ML20234F350

Proposed Tech Spec 3/4.4.3.2, Operational Leakage & Table 3.4.3.2-1, RCS Pressure Isolation Valves, Correcting Alarm Setpoints

ML20234F350
Person / Time
Site:	Fermi
Issue date:	01/06/1988
From:	DETROIT EDISON CO.
To:
Shared Package
ML20234F337	List: ML20234F350 NRC-88-0001, Application for Amend to License NPF-43,changing Tech Spec Table 3.4.3.2-2 & Bases 3/4.4.3.2 to Correct Alarm Setpoints for RCS Interface Valve Leakage Pressure Monitors.Processing Per 10CFR50.91 Requested.Related Info Encl.Fee Paid
References
NUDOCS 8801110438
Download: ML20234F350 (2)

Text

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REACTOR COOLANT SYSTEM BASES 3/4.4.3 REACTOR COOLANT SYSTEM LEAKAGE 3/4.4.3.1 LEAKAGE DETECTION SYSTEMS The RCS leakage detection systems required by this specification are provided to monitor and detect leakage from the reactor coolant pressure boundary. These detection' systems are consistent with the recommendations of Regulatory Guide 1.45, " Reactor Coolant Pressure Boundary Leakage Detection Systems", May 1973.

3/4.4.3.2 OPERATIONAL LEAKAGE The allowable leakage rates from the reactor coolant system have been based on the predicted and experimentally observed behavior of cracks in pipes. The j normally expected background leakage due to equipment design and the detection capability of the instrumentation for determining system leakage was also con-  ;

sidered. The evidence obtained from experiments suggests that for leakage 1 somewhat greater than that specified for UNIDENTIFIED LEAKAGE the probability j is small that the imperfection or crack associated with such leakage would grow l rapidly. However, in all cases, if the leakage rates exceed the values specified or the leakage is located and known to be PRESSURE BOUNDARY LEAKAGE, the reactor-will be shutdown to allow further investigation and corrective action. Service inless steel i sensitivei.e.,

piping; reactor coolant those system that are Type subject to 304 highand 316oraustenitic stress that cJ gtgM relatively 1 stagnant, intermittent, or low flow fluids, requires additional surveillance and leakage limits.

The Surveillance Eaquirements for RCS pressure isolation valves provide added assurance of valve integrity thereby reducing the probability of gross valve failure and consequent intersystem LOCA. Leakage from the RCS pressure ,

isolation valves is IDENTIFIED LEAKAGE and will be considered as a portion of the allowed limit. h Leak %e Pvasme. (%J4ut c. tar m s ef p*o isd*, are e.s M idhed 4e be beleu> 4ho lowes + pressure celia.f vg ig e. .c h h yec w e.

3/4.4.4 CHEMISTRY The water chemistry limits of the reactor coolant system are established to prevent damage to the reactor materials in contact with the coolant. Chloride limits are specified to prevent stress corrosion cracking of the stainless steel.

The effect of chloride is not as great when the oxygen concentration in the coolant is low, thus the 0.2 ppm limit on chlorides is permitted during POWER OPERATION. During shutdown and refueling operations, the temperature necessary for stress corrosion to occur is not present so a 0.5 ppm concentration of chlorides is not considered harmful during these periods. l Conductivity measurements are required on a continuous basis since changes in this parameter are an indication of abnormal conditions. When the conductivity _',

is within limits, the pH, chlorides and other impurities affecting conductivity must also be within their acceptable limits. With the conductivity meter inoperable, additional samples must be analyzed to ensure that the chlorides are not exceeding the limits.

The surveillance requirements provide adequate. assurance that concentrations in excess of the limits will be detected in sufficient time to take corrective

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8801110438 880106 PDR ADOCK 05000341 P PDR

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TABLE 3.4.3.2-1 REACTOR COOLANT SYSTEM PRESSURE ISOLATION VALVES VALVE NUMBER VALVE DESCRIPTION

1. RHR System E11-F015A LPCI Loop A Injection Isolation Valve E11-F0158 LPCI Loop B Injection Isolation Valve E11-F050A LPCI Loop A Injection Line Testable-Check Valve E11-F050B LPCI Loop B Injection Line Testable Check Valve E11-F023 RPV Head Spray Outboard Isolation Valve E11-F022 RPV Head Spray Inboard Isolation Valve E11-F008 Shutdown Cooling RPV Suction Outboard; Isolation Valve E11-F009 Shutdown Cooling RPV Suction Inboard Isolation Valve E11-F608 Shutdown Cooling Suction Isolation valve

2. Core Spray System E21-F005A Loop A Inboard Isolation Valve E21-F0058 Loop B Inboard Isolation Valve E21-F006A Loop A Containment Check Valve E21-F006B Loop B Containment Check Valve

3. High Pressure Coolant Injection System E41-F007 Pump Discharge Outboard Isolation Valve E41-F006 Pump Discharge Inboard Isolation Valve

4. Reactor Core Isolation Cooling System E51-F012 Pump Discharge Isolation Valve E51-F013 Pump Discharge to Feedwater Header Isolation Valve TABLE 3.4.3.2-2 REACTOR COOLANT SYSTEM INTERFACE VALVES LEAKAGE PRESSURE MONITORS ALARM SETPOINT SYSTEM (psig)

VALVE NUMBER E11-F015A & B. E11-F022, F023, RHR LPCI 4C2 . 12 si vyg E11-F050A & B f E11-F008, F009, F608 RHR Shutdown Cooling 130 2 0 6 155' E21-F005A & B, E21-F006A & B Core Spray 400 : 12 su VSA.

E41-F006, F007 HPCI 70 _ 1 di 71

• E51-F012, F013 RCIC 70 : I f- 77 i

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