ML20126D960

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Discusses Discrepancy Between STS for GE BWRs,NUREG-0123, Revision 1 & Reg Guide 1.56,Revision 1, Maint of Water Purity in Bwrs, Found During Review of Proposed Tech Specs for facility.Marked-up Tech Spec 3.4.4 Encl
ML20126D960
Person / Time
Site: 05000000, LaSalle
Issue date: 07/08/1980
From: Benaroya V
Office of Nuclear Reactor Regulation
To: Skovholt D
Office of Nuclear Reactor Regulation
Shared Package
ML082410334 List:
References
FOIA-85-243, RTR-NUREG-0123, RTR-NUREG-123 NUDOCS 8010030467
Download: ML20126D960 (2)


Text

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UNITED STATES ff. T1 e.f i NUCLEAR REGULATORY COMMISSION y

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f WASHINGTON. D. C. 20555

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JU' 0 E 1550 f4Ei40RAl;DUi4 FOR:

D. J. Skovholt, Chief Licensing Guidance Branch Division of Safety Technology FR0f4:

V. Benaroya, Chief Chemical Engineering Branch Division of Engineering

SUBJECT:

UPDATING BWR STANDARD TECHf1ICAL SPECIFICATI0fiS Off WATER CHEF 4ISTRY In reviewing the Technical Specifications proposed for LaSalle County Station, we found discrepancies between the Standard Technical Specifica-tions for General Electric Boiling Water Reactors, NUREG-0123, revision 1 (April 1, 1978) and Regulatory. Guide 1.56, " Maintenance of. Water Purity in Boiling Water Reactors", revision 1 (July 1978). We have updated Section 3.4.4, Chemistry of Reactor Coolant System, of the Standard Tech-nical Specifications to conform to the regulatory positions in Regulatory Guide 1.56, revision 1.

Attached is a marked-up copy of the updated Technical Specifications which resulted from our discussion with R. Bottimore.

We request that the updated Technical Specifications be incorporated into the next revision of NUREG-0123.

\\

Victor Be aroya, Chief' Chemical Engineering Branch

Enclosure:

As stated Division of Engineering Centact:

J. Wing X27642 cc:

R. Vollmer V. Noonan R. f4attson F. Schroeder R. Bottimore P. Matthews J. Wing A. Ecurnia f

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' REACTOR COOLANT SYSTEM 3/4.4.4 CHEMISTRY LIMITING CONDITION FOR OPERATION 3.4.4 The chemistry of the reacu r coolant system shall be maintained within the limits specified in Table 3.4.4-1.

APPLICASILITY:

At all times.

ACTION:

A In OPERATIONAL CONDITION 1:

fS With the conductivity o)r chloride concentration exceeding the limit 1.

j specified in Table 3.*.4-1 ahml Qh >c;:e 72 A w J u $3;

% GKwe u L f'

' s. Mm bIbNsYtD ld"p f A k w jb 1' mhi/cm at 25"C and less than 0.5 ppm, respectively, operation may continue ?

=4 htmeer end this need noc be reported to the Commission pr..h..d c e ;. i r --- f =-

J.. w w e-n. 4 5 & a w, ys The provisions of Specification 3.0.4 are not applicable.

2.

With the conductivity, chloride concentration or PH exceeding the limit specified in Table 3.4.4-1 for more than 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> during one continuous time interval a-c % 4 Syg h a

p GMW h c.

cdet W d d h be in at east l

STARTUP withi,1 the next 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

y *4 _

\\fith the conductivity ad.:seding 10 pmho/cr at 25'C or chloride exceeding 0.5 ppm, 4 Q q g SHv7D0u/Al @ ~ & % nl. & CM.s"Wurmwd det.

w m iv,4 pu *%.

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t>.

In OPERATIONAL CONDITION 2 and 3 with the conductiXity Chloride concen-tration or pH exceeding tne limit specified in Table 3'.4.4,

o ca_. h te h hg a cdh +h uAwc t I,beinat least HOT SHUTDOWN withinvl2 hours and in COLD SHUTDOWN within theas=1 dM 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.,

c.

At all other times:

1.

With the conductivity or pH exceeding the limit specified in T'ble 3.4.4-1, restore the conductivity and pH to within the limit withic.

72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.

2.

With the chloriae concentration limit of Table 3.4.4-1 exceeded for more than 2c hours, perform an engineering evaluation to cetermine tne effects of tne out-of-limit concition on the structural integrity of tne reactor coolant system.

Determine that the structural inte;-

rity of the reactor coolant system remains acceptacle for con ince:

operation prict to proceeding to OPERATIONAL CONDITION 3.

3.

The provisions of Specification 3.0.3 are not applicasle.

M-575