ML19221B090

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Srp,Revision 1 to Section 10.4.6, Condensate Cleanup Sys
ML19221B090
Person / Time
Issue date: 03/31/1979
From:
Office of Nuclear Reactor Regulation
To:
References
NUREG-75-087, NUREG-75-087-10.4.6, NUREG-75-87, NUREG-75-87 10.4.6, SRP-10.04.06, SRP-SRP-10.04.06, NUDOCS 7907120405
Download: ML19221B090 (4)


Text

U.S. NUCLEAR REGULATORY COMMISSION STANDARD REVIEW PLAN OFFICE OF NUCLEAR REACTOR REGU' ATION SECTION 10.4.6 CONDENSATE CLEANUP SYSTEM REVIEW RESPONSIBILITIES I

Primary - Auxiliaiy Systems Franch (aSB)

Secondary - Materials Engineerine Branct. (MIEB) l I.

AREAS OF REVIEW The condansate cleanup system (CCS) removes dissolved and suspended impurities due to corrosion from condenser or steam generator leaks that could be intraduced into the CCS by carryover f rom the main steam system. The CCS is not required for safe shutdono or mitigation of postulated accidents, but is important in maintainir,g the primary coolant quality in direct cycle plants or the secondary coolant quality in indirect cycle plants.

The ASB reviews the CCS from the supply point downstream of the condensate cumps to the l

discharge point upstream of the feedwater heaters, and also to the interfaces with the effluent treatment systems.

1.

The ASB asstres that the CCS is reviewed to verify that the system proviJes feedwater to the reactor for direct cycle plants or to steam generators for indirect cycle plants that meets water purity requirements. Condensers are reviewed to dete ~im that proper design treasures are taken to a< sure that the chloride c ;.,tentration and other contaminant concentrations are limited to allowable values until the condensate and feedwater systems can be isolated in the event of condenser tube leaks.

2.

ASB reviews the system to determine that the design satisfies the recomme7dations of Branch Technical Position ASB 3-1 with respect to brcaks and cracks in high and moderate energy system piping.

3.

The applicant's proposed technica! specifications are reviewed for cperating license applications as they relate to areas covered in this SRP sect'on.

I 4.

ETSB determines the ef fect of the CCS on fission and corrosion product concentrations l and the effect of the quantity of spent resin and reaenerant solutior on radwaste I

system requirements as described in SRP Section 11.2.

Secondary review is performed by MTEB to determine it.at the quality of the water suoplied to the reacto-for direct cycle plants, and to the steam generators :or indirect cycle USNRC STAND ARD REVIEW PLAN

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plants, meets water purity requirements. MTLB reviews are performed to verify the compatibility of the materials of con 3truction with tne service conditions. MTtB will perform reviews to verify that the inservice inspection program requirements are met for the system components.

II.

ACCEPTANCE CRITERIA Acceptability of the CCS design, as described in the applicant's safety analysis repor' (SAR), is based on the crit eria below.

There are no general design criteria that apply directly to the CCS.

1.

For direct cycle plants, the design of the CCS shoulti conform to the recommendations of Regulatory Guide 1.56, as related to the design of condensate demineralizer j

systems to maintain the proper water purity specified for the reactor. For indirect cycle nlants the design should conform with Positions C. l through C.5 of Regulatory Guide 1.56 and the secondary water chemistry requirements as specified in the plant Technical Specifications 2.

The design of the CC5 should meet Eranch Technical Positions ASB 3-1 :ind MEB 3-1, as related to breaks in high and mcderate energy piping systems outside containment.

3.

Inservice inspection requirements should conform to those in ASML Boiler and Pressure Vessel Code,Section XI for Class 2 and 3 components, as appropriate for those areas ci review identified in subsection I of this SRP section as being the responsibility of MTEB, the acceptance criteria and their methods of application are contained in the SRP sections corresponding to the MTEB.

III. REVIEW PROCfDURES Ihe review procedures below are used during the construction permit (CP) review to determine that the design criteria and bases and the preliminary desion as set forth in the preliminary safety analysis report (PSAR) meet the acceptance criteria given in subsection II.

For the review of operating license (OL) applications, the prccedures l

are used to serify that the initial design criteria and bises have been appropriately implemented in the final design as set forth in the,inal safety analysis report (FSAR).

Upon request from the primary reviewer, the MTEB will provide input f or the areas of revie.v stated in subsection I.

The primary reviewer uses such input as required to assu e that this review procedure is complete.

The procedures for OL reviews include a determination that the content and intent of the technical specifications ?repared by the app 1= ant are in agreement with the requirements for system testing, minimum perform 1nce, and surveillance developed as a result of the staff's review.

The reviewer will select and emphasize material from the paragraphs below, as may be appropriate for a particular case.

Rev. 1 10.4.6-2

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1.

Layout drawings are reviewed to ascertain there are no safety-related components or systems located close to the high or moderate energy pipes of the CCS, or that protection from the effects of failures of these pipes is provided.

The me ns of providing such protectica will be given in Chapter 3.6 of the SAR and procedures I

for reviewing this information are given in SRP Section a.C.

2.

The ASB evaluates the system design inform' tion and drawings and, utilizing engineer-l ing judgment, operational axperience, and performance characteristio of similar, previously approved systems, verifies that:

a.

The system meets the requirements for condensate cleanup capacity, provides effluent of the required purity, and contains adequite instrumentati n to monitor the effectiveness of the system, b.

The system has adequate ci ity to maintain acceptable chloride cor.centrations and other contaminant cors. ations in the feedwater system for a sufficient period of time to allow remedial action in the event of condenser tube failures, and the technical specifications and operational procedures adequately describe the method used to isolate the condensate and feedwater systems during repairs. I The system is connected to radioactive waste disposal systems to allnw disposal c.

of spent resin or regenerant solutions when required.

IV.

EVALUATION flNDINGS The reviewer verifies that sufficient information has been provided and his review suppo ts conclusions of the following type, to be incladed in the staff's safety evaluation report:

"The condensate cleanup system includes all components and equipment necessary for the removal of dissolved and suspended impurities which may be present in the condensate. Based on the review of the applicant's proposed design criteria and l

design bases for the Londensate cleanup system and the requirements for operation of the system, the staff ccncludes that the design of the condensate cleanup system l and supporting systems is in conformance with the design criteria av i design bases.

(0L)

"The basis for acceptance in the staf f review has been conf ormance of the applicant's design criteria and design basis for the condensate cleanup system and supporting systems to applicabl? regulatory guides, staf f technical positions, and indury standards.

"The statf concludes that the design of the condensate cleanup system conforms to all applicable guides, staff positions, and industry standards, and is acceptable."

10.4.6-3

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V.

REFERENCES 1.

Regulatory Guide 1.56, "Miintenance of Purity in Boiling Watar Reactors."

2.

Branch Technical Positions ASB 3-1, " Protection Against Postulated Piping Failures in Fluid Systems Outside Containment," attached to SRP Section 3.6.1, and MfB 3-1,

" Postulated Break and Leakage Locations in fluid System Piping Outside Containment,"

attached to SRP Section 3.6.2.

I 3.

ASME Boiler and Pressure Vessel Code Section XI, " Rules for Inservice Inspection of Nuclear Plant Co conents."

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