (SA) of i I

G the excore detector signals. l

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