Regulatory Guide 1.33: Difference between revisions

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{{Adams
{{Adams
| number = ML13350A365
| number = ML003739995
| issue date = 01/31/1977
| issue date = 02/28/1978
| title = Quality Assurance Program Requirements (Operation)
| title = Quality Assurance Program Requirements (Operation)
| author name =  
| author name =  
| author affiliation = NRC/OSD
| author affiliation = NRC/RES
| addressee name =  
| addressee name =  
| addressee affiliation =  
| addressee affiliation =  
Line 10: Line 10:
| license number =  
| license number =  
| contact person =  
| contact person =  
| document report number = RG-1.033, Rev. 1
| document report number = RG-1.33, Rev 2
| document type = Regulatory Guide
| document type = Regulatory Guide
| page count = 8
| page count = 8
}}
}}
{{#Wiki_filter:Revision 1 January 1977 U.S. NUCLEAR REGULATORY  
{{#Wiki_filter:Revlklon 2 U.S. NUCLEAR REGULATORY COMMISSION                                                                               February 1978 REGULATORY GUIDE
COMMISSION
                                      OFFICE OF STANDARDS DEVELOPMENT
* REGULATORY  
                                                                      REGULATORY GUIDE 1.33 QUALITY ASSURANCE PROGRAM REQUIREMENTS
GUIDE OFFICE OF STANDARDS  
                                                                                  (OPERATION)
DEVELOPMENT
REGULATORY  
GUIDE 1.33 QUALITY ASSURANCE  
PROGRAM REQUIREMENTS (OPERATION)


==A. INTRODUCTION==
==A. INTRODUCTION==
Appendix B, "Quality Assurance Criteria for N2 r P~nis.'s, Ph:nl nr anfl Fns't R nrncetcinr'
ANS-3.2, "Administrative Controls and Quality As surance for the Operational Phase of Nuclear Power Appendix B, "Quality Assurance Criteria for Nu                                        Plants," by the American National Standards Insti clear Power Plants and Fuel Reprocessing Plants," to                                      tute on February 19, 1976.
for the Operational Phase of Nuclear Power Plants.'" by tile American National Standards Institute on February 19, 1976.Plants." to 10 CFR Part 50, "Licensing of Produc- Some uncertainty has arisen with regard to the tion and Utilization Facilities." establishes quality NRC staffs position when a regulatory guide en-assurance requirements for the operation of nuclear dorses. as an acceptable method, the "guidelines as power plant safety-related structures.


svstems. and well as the "requirements" included in a standard.components.
10 CFR Part 50, "Licensing of Production and Utili zation Facilities," establishes quality assurance re                                          There had been some uncertainty with regard to the quirements for the operation of nuclear power plant                                        NRC staff's position when a regulatory guide en safety-related structures, systems, and components.                                       dorses, as an acceptable method, the "guidelines" as This regulatory guide describes a method acceptable                                        well as the "requirements" included in a standard.


This regulatory guide describes a The NRC staff has evaluated the guidelines con-methiid acceptable to the NRC staff for complying tained in N 18.7-1976/ANS-3.2.with respect to impor.with the Commission's regulations with regard to tance to safety. This~regulatory guide is intended to overall quality assurance program requirements for clarify the NRC .:staff's position on the "re-the operation phase of nuclear power plants. quiretnents" ',anid "guidelines" included in ANSI N 18.7-1976/NS-3.2.
to the NRC staff for complying with the Commis                                            The NRC staff has evaluated the guidelines contained sion's regulations with regard to overall quality as                                        in N18.7-1976/ANS-3.2 with respect to importance surance program requirements for the operation phase                                      to safety. Revision I of this regulatory guide clarified of nuclear power plants. The Advisory Committee on                                          the NRC staff's position on the "requirements" and Reactor Safeguards has been consulted concerning                                            "guidelines" included in ANSI N18.7-1976/ANS
 
this guide and has concurred in the regulatory                                              3.2. Where conformance to the recommendations of position.                                                                                  this regulatory guide is indicated in an application without further qualification, this indicates the appli
' cWhere conformance to the  


==B. DISCUSSION==
==B. DISCUSSION==
reconimendatiotns-`.
cant will comply with the "requirements" of ANSI
of this regulatory puide is in-dicaited inn :.application without further qualifica- Subcommittee ANS-3. Reactor Operations.
                                                                                            N18.7-1976/ANS-3.2, as supplemented or modified Subcommittee ANS-3,' Reactor Operations, of the                                        by the regulatory position of this guide.
 
of the ...tion.-this indicates thle applicant will comply with the American Nuclear Society Standards of ANSI N18.7-1976/ANS-3.2.
 
as developed ANSI N 18.7-1972 that contained critcria or modified by the regulatory position for administrative controls for nuclear powerpiants-, tIis guide.during operation.


This standard.
American Nuclear Society Standards Committee de veloped ANSI N18.7-1972, which contained criteria for                                        Section 1, "Scope," of ANSI NI8.7-1976/ANS
administrative controls for nuclear power plants dur                                      3.2 states that this standard contains criteria for ad ing operation. This standard, along with ANSI                                            ministrative controls and quality assurance for nu N45.2-1971, "Quality Assurance Program Require                                            clear power plants during the operational phase of ments for Nuclear Power Plants," was endorsed by                                          plant life and that this phase is generally considered Regulatory Guide 1.33. The dual endorsement was                                            to commence with initial fuel loading, except for cer necessary in order for the guidance contained in the                                      tain preoperational activities. In this regard, a sepa regulatory guide to be consistent with the require                                        rate regulatory guide addressing the quality assurance ments of Appendix B to 10 CFR Part 50; however,                                          program for the preoperational phase will be issued.


along with.\ANS1'" S
this dual endorsement caused some confusion among                                        Other regulatory guides may be issued or this regula users. To clarify this situation, ANSI N18.7-1972                                          tory guide may be revised, if necessary, to amplify was revised so that a single standard would define the                                   the general requirements contained in this standard.
* .... o.N45.2-1971. "Quality Assurance Pro. ..u.. c... s" tectton i. Scopetd of ANSI NIc.7-19ri/,,aNS-
ments for Nuclear Power Plants, Vus endors&eFdb
3.2 ". "a .....Reguator Gue .3. The, dti-. .,
1 " ministrative controls and qualitV assurance for Regulatory Guide 1.33. The dual eolaorsewent was,, ., ....t .-...,,- ..', ;,.... nuclear power nlants dutnn the operational h',se of necessary in order for the guidance conta ied in the he ' p,, of regulatory gui. e to btvvonsistent with the require- plant life and that this phase is generally considered ments of Appending'
t10 CFR Part 50: however, to commence with initial fuel loading. except for cer-this dualendosem~~
A someconfusionamong tain preoperational activities.


In this regard. a users. To is !
general quality assurance program "requirements"
ANSI N!8.7-1972 was separate regulatory guide addressing the quality as-revisedso .at .-!ngstandard would define the surance program for the preoperational phase will he nri utii a*irance program "requirements" issued. Other regulaory guides may he issued or thisVu 'tyaba rgam*rqieet*
for the operation phase. This revised standard was                                             Appendix A to this guide has been further revised approved by the American National Standards Com                                          as a result of additional' comments received on the mittee NI8, Nuclear Design Criteria. It was sub                                          guide and additional staff review.
for Aimrb 'phase. This revised standard was regulatory, guide may be revised, if necessary, to appr7 d by the American National Standards Coin- amplify the general requirements contained in thisI8. Nuclear Design Criteria.


It was sub.,e- standard.quently approved and designated N 18.7-1976/ANS-
sequently approved and designated N18.7-1976/
Copic% ma. hbe obtained from American Nucle:r Sriciety.
                                                                                          ,Copies may be obtained from American Nuclear Society, 555
-*Lines indicate substantive changes from previous issue.                                North Kensington Avenue, La Grange Park, Illinois 60525.


244 IVa.st 3.2. "Administrative Controls and Quality Assurance Ogden Avenue. Htinsdale.
USNRC REGULATORY GUIDES                                        Comments shoukl      be sent to the Secretary of the Commission. US. Nuclear Regu latory Commission, Washington, D.C.        20555, Attention: Docketing and Service Regulatory Guides ore issued to describe and make available to the Public methods acceptable to the NRC staff of implementing specific parts of the Commission's regulations, to delineate techniques used by the staff in evaluating specific problems The guides are issued in the following ten broad divisions or postulated accidents, or to Provide guidance to applicants. Regulatory Guides awt not substitutes for regulations, and compliance with them is not required.          1.  Power Reaclors                          6. TProducts Methods and solutions different from those set out in the guides will be accept.       2.   Research and Test Reactors              7. Trancsortation aWle if they provide a basis for the findings requisite to the issuance or continuance 3.   Fuels and Materials Facilities          a. Occupational Health o fa p ecr mitor license aby th eCo mni, son.                                          4.  Environm etntl and Siting               


Illinoi 60521 USNRC REGULATORY
===9. Antitrust Review===
GUIDES C-',avents Should ho' Sam0 to 11h0 Srlysetary of It, Corn.rr,',,i U S N., 1'.,i Regulatory Guitdes a'e issued to d scribe and m.,ke Availatble to the, public SRviegltr S oetiron~sr a$.. fin 0,5 treoe o&, nreithods d c Ceptab le to the NAC s.tafft of mp~irem..t~rg specific pat,% of int-Conre,tus'.in s agegatiorns, to delineate tech q.0% tased by sthe .101 .' .. -0. ~ ' The 0 gude resu,!d in Sthe following for% bto.id d-%i'.ns, dm5.3 specific prohlemns us postulated Accullentr of to p'ovide guidwice it) apple cants. Regulatory Guides .sre not substitutill tor regulations.
                                                                                        5.   Materials and Plant Protection          t0. General Comments end suggestions for improvements in these guides we encouraged at all        Requests for single copies of issued guides iwhich may be reiroduced) or for place tires, and guides will be revised, as appropriate, to accomnmodate comments and        ment on an automatic distribution list for single copies of future guides in specific
"toreflect new information or experience. This guide was revised as a result of         divisions should be made in writing to the US. Nuclear Regulatory Commission.


and comipliance I P.ee Rear~~. I~6 P~odlutts witht then, is not faquited Methods .snd soluto,'.s different fromt those %at out -~ 2 RC'.Oa,c1, .snt Ti,,1 R.',tct 7 t,.itttit the of uides. wilt be acceptable it they p~rovide.s abase%" for the find~ng,, requisite to 3FWels .,nsl Mate',,..m I..,clrte'.
eubltantive comments received from the Public and additional staff review.             Washington, D.C.     20555. Attention    Director. Division of Document Coistrol.
9 Uec-aum.rt1n H-1lt the ,ssuineeo, cooitti itceotatternti or licenste byt the Catnrnnssittn
4 0tr,.eirneent.'.l -td Soling 9 Antitru'.t tlei.iev Coniroit,e~t anfd ouggestiors toe improvementtels on these guides are encoruraged
5 Nlatevials.trid Plasnt P'otect~oos t0 Generasl.st alt titos,es ..Id guides wilt he retvised.


JS appropriate.
==C. REGULATORY POSITION==
and will be endorsed by a regulatory guide The overall quality assurance program require                      upon its approval as an ANSI standard.


to ACCOMniUSjtIA
ments for the operation phase that are included in ANSI N18.7-1976/ANS-3.2 are acceptable to the                      3. Section 4.3.4, "Subjects Requiring Independ NRC staff and provide an adequate basis for comply              ent Review," Item (3) states, in part, that changes to ing with the quality assurance program requirements            the technical specifications or license amendments re of Appendix B to 10 CFR Part 50, subject to the fol              lated to nuclear safety are required to be reviewed by lowing:                                                          the independent review body prior to implementation.
LUM1 n.1-t .rrd to f eflect stew nslornitrristor or experutenr.o However. conriiin1t'
otn Copies of published guides. mayr be obtained by wr,otte,.vttuetl -d',di...,i I th'thi'% guide. it #received wIth,., about two nsor,th% .tle 1%' issuabnce.


will he. Lid' divst'ions'
It should be noted that proposed changes to technical I. ANSI N18.7-1976/ANS-3.2 requires the prep                specifications or license amendments should be re aration of many procedures to carry out an effective            viewed by the independent review body prior to their quality assurance program. Appendix A, "Typical                 submittal to the Commission for approval.
de',oued to top U S Nuclear Regulatory Cuorn-mlaiis W.rsh,,iqtiii'
1) C tI~ua usef'ul ... evao.atl...
iq tlre need for an, earty ,esis-on 2055. Attention Director Ottice of Standard'.
Oevelopnsen'"
Appendix A to this guide has been revised as a result of comments received on the guide and ad-ditional staff review.C. REGULATORY
POSITION The overall quality assurance program require-ments for the operation phase that are included in ANSI N18.7-1976/ANS-3.2 are acceptable to the NRC staff and provide an adequate basis for comply-ing with the quality assurance program requirements of Appendix B to 10 CFR Part 50, subject to the fol-lowing: I. ANSI NI8.7-1976/ANS-3.2 requires the preparation of many procedures to carry out an effec-tive quality assurance program. Appendix A,"Typical Procedures for Pressurized Water Reactors and Boiling Water Reactors," to this regulatory guide should be used as guidance to ensure minimum procedural coverage for plant operating activities, in-cluding related maintenance activities.


Appendix A lists typical safety-related activities that should be covered by written procedures but does not provide a complete listing of needed procedures.
Procedures for Pressurized Water Reactors and Boil ing Water Reactors," to this regulatory guide should                4. Section 4.5, "Audit Program," of ANSI
be used as guidance to ensure minimum procedural                N18.7-1976/ANS_3.2 states that audits of selected coverage for plant operating activities, including re          aspects of operational phase activities shall be per lated maintenance activities. Appendix A lists typical         formed with a frequency commensurate with their safety-related activities that should be covered by             safety significance and in such a manner as to ensure written procedures but does not provide a complete             that an audit of all safety-related functions is com listing of needed procedures. Many other activities            pleted within a period of 2 years. In amplification of carried out during the operation phase of a nuclear            this requirement, the following program elements power plant require written procedures not included            should be audited at the indicated frequencies:
in Appendix A. Appendix A may also contain proce dures that are not applicable to an applicant because                  a. The results of actions taken to correct de of the configuration of the nuclear power plant. The            ficiencies that affect nuclear safety and occur in facil procedures listed in Appendix A may be combined,                ity equipment, structures, systems, or method of separated, or deleted to conform to the applicant's            operation-at least once per 6 months.


Many. other activities carried out during the operation phase of a nuclear power plant require written procedures not included in Appendix A. Appendix A may also con-tain procedures that are not applicable to an appli-cant because of the configuration of the nuclear power plant. The procedures listed in Appendix A may be combined, separated.
procedures plan.                                                      b. The conformance of facility operation to pro
    2. Throughout ANSI NI8.7-1976/ANS-3.2, other               visions contained within the technical specifications documents required to be included as a part of this            and applicable license conditions-at least once per standard are identified at the point of reference. The         12 months.


or deleted to conform to the applicant's procedures plan.2. Throughout ANSI N18.7-1976/ANS-3.2, other documents required to be included as a part of this standard are identified at the point of reference.
specific acceptability of these standards listed in ANSI N18.7-1976/ANS-3.2 has been addressed in                          c. The performance, training, and qualifications the latest revision of the following regulatory guides:        of the facility staff-at least once per 12 months.


The specific acceptability of these standards listed in ANSI N 18.7-1976/ANS-3.2 has been addressed in the latest revision of the following regulatory guides: Design and Procurement Phase of Nuclear Power Plants," (Grey Book) and WASH-1309. "Guidance on Quality As-surance Requirements During the Construction Phase of Nuclear Power Plants," (Green Book) and will be en-dorsed by a regulatory guide upon its ap-proval as an ANSI standard.3. Section 4.5, "Audit Program," of ANSI N 18.7-1976/A NS-3.2 states that audits of selected aspects of operational phase activities shall be performed with a frequency commensurate with their safety significance and in such a manner as to ensure that an audit of all safety-related functions is completed within a period of 2 years. In amplification of this re-quirement, the following program elements should be audited at the indicated frequencies:
5. The ANSI Standard          Regulatory Guide                "should") guidelines        (indicated by the verb of ANSI N18.7-1976/ANS-3.2 contained N45.2                    1.28                        in the following sections have sufficient safety impor N45.2.1                  1.37                        tance to be treated the same as the requirements (in N45.2.2                  1.38                        dicated by the verb "shall") of the standard:
a. The results of actions taken to correct deficiencies that affect nuclear safety and occur in facility equipment.
        N45.2.3                   1.39 N45.2.4                                                      a. Section 4.4-The guidelines concerning re
                                  1.30
        N45.2.5                                                view activities of the onsite operating organization,
                                  1.94                        except the guideline that refers to screening subjects N45.2.6                    1.58 N45.2.8                                                of potential concern.


structures, systems. or method of operation-at least once per 6 months.b. The conformance of facility operation to provisions contained within the technical specifica- tions and applicable license conditions-at least once per 12 months.c. The performance.
1.116 N45.2.9                    1.88                              b. Section 5.2.3-The guideline concerning re N45.2. 10                  1.74                        view and updating of standing orders.


training, and qualifications of the facility staff-at least once per 12 months.4. The guidelines (indicated by the verb "should")of ANSI N 18.7-1976/ANS-3.2 contained in the fol-lowing sections have sufficient
N45.2. I I                1.64 N45.2.13                  1.123                              c. Section 5.2.4-The guideline concerning re N18. 1                                                view, updating, and cancellation of special orders.
.,afety importance to be treated the same as the requirements (indicated by the verb "shall") of the standard: a. Section 4.,4-The guidelines concerning review activities of ihe onsi~e operating organization.


except the guideline that refers to screening subjects of potential concern.b. Section 5.2.3-The guideline concerning review and updating of standing orders.c. Section 5.2.4-The guideline concerning review, updating, and cancellation of special orders.d. Section 5.2.7.1-The guidelines that address adequate design and testing of replacement parts.e. Section 5.2.13.4-The guideline concerning special handling tools and equipment.
1.8 N 18.17                    1.17                              d. Section 5.2.7. 1-The guidelines that address N 101.4                    1.54                      adequate design and testing of replacement parts.


f. Section 5.2.19(2)-The guideline for checking plant operating procedures during the testing program.g. Section 5.2.19.1-The guidelines for preoperational tests, except the guideline that refers to a run-in period for equipment.
Note: N45.2.12 is discussed in NRC                          e. Section 5.2.13.4-The guideline concerning documents WASH-1283, "Guidance on                        special handling tools and equipment.


In addition to these ANSI Standard N45.2 N45.2.1 N45.2.2 N45.2.3 N45.2.4 N45.2.5 N45.2.6 N45.2.8 N45.2.9 N45.2. 10 N45.2. II N45.2.13 N 18.1 N 18.17 N 101.4 Regulatory Guide 1.28 1.37 1.38 1.39 1.30 1.94 1.58 1.116 1.88 1.74 1.64 1.123 1.8 1.17 1.54 Note: N45.2.12 is discussed in NRC documents WASH-1283, "Guidance on Quality Assurance Requirements During 1.33-2 U ----guidelines, the prerequisite steps for each equipment test should be completed prior to the commencement oft the preoperational test.h. Section 5.3.2-The guidelines that describe the content (excluding format) of procedures.
Quality Assurance Requirements During Design and Procurement Phase of Nuclear                        f. Section 5.2.19(2)-The guideline for check Power Plants," (Grey Book) and WASH                    ing plant operating procedures during the testing pro
    1309, "Guidance on Quality Assurance Re                gram.


except for the guidelines that address (I) a separate state-ment of applicability in Section 5.3.2(2).
quirements During the Construction Phase of Nuclear Power Plants," (Green Book)                         g. Section 5.2.19. 1-The guidelines for preop erational tests, except the guideline that refers to a
(2) inclusion of references in procedures, as applicable, in Section 5.3.2(3).  
                                                      1.33-2
and (3) inclusion of quantitative control guides in Section 5.3.2(6).i. Section 5.3.9-The guideline concerning emergency procedures requiring prompt implementa- tion of immediate operator actions when required to prevent or mitigate the consequences of a serious condition.


j. Section 5.3.9.1-The guidelines that describe the content (excluding format) for: the tith,! in Section 5.3.9.1(1):
tification in Section 5.3.9.1(2); automatic actions in run-in period for equipment. In addition to these              Section 5.3.9.1(3); immediate operator action, guidelines, the prerequisite steps for each equipment          excluding those guidelines contained in the examples,
the inclusion of svmploms to aid in iden-tificaltion in Section 5.3.9.1(2):
- test should be completed prior to the commencement            in Section 5.3.9.1(4); and subsequent operator ac of the preoperational test.                                    tions in Section 5.3.9.1(5).
automatic actions in Section 5.3.9.1(3):
        h. Section 5.3.2-The guidelines that describe the content (excluding format) of procedures, except                         
immediate operator action, ex-cluding those guidelines contained in the examples, in Section 5.3.9.1(4):
and subsequent operator actions in Section 5.3.9.1(5).


==D. IMPLEMENTATION==
==D. IMPLEMENTATION==
The purpose of this section is to provide informa-tion to applicants and licensees regarding the NRC staff's plans for using this regulatory guide. Except in those cases in which the applicant proposes an alter-native method for complying with specified portions or the Commission's regulations.
for the guidelines that address (1) a separate state ment of applicability in Section 5.3.2(2), (2) inclu            The purpose of this section is to provide informa sion of references in procedures, as applicable, in          tion to applicants and licensees regarding the NRC
 
  Section 5.3.2(3), and (3) inclusion of quantitative          staff's plans for using this regulatory guide.
the method described herein will he used in the evaluation ofsub-inittals for operating license applications docketed after September I. 1977. If an applicant whosc ap-plication for an operating license is docketed on or prior to September I. 1977. wishes to use this regulatory guide in developing submittals for applic.-lions, the pertinent portions of the application kwill be evaluated on the basis of this guide.1.33-3 APPENDIX A TYPICAL PROCEDURES
FOR PRESSURIZED
WATER REACTORS AND BOILING WATER REACTORS The following are typical safety-related activities that should be covered by written procedures.
 
This appendix is not intended as an inclusive listing of all needed procedures since many other activities carried out during the operation phase of nuclear power plants should be covered by procedures not included in this list.1. Administratiie Procedures a. Security and Visitor Control b. Authorities and Responsibilities for Safe Operation and Shutdown c. Equipment Control (e.g.. locking and tagging)d. Procedure Adherence and Temporary Change Method e. Procedure Review and Approval f. Schedule for Surveillance Tests and Calibration g. Shift and Relief Turnover h. Log Entries, Record Retention, and Review Procedures i. Access to Containment j. Bypass of Safety Functions and Jumper Control k. Maintenance of Minimum Shift Complement and Call-In of Personrel I. Plant Fire Protection Program m. Communication System Procedures
2. General Plant Operating Procedures a. Cold Shutdown to Hot Standby b. Hot Standby to Minimum Load (nuclear startup)c. Recovery from Reactor Trip d. Operation at Hot Standby e. Turbine Startup and Synchronization of Generator f. Changing Load and Load Follow (if applicable)
g. Power Op.ration and Process Monitoring h. Power Operation with less than Full Reactor Coolant Flow i. Plant Shutdown to Hot Standby j. Hot Standby to Cold Shutdown k. Preparation for Refueling and Refueling Equip-ment Operation I. Refueling and Core Alterations
3. Procedures for Startup, Operation, and Shutdown of Safety-Related PWR Systems Instructions for energizing, filling, venting, drain-ing, startup, shutdown, and changing modes of operation should be prepared, as appropriate, for the following systems:* Linc. indicate substantive changes from previous issue.a. Reactor Coolant System b. Control Rod Drive System (including part-length rods)c. Shutdown Cooling System d. Emergency Core Cooling System e. Component Cooling Water System
 
====f. Containment====
(!) Maintaining Containment Integrity (2) Special Containment Systems (a) Atmospheric (b) Subatmospheric (c) Double-Wall Containment with Con-trolled Interspace (d) Ice Condenser (3) Containment Ventilation S)stem (4) Containment Cooling System g. Atmosphere Cleanup Systems h. Fuel Storage Pool Purification and Cooling System i. Main Steam System j. Pressurizer Pressure and Spray Control Systems k. Feedwater System (feedwater pumps to steam generator)
I. Auxiliary Feedwater System m.Service Water System n. Chemical and Volume Control System (including Letdown/Purification System)o. Auxiliary or Reactor Building Heating and Ventilation p. Control Room Heating and Ventilation q. Radwaste Building Heating and Ventilation r. Instrument Air System s. Electrical System (1) Offsite (access circuits)(2) Onsite (a) Emergency Power Sources (e.g., diesel generator, batteries)(b) A.C. System (c) D.C. System t. Nuclear Instrument System (I) Source Range (2) Intermediate Range (3) Power Range (4) Incore System u. Reactor Control and Protection System


====v. Hydrogen Recombiner====
control guides in Section 5.3.2(6).                               This guide reflects current NRC practice. There fore, except in those cases in which the applicant i.. Section 5.3.9-The guideline concerning              proposes an acceptable alternative method for com emergency procedures requiring prompt implementa              plying with the specified portions of the Commis tion of immediate operator actions when required to           sion's regulations, the method described herein is prevent or mitigate the consequences of a serious              being and will continue to be used in the evaluation condition.                                                     of submittals for operating license applications until j. Section 5.3.9.1-The guidelines that describe          this guide is revised as a result of suggestions from the content (excluding format) for.' the title in Section      the public or additional staff review.
1.33-4 I--4. Procedure for Startup, Operation, and Shutdown of Safety-Related BWR Systems Instructions for energizing, filling, venting, drain-ing, startup, shutdown, and changing modes of operation should be prepared, as appropriate, for the following systems: a. Nuclear Steam Supply System (Vessel and Re-circulating System)b. Control Rod Drive System c. Reactor Cleanup System d. Liquid Poison System (Standby Liquid Control System)e. Shutdown Cooling and Reactor Vessel Head Spray System.f. High Pressure Coolant Injection g. Reactor Core Isolation Cooling System h. Emergency Core Cooling Systems i. Closed Cooling Water System j. Containment (I) Maintaining Integrity (2) Containment Ventilation System (3) Inerting and Deinerting k. Fuel Storage Pool Purification and Cooling System I. Main Steam System (reactor vessel to turbine)m.Turbine-Generator System n. Condensate System (hotwell to feedwater pumps. including demineralizers and resin regeneration)
o. Feedwater System (feedwater pumps to reactor vessel)p. Makeup System (filtration, purification, mid water transfer)q. Service Water System r. Reactor Building Heating and Ventilation Systems s. Control Room Heating and Ventilation Systems t. Radwaste Building Heating and Ventilation Systems u. Standby Gas Treatment System v. Instrument Air System w. Electrical System (I) Offsite (access circuits)(2) Onsite (a) Emergency Power Sources (e.g.. diesel generator, batteries)(b) A.C. System (c) D.C. System x. Nuclear Instrument System (i) Source Range (2) Intermediate Range (3) Power Range (4) TIP System y. Reactor Protection System z. Rod Worth Minimizer 5. Procedures for Abnormal, Offnormal.


or Alarm Ccnditions Since these procedures are numerous and corres-pond to the number of alarm annunciators, the procedures are not individually listed. Each safety-related annunciator should have its own written procedure, which should normally contain (I) the meaning of the annunciator, (2) the source of the signal, (3) the immediate action that is to occur automatically, (4) the immediate operator action, and (5) the long-range actions.6. Procedures for Combating Emergencies and Other Significant Fients a. Loss of Coolant (including significant PWR steam generator leaks) (inside and outside primary containment) (large and small, including leak-rate determination)
5.3.9.1 (1); the inclusion of symptoms to aid in iden-
b. Loss of Instrument Air c. Loss of Electrical Power (and/or degraded power sources)d. Loss of Core Coolant Flow c. Loss of Condenser Vacuum f. Loss of Containment Integrity g. Loss of Service Water h. Loss of Shutdown Cooling i. Loss of Component Cooling System and Cool-ing to Individual Components j. Loss of Feedwater or Feedwater System Failure k. Loss of Protective System Channel I. Mispositioned Control Rod or Rods (and rod drops)m.Inability to Drive Control Rods n. Conditions Requiring Use of Emergency Bora-tion or Standby Liquid Control System o. Fuel Cladding Failure or High Activity in Reac-tor Coolant or Offgas p. Fire in Control Room or Forced Evacuation of Control Room q. Turbine and Generator Trips r. Other Expected Transients that may be Ap-plicable s. Malfunction of Automatic Reactivity Control System t. Malfunction of Pressure Control System u. Reactor Trip v. Plant Fires w.Acts of Nature (e.g.. tornado, flood, dam failure, earthquakes)
                                                            1.33-3
x. Irradiated Fuel Damage While Refueling y. Abnormal Releases of Radioactivity
7. Procedures for Control of Radioactiity For limiting materials released to emironment and limiting personnel exposure)a. Liquid Radioactive Waste System 1.33-5 (I) Collection, Demineralizing, Filtering.


Evaporating and Concentrating, and Neutralizing
APPENDIX A
(2) Sampling and Monitoring
                      TYPICAL PROCEDURES FOR PRESSURIZED WATER REACTORS
(3) Discharging to Effluents b. Solid Waste System (I)(2)(3)Spent Resins and Filter Sludge Handling Baling Machine Operation Drum Handling and Storage c. PWR Gas Systems (1)(2)(3)(4)Collection, Storage, and Discharge Sampling and Monitoring Air Ejector and Stack Monitoring Clean Air Monitoring
                                        AND BOILING WATER REACTORS
(1) Pressurized Water Reactors (a) Containment Leak-Rate Tests (b) Containment Isolation Tests (c) Containment Local Leak Detection Tests (d) Containment Heat and Radioactivity Removal Systems Tests (e) Containment Tendon Tests and Inspec-tions (f) Service Water System Functional Tests (g) Main Steam Isolation Valve Tests (h) Fire Protection System Functional Tests (i) Boric Acid Tanks-Level Instrumenta- tion Calibrations (j) Emergency Core Cooling System Tests (k) Control Rod Operability and Scram Time Tests (1) Reactor Protection System Tests and Calibrations (m) Permissives-Tests and Calibrations (n) Refueling System Circuit Tests (o) Emergency Boration System Functional Tests (p) DNB Checks and Incore-Excore Flux Monitor Correlations (q) Emergency Power Tests (r) Auxiliary Feedwater System Tests (s) NSSS Pressurization and Leak Detection (t) Inspection of Reactor Coolant System Pressure Boundary (u) Inspection of Pipe Hanger Settings (v) Control Rod Drive System Functional I d. BWR Air Extraction and Offgas Treatment System (1)(2)(3)(4)(5)Mechanical Vacuum Pump Operation Air Ejector Operation Packing Steam Exhauster Operation Sampling Air Ejector and Stack Monitoring e. Personnel Monitoring and Special Work Permit (I) Restrictions and Activities in Radiation Areas and High Radiation Areas (2) Respirator Equipment (3) Surveys and Monitoring
      The following are typical safety-related activities          b. Control Rod Drive System (including part that should be covered by written procedures. This            length rods)
(4) Protective Clothing (5) Radiation Work Permit Procedure r, Area Radiation Monitoring System Operation g. Process Radiation Monitoring System Opera-tion h. Meteorological Monitoring
  appendix is not intended as an inclusive listing of all c. Shutdown Cooling System needed procedures since many other activities carried d. Emergency Core Cooling System out during the operation phase of nuclear.power e. Component Cooling Water System plants should be covered by procedures not included f. Containment in this list.
8. Procedures for Control of Measuring and Test Equipment and for Suncillance Tests. Procedures.


and Calibrations a. Procedures of a type appropriate to the circum-stances should be provided to ensure that tools, gauges, instruments, controls, and other measuring and testing devices are properly controlled, calibrated, and adjusted at specified periods to main-tain accuracy.
(1) Maintaining Containment Integrity
  1. Administrative Procedures                                          (2) Special Containment Systems a. Security and Visitor Control                                      (a)  Atmosphere b. Authorities and Responsibilities for Safe Opera                    (b)  Subatmospheric tion and Shutdown                                                        (c)  Double-Wall Containment with Controlled c. Equipment Control (e.g., locking and tagging)          Interspace d. Procedure Adherence and Temporary Change                          (d)  Ice Condenser Method                                                                (3) Containment Ventilation System e. Procedure Review and Approval
                                                                      (4) Containment Cooling System f. Schedule for Surveillance Tests and Calibration g. Shift and Relief Turnover                                  g. Atmosphere Cleanup Systems h. Log Entries, Record Retention, and Review                  h. Fuel Storage Pool Purification and Cooling Sys Procedures                                                     tem i. Access to Containment                                      i. Main Steam System j. Bypass of Safety Functions and Jumper Control              j. Pressurizer Pressure and Spray Control Systems k. Maintenance of Minimum Shift Complement                    k. Feedwater System (feedwater pumps to steam and Call-In of Personnel                                      generator)
    I. Plant Fire Protection Program                              1. Auxiliary Feedwater System m. Communication System Procedures                            m. Service Water System n. Chemical and Volume Control System (includ
2. General Plant Operating Procedures                        ing Letdown/Purification System)
    a. Cold Shutdown to Hot Standby                              o. Auxiliary or Reactor Building Heating and b. Hot Standby to Minimum Load (nuclear start              Ventilation up)                                                              p. Control Room Heating and Ventilation c. Recovery from Reactor Trip                                q. Radwaste Building Heating and Ventilation d. Operation at Hot Standby                                  r. Instrument Air System e. Turbine Startup and Synchronization of                    s. Electrical System Generator                                                            (1) Offsite (access circuits)
    f. Changing Load and Load Follow (if applicable)                  (2) Onsite g. Power Operation and Process Monitoring h. Power Operation with less than Full Reactor                      (a)  Emergency Power Sources (e.g., diesel Coolant Flow                                                  generator,      batteries)
    i. Plant Shutdown to Hot Standby                                    (b)  A.C. System j. Hot Standby to Cold Shutdown                                      (c)  D.C. System k. Preparation for Refueling and Refueling                    t. Nuclear Instrument System Equipment Operation I. Refueling and Core Alterations                                (1) Source Range
                                                                    (2) Intermediate Range
3. Procedures for Startup, Operation, and Shutdown                  (3) Power Range of Safety-Related PWR Systems                                    (4) Incore System Instructions for energizing, filling, venting, drain          u. Reactor Control and Protection System ing, startup, shutdown, and changing modes of oper              v. Hydrogen Recombiner ation should be prepared, as appropriate, for the fol lowing systems:
                                                              4. Procedure for Startup, Operation, and Shutdown a. Reactor Coolant System of Safety-Related BWR Systems
                                                        1.33-4


Specific examples of such equipment to be calibrated and tested are readout instruments, interlock permissive and prohibit circuits, alarm devices, sensors, signal conditioners, controls, protec-tive circuits, and laboratory equipment.
Instructions for energizing, filling, venting, drain      5. Procedures for Abnormal, Offnormal, or Alarm ing, startup, shutdown, and changing modes of oper                Conditions ation should be prepared, as appropriate, for the Since these procedures are numerous and corre following systems:
                                                              spond to the number of alarm annunciators, the pro cedures are not individually listed. Each safety related annunciator should have its own written a. Nuclear Steam Supply System (Vessel and                 procedure, which should normally contain (1) the Recirculating System)                                        meaning of the annunciator, (2) the source of the sig b. Control Rod Drive System                                nal, (3) the immedate action that is to occur automat c. Reactor Cleanup System                                  ically, (4) the immediate operation action, and (5) the d. Liquid Poison System (Standby Liquid Con                long-range actions.


b. Specific procedures for surveillance tests, in-spections, and calibrations should be written (implementing procedures are required for each sur-veillance test, inspection, or calibration listed in the technical specifications):
trol System)
Tests tions Tests (w) Heat Balance-Flux Monitor Calibra-(x) Pressurizer and Main Steam Safety Valve (y) Leak Detection Systems Tests (z) Axial and Radial Flux Pattern Deter-minations (aa) Area Radiation Monitor Calibrations (bb) Process Radiation Monitor Calibrations (cc) Environmental Monitor Calibrations (dd) Safety Valve Tests (ee) Turbine Overspeed Trip Tests (f) Water Storage Tanks-Level In-strumentation Calibration
  e. Shutdown Cooling and Reactor Vessel Head Spray System
(2) Boiling Water Reactors (a) Containment Leak-Rate and Penetration Leak-Rate Tests (b)(c)(d)(e)(including (M)(g)Containment Isolation Tests Containment Vacuum Relief Valve Tests Containment Spray System Tests Standby Gas Treatment System Tests filter tests)Main Steam Isolation Valve Tests Nitrogen Inerting System Tests 1 33-6 (h) Reactor Building Inleakage Tests (i) Emergency Core Cooling System Tests (j) Control Rod Operability and Scram Time Tests (k) Reactor Protection System Tests and Calibrations (I) Rod Blocks-Tests and Calibrations (m) Refueling System Circuit Tests (n) Liquid Poison System Tests (o) Minimum Critical Heat Flux Checks and Incore Flux Monitor Calibrations (p) Emergency Power Tests (q) Isolation Condenser or RCIC Tests (r) NSSS Pressurization and Leak Detection (s) Inspection of Reactor Coolant System Pressure Boundary (t) Inspection of Pipe Hanger Settings (u) Control Rod Drive System Functional Tests (v)(w)(x)09 (z)(aa)minations (bb)(cc)tions Heat Balance Safety Valve Tests Turbine Overspeed Trip Test Leak Detection System Tests Autoblowdown System Tests Axial and Radial Flux Pattern Deter-Area Radiation Monitoring Calibrations Process Radiation Monitoring Calibra-(dd) Water Storage Tanks-Level In-strumentation Calibrations (ee) Fire Protection System Functional Tests 9. Procedures for Performing Maintenance a. Maintenance that can affect the performance of safety-related equipment should be properly preplan-ned and performed in accordance with written procedures, documented instructions, or drawings appropriate to the circumstances.
                                                              6. Procedures for Combating Emergencies and Other f. High Pressure Coolant Injection Significant Events g. Reactor Core Isolation Cooling System h. Emergency Core Cooling Systems                            a. Loss of Coolant (including significant PWR
    i. Closed Cooling Water System                            steam generator leaks) (inside and outside primary j. Containment                                            containment) (large and small, including leak-rate
      (1) Maintaining Integrity                              determination)
      (2) Containment Ventilation System                        b. Loss of Instrument Air
      (3) Inerting and deinerting                              c. Loss of Electrical Power (and/or degraded power sources)
  k. Fuel Storage Pool Purification and Cooling                d. Loss of Core Coolant Flow System                                                          e. Loss of Condenser Vacuum I. Main Steam System (reactor vessel to turbine)             f. Loss of Containment Integrity m. Turbine-Generator System                                   g. Loss of Service Water n. Condensate System (hotwell to feedwater                    h. Loss of Shutdown Cooling pumps, including demineralizers and resin                        i. Loss of Component Cooling System and Cool regeneration)                                                 ing to Individual Components o. Feedwater System (feedwater pumps to reactor              j. Loss of Feedwater or Feedwater System vessel)                                                       Failure p. Makeup System (filtration, purification, and               k. Loss of Protective System Channel water transfer)                                                   1. Mispositioned Control Rod or Rods (and rod drops)
  q. Service Water System                                     m. Inability to Drive Control Rods r. Reactor Building Heating and Ventilation                  n. Conditions Requiring Use of Emergency Bora Systems                                                      tion or Standby Liquid Control System s. Control Room Heating and Ventilation                      o. Fuel Cladding Failure or High Activity in Systems                                                      Reactor Coolant or Offgas t. Radwaste Building Heating and Ventilation                p. Fire in Control Room or Forced Evacuation of Systems                                                      Control Room u. Standby Gas Treatment System                              q. Turbine and Generator Trips v. Instrument Air System                                    r. Other Expected Transients that may be w. Electrical System                                      Applicable
        (1) Offsite (access circuits)                           s. Malfunction of Automatic Reactivity Control
        (2) Onsite                                            System t. Malfunction of Pressure Cdntrol System (a) Emergency Power Sources (e.g., diesel            u. Reactor Trip generator, batteries)                                           v. Plant Fires (b) A.C. System                                      w. Acts of Nature (e.g., tornado, flood, dam (c) D.C. System                                    failure, earthquakes)
    x. Nuclear Instrument System                                x. Irradiated Fuel Damage While Refueling y. Abnormal Releases of Radioactivity
        (1) Source Range
        (2) Intermediate Range
        (3) Power Range z. Intrusion of Demineralizer Resin Into Primary System (BWR Plants)                                     I
        (4) TIP System                                       7. Procedures for Control of Radioactivity (For limit y. Reactor Protection System                                  ing materials released to environment and limiting z. Rod Worth Minimizer                                        personnel exposure)
                                                        1.33-5


Skills normally possessed by qualified maintenance personnel may not require detailed step-by-step delineation in a procedure.
a. Liquid Radioactive Waste System
                                                                    (1) Pressurized Water Reactors
    ( I) Collection.      Demineralizing. Filtering, Evaporating          and      Concentrating,                                (a) Containment Leak-Rate Tests and Neutralizing                                                                (b) Containment Isolation Tests
        (2) Sampling and Monitoring                                          (c) Containment Local Leak Detection Tests
        (3) Discharging to Effluents (d) Containment Heat and Radioactivity b. Solid Waste System                                        Removal Systems Tests
        (1) Spent Resins and Filter Sludge Handling                          (e) Containment Tendon Tests and
        (2) Baling Machine Operation                              Inspections
        (3) Drum Handling and Storage                                        (f) Service Water System Functional Tests (g) Main Steam Isolation Valve Tests c. PWR Gaseous Effluent System                                          (hi Fire Protection System Functional Tests
        (1) Collection. Storage. and Discharge                              (i) Boric Acid Tanks-Level Instrumenta tion Calibrations
        (2) Sampling and Monitoring
        (3) Air Ejector and Stack Monitoring                                (j) Emergency Core Cooling System Tests
        (4) Ventilation Air Monitoring (k Control Rod Operability and Scram Time Tests d. BWR Air Extraction. Offgas Treatment. and                            (1) Reactor Protection System Tests and Other Gaseous Effluent Systems                                  Calibrations
        (1) Mechanical Vacuum Pump Operation                                (m) Permissi',es-Tests and Calibrations
        (2) Air Ejector Operation                                          (n) Refueling System Circuit Tests
        (3) Packing Steam Exhauster Operation                              (o) Emergency Boration System Functional
        (4) Sampling                                            Tests
        (5) Air Ejector. Ventilation. and Stack Monitor                    (p) DNB Checks and Incore-Excore Flux Monitor Correlations e. Radiation Protection Procedures                                      (q) Emergency Power Tests (I) Access Control to Radiation Areas Includ.                      tr) Auxiliary Feedwater System Tests ing a Radiation Work Permit System                                        (s) NSSS Pressurization and Leak
        (2) Radiation Sur\e\s                                    Detection
        (3) Airborne Radioactiv.ity Monitoring                              (t) Inspection of Reactor Coolant System
        (4) Contamination Control                                Pressure Boundary
        (5) Respiratory Protection                                          (u) Inspection of Pipe Hanger Settings
        (6) Training in Radiation Protection                                (v) Control Rod Drive System Functional
        (7) Personnel Monitoring                                Tests
        (8) Bioassay Program                                              (w) Heat      Balance-Flux        Monitor
        (9) Implementation of ALARA Program                    Calibrations Ix) Pressurizer and Main Steam Safety f. Area Radiation Monitoring S)stem Operation                Valve. Tests g. Process Radiation Monitoring System                                  (y) Leak Deection Systems Tests Operation                                                                  (z) Axial and Radial Flux Pattern Determi h. Meteorological Monitoring                                  nations
8. Procedures for Control of Measuring and Test                          (aa) Area. Portable. and Airborne Radiation Equipment and for Surveillance Tests, Proce                M on it or Calibrations dures. and Calibrations                                            (bb) Process a. Procedures of a type appropriate to the cir                                            Radiation    Monitor Calibrations cumstances should be provided to ensure that tools, (cc) Environmental Monitor Calibrations gauges. instruments, controls, and other measuring                      (dd) Safety Valve Tests and testing devices are properly controlled, calib (ee) Turbine Overspeed Trip Tests rated. and adjusted at specified periods to maintain (ff) Water Storage Tanks-Level In accuracy. Specific examples of such equipment to be            strumentation Calibration calibrated and tested are readout instruments, inter                (2) Boiling Water Reactors lock permissive and prohibit circuits, alarm devices, sensors. signal conditioners, controls, protective cir                    (a) Containment Leak-Rate and Penetration cuits, and laboratory equipment.                                Leak-Rate Tests (b) Containment Isolation Tests b. Specific procedures for surveillance tests, in                      (c) Containment Vacuum Relief Valve spections. and calibrations should be written (imple            Tests menting procedures are required for each surveillance                      (d) Containment Spray System Tests test. inspection, or calibration listed in the technical (e) Standby Gas Treatment System Tests specifications):                                                (including filter tests)
                                                        1.33-6


The following types of activities are among those that may not require detailed step-by-step written procedures:
(f) Service Water System Functional Tests            c. Procedures for the repair or replacement of (g)  Main Steam Isolation Valve Tests              equipment should be prepared prior to beginning (h)  Fire Protection System Functional Tests      work. Such procedures for major equipment that is (i)  Nitrogen Inerting System Tests                expected to be repaired or replaced during the life of (j)  Emergency Core Cooling System Tests          the plant should preferably be written early in plant (k)    Control Rod Operability and Scram Time      life. The following are examples of such procedures Tests                                                          for major equipment:
(1) Gasket Replacement
            (1) Reactor Protection System Tests and                (1) Repair of PWR Steam Generator Tubes Calibrations                                                        (2) Replacement and Repair of Control Rod (m) Rod Blocks-Tests and Calibrations                Drives (n) Refueling System Circuit Tests                        (3) Replacement of Recirculation Pump Seals (o) Liquid Poison System Tests                            (4) Replacement of Important Strainers and (p) Minimum Critical Heat Flux Checks and          Filters Incore Flux Monitor Calibrations                                        Repair or Replacement of Safety Valves
(2) Trouble-Shooting Electrical Circuits (3) Changing Chart or Drive Speed Gears or Slide Wires on Recorders b. Preventive maintenance schedules should be developed to specify lubrication schedules, inspec-tions of equipment, replacement of such items as filters and strainers, and inspection or replacement of parts that have a specific lifetime such as wear rings.c. Procedures for the repair or replacement of equipment should be prepared prior to beginning work. Such procedures for major equipment that is expected to be repaired or replaced during the life of the plant should preferably he written early in plant life. The following are examples of such procedures for major equipment: (I) Repair of PWR Steam Generator  
                                                                    (5)
'rubes (2) Replacement and Repair of Control Rod Drives (3) Replacement of Recirculation Pump Seals (4) Replacement of Important Strainers and Filters (5) Repair or Replacement of Safety Valves (6) Repair of Incore Flux Monitoring System (7) Replacement of Neutron Detectors d. Procedures that could he categorized either as maintenance or operating procedures should he developed for the following activities.
          (q) Emergency Power Tests                                (6) Repair of Incore Flux Monitoring System (r) Isolation Condenser or RCIC Tests                        Replacement of Neutron Detectors
                                                                    (7)
            (s) NSSS Pressurization and Leak Detection (t) Inspection of Reactor Coolant System            d. Procedures that could be categorized either as Pressure Boundary                                              maintenance or operating procedures should be (u) Inspection of Pipe Hanger Settings            developed for the following activities. Instructions (v) Control Rod Drive System Functional            for these activities may be included in systems Tests                                                          procedures.


Instructions for these activities may be included in systems procedures.(I) Exercise of equipment that is normally idle but that must operate %%hen required (2) Draining and Refilling Heat Exchangers
(w) Heat Balance
(3) Draining and Refilling Recirculation Loop (4) Draining and Refilling the Reactor Vessel (5) Draining and Refilling Steam Generators
                                                                    (1) Exercise of equipment that is normally idle (x) Autoblowdown System Tests (y) Leak Detection System Tests                  but that must operate when required (z) Axial and Radial Flux Pattern Determi                (2) Draining and Refilling Heat Exchangers
(6) Removal of Reactor Head (7) Disconnection and Reconnection of Wiring Penetrating Reactor Vessel Head (8) Demineralizer Resin Regeneration or Replacement e. General procedures for the control of maintenance, repair. replacement, and modification work should be prepared before reactor eperation is begun. These procedures should include information on areas such as the following: (I) Method for obtaining permission and clearance for operation personnel to work and for logging such work and (2) Factors to be taken into account, including the necessity for minimizing radiation exposure to workmen, in preparing the detailed work procedures.
                                                                    (3) Draining and Refilling Recirculation Loop nations (aa) Area, Portable, and Airborne Radiation                (4) Draining and Refilling the Reactor Vessel Monitor Calibrations                                                (5) Draining and Refilling Steam Generators (bb) Process Radiation Monitor Calibrations                (6) Removal of Reactor Head
                                                                    (7) Disconnection and Reconnection of Wiring I        (cc) Environmental Monitor Calibrations              Penetrating Reactor Vessel Head (dd) Safety Valve Tests
                                                                    (8) Demineralizer Resin Regeneration or (ee) Turbine Overspeed Trip Test Replacement (ff) Water Storage Tanks-Level In strumentation Calibrations                                        e. General procedures for the control of mainte (gg) Reactor Building Inleakage Tests                nance, repair, replacement, and modification work should be prepared before reactor operation is begun.


10. Chemical and Radiochemical Control I'rcedure, Chemical and radiochemical control procedures should be written to prescribe the nature and fre-quency of sampling and analyses.
9. Procedures for Performing Maintenance                      These procedures should include information on areas such as the following:
    a. Maintenance that can affect the performance
                                                                    (1) Method for obtaining permission and clear of safety-related equipment should be properly pre planned and performed in accordance with written               ance for operation personnel to work and for logging procedures, documented instructions, or drawings              such work and appropriate to the circumstances. Skills normally                    (2) Factors to be taken into account, including possessed by qualified maintenance personnel may              the necessity for minimizing radiation exposure to not require detailed step-by-step delineation in a pro        workmen, in preparing the detailed work procedures.


the instructions maintaining water quality within prescribed limits.and the limitations on concentrations of agents that may cause corrosive attack or fouling of heat-transfer surfaces or that may become sources of radiation hazards due to activation.
cedure. The following types of activities are among those that may not require detailed step-by-step writ          10. Chemical and Radiochemical Control Procedures ten procedures:                                                  Chemical and radiochemical control procedures
      (1) Gasket Replacement                                should be written to prescribe the nature and fre
      (2) Trouble-Shooting Electrical Circuits              quency of sampling and analyses, the instructions
      (3) Changing Chart or Drive Speed Gears or            maintaining water quality within prescribed limits, Slide Wires on Recorders                                    and the limitations on concentrations of agents that may cause corrosive attack or fouling of heat-transfer b. Preventive maintenance schedules should be              surfaces or that may become sources of radiation developed to specify lubrication schedules, inspec            hazards due to activation. These procedures should tions of equipment, replacement of such items as fil          specify laboratory instructions and calibration of lab ters and strainers, and inspection or replacement of          oratory equipment. Extreme importance must be parts that have a specific lifetime such as wear rings.      placed on laboratory procedures used to determine
                                                        1.33-7


These procedures should specify laboratory instructions and calibration of laboratory equipment.
concentration and species of radioactivity in liquids and gases prior to release, including representative  sampling, validity of calibration techniques, and ade.


Extreme importance must he placed on laboratory procedures used to determine concentration and species of radioactivity in liquids and gases prior to release, including representative sampling, validity of calibration techniques.
quacy of analyses.


and ade-quacy of analyses.1.33-7 UNITECV STATES NUCLE~AR REGUiLATORY
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Latest revision as of 11:24, 28 March 2020

Quality Assurance Program Requirements (Operation)
ML003739995
Person / Time
Issue date: 02/28/1978
From:
Office of Nuclear Regulatory Research
To:
References
RG-1.33, Rev 2
Download: ML003739995 (8)
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Revlklon 2 U.S. NUCLEAR REGULATORY COMMISSION February 1978 REGULATORY GUIDE

OFFICE OF STANDARDS DEVELOPMENT

REGULATORY GUIDE 1.33 QUALITY ASSURANCE PROGRAM REQUIREMENTS

(OPERATION)

A. INTRODUCTION

ANS-3.2, "Administrative Controls and Quality As surance for the Operational Phase of Nuclear Power Appendix B, "Quality Assurance Criteria for Nu Plants," by the American National Standards Insti clear Power Plants and Fuel Reprocessing Plants," to tute on February 19, 1976.

10 CFR Part 50, "Licensing of Production and Utili zation Facilities," establishes quality assurance re There had been some uncertainty with regard to the quirements for the operation of nuclear power plant NRC staff's position when a regulatory guide en safety-related structures, systems, and components. dorses, as an acceptable method, the "guidelines" as This regulatory guide describes a method acceptable well as the "requirements" included in a standard.

to the NRC staff for complying with the Commis The NRC staff has evaluated the guidelines contained sion's regulations with regard to overall quality as in N18.7-1976/ANS-3.2 with respect to importance surance program requirements for the operation phase to safety. Revision I of this regulatory guide clarified of nuclear power plants. The Advisory Committee on the NRC staff's position on the "requirements" and Reactor Safeguards has been consulted concerning "guidelines" included in ANSI N18.7-1976/ANS

this guide and has concurred in the regulatory 3.2. Where conformance to the recommendations of position. this regulatory guide is indicated in an application without further qualification, this indicates the appli

B. DISCUSSION

cant will comply with the "requirements" of ANSI

N18.7-1976/ANS-3.2, as supplemented or modified Subcommittee ANS-3,' Reactor Operations, of the by the regulatory position of this guide.

American Nuclear Society Standards Committee de veloped ANSI N18.7-1972, which contained criteria for Section 1, "Scope," of ANSI NI8.7-1976/ANS

administrative controls for nuclear power plants dur 3.2 states that this standard contains criteria for ad ing operation. This standard, along with ANSI ministrative controls and quality assurance for nu N45.2-1971, "Quality Assurance Program Require clear power plants during the operational phase of ments for Nuclear Power Plants," was endorsed by plant life and that this phase is generally considered Regulatory Guide 1.33. The dual endorsement was to commence with initial fuel loading, except for cer necessary in order for the guidance contained in the tain preoperational activities. In this regard, a sepa regulatory guide to be consistent with the require rate regulatory guide addressing the quality assurance ments of Appendix B to 10 CFR Part 50; however, program for the preoperational phase will be issued.

this dual endorsement caused some confusion among Other regulatory guides may be issued or this regula users. To clarify this situation, ANSI N18.7-1972 tory guide may be revised, if necessary, to amplify was revised so that a single standard would define the the general requirements contained in this standard.

general quality assurance program "requirements"

for the operation phase. This revised standard was Appendix A to this guide has been further revised approved by the American National Standards Com as a result of additional' comments received on the mittee NI8, Nuclear Design Criteria. It was sub guide and additional staff review.

sequently approved and designated N18.7-1976/

,Copies may be obtained from American Nuclear Society, 555

-*Lines indicate substantive changes from previous issue. North Kensington Avenue, La Grange Park, Illinois 60525.

USNRC REGULATORY GUIDES Comments shoukl be sent to the Secretary of the Commission. US. Nuclear Regu latory Commission, Washington, D.C. 20555, Attention: Docketing and Service Regulatory Guides ore issued to describe and make available to the Public methods acceptable to the NRC staff of implementing specific parts of the Commission's regulations, to delineate techniques used by the staff in evaluating specific problems The guides are issued in the following ten broad divisions or postulated accidents, or to Provide guidance to applicants. Regulatory Guides awt not substitutes for regulations, and compliance with them is not required. 1. Power Reaclors 6. TProducts Methods and solutions different from those set out in the guides will be accept. 2. Research and Test Reactors 7. Trancsortation aWle if they provide a basis for the findings requisite to the issuance or continuance 3. Fuels and Materials Facilities a. Occupational Health o fa p ecr mitor license aby th eCo mni, son. 4. Environm etntl and Siting

9. Antitrust Review

5. Materials and Plant Protection t0. General Comments end suggestions for improvements in these guides we encouraged at all Requests for single copies of issued guides iwhich may be reiroduced) or for place tires, and guides will be revised, as appropriate, to accomnmodate comments and ment on an automatic distribution list for single copies of future guides in specific

"toreflect new information or experience. This guide was revised as a result of divisions should be made in writing to the US. Nuclear Regulatory Commission.

eubltantive comments received from the Public and additional staff review. Washington, D.C. 20555. Attention Director. Division of Document Coistrol.

C. REGULATORY POSITION

and will be endorsed by a regulatory guide The overall quality assurance program require upon its approval as an ANSI standard.

ments for the operation phase that are included in ANSI N18.7-1976/ANS-3.2 are acceptable to the 3. Section 4.3.4, "Subjects Requiring Independ NRC staff and provide an adequate basis for comply ent Review," Item (3) states, in part, that changes to ing with the quality assurance program requirements the technical specifications or license amendments re of Appendix B to 10 CFR Part 50, subject to the fol lated to nuclear safety are required to be reviewed by lowing: the independent review body prior to implementation.

It should be noted that proposed changes to technical I. ANSI N18.7-1976/ANS-3.2 requires the prep specifications or license amendments should be re aration of many procedures to carry out an effective viewed by the independent review body prior to their quality assurance program. Appendix A, "Typical submittal to the Commission for approval.

Procedures for Pressurized Water Reactors and Boil ing Water Reactors," to this regulatory guide should 4. Section 4.5, "Audit Program," of ANSI

be used as guidance to ensure minimum procedural N18.7-1976/ANS_3.2 states that audits of selected coverage for plant operating activities, including re aspects of operational phase activities shall be per lated maintenance activities. Appendix A lists typical formed with a frequency commensurate with their safety-related activities that should be covered by safety significance and in such a manner as to ensure written procedures but does not provide a complete that an audit of all safety-related functions is com listing of needed procedures. Many other activities pleted within a period of 2 years. In amplification of carried out during the operation phase of a nuclear this requirement, the following program elements power plant require written procedures not included should be audited at the indicated frequencies:

in Appendix A. Appendix A may also contain proce dures that are not applicable to an applicant because a. The results of actions taken to correct de of the configuration of the nuclear power plant. The ficiencies that affect nuclear safety and occur in facil procedures listed in Appendix A may be combined, ity equipment, structures, systems, or method of separated, or deleted to conform to the applicant's operation-at least once per 6 months.

procedures plan. b. The conformance of facility operation to pro

2. Throughout ANSI NI8.7-1976/ANS-3.2, other visions contained within the technical specifications documents required to be included as a part of this and applicable license conditions-at least once per standard are identified at the point of reference. The 12 months.

specific acceptability of these standards listed in ANSI N18.7-1976/ANS-3.2 has been addressed in c. The performance, training, and qualifications the latest revision of the following regulatory guides: of the facility staff-at least once per 12 months.

5. The ANSI Standard Regulatory Guide "should") guidelines (indicated by the verb of ANSI N18.7-1976/ANS-3.2 contained N45.2 1.28 in the following sections have sufficient safety impor N45.2.1 1.37 tance to be treated the same as the requirements (in N45.2.2 1.38 dicated by the verb "shall") of the standard:

N45.2.3 1.39 N45.2.4 a. Section 4.4-The guidelines concerning re

1.30

N45.2.5 view activities of the onsite operating organization,

1.94 except the guideline that refers to screening subjects N45.2.6 1.58 N45.2.8 of potential concern.

1.116 N45.2.9 1.88 b. Section 5.2.3-The guideline concerning re N45.2. 10 1.74 view and updating of standing orders.

N45.2. I I 1.64 N45.2.13 1.123 c. Section 5.2.4-The guideline concerning re N18. 1 view, updating, and cancellation of special orders.

1.8 N 18.17 1.17 d. Section 5.2.7. 1-The guidelines that address N 101.4 1.54 adequate design and testing of replacement parts.

Note: N45.2.12 is discussed in NRC e. Section 5.2.13.4-The guideline concerning documents WASH-1283, "Guidance on special handling tools and equipment.

Quality Assurance Requirements During Design and Procurement Phase of Nuclear f. Section 5.2.19(2)-The guideline for check Power Plants," (Grey Book) and WASH ing plant operating procedures during the testing pro

1309, "Guidance on Quality Assurance Re gram.

quirements During the Construction Phase of Nuclear Power Plants," (Green Book) g. Section 5.2.19. 1-The guidelines for preop erational tests, except the guideline that refers to a

1.33-2

tification in Section 5.3.9.1(2); automatic actions in run-in period for equipment. In addition to these Section 5.3.9.1(3); immediate operator action, guidelines, the prerequisite steps for each equipment excluding those guidelines contained in the examples,

- test should be completed prior to the commencement in Section 5.3.9.1(4); and subsequent operator ac of the preoperational test. tions in Section 5.3.9.1(5).

h. Section 5.3.2-The guidelines that describe the content (excluding format) of procedures, except

D. IMPLEMENTATION

for the guidelines that address (1) a separate state ment of applicability in Section 5.3.2(2), (2) inclu The purpose of this section is to provide informa sion of references in procedures, as applicable, in tion to applicants and licensees regarding the NRC

Section 5.3.2(3), and (3) inclusion of quantitative staff's plans for using this regulatory guide.

control guides in Section 5.3.2(6). This guide reflects current NRC practice. There fore, except in those cases in which the applicant i.. Section 5.3.9-The guideline concerning proposes an acceptable alternative method for com emergency procedures requiring prompt implementa plying with the specified portions of the Commis tion of immediate operator actions when required to sion's regulations, the method described herein is prevent or mitigate the consequences of a serious being and will continue to be used in the evaluation condition. of submittals for operating license applications until j. Section 5.3.9.1-The guidelines that describe this guide is revised as a result of suggestions from the content (excluding format) for.' the title in Section the public or additional staff review.

5.3.9.1 (1); the inclusion of symptoms to aid in iden-

1.33-3

APPENDIX A

TYPICAL PROCEDURES FOR PRESSURIZED WATER REACTORS

AND BOILING WATER REACTORS

The following are typical safety-related activities b. Control Rod Drive System (including part that should be covered by written procedures. This length rods)

appendix is not intended as an inclusive listing of all c. Shutdown Cooling System needed procedures since many other activities carried d. Emergency Core Cooling System out during the operation phase of nuclear.power e. Component Cooling Water System plants should be covered by procedures not included f. Containment in this list.

(1) Maintaining Containment Integrity

1. Administrative Procedures (2) Special Containment Systems a. Security and Visitor Control (a) Atmosphere b. Authorities and Responsibilities for Safe Opera (b) Subatmospheric tion and Shutdown (c) Double-Wall Containment with Controlled c. Equipment Control (e.g., locking and tagging) Interspace d. Procedure Adherence and Temporary Change (d) Ice Condenser Method (3) Containment Ventilation System e. Procedure Review and Approval

(4) Containment Cooling System f. Schedule for Surveillance Tests and Calibration g. Shift and Relief Turnover g. Atmosphere Cleanup Systems h. Log Entries, Record Retention, and Review h. Fuel Storage Pool Purification and Cooling Sys Procedures tem i. Access to Containment i. Main Steam System j. Bypass of Safety Functions and Jumper Control j. Pressurizer Pressure and Spray Control Systems k. Maintenance of Minimum Shift Complement k. Feedwater System (feedwater pumps to steam and Call-In of Personnel generator)

I. Plant Fire Protection Program 1. Auxiliary Feedwater System m. Communication System Procedures m. Service Water System n. Chemical and Volume Control System (includ

2. General Plant Operating Procedures ing Letdown/Purification System)

a. Cold Shutdown to Hot Standby o. Auxiliary or Reactor Building Heating and b. Hot Standby to Minimum Load (nuclear start Ventilation up) p. Control Room Heating and Ventilation c. Recovery from Reactor Trip q. Radwaste Building Heating and Ventilation d. Operation at Hot Standby r. Instrument Air System e. Turbine Startup and Synchronization of s. Electrical System Generator (1) Offsite (access circuits)

f. Changing Load and Load Follow (if applicable) (2) Onsite g. Power Operation and Process Monitoring h. Power Operation with less than Full Reactor (a) Emergency Power Sources (e.g., diesel Coolant Flow generator, batteries)

i. Plant Shutdown to Hot Standby (b) A.C. System j. Hot Standby to Cold Shutdown (c) D.C. System k. Preparation for Refueling and Refueling t. Nuclear Instrument System Equipment Operation I. Refueling and Core Alterations (1) Source Range

(2) Intermediate Range

3. Procedures for Startup, Operation, and Shutdown (3) Power Range of Safety-Related PWR Systems (4) Incore System Instructions for energizing, filling, venting, drain u. Reactor Control and Protection System ing, startup, shutdown, and changing modes of oper v. Hydrogen Recombiner ation should be prepared, as appropriate, for the fol lowing systems:

4. Procedure for Startup, Operation, and Shutdown a. Reactor Coolant System of Safety-Related BWR Systems

1.33-4

Instructions for energizing, filling, venting, drain 5. Procedures for Abnormal, Offnormal, or Alarm ing, startup, shutdown, and changing modes of oper Conditions ation should be prepared, as appropriate, for the Since these procedures are numerous and corre following systems:

spond to the number of alarm annunciators, the pro cedures are not individually listed. Each safety related annunciator should have its own written a. Nuclear Steam Supply System (Vessel and procedure, which should normally contain (1) the Recirculating System) meaning of the annunciator, (2) the source of the sig b. Control Rod Drive System nal, (3) the immedate action that is to occur automat c. Reactor Cleanup System ically, (4) the immediate operation action, and (5) the d. Liquid Poison System (Standby Liquid Con long-range actions.

trol System)

e. Shutdown Cooling and Reactor Vessel Head Spray System

6. Procedures for Combating Emergencies and Other f. High Pressure Coolant Injection Significant Events g. Reactor Core Isolation Cooling System h. Emergency Core Cooling Systems a. Loss of Coolant (including significant PWR

i. Closed Cooling Water System steam generator leaks) (inside and outside primary j. Containment containment) (large and small, including leak-rate

(1) Maintaining Integrity determination)

(2) Containment Ventilation System b. Loss of Instrument Air

(3) Inerting and deinerting c. Loss of Electrical Power (and/or degraded power sources)

k. Fuel Storage Pool Purification and Cooling d. Loss of Core Coolant Flow System e. Loss of Condenser Vacuum I. Main Steam System (reactor vessel to turbine) f. Loss of Containment Integrity m. Turbine-Generator System g. Loss of Service Water n. Condensate System (hotwell to feedwater h. Loss of Shutdown Cooling pumps, including demineralizers and resin i. Loss of Component Cooling System and Cool regeneration) ing to Individual Components o. Feedwater System (feedwater pumps to reactor j. Loss of Feedwater or Feedwater System vessel) Failure p. Makeup System (filtration, purification, and k. Loss of Protective System Channel water transfer) 1. Mispositioned Control Rod or Rods (and rod drops)

q. Service Water System m. Inability to Drive Control Rods r. Reactor Building Heating and Ventilation n. Conditions Requiring Use of Emergency Bora Systems tion or Standby Liquid Control System s. Control Room Heating and Ventilation o. Fuel Cladding Failure or High Activity in Systems Reactor Coolant or Offgas t. Radwaste Building Heating and Ventilation p. Fire in Control Room or Forced Evacuation of Systems Control Room u. Standby Gas Treatment System q. Turbine and Generator Trips v. Instrument Air System r. Other Expected Transients that may be w. Electrical System Applicable

(1) Offsite (access circuits) s. Malfunction of Automatic Reactivity Control

(2) Onsite System t. Malfunction of Pressure Cdntrol System (a) Emergency Power Sources (e.g., diesel u. Reactor Trip generator, batteries) v. Plant Fires (b) A.C. System w. Acts of Nature (e.g., tornado, flood, dam (c) D.C. System failure, earthquakes)

x. Nuclear Instrument System x. Irradiated Fuel Damage While Refueling y. Abnormal Releases of Radioactivity

(1) Source Range

(2) Intermediate Range

(3) Power Range z. Intrusion of Demineralizer Resin Into Primary System (BWR Plants) I

(4) TIP System 7. Procedures for Control of Radioactivity (For limit y. Reactor Protection System ing materials released to environment and limiting z. Rod Worth Minimizer personnel exposure)

1.33-5

a. Liquid Radioactive Waste System

(1) Pressurized Water Reactors

( I) Collection. Demineralizing. Filtering, Evaporating and Concentrating, (a) Containment Leak-Rate Tests and Neutralizing (b) Containment Isolation Tests

(2) Sampling and Monitoring (c) Containment Local Leak Detection Tests

(3) Discharging to Effluents (d) Containment Heat and Radioactivity b. Solid Waste System Removal Systems Tests

(1) Spent Resins and Filter Sludge Handling (e) Containment Tendon Tests and

(2) Baling Machine Operation Inspections

(3) Drum Handling and Storage (f) Service Water System Functional Tests (g) Main Steam Isolation Valve Tests c. PWR Gaseous Effluent System (hi Fire Protection System Functional Tests

(1) Collection. Storage. and Discharge (i) Boric Acid Tanks-Level Instrumenta tion Calibrations

(2) Sampling and Monitoring

(3) Air Ejector and Stack Monitoring (j) Emergency Core Cooling System Tests

(4) Ventilation Air Monitoring (k Control Rod Operability and Scram Time Tests d. BWR Air Extraction. Offgas Treatment. and (1) Reactor Protection System Tests and Other Gaseous Effluent Systems Calibrations

(1) Mechanical Vacuum Pump Operation (m) Permissi',es-Tests and Calibrations

(2) Air Ejector Operation (n) Refueling System Circuit Tests

(3) Packing Steam Exhauster Operation (o) Emergency Boration System Functional

(4) Sampling Tests

(5) Air Ejector. Ventilation. and Stack Monitor (p) DNB Checks and Incore-Excore Flux Monitor Correlations e. Radiation Protection Procedures (q) Emergency Power Tests (I) Access Control to Radiation Areas Includ. tr) Auxiliary Feedwater System Tests ing a Radiation Work Permit System (s) NSSS Pressurization and Leak

(2) Radiation Sur\e\s Detection

(3) Airborne Radioactiv.ity Monitoring (t) Inspection of Reactor Coolant System

(4) Contamination Control Pressure Boundary

(5) Respiratory Protection (u) Inspection of Pipe Hanger Settings

(6) Training in Radiation Protection (v) Control Rod Drive System Functional

(7) Personnel Monitoring Tests

(8) Bioassay Program (w) Heat Balance-Flux Monitor

(9) Implementation of ALARA Program Calibrations Ix) Pressurizer and Main Steam Safety f. Area Radiation Monitoring S)stem Operation Valve. Tests g. Process Radiation Monitoring System (y) Leak Deection Systems Tests Operation (z) Axial and Radial Flux Pattern Determi h. Meteorological Monitoring nations

8. Procedures for Control of Measuring and Test (aa) Area. Portable. and Airborne Radiation Equipment and for Surveillance Tests, Proce M on it or Calibrations dures. and Calibrations (bb) Process a. Procedures of a type appropriate to the cir Radiation Monitor Calibrations cumstances should be provided to ensure that tools, (cc) Environmental Monitor Calibrations gauges. instruments, controls, and other measuring (dd) Safety Valve Tests and testing devices are properly controlled, calib (ee) Turbine Overspeed Trip Tests rated. and adjusted at specified periods to maintain (ff) Water Storage Tanks-Level In accuracy. Specific examples of such equipment to be strumentation Calibration calibrated and tested are readout instruments, inter (2) Boiling Water Reactors lock permissive and prohibit circuits, alarm devices, sensors. signal conditioners, controls, protective cir (a) Containment Leak-Rate and Penetration cuits, and laboratory equipment. Leak-Rate Tests (b) Containment Isolation Tests b. Specific procedures for surveillance tests, in (c) Containment Vacuum Relief Valve spections. and calibrations should be written (imple Tests menting procedures are required for each surveillance (d) Containment Spray System Tests test. inspection, or calibration listed in the technical (e) Standby Gas Treatment System Tests specifications): (including filter tests)

1.33-6

(f) Service Water System Functional Tests c. Procedures for the repair or replacement of (g) Main Steam Isolation Valve Tests equipment should be prepared prior to beginning (h) Fire Protection System Functional Tests work. Such procedures for major equipment that is (i) Nitrogen Inerting System Tests expected to be repaired or replaced during the life of (j) Emergency Core Cooling System Tests the plant should preferably be written early in plant (k) Control Rod Operability and Scram Time life. The following are examples of such procedures Tests for major equipment:

(1) Reactor Protection System Tests and (1) Repair of PWR Steam Generator Tubes Calibrations (2) Replacement and Repair of Control Rod (m) Rod Blocks-Tests and Calibrations Drives (n) Refueling System Circuit Tests (3) Replacement of Recirculation Pump Seals (o) Liquid Poison System Tests (4) Replacement of Important Strainers and (p) Minimum Critical Heat Flux Checks and Filters Incore Flux Monitor Calibrations Repair or Replacement of Safety Valves

(5)

(q) Emergency Power Tests (6) Repair of Incore Flux Monitoring System (r) Isolation Condenser or RCIC Tests Replacement of Neutron Detectors

(7)

(s) NSSS Pressurization and Leak Detection (t) Inspection of Reactor Coolant System d. Procedures that could be categorized either as Pressure Boundary maintenance or operating procedures should be (u) Inspection of Pipe Hanger Settings developed for the following activities. Instructions (v) Control Rod Drive System Functional for these activities may be included in systems Tests procedures.

(w) Heat Balance

(1) Exercise of equipment that is normally idle (x) Autoblowdown System Tests (y) Leak Detection System Tests but that must operate when required (z) Axial and Radial Flux Pattern Determi (2) Draining and Refilling Heat Exchangers

(3) Draining and Refilling Recirculation Loop nations (aa) Area, Portable, and Airborne Radiation (4) Draining and Refilling the Reactor Vessel Monitor Calibrations (5) Draining and Refilling Steam Generators (bb) Process Radiation Monitor Calibrations (6) Removal of Reactor Head

(7) Disconnection and Reconnection of Wiring I (cc) Environmental Monitor Calibrations Penetrating Reactor Vessel Head (dd) Safety Valve Tests

(8) Demineralizer Resin Regeneration or (ee) Turbine Overspeed Trip Test Replacement (ff) Water Storage Tanks-Level In strumentation Calibrations e. General procedures for the control of mainte (gg) Reactor Building Inleakage Tests nance, repair, replacement, and modification work should be prepared before reactor operation is begun.

9. Procedures for Performing Maintenance These procedures should include information on areas such as the following:

a. Maintenance that can affect the performance

(1) Method for obtaining permission and clear of safety-related equipment should be properly pre planned and performed in accordance with written ance for operation personnel to work and for logging procedures, documented instructions, or drawings such work and appropriate to the circumstances. Skills normally (2) Factors to be taken into account, including possessed by qualified maintenance personnel may the necessity for minimizing radiation exposure to not require detailed step-by-step delineation in a pro workmen, in preparing the detailed work procedures.

cedure. The following types of activities are among those that may not require detailed step-by-step writ 10. Chemical and Radiochemical Control Procedures ten procedures: Chemical and radiochemical control procedures

(1) Gasket Replacement should be written to prescribe the nature and fre

(2) Trouble-Shooting Electrical Circuits quency of sampling and analyses, the instructions

(3) Changing Chart or Drive Speed Gears or maintaining water quality within prescribed limits, Slide Wires on Recorders and the limitations on concentrations of agents that may cause corrosive attack or fouling of heat-transfer b. Preventive maintenance schedules should be surfaces or that may become sources of radiation developed to specify lubrication schedules, inspec hazards due to activation. These procedures should tions of equipment, replacement of such items as fil specify laboratory instructions and calibration of lab ters and strainers, and inspection or replacement of oratory equipment. Extreme importance must be parts that have a specific lifetime such as wear rings. placed on laboratory procedures used to determine

1.33-7

concentration and species of radioactivity in liquids and gases prior to release, including representative sampling, validity of calibration techniques, and ade.

quacy of analyses.

UNITED STATES

NUCLEAR REGULATORY COMMISSION

FIRST CLASS MAIL

WASHINGTON, D.C. 20555-0001 POSTAGE AND FEES PAID

USNRC

PERMIT NO. G-67 OFFICIAL BUSINESS

PENALTY FOR PRIVATE USE, $300

PRNTED ON RECYCLED PAPER


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