ML20096D718

Proposed TS Bases Section 3/4.4.3.1 Re Accuracy of Procedural Leak Calculations

ML20096D718
Person / Time
Site:	Hope Creek
Issue date:	05/11/1992
From:	Public Service Enterprise Group
To:
Shared Package
ML20096D715	List: ML20096D713 ML20096D718
References
NUDOCS 9205180207
Download: ML20096D718 (4)

Text

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4 Reference LCR 91-01 Supplement L

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Rafnrence: LCR 91-01 Supplement M2AQ)JMENT 1 1

Based upon NRC-expressed concerns, PSE&G proposes the following revised or additional inserts:

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f. '1ho Inr ice Inspection Program for pipinj identified in Imc Generic .

Irtter 88-01 shall conform to tbo staff positions on schedulo, nothods, personnel, ard sanple expanslan included in that generic letter, or an othelwino approved by the Imc.

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( Proceduralized, ranual quantitative cc.lculation of leakage ratt-s, found by the NRC staff, in GL 88-01, Curp.1, to bo en acceptable alternative durirrJ repair );nriods of up to 30 days, is of amparable accuracy to the insta.lled drwell floor ard equirnent drain sump monitorirg system.

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REACTOR C00dNT SYSTEM BASE _S 3/4.4.3 RE CTOR COOLANT SYSTEM LEAKAGE 3/4.4.3.1 LEAKAGE DETECTION SYS IMS The RCS leakage detection systems required by this specificat. ion are provided to monitor and detect leakage from the reactor coolant pressure M undary. These detection systems are consistent with the recommendations of Regulatory Guide 1.45, "Reector Conlant Pressure Boundary Leakage Cetection Systems", May 1973.

Proceduralized, manual quantitative calculation of leakage rates, found by the NRC staff, in GL 38-01, Cupp. 1, to be an acceptable alternative during repair periods of up to 30 days, is of emaparable accuracy to the installe'l drywell floor and equipment drain sump monitoring system.

3/4 4.3.2 OPERATIONAL LEAKAGE The allowable leakage rates from the reactor coolant syster have been based on the predicted anti experimentally observed behavior of cracks in pipes. The normally expected background leakage due to equiptrent design and the detection capability of the instrumentation for determining system leakage was also con-sidered. The evidence obtained from erSeriments suggests that for leakage somewhat greater than that specified for UNIDENTIFIED LEAKAGE the probability is small that the imperfection or crack associated with such leakage would grow rapidly. However, in cll cases, If the leakage rates exceed the values specified or the leakage is located and known to be PRESSURE BOUNDARY LEAKACE, the reactor will be shutdown to allow further investigation and corrective action.

The Surveillsnce Requirements for RCS pressure isolation valves provide added assurance of valve inteprity thereby reducing the probability of gross valve failure and consequent intersystem LOCA. Leakage from the RCS pressure isolation valves n IDENTIFIED LEAKAGE and wili be considered as a portion of the allowed limit.

3/4.4.4 CHEMISTRY The water chemistry limits of the reactor cool 0nt system are established to prevent damage te 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 nct 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 +o occur is not present so a 0.5 ppm concentration of chlorines is not considered harmful during these periods.

Conductivity measurements are required on a continuous basis since changes in this parameter are an indication of abnormal conditions. When the conductisity ,

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

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

HOPE CREEK B 3/4 4-3 I

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.APOLICABIQT1 '

SUP.VEgtANCEREQUIREMENTS(Continued)

Pressure Vessel Code and applicable Addenda shall be applicaule as follows in these Technical Specifications:

ASME Boiler and Pressure Vessel Required frequencies I Code and applicable Addenda for performing inservice terminology for inservice inspection and testing )

inspection and testing activities activities i

Weekly At least once per 7 days l Monthly At least once per 31 days 1 Quarterly cr every 3 months At least once per 92 dars Semiannually or every 6 months At least once per 184 days Every 9 months At least once per 276 days Yearly or annually At least once per 366 days

c. The provisions of Specification 4.0.2 are applicable to the above required frequ2ncias for performing inservice inspection and testing activities.

d. Performance of the above inservice inipection and testing activities shall be in addition to other specified Surveillance Requirements,

e. Nothing in the ASME Boiler and Pressure Vessel Code shall be con-strued to supersede the requirements of any Technical Specification.

f. Tre Inservice Inspection Program for piping identified in NRC Generic Letter 88-01 shall conform to the staff positions on achedule, methods, personnel, and sample expansion included in that generic letter, or as otherwise approved by the NRC,

-HOPE CREEK 3/4 0-3 hendment No.

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