ML19221A983
| ML19221A983 | |
| Person / Time | |
|---|---|
| Issue date: | 11/24/1975 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| References | |
| NUREG-75-087, NUREG-75-087-03.2.2, NUREG-75-87, NUREG-75-87-3.2.2, SRP-03.02.02, SRP-3.02.02, NUDOCS 7907120128 | |
| Download: ML19221A983 (12) | |
Text
NU REG-15/087 fpanog%b U.S. NUCLEAR REGULATORY COMMISSION N[Vh) STANDARD REVIEW PLN\\1
'%.*.... /
OFFICE OF NUCLEAR REACTOR REGULATION SECTION 3.2.2 SYSTEM QUALITY GROUP CLASSIFICATION REVIEW RESPONSIBILITIES Primary - Peactor Systems Branch (RSB)
Secondary - Containment Systems Branch (CSB)
Auxiliary and Power Conversion Systens Branch (APCSB)
Effluent Treatment Systens Branch (ETSB)
I.
AREAS OF REVIEW Nuclear pcwer plant systens and conponents important to safety should be designed, fabricated, erected, and tested to quality standards corrensurate with the importance of the safety function to be performed.
The RSB reviews the applicant's classification systen for pressure-retaining conponents such as pressure vessels, heat excha'icers, storage tanks, purps, piping - and valves in fluio systens important to safety, and the assignnent by the applicant of quality groups to those sections of systens required to perforn safety functions. Where required, specific infor-nation or assistance may be required from the EICSU to review electrical and instrumenta-tion systens needed for functioning of plant features important to safety. This review is dcne for both construction pemit (CP) and operating license (OL) applications. Excluded from this review are: structures ; parts such as pump notors, shaf ts, seals, impellers,
packing, and gaskets; containment; fuel and rentor core internals; mechanical, electrical, and instrunentatica systens and valve actuation devices; vessel and piping supports and snubaing devices.
The applicant presents data in his safety analysis report (SAR) in the form of a table which idcntifies the fluid systens innortant to safety; the systen components such as pressure vessels, heat exchangers, storage tanks, purps, piping, and valves; the associated quality group classification, ASME Code and code class; and the quality assurance requirements. In addition, the applicant presents on suitable piping and instrunentation diagrams the syston quality group classifications.
The CSB reviews, in SAR Section 6.2.5, the detailed system design of fluid systens designated AEC Quality Group B, which are provided for the control of combustible gas concentrations in containment following a loss of coolant accident.
USNRC STANDARD REVIEW PLAN
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37120193 146 057
The APCSB reviews, in SAR Sections 9 and 10, the detailed systen design of auxiliary fluid systens important to safety that are designated AEC Quality Groups B and C.
The ETSB reviews, in SAR Sections 11.2 and 11.3, the detailed design of liquid, gaseous, and solid radioactive waste systems designated AEC Quality Groups C and D.
The RSS will review the detailed systen design of engineered safeguards systens that are designated AEC Quality Group B.
The branches that have secondary re/iew responsibility will confirn that the quality group classifications of systems and components within their review scopes are acceptable.
If there are systems or components other than those identified by the RSC that are deened to be important to safety this information should be transmitted to the RS3.
II.
ACCEPTANCE CRITERIA 1.
10 CFR Part 50, Appendix A, General Design Criterion 1, " Quality Standards and Records." This criterion requires tnat structures, systens, and components important to safety shall be designed, fabricated, erected, and tested to quality standards corrensurate with the importance of the safety functions to be performed.
2.
10 CFR Part 50, Appendix 3 " Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants." This apperdix establishes quality assurance requirements for the design, construction, and operation of those structures, systems, and con-ponents of nuclear power plants important to safety.
3.
Regulatory Guide 1.26, " Quality Group Classification and Standards." This RegJlatory Guide describes an acceptable nethod for detemining quality standards for Quality Group B, C, and 0 water-and stean-containing components important to safety of water-cooled nuclear power plants. The applicant nay use the AEC Group Classification system identified in the Regulatory Guide 1.26 or, alternately, the corresponding ANS classification systen of Safety Classes which can be cross-referenced with the classification groups in Regulatory Guide 1.26.
Clarification of Regulatory Guide 1.26 provisions with respect to boiling water reactor plant nain steam and feedwater systems, and acceptable alternate provisions for these systens are given in branch technical positions attached to this plan.
III. _ IEW PROCEDURES Selection and emphasis of various aspects of the areas covered by this review plan will be made by the reviewer on each case. The judgenent on the areas to be given attention during the review is to be based on an inspection of the material presented, the similarity of the material to that recently reviewed on other plants, and whether items of special safety significance are involved.
Section 50.55a of 10 CFR Part 50 identifies those ASME Section III, Code Class I com-ponents of light-water-cooled reactors important to safety which are part of the reactor coolant pressure boundary. These components are designated in Regulatory Guide 1.26 as Quality Group A.
In addition, Regulatory Guide 1.26 identifies, on a functional basis, water-and steam-containing conponents of those systems important to safety which are
- 3. 2.2 -2 146 058
ouality Groups B and C.
Quality Group D applies to water-and steam-containing components of systems that are less important to safety.
There are also systems of light-water-cooled reactors important to safety that are not identified in Regulatory Guide 1.26 and which the staf f considers should be classified Quality Group C.
Examples of these systers are: diesel fuel oil system; diesel gener-ator cooling, lubricating oil, and air startuo systems; instrument and service air systems required to cerform a safety function; and certain ventilation syctems. Gas treatnent systens which are considered as enqineered safeguards systens should be classified Quality Group B.
The information supplied in the application identifying fluid systens important to safety is reviewed for conpleteness, and the quality group classification, ASME Code and code class, and quality assurance requirenents of each individual major component are checked for compliance with the above criteria. The various modes of systen operation are checked to assure that the assigned AEC quality groups are acceptable.
The piping and instrumentation diagrams are reviewed to assure that the applicant has delineated in detail the systen quality group classification boundaries for systens inportant to safety. Each individual line on a diagran is checked to assure the accuracy of the assigned quality group classification, including branch lines such as vents, drains, and sample lines. Changes in quality group classification are permit *ed normally only at valve locations, with the valve assigned the higher classification. A change in quality group classification with no valve present is perm 1.
ed only when it can be demonstrated that the safety function of the system is not impaired by a failure on the lower-classification side of the boundary.
The following fluid systens important to safety for pressurized water reactor (PE) and boiling water reactor (BLlR) plants are reviewed by the R$B with regard to quality group classification.
FLUID SYSTEMS IMPORTANf TO SAFETY FOR PWR PLANTS Reactor Coolant Systcm Emergency Core Cooling System Containment Spray System Chemical and Volume Control System Baron Thermal Regeneration System Baron Recycle System Residual Heat Removal System Component Cooling Water Syster> I Spent Fuel Pool Cooling and Cleanup SystenEl Sampling System /
3 Service Water SystemE/
2 Compressed Air System /
Diesel Fuel Oil System 146 059 3.2.2-3
Diesel Generator Auxiliary Systems MainSteamSysted FeedwaterSysteM Auxiliary Feedwater System Liquid Waste Processing Systenbl Gaseous Waste Processing Systen1/
Containr,ent Corling System Containment Purge System Ventilation Systems for Areas such as Control Room and Engineered Safety Features Roons Fire Protection Systen /l-Combustible Gas Control System Condensate Storage System 1/
FLUID SYSTEMS IMPORTANT TO SAFETY FOR BWR PLA1TS Roactor Recirculation Systen
'iain Steam System (up to but not including the turbine)
E Feedwater System Relief Valve Discharge Piping Control Rod Drive Hydraulic System Standby Liquid Control System Reactor Water Cleanup Systen LiquidRaduasteSystedl Gaseous Radwaste System (Off-gas)1/
2 Fuel Pool Cooling and Cleanup System _/
SamplingSysteMI Residual Heat Removal Systen High Pressure Core Spray System Low Pressure Core Spray Systen Reactor Core : solation Ceoling System RHR Service Water System Emergency Equipment Service Water System 2
Compressed Air System /
Diesel Generator Auxiliary Systems Standby Gas Treatrent System Combustible Gas Control System Containment Cooling System Main Steam Line Isolation Valve Sealing System I
Condensate and Refueling Water Storage System Ventilatio-Systems for Areas such as Control Roon and Engineered Safety Features Rooms Fire Protection System 1/ U 1/ n so e plants this system may be non-safety-related, providing it complies with the O
requirements of Regulatory Guide 1.26.
Fortions of the system that perform a safety-related function.
1/ ortions of the system to outermost containment isolation valve.
P 3.2.2-4 146 060
Provisions applicable to BWR main steam and feedwater system quality group and seismic classifications, for those portions of tne system on the turbine side of the containment isolation valves, are given in Branch Technical Positions RSB No. 3-1 and 3-2, attached to this plan.
In the event an applicant intends to take exception to Regulatory Guide 1.26 and has not provided adequate justification for his proposed quality group classification, questions are prepared by the staff which may require additional docunentation or an analysis to establish an acceptable basis for his proposed quality group classification.
Staff coments may also be prepared requesting clarification, in order to assure a clear understanding of the quality group classifications assigned to a system by the applicant.
Exceptions and alternatives to the specified quality group classifications of Regulatory Guide 1.26 are unacceptable unless "equivaleat quality level" is justified. In such cases, justitication can be demonstrated if: the component is classified to meet the requirements of a higher group classification than specified in Regulatory Guiue 1.26 or alternative design rules are based on the use of a more conservative design; the extent of corponent nondestructive examination is equal to or greater than required by the speci fied code; and the quality assurance requirenents of Appendix B,10 CFR Part 50 are net.
If the staff's questions are not resolved in a satisfactory nanner, a staff position is taken requiring confornance to kegulatory Guide 1.26.
IV.
EVALUATION FINDINGS The staff's review should verify that adequate and sufficient infornation is contained in the SAR and amendnents to arrive at a conclusion of the following type, which is to be included in the staff's Safety Evaluation report:
" Fluid systen pressure-retaining components inportant to safety will be designed, fabricated, erected, and tested to quality standards comensurate with the importance of the safety function to be performed. Water-and stean-containing conponents which are part of the reactor coolant pressure boundary and other fluid systems important to safety, where reliance is placed on these systens (1) to prevent or mitigate the consequences of accidents and malfunctions originating within the reactor coolant pressure boundary, (2) to permit shutdown of the reactor and maintenance in the safe shutdown condition, and (3) to contain radioactive material, have been classified in an acceptable runner in Tables 3.X.X and 3.X.X and on system piping and instrunentation diagra ns.
"The basis for acceptance in the staff's review has been conformance of the applicant's designs, design criteria, and design bases for pressure-retaining components such as pressure vessels, heat exchangers, storage tanks, pumps, piping dnd Valves in fluid systems important to safety with the Comission's regulations 3.2.2-5
as set forth in General Design Criterion 1, with the requirements of the Codes specified in Section 50.55a of 10 CFR Part 50, with Regulatory Guide 1.26, and with staff technical positions and industry standards."
V.
REFERENCES 1.
10 CFR Part 50, Appendix A, General Design Criterion 1, " Quality Standards and Records."
2.
10 CFR Part 50, Appendix B, " Quality Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants."
3.
Regulatory Guide 1.26, " Quality Group Classifications and Standards."
4.
ANSI N18.2a-1975, Revision and Addenda to ANSI *:18.2, " Nuclear Safety Criteria for the Design of Stationary Pressurized Water Reactor Plants," American National Standards I.istitute (1973).
5.
ANS N212, " Nuclear Safety Criteria for the Design of Stationary Boiling Water Reactor Plants," Draft No. 4, Pev. 2, April 1974, ANS Standard Issued for Trial Use and Comment, American Nuclear Society (1974).
6.
ANS N213 " Nuclear Safety Criteria for the Design of Stationary Gas Cooled Reactor Plants," Draft No. 9, Rev. 2, January 1974, ANS Standard Issued for Comnent, American Nuclear Society (1974).
7.
ASME Boiler and Pressure Vessel Code, 1974 Edition,Section III, " Nuclear Power Plant Components," American Society of Mechanical Engineers (1974).
8.
ASME Boiler and Pressure Vessel Code,1974 Edition,Section VIII, Division 1,
" Pressure Vessels," American Society of Mechanical Engineers (1974).
9.
ANSI B31.1-1973, " power Piping," American National Standards Institute (1973).
10.
API Standard 620, Fifth Edition, " Recommended Rules for Design and Construction of Large, Welded, Low-Pressure Storage Tanks," Americal Petroleum Institute (1973).
11.
API Standard 650, Fifth Edition, " Welded Steel Tanks for Oil Storage," American Petroleum Institute (1973),
12.
AWWA D100-73, "AWWA Standard for Steel Tanks-Standpipes, Reservoirs, and Elevated Tanks for Water Storage," Anerican Water Works Association (1973).
13.
ANSI B96.1-1973, " Specification for Welded Aluminum-Alloy Field-Erected Storage Tanks," American National Standards Institute (1973).
3.2.2-6
- 14. Branch Technical Position - RSS 'to. 3-1, " Classification of Main Stean Cmponents Other Than the Reactor Ccolant Pressure Boundary for BWR Plants."
15.
Branch Technical Positica - RSB No. 3-2, " Classification of BWR/6 Main Steam and Feedwater Cmponents Other Than the Reactor Coolant Pressure Boundary."
146 063 3.7.2-7
BRANCH TECHNICAL POSITION - RSB NO. 3-1 CLASSIFICATION OF MAIN STEAM COMPCNENTS OTHER THAN THE REACTOR COOLANT PRESSURE BOUNDARY FOR BWR PLANTS A
BACKGROUND A pipe classification of "D + QA" for main steam line components of BWR plants was proposed by the General Electric Company in 1971 as an alternative to Quality Group B and has been accepted by the staff in a number of licensinq case reviews.
However, we have recently identified a number of potential problems which are applicable to nain steam lines of BWR olants. These problens relate to postulated breaks in high-energy fluid-containing lines outside the containment. The criteria pertaining to protection re-quired for structures, systems, and conponents outside containment from the effects of postu-lated oipe breaks, as contained in the Director of Licensing's letter to utilities dated July 12, 1973, reference ASME Section III, Class 2, which corresponds to AEC Quality Group B.
The recent ASME Code Section XI revision contains in-service inspection require-ents for Class 2 components. Steam lines classified as "O + QA" could be intrepreted to be exempt from these inspection requirements. Such interpretations would be contrary to the intent of the code and inconsistent with requirenents of the AEC Codes and Standards rule, Section 50.55a of 10 CFR Part 50.
Furthermore, the apolicability of the following AEC Regulatory Guides and Regulations, as they relate to ASME Class 2 components is not always clearly identified or implenented in case applications wherever "D + QA" classification is adopted:
1.
Regulatory Guide 1.51, "In-service Inspection of ASME Code Class 2 and 3 Nuclear Power Plant Components."
2.
Regulatory Guide 1.48, " Design Limits and Loading Corbinations for Seismic Category I Fluid System Components."
3.
Regulatory Guide 1.26, " Quality Group Classifications and Standards.'
4.
10 CFR 5 50.55a. " Codes and Standards for Nuclear Power Plants."
5.
10 CFR Part 50, Appendix B, " Quality Assurance Criteria for Nuclear Power Plants."
In view of the foregoing, we find it necessary to clarify the quality group classification criteria for main steam cenponents for BWR plants.
B.
BRANCH TECHNICAL POSITIO1 The main steam line components of BWR plants should conform to the criteria listed in the attached Table 3-1.1, 3.2.2-8 146 064
C.
REFERENCES 1.
Letter of March 22, 1973, J. A. Hinds to J.M. Hendrie.
2.
Letters of August 13, 1973 and November 26, 1973, J.M. Hendrie to J.A. Hinds.
Tabl e 3-1.1 CLASSIFICATION REQUIREMENTS FOR MAIN STEAM COMPONENTS OTHER THAN THE REACTOR COOLANT PRESSURE BOUNDARY Classification Item System or Corponent Qua l_i ty Group __
l.
Main Steam Line from 2nd Isolation B
Valve to Turbine Stop Valve.
2.
Main Steam Line Branch Lines to B
First Valve.
3.
Main Turbine Bypass Line to B
Bypass Valve.
4.
First Valve in Branch Lines B
Connected to Either Main Steam Lines or Turbine Bypass Lines.
5.
a.
Turbine Stop Valves, Turbine D + 0; l/
Control Valves, and Turbine or Bypass Valves.
Certification 2/
b.
Main Steam Leads from Turbine D + QA 1/3/
Control Valves to Turbiae Casing.
or Ce -ti fi ca ti on 2/
1/- The following requirements shall be met in a adition to the Quality Group D requirements:
1.
All cast pressure-retaining parts of a size and configuration for which volumetric examination methods are effective Shall be examined by radiographic meth';ds by qualified personnel. Ultrasonic examination to equivalent standards may be used as an alternate to radioqraphic metnods.
2.
Examination procedures and acceptance standards shall be at least equivalent to those specified as supplementary types of examination in ANSI B31.1-1973, Par. 136.4 I
- The followinq qualification shall be net with respect to the certification requirements:
1.
The manufacturer of the turbine stop valves, turbine control valves, turbine bypass valves, and ruin steam leeds from turbine cor 'rol valves to the turbine casing shall utilize quality control procedures equivalent to those defined in General Electric Publication GEZ-4982A, " General Electric Large Steam Turbine - Generator Quality Ccntrol Program."
2.
A certification shall be obtained from the runufacturer of these valves and steam leads that the quality control program so defined has been accomplished.
! e following requirements shall be met in addition to the Quality Group D requirements:
Th 9
1.
All longitudinal and circumferential butt weld joint shall be radiographed (or ultra-sonically tested to equivalent standards). Where size or cenfiguration does not permit effective volumetric exambation, magnetic particle or liquid penetrant examination may 146 065 3.2.2-9
Table 3-1.1 (cont'd) be substituted. Examination procedures and acceptance standards sh. 41 be at least equivalent to those specified as supplementary types of examinations, Paragraph 136.4 in ANSI B31.1 -1973.
2Property "ANSI code" (as page type) with input value "ANSI B31.1 -1973.</br></br>2" contains invalid characters or is incomplete and therefore can cause unexpected results during a query or annotation process..
All fillet and socket welds shall be examined by either magnetic particle or liquid penetrant methods. All struc'u-al attachment welds to pi essure retaining materials shall be examined by either magnetic particle or liquid penetract methods. Examina ti on procedures and acceptance standards shall be at least equivalent to those specified as supplementary types of examinations, Paragraph 136.4 in ANSI B31.1-1973.
3Property "ANSI code" (as page type) with input value "ANSI B31.1-1973.</br></br>3" contains invalid characters or is incomplete and therefore can cause unexpected results during a query or annotation process..
All inspection records shall be ruintained for the life of the plant. These records shall include data pertaining to qualification of inspection personnel, examination procadures, and examination results.
O 3.2. "
146 066
BRANCH TECHNICAL POSITION - RSB NO. 3-2 CLASSIFICATIM " BWR/6 MAIN STEAM AND FEEDWATER COMPONENTS OTHER TL fHE REACTOR COOLANT PRESSURE BOUNDARY A.
BACKGROUND At.9rious times the AEC staff has discussed with the General Electric Company the subject of approp iate classification requirenents in boiling water reactor (BNR) plants for main steam system conponents. These discussions have included consideration of components that are (a) not classified as safety-related items but are located di vnstream of the isolation valves, (b) not specifically designed to seismic Category I standards, and (c) not housed in seismic Category I structures.
To date, BWR plant reviews have resulted in various approaches for different individual applications. While these dif ferent approaches have resulted in acceptable levels of safety in each case, they have required time-consuminq case-by-case reviews. The GESSAR BWR/6 application, under review as part of our standardization proqram, includes this portion of the BWR plant.
In the course of the GESSAR review, we have identified a systematic basis for classification of such components that will result in an acceptable and uniform design basis for the main steam lines (MSL) and main feedwater lines (MFL) in BWR/6 plants.
B.
B_ RANCH TECHNICAL POSITION The main steam and feedwater system components of BWR/6 plants should be classified in accordance with BTP-RSB No. 3-1, or alternately, in accordance with the attached Table 3-2.1.
The classifications indicated are acceptable alternates to the guidelines currently specified in Regulatory Guide 1.26 and Regulatory Guide 1.29.
As an additional requirement, a suitable interface restraint should be provided at the point of departure from the Ciass I structure where the interface exists between the safety and nonsafety-related portions of the MSL and MFL.
A sketch is attached (Figure 3-2.1) to clarify the specified alternate classification system.
C.
REFERENCES 1.
Letter of April 19, 1974, J.M. Hendrie tc J. A. Hinds.
14 ti Oti7 3.2.2-11
Table 3-2.1 CLASSIFICATION REQUIREME'lTS FOR B'lR/6 MAIN STEA'i A';D FEEDWATER SYSTEM COMPONENTS OTHER THAN THE REACTOR COOLANT PRESS!!RE BOUNDARY QUALITY GROUP ITEM SYSTEM OR C0PONENT CLASSIFICATION 1.
Main Steam Line (MSL) from second isolation valve to and B
including shutoff vilve.
2.
Branch lines of MSL between the second isolation valve and the B
MSL shutoff valve, from branch point at MSL to and including the first valve in the branch line.
3.
Main feedwater line (MFL) from second isolation valve and B
including shutoff valve.
4.
Branch lines of MFL between the second isolation valve and the B
MFL n stoff valve, from the branch point at MFL to and including the first valve in the branch line.
5.
Main steam line piping between the MSL shutoff valve and the D (1) turbine nain stop valve.
6.
Turbine bypass riping.
D 7.
Branch lines of the PGL between the MSL shutoff valve and the turbine D
rain stop valve.
8.
Turbine valves, turbine control valves, turbine bypass valves, and D (1,2) rvain steam leads from the turbina control valves to the turbine casina.
or Certification (3) 9.
Feedwater system components beyond the MFL shutcff v11ve.
D flT All inspection records shall be niintained for the life of the plant. These records shall include data pertaining to qualification of inspection personnel, examination procedures, and examination results.
(2)
All cast pressure-retaining parts of a size and configuration for which volumetri methods are effective shall be examined by radiographic nethods by qualified personnel. Ultrasonic examination to eqt ' valent standards may be used as an alternate to radiographic methods. Exan-stion procedures and acceptance standards shall be at least equivalent to those defined in Pi.ragraph 136.1, " Examination Methods of Welds - Non-Boiler External Piping," ANSI B31.1-1973.
(3)
The f ollowing qualifications shall be net with respect to the certification recuirements:
1.
The manufacturer of the turbine stop valves, turbine control vclves, turbine bypass valves, and main steam leads from turbine control valves to the t;rbine casing shall utilize quality control procedures equivalent to those defined in General Electric Publication GEZ-4982A, " General Electric Large Steam Turbine-Generator Quality Control Program."
2.
A certification shall be obtained from the manufacturer of these valves and ste in leads that the quality control progran 50 defined has been accomplished.
146 068 3.2.2-12