ML19221B095
| ML19221B095 | |
| Person / Time | |
|---|---|
| Issue date: | 03/31/1979 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| References | |
| NUREG-75-087, NUREG-75-087-10.4.8, NUREG-75-87, NUREG-75-87 10.4.8, SRP-10.04.08, SRP-SRP-10.04.08, NUDOCS 7907120414 | |
| Download: ML19221B095 (3) | |
Text
NUR EG.75/087 fga af og%
.?. '
't U.S. NUCLEAR REGULATORY COMMISSION n
3#
-!M(d STANDARD REVIEW PLAN s% gg e*... #*OFFICE OF NUCLEAR REACTOR REGULATION SECTICN 10.4.B STEAM GENERATOR BlCWDChN SYSTEM (PWR)
REVIEW RESPONSIBILITIES Primary - Effluent Treatment Systems Branch (ETSB)
Secondary - None I.
AREAS OF REVIEW At the construction permit (CP) stage, ETSB reviews the steam generator blowdown system (SGBS), as describcd in the applicant's safety analysis report (SAR), in the specific areas that fcllow. At the cperating license (OL) stage, the ETSB review consists of confirming the design accepted at the CP stage.
1.
ETSB reviens the SGBS design objectives in terms of e p ected and desigi, flows, process design parameters and equipment design capacities, expected and design temperatures for terrperature-sensitive treatment processes (e.g., demineralization and reverse osmosis), and process instrumentation and controls for maintaining cperations within established parameter ranges.
2.
ETSB reviews the seismic design and quality group classifications for equipment, piping, and comperents.
The liquid and gaseous waste treatment aspects of the SGBS are reviewed under SRP Sections 11.2 and 11.3.
Liquidandgaseousprocessandeffluentradiologicalmonitoringl is reviewed under SRP Section 11.5 and process sampling is reviewed under SRP l
Section 9.3.2.
ASB evaluates the effect of system failures to assure that safety-related equipment will not be made iroperable under SRP Section 3.6.1.
l II.
ACCEPTANCE CRITERIA ETSB accepts the design of the steam generator blowdown system if the follod ng conditions are met.
1.
The SGBS is sized to accommodate the design blowdown flow needed to maintain secondary coolant chemistry for normal operation, including anticipated operational occurrences. Equipment capacities are based on design blowdown flow rates and are such that temperature limits for heat-sensiti.e processes are not exceeded. Instru-mentation and autcmatic controls ensure operation within design parameters.
USNRC STANDARD REVIEW PLAN standers re,.ew piene are prepared foe t*G euedence of t** of' ice et muc+eer neector aesuietica et.ff resoonsibie for the rowiew of e,ps.catione to construct.ad operate nucteer power plente These docurnente are enade swee'abie to tne pubhc es part of the Commeesson a popcv to enform the nucteer industry and the generet erubl4C Of reguketery procedures and polectee Stenderd rewtow piene tre not oube% tee for reguietory guides or the Commiseson a regulettone end CompfkMee wit
- thent to not,equ4 rad The steaderd review plan ectione are heyed to Reveeson 2 of the Stenderd Forenet end Content of Safety Anetwe+e Reporte for %uclear Power Plente %et adl sect 5ene of the $1onderd Eermet hewe e correspondtag towsew g6en Publiened stenderd review plane wtM be revreed periodiceity, es appropriate to eccommodete sommente end to rettect new Information and espersonce Centatente and suggeettone for emprovement Will be Conetdered and ehould be eent to the U S 88velser Reguaatory Comm6eeson.Offke of Nucteer Reector 1 [f /W, 4, i n.,u..t.en. weea.neten o C miss
~
~.
(
i l
__m "ona*a0 79071204l44 Rev. 1
2.
The design of the SGBS downstream of the outer containrr.ent isolation valves is in accord with the provisions of Regulatory Guide 1.143.
III. REVIEW PROCEDURES The reviewer selects and emphasizes material from this review plan as may be appropriate for a particular case.
1.
ETSB considers the pressure, temperature, flow rate, secondary coolant chemistry, main condenser water inleakage, and primary to secondary leakage to determine whether the SGBS design has included the effects of normal operation and anticipated operational occurrences (e.g., train condenser inleakage or primary to secondary leakage). ETSB determines that the desiqq parameters are reasonable. If the proposed system includes processes which are heat-sensitive (e.g., demineralization or reverse osmosis), ETSB verifies that the design includes instrumentation and controls to protect the temperature sensitive elements. ETSB ensures that instrumentation and process controls are provided to control flashing, liquid levels, and process flow through the proper components for the radioactivity levels expected.
2.
ETSB compares the quality group and seismic design classifications of SGBS components to the guidelines of Regulatory Guide 1.143.
l 3.
ETSB reviews the waste treatment and radiological process and effluent monitoring aspects of the SGBS in SRPs 11.2, 11.3, 11.5 and 9.3.2.
ETSB reviews the proposed l
piping and instrumentation diagrams (P& ids) and process flow diagrams, the method of operation, the processing to be provided, and the interfaces between the blowdown system and other plant systems to determine: (1) whether unusual design conditions exist which could lead to safety pr3blems, and (2) that the system is capable of performing its intended functions.
IV.
_ EVALUATION FINDINGS ETSB verifies that sufficient information has been provided and that the review is adequate to support conclusions of the following type, to be included in the staff's safety evaluation report:
"The staam generator blowdown system (5GBS) controls the concentration of chemical impurities and radioactive materials in the secondary coolant. The scope of review of the SGBS included piping and instrumentation diagrams, seismic and quality group classifications, design process parameters, and instrumentation and process controls.
The review has included the applicant's evaluation of the proposed system operation and the applicant's estimate of the controlling proce3s parameters.
. 4 i L
1 Rev. I 10.4.8-2
"We have reviewed the capability of the system to process blowdown ficws and to maintain secondary coolant chemical and raciological limits, and the capability of the instrumentation and process controls to maintain system operation within
'.he proposed limits.
"The basis for acceptance in our review has been conformance of the applicant's designs ad design criteria to applicable regulatory guides.
" Based ca the foregoing evaluation, we conclude th3t the prcposed steam generator blcodewn system is acceptable."
V.
REFEPENCES 1.
Regulatory Guide 1.143, " Design Guidance ter Radioactive Waste Management Systems, Structures and Components in Light-Water-Cooled Nuclear Reactor Power Plants."
10.4.c-3 Rev. 1