ML19221B134
| ML19221B134 | |
| Person / Time | |
|---|---|
| Issue date: | 03/31/1979 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| References | |
| NUREG-75-087, NUREG-75-087-15.0, NUREG-75-87, NUREG-75-87-15.0, SRP-15.0, NUDOCS 7907120481 | |
| Download: ML19221B134 (4) | |
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STANDARD REVIEW PLAN O
U.S. NUCLEAR REGULATORY COMMISSION
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OFFICE OF NUCLEAR REACTOR REGULATION
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SECTICN 15.0 INTRCDUCTICN The review braaches in the Division of systems Safety and the Division of Site Safety and Ervironmer.tal Analysis that have some responsibility for review of the postulated transients and accidents listed in this chapter are as follows:
Reactor 5) stems Branch (R$8) reviews analyses of the transients and accidents from the vie. point of systems operation and core thermal-hydraulic performance.
Core Performance Branch JPB) reviews analyses of core physics and fuel behavior.
Analysis Branch ( AB) performs generic reviews of thermal-hydraulic computer ccdes and copical reports.
Ef fluent Treatment Systems Branch (ETSR) - revie.s analyses of postulated spills of radioactive material outside containment.
Accident Analysis Branch (AAB) - evaluates possible radiological consequences of the transients and accidents.
Instrumentation and Controls Systems Branch (ICSB) - reviews and evaluates the reactor protection and safety instrumentation and control instrumentation.
Power Systems Branch (PSB) reviews and e ultates emergency onsite pcwer.
Auxiliary Systems Branch ( ASB) - evaluates the operation and performance of the juxiliary systems follcwing ac idents and transients (i.e., auxiliary feedwater systems) and classificat.on of 'tructures, components ano systems.
Mechanical Engineering Branch (MEB) ev3luates the mechanical design of the reactor primary system and components, pipe restraints and other safety related mechanical components.
Containment Systems Branch (CSB) evaluates the response of the containment to postulated accidents.
Events such as fire;, floods, storms, or earthquakes are not explicitly considered in the review of postulated transients and accidents Chapter 15.
Rather, the requirements to design far these postulated events are review d under other S P sections, as listed in Table 15-1 (attached).
The reviewers are responsible for the selection and emphasis of aspects of the reviews of transients and accidents in this chapter. Judgment on the areas to be given attention dJPing each review is based on an inspection of the information provided, the similarity of this material to that recently reviewed on other plants, and whether items of special or unique safety significance are involved.
7 7120VPI The Reactor 5 stems Branch reviews the majority of the postulated transients and accidents, 3
as indicated in the SRP sections for Chapter 15.
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equi p nt malfunctions, and postulated component tailures are examined to evaluate the plant capability to control or accommodate such f ailur es and malf unctions. The RSB re,,ew ir.iudes an analysis of the pressure to which the reactor and steam systems are subjected anc' the need for engineered safety features to mitigate the consequences of accidents. The impact of various single failures on the course of a.ransient or accident is also considered.
The Core Performance Branch is responsible f er the review of all reactor physics d3ta p esented in this chapter.
This includes po-er lesels, power distributions, Doppler coeffi-cients, moderator terrperature coef ficients, void ccef ficients, reactor kinetics parameters, and centrol rod worths.
The CPB review includes the evaluation of possible damage to the f el. CPB also reviews the ocerating bands and unce>cainty bands associated with these variables and assists RSB as requested.
The review of transients and accidents by RSB requires an evaluation of results, presented in the application, of analytical methods which frequently are not documented in the aopli-c a t i u:1.
In such cases, the applicant may refer to a vendor topical report.
The methods include CNB (departure from nucleate boiling) correlation developmert, subchannel analysis, system transient analysis, analysis of RI A (reactivity-initiated accidents), and LOCA (loss of-coolant accident) analysis. For those cases where applicants use techniques previously considered and approsed by the staf f, additional review of methods may not tie required. However, if new methods are invol,ed, the AB performs a review of topical reports and other inf vmation which describe the method of analysis. Such a review generally includes oendor model description, data correlations and empirical relation 5 hips, solution techniques, summary of computer codes if involved, sample problems, experimental verifica-tion, and comparative calculations.
In its review of transients and accidents, RSB may request from AB, 3s the need is identi-fied, an independent check of the results submitted by the applicant.
'n such cases, AB obtains input data from apolicant for use in auditing-codes availatle to the staff.
Upon request of RSB, the Instrumentation and Control Systems Branch provides assistance in evaluating the sequence of postulated events, protective and safeguards systems actuation and potential bypass modes, and manual control. ICSB determines whether reactor protection and safeguards controls and instrumentation will function as assumed in the transi analysis with regard to manual or autoratic actuation; remote sensing, indication, control; and inte: locks with auxiliary or shared systems. PSB aetermines the adequacy of onsite emergency power systems.
The AAB review is concer'. rated on those more severe accidents that could result in the release of radioactive materials and could have significant radiolog; cal consequences involving the general public. AAB determines the potential doses resJlting from the acci-dents and compares these doses to established dose criteria and guidelines. Based on the results of these analyses, AAB determines the adequacy of equipment designed to mitigate radiological consequences. In addition, radiological analyses are made to determine certain technical specification limits for safety-related equipment and structures.
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lie ASB prosides an evaluation of the auxiliary systems to confirm that these >ystems can supply all the functions required to support ECCS during and fallowing a DBA LOCA or any other NSSS pipe break.
CSB evaluates the functional capability of the containment and subcompartments for the spectrum of loss-of coolant events under SRP Section 6.2.1.
CSB, on request from the RSB, also provides an evaluation of containment pressura calculations utilized in the reflood portion of the ECC5 performance analyses.
MEC is responsit'le for the review of the ef fects of blowdown loads on core support struc-t.r?s and on control rod guide structures. MEB verifies that the core remains in p;oce in case of a LOCA and that the control rods can be inserted. MEB is also responsible for evaluating the effects of blewdowr, loads including jet f orces or, the piping of the reactor coolant system and on the support structures of the components of the reactor coolant system.
MEB verifies that acceptable criteria have been enployed in the design of the redctor coolant system and its supports to prevent failures in the reactor coolant pressure boundaiy or in engineered safety feature equipment in the event of a LOCA.
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L 15.0-3 Pev. 1
TAELE 15-1 Branches Having Frimary Peview Postulated Event SRP Section Responsibility Accidents at Nearby 2.2.3 Evaluation of Dotential Accident Analysis Locaticos Accidents Branch Storms 2.3 Meteorology Site Analysis Branch
- 3. 3 Wind and Tornado Loadings Structural Engineering Branch Floods 2.4 Hydrologic Engineering Site Analysis Branch 3.4 Water Le cl (Flood) Design Auxiliary Systems Branch Earthquakes
- 2. 5 Geology and Seismology Site Analysis Branch 3.2 Classification of Struc-Auxiliary Systems Branch tures, Components and Systems 3.7 5eismic Design of Structural Engineering Structures Branch 3.8 Design of C3tegory I Structural Engineering Structures Branch 3.10 Seismic Design of Cate-Mechanical Engineering gory I Instrumentation Branch and Electrical Equipment 3.11 Environmental Design of Instrumentation and Mechanical and Elec-Control Systems trical EqJipment Branch Power Systems Branch Missiles
- 3. 5 Missile Protection Accident Analysis Branch Reactor Systems Branch Auxiliary Systems Branch Structural Engineering Branch Fires 9.5.1 Fire Pr;tection System Auxiliary Svstems Branch 9
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