ML20195G907

Proposed Tech Spec Page 3.3-8 to Correct Inadvertent Omission from 880331 Tech Spec Change Request 164

ML20195G907
Person / Time
Site:	Oyster Creek
Issue date:	11/15/1988
From:	GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML20195F512	List: ML20195F505 ML20195G907
References
NUDOCS 8811300117
Download: ML20195G907 (1)

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pH, chloride, and other chemical parameters are made to determine the cause of the unusual conductivity and instigate proper corrective action. These can be done before limiting conditions, with respect to variables affecting the boundaries of the reactor coolant, are exceeded. Several techniaues are available to correct off-standard reactor water cuality conditions including removal of 1mpurities from reactor water by the cleanup system, reducing input of impurities causing off-standard conditions by reducing power and reducing the reactor coolant temperature to less than 212*F. The major benefit of reducing the reactor coolant temperature to less than 212*F is to reduce the temperature dependent corrosion rates and thereby pro /1de time for the cleanup system to re-establish proper water quality.

Specifications 3.3.F.I and 3.3.F.2 reautre a minimum of four l OPERATING recirculation loops during reactor POWER OPERATION. Core parameters have not been established for POWER OPERATION with less than four OPERATING loops. Therefore, Specification 3.3 F.3 reauires reactor POWER OPERATION to he terminated and the reactor placed in the REFUEL MODE or SHUTOOWN CONDITION within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />.

During four loop POWER OPERATION the idle loop is reauired to have its discharge valve closed and its discharga bypass and suction valves open. This minimizes the occurrence of a severe cold water addition transient during startup of an 1dle loop. In addition, with the discharge bypass and suction valves in an idle loop open the coolant inventory in the loop 15 available during LOCA blowdown.

Specifications 3.3.F.4 and 3.3.F.6 assure that an adeouate flow path exists from the annular space, between the pressure vessel wall and the core shroud, to the core region. This provides sufficient hydraulic communication between these areas, thus assuring that reactor water level instrument readings are For the bounding indicative of the water lev 91)in the core region. loss of feedwater transientt2 , a loop transfers coolant from the annulus to the acre reg'on at approximate circulationg)fivetimestheho110ffratewithnoforced

. Nith the reactor vessel flooded to a level above 185 inches TAF or when the steam separator and dryer are removeo, the core region is in hydraulic communication with the annulus above the core region and all recirculation loops can therefore be isolated. Nhen the steam separator and dryer are removed, safety limit 2.l.0 ensures water level is maiatained above the core shroud.

References (1) FDSAR, Volume I, Section IV-2 (2) letter to NRC dated May 19, 1979, "Transient of May 2, 1979" (3) General Electric Co. Letter G-EN-9-55, "Revised Natural Circulation Flow Calculation", dated May 29, 1979 (4) Licensing Application Amendment 16, Design Reautrements Section (5) (Deleted)

(6) FDSAR, Volume I, Section IV-2.3.3 and Volune II, Appendix H (7) FDSAR, Volume I, Table IV-2-1 (8) Licensing Application Amendment 34, Question 14 OYSTER CREEK 3.3-8 Amendment No.: 42, 93 770lf 8811300117 881115 ADOCK 050 9 JDR