Regulatory Guide 1.33: Difference between revisions

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{{Adams
{{Adams
| number = ML003739995
| number = ML13350A365
| issue date = 02/28/1978
| issue date = 01/31/1977
| title = Quality Assurance Program Requirements (Operation)
| title = Quality Assurance Program Requirements (Operation)
| author name =  
| author name =  
| author affiliation = NRC/RES
| author affiliation = NRC/OSD
| addressee name =  
| addressee name =  
| addressee affiliation =  
| addressee affiliation =  
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| license number =  
| license number =  
| contact person =  
| contact person =  
| document report number = RG-1.33, Rev 2
| document report number = RG-1.033, Rev. 1
| document type = Regulatory Guide
| document type = Regulatory Guide
| page count = 8
| page count = 8
}}
}}
{{#Wiki_filter:U.S. NUCLEAR REGULATORY  
{{#Wiki_filter:Revision 1 January 1977 U.S. NUCLEAR REGULATORY  
COMMISSION
COMMISSION
Revlklon 2 February 1978 REGULATORY  
* REGULATORY  
GUIDE OFFICE OF STANDARDS  
GUIDE OFFICE OF STANDARDS  
DEVELOPMENT  
DEVELOPMENT
REGULATORY  
REGULATORY  
GUIDE 1.33 QUALITY ASSURANCE  
GUIDE 1.33 QUALITY ASSURANCE  
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==A. INTRODUCTION==
==A. INTRODUCTION==
Appendix B, "Quality Assurance Criteria for Nu clear Power Plants and Fuel Reprocessing Plants," to 10 CFR Part 50, "Licensing of Production and Utili zation Facilities," establishes quality assurance re quirements for the operation of nuclear power plant safety-related structures, systems, and components.
Appendix B, "Quality Assurance Criteria for N2 r P~nis.'s, Ph:nl nr anfl Fns't R nrncetcinr'
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.


This regulatory guide describes a method acceptable to the NRC staff for complying with the Commis sion's regulations with regard to overall quality as surance program requirements for the operation phase of nuclear power plants. The Advisory Committee on Reactor Safeguards has been consulted concerning this guide and has concurred in the regulatory position.
svstems. and well as the "requirements" included in a standard.components.
 
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.
 
' cWhere conformance to the  


==B. DISCUSSION==
==B. DISCUSSION==
Subcommittee ANS-3,' Reactor Operations, of the American Nuclear Society Standards Committee de veloped ANSI N18.7-1972, which contained criteria for administrative controls for nuclear power plants dur ing operation.
reconimendatiotns-`.
of this regulatory puide is in-dicaited inn :.application without further qualifica- Subcommittee ANS-3. Reactor Operations.


This standard, along with ANSI N45.2-1971, "Quality Assurance Program Require ments for Nuclear Power Plants," was endorsed by Regulatory Guide 1.33. The dual endorsement was necessary in order for the guidance contained in the regulatory guide to be consistent with the require ments of Appendix B to 10 CFR Part 50; however, this dual endorsement caused some confusion among users. To clarify this situation, ANSI N18.7-1972 was revised so that a single standard would define the general quality assurance program "requirements" for the operation phase. This revised standard was approved by the American National Standards Com mittee NI8, Nuclear Design Criteria.
of the ...tion.-this indicates thle applicant will comply with the American Nuclear Society Standards of ANSI N18.7-1976/ANS-3.2.


It was sub sequently approved and designated N18.7-1976/
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.
-*Lines indicate substantive changes from previous issue.ANS-3.2, "Administrative Controls and Quality As surance for the Operational Phase of Nuclear Power Plants," by the American National Standards Insti tute on February 19, 1976. There had been some uncertainty with regard to the NRC staff's position when a regulatory guide en dorses, as an acceptable method, the "guidelines" as well as the "requirements" included in a standard.


The NRC staff has evaluated the guidelines contained in N18.7-1976/ANS-3.2 with respect to importance to safety. Revision I of this regulatory guide clarified the NRC staff's position on the "requirements" and "guidelines" included in ANSI N18.7-1976/ANS
This standard.
3.2. Where conformance to the recommendations of this regulatory guide is indicated in an application without further qualification, this indicates the appli cant will comply with the "requirements" of ANSI N18.7-1976/ANS-3.2, as supplemented or modified by the regulatory position of this guide.  Section 1, "Scope," of ANSI NI8.7-1976/ANS
3.2 states that this standard contains criteria for ad ministrative controls and quality assurance for nu clear power plants during the operational phase of plant life and that this phase is generally considered to commence with initial fuel loading, except for cer tain preoperational activities.


In this regard, a sepa rate regulatory guide addressing the quality assurance program for the preoperational phase will be issued.  Other regulatory guides may be issued or this regula tory guide may be revised, if necessary, to amplify the general requirements contained in this standard.
along with.\ANS1'" S
* .... 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.


Appendix A to this guide has been further revised as a result of additional'  
In this regard. a users. To is !
comments received on the guide and additional staff review. ,Copies may be obtained from American Nuclear Society, 555 North Kensington Avenue, La Grange Park, Illinois 6052
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 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.


===5. USNRC REGULATORY ===
It was sub.,e- standard.quently approved and designated N 18.7-1976/ANS-
GUIDES Comments shoukl be sent to the Secretary of the Commission.
Copic% ma. hbe obtained from American Nucle:r Sriciety.


US. Nuclear Regu Regulatory Guides ore issued to describe and make available to the Public methods latory Commission, Washington, D.C. 20555, Attention:
244 IVa.st 3.2. "Administrative Controls and Quality Assurance Ogden Avenue. Htinsdale.
Docketing and Service 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.
Illinoi 60521 USNRC REGULATORY
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.


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
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'.
3. Fuels and Materials Facilities a. Occupational Health o f a p ecr mit or license aby th e Co mni, son. 4. Environm etnt l 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)
9 Uec-aum.rt1n H-1lt the ,ssuineeo, cooitti itceotatternti or licenste byt the Catnrnnssittn
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 "to reflect new information or experience.
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.


This guide was revised as a result of divisions should be made in writing to the US. Nuclear Regulatory Commission.
JS appropriate.


eubltantive comments received from the Public and additional staff review. Washington, D.C. 20555. Attention Director.
to ACCOMniUSjtIA
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.


Division of Document Coistrol.
will he. Lid' divst'ions'
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.


C. REGULATORY
Appendix A lists typical safety-related activities that should be covered by written procedures but does not provide a complete listing of needed procedures.
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 N18.7-1976/ANS-3.2 requires the prep aration of many procedures to carry out an effective quality assurance program. Appendix A, "Typical Procedures for Pressurized Water Reactors and Boil ing Water Reactors," to this regulatory guide should be used as guidance to ensure minimum procedural coverage for plant operating activities, including re lated 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.
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.


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 contain proce dures that are not applicable to an applicant because of the configuration of the nuclear power plant. The procedures listed in Appendix A may be combined, separated, or deleted to conform to the applicant's procedures plan. 2. Throughout ANSI NI8.7-1976/ANS-3.2, other documents required to be included as a part of this standard are identified at the point of reference.
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.


The specific acceptability of these standards listed in ANSI N18.7-1976/ANS-3.2 has been addressed in the latest revision of the following regulatory guides: 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. I I N45.2.13 N18. 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 Design and Procurement Phase of Nuclear Power Plants," (Grey Book) and WASH 1309, "Guidance on Quality Assurance Re quirements During the Construction Phase of Nuclear Power Plants," (Green Book)and will be endorsed by a regulatory guide upon its approval as an ANSI standard.
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:
a. The results of actions taken to correct deficiencies that affect nuclear safety and occur in facility equipment.


3. Section 4.3.4, "Subjects Requiring Independ ent Review," Item (3) states, in part, that changes to the technical specifications or license amendments re lated to nuclear safety are required to be reviewed by the independent review body prior to implementation.
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.


It should be noted that proposed changes to technical specifications or license amendments should be re viewed by the independent review body prior to their submittal to the Commission for approval.
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
.,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.


4. Section 4.5, "Audit Program," of ANSI N18.7-1976/ANS_3.2 states that audits of selected aspects of operational phase activities shall be per formed 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 com pleted within a period of 2 years. In amplification of this requirement, the following program elements should be audited at the indicated frequencies:
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.
a. The results of actions taken to correct de ficiencies that affect nuclear safety and occur in facil ity equipment, structures, systems, or method of operation-at least once per 6 months. b. The conformance of facility operation to pro visions contained within the technical specifications and applicable license conditions-at least once per 12 months. c. The performance, training, and qualifications of the facility staff-at least once per 12 months. 5. The guidelines (indicated by the verb "should")
of ANSI N18.7-1976/ANS-3.2 contained in the following sections have sufficient safety impor tance to be treated the same as the requirements (in dicated by the verb "shall") of the standard:
a. Section 4.4-The guidelines concerning re view activities of the onsite operating organization, except the guideline that refers to screening subjects of potential concern.


b. Section 5.2.3-The guideline concerning re view and updating of standing orders.  c. Section 5.2.4-The guideline concerning re view, 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.
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.


f. Section 5.2.19(2)-The guideline for check ing plant operating procedures during the testing pro gram. g. Section 5.2.19. 1-The guidelines for preop erational tests, except the guideline that refers to a 1.33-2 run-in period for 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.


In addition to these guidelines, the prerequisite steps for each equipment
except for the guidelines that address (I) a separate state-ment of applicability in Section 5.3.2(2).
-test should be completed prior to the commencement of the preoperational test.  h. Section 5.3.2-The guidelines that describe the content (excluding format) of procedures, except for the guidelines that address (1) a separate state ment of applicability in Section 5.3.2(2), (2) inclu sion of references in procedures, as applicable, in Section 5.3.2(3), and (3) inclusion of quantitative control guides in Section 5.3.2(6).
(2) inclusion of references in procedures, as applicable, in Section 5.3.2(3).
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.
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 title in Section 5.3.9.1 (1); the inclusion of symptoms to aid in iden-tification in Section 5.3.9.1(2);
j. Section 5.3.9.1-The guidelines that describe the content (excluding format) for: the tith,! in Section 5.3.9.1(1):
automatic actions in Section 5.3.9.1(3);
the inclusion of svmploms to aid in iden-tificaltion in Section 5.3.9.1(2):
immediate operator action, excluding those guidelines contained in the examples, in Section 5.3.9.1(4);
automatic actions in Section 5.3.9.1(3):
and subsequent operator ac tions in Section 5.3.9.1(5).
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. This guide reflects current NRC practice.
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.


There fore, except in those cases in which the applicant proposes an acceptable alternative method for com plying with the specified portions of the Commis sion's regulations, the method described herein is being and will continue to be used in the evaluation of submittals for operating license applications until this guide is revised as a result of suggestions from the public or additional staff review.1.33-3 APPENDIX A TYPICAL PROCEDURES  
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  
FOR PRESSURIZED  
WATER REACTORS AND BOILING WATER REACTORS The following are typical safety-related activities that should be covered by written procedures.
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. Administrative Procedures a. Security and Visitor Control b. Authorities and Responsibilities for Safe Opera tion 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 Personnel I. Plant Fire Protection Program m. Communication System 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 start up) 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)  
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 Operation 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 Equipment Operation I. Refueling and Core Alterations  
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 oper ation should be prepared, as appropriate, for the fol lowing systems: 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  
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 ====
====f. Containment====
(1) Maintaining Containment Integrity  
(!) 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)
(2) Special Containment Systems (a) Atmosphere (b) Subatmospheric (c) Double-Wall Containment with Controlled Interspace (d) Ice Condenser  
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  
(3) Containment Ventilation System (4) Containment Cooling System g. Atmosphere Cleanup Systems h. Fuel Storage Pool Purification and Cooling Sys tem i. Main Steam System j. Pressurizer Pressure and Spray Control Systems k. Feedwater System (feedwater pumps to steam generator)  
1. Auxiliary Feedwater System m. Service Water System n. Chemical and Volume Control System (includ ing 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 (1) Source Range (2) Intermediate Range (3) Power Range (4) Incore System u. Reactor Control and Protection System  


====v. Hydrogen Recombiner ====
====v. Hydrogen Recombiner====
4. Procedure for Startup, Operation, and Shutdown of Safety-Related BWR Systems 1.33-4 Instructions for energizing, filling, venting, drain ing, startup, shutdown, and changing modes of oper ation should be prepared, as appropriate, for the following systems: a. Nuclear Steam Supply System (Vessel and Recirculating System) b. Control Rod Drive System c. Reactor Cleanup System d. Liquid Poison System (Standby Liquid Con trol 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  
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.


====j. Containment ====
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)
(1) Maintaining Integrity
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)
(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)
x. Irradiated Fuel Damage While Refueling y. Abnormal Releases of Radioactivity
o. Feedwater System (feedwater pumps to reactor vessel) p. Makeup System (filtration, purification, and water transfer)
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.
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 (1) 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 (1) 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 Conditions Since these procedures are numerous and corre spond to the number of alarm annunciators, the pro cedures are not individually listed. Each safety related annunciator should have its own written procedure, which should normally contain (1) the meaning of the annunciator, (2) the source of the sig nal, (3) the immedate action that is to occur automat ically, (4) the immediate operation action, and (5) the long-range actions.


6. Procedures for Combating Emergencies and Other Significant Events a. Loss of Coolant (including significant PWR steam generator leaks) (inside and outside primary containment) (large and small, including leak-rate determination)  
Evaporating and Concentrating, and Neutralizing
b. Loss of Instrument Air c. Loss of Electrical Power (and/or degraded power sources) d. Loss of Core Coolant Flow e. 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 1. 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 Reactor 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 Applicable s. Malfunction of Automatic Reactivity Control System t. Malfunction of Pressure Cdntrol System u. Reactor Trip v. Plant Fires w. Acts of Nature (e.g., tornado, flood, dam failure, earthquakes)  
(2) Sampling and Monitoring
x. Irradiated Fuel Damage While Refueling y. Abnormal Releases of Radioactivity z. Intrusion of Demineralizer Resin Into Primary System (BWR Plants) 7. Procedures for Control of Radioactivity (For limit ing materials released to environment and limiting personnel exposure)1.33-5 I
(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
a. Liquid Radioactive Waste System ( I) Collection.
(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
(4) Protective Clothing (5) Radiation Work Permit Procedure r, Area Radiation Monitoring System Operation g. Process Radiation Monitoring System Opera-tion h. Meteorological Monitoring
8. Procedures for Control of Measuring and Test Equipment and for Suncillance Tests. Procedures.


Demineralizing.
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.


Filtering, Evaporating and Concentrating, and Neutralizing
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.
(2) Sampling and Monitoring
(3) Discharging to Effluents b. Solid Waste System (1) Spent Resins and Filter Sludge Handling (2) Baling Machine Operation
(3) Drum Handling and Storage c. PWR Gaseous Effluent System (1) (2) (3) (4)Collection.


Storage. and Discharge Sampling and Monitoring Air Ejector and Stack Monitoring Ventilation Air Monitoring d. BWR Air Extraction.
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):
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
(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.


Offgas Treatment.
Skills normally possessed by qualified maintenance personnel may not require detailed step-by-step delineation in a procedure.


and Other Gaseous Effluent Systems (1) (2) (3) (4) (5)Mechanical Vacuum Pump Operation Air Ejector Operation Packing Steam Exhauster Operation Sampling Air Ejector. Ventilation.
The following types of activities are among those that may not require detailed step-by-step written procedures:
(1) Gasket Replacement
(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
'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.


and Stack Monitor e. Radiation Protection Procedures (I) Access Control to Radiation Areas Includ.  ing a Radiation Work Permit System (2) Radiation Sur\e\s (3) Airborne Radioacti
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
(3) Draining and Refilling Recirculation Loop (4) Draining and Refilling the Reactor Vessel (5) Draining and Refilling Steam Generators
(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.


====v. ity Monitoring ====
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.
(4) Contamination Control (5) Respiratory Protection
(6) Training in Radiation Protection
(7) Personnel Monitoring
(8) Bioassay Program (9) Implementation of ALARA Program f. Area Radiation Monitoring S)stem Operation g. Process Radiation Monitoring System Operation h. Meteorological Monitoring
8. Procedures for Control of Measuring and Test Equipment and for Surveillance Tests, Proce dures. and Calibrations a. Procedures of a type appropriate to the cir cumstances should be provided to ensure that tools, gauges. instruments, controls, and other measuring and testing devices are properly controlled, calib rated. and adjusted at specified periods to maintain accuracy.


Specific examples of such equipment to be calibrated and tested are readout instruments, inter lock permissive and prohibit circuits, alarm devices, sensors. signal conditioners, controls, protective cir cuits, and laboratory equipment.
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.


b. Specific procedures for surveillance tests, in spections.
These procedures should specify laboratory instructions and calibration of laboratory equipment.


and calibrations should be written (imple menting procedures are required for each surveillance test. inspection, or calibration listed in the technical specifications):
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.
(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 Inspections (f) Service Water System Functional Tests (g) Main Steam Isolation Valve Tests (hi 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) Permissi',es-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 tr) 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 Tests (w) Heat Balance-Flux Monitor Calibrations Ix) Pressurizer and Main Steam Safety Valve. Tests (y) Leak Deection Systems Tests (z) Axial and Radial Flux Pattern Determi nations (aa) Area. Portable.


and Airborne Radiation M on it or Calibrations (bb) Process Radiation Monitor Calibrations (cc) Environmental Monitor Calibrations (dd) Safety Valve Tests (ee) Turbine Overspeed Trip Tests (ff) Water Storage Tanks-Level In strumentation Calibration
and ade-quacy of analyses.1.33-7 UNITECV STATES NUCLE~AR REGUiLATORY
(2) Boiling Water Reactors (a) Containment Leak-Rate and Penetration Leak-Rate Tests (b) Containment Isolation Tests (c) Containment Vacuum Relief Valve Tests (d) Containment Spray System Tests (e) Standby Gas Treatment System Tests (including filter tests)1.33-6 (f) Service Water System Functional Tests (g) Main Steam Isolation Valve Tests (h) Fire Protection System Functional Tests (i) Nitrogen Inerting System Tests (j) Emergency Core Cooling System Tests (k) Control Rod Operability and Scram Time Tests (1) Reactor Protection System Tests and Calibrations (m) Rod Blocks-Tests and Calibrations (n) Refueling System Circuit Tests (o) Liquid Poison System Tests (p) Minimum Critical Heat Flux Checks and Incore Flux Monitor Calibrations (q) Emergency Power Tests (r) Isolation Condenser or RCIC 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 Tests (w) Heat Balance (x) Autoblowdown System Tests (y) Leak Detection System Tests (z) Axial and Radial Flux Pattern Determi nations (aa) Area, Portable, and Airborne Radiation Monitor Calibrations (bb) Process Radiation Monitor Calibrations I (cc) Environmental Monitor Calibrations (dd) Safety Valve Tests (ee) Turbine Overspeed Trip Test (ff) Water Storage Tanks-Level In strumentation Calibrations (gg) Reactor Building Inleakage Tests 9. Procedures for Performing Maintenance a. Maintenance that can affect the performance of safety-related equipment should be properly pre planned and performed in accordance with written procedures, documented instructions, or drawings appropriate to the circumstances.
COMMISSION
 
WA%.INGTON, D. C. 20555 OFFICIAL BUSINESS I'( NALTY IFOR PRIVAITE USE. $300 POSTAGE AN40 PIES PAID U.S NUCLEAR REGULATORY
Skills normally possessed by qualified maintenance personnel may not require detailed step-by-step delineation in a pro cedure. The following types of activities are among those that may not require detailed step-by-step writ ten procedures:
COMMISSION
(1) Gasket Replacement
1.33-8}}
(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 fil ters 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 be written early in plant life. The following are examples of such procedures for major equipment:
(1) Repair of PWR Steam Generator Tubes (2) Replacement and Repair of Control Rod Drives (3) (4) Filters (5) (6) (7)Replacement of Recirculation Pump Seals Replacement of Important Strainers and Repair or Replacement of Safety Valves Repair of Incore Flux Monitoring System Replacement of Neutron Detectors d. Procedures that could be categorized either as maintenance or operating procedures should be developed for the following activities.
 
Instructions for these activities may be included in systems procedures.
 
(1) Exercise of equipment that is normally idle but that must operate when required (2) Draining and Refilling Heat Exchangers
(3) Draining and Refilling Recirculation Loop (4) Draining and Refilling the Reactor Vessel (5) Draining and Refilling Steam Generators
(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 mainte nance, repair, replacement, and modification work should be prepared before reactor operation is begun.  These procedures should include information on areas such as the following:
(1) Method for obtaining permission and clear ance 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.
 
10. Chemical and Radiochemical Control Procedures Chemical and radiochemical control procedures should be written to prescribe the nature and fre quency of sampling and analyses, 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.
 
These procedures should specify laboratory instructions and calibration of lab oratory equipment.
 
Extreme importance must be placed on laboratory procedures used to determine 1.33-7 concentration and species of radioactivity in liquids and gases prior to release, including representative UNITED STATES NUCLEAR REGULATORY
COMMISSION  
WASHINGTON, D.C. 20555-0001 OFFICIAL BUSINESS PENALTY FOR PRIVATE USE, $300 sampling, validity of calibration techniques, and ade.  quacy of analyses.
 
FIRST CLASS MAIL POSTAGE AND FEES PAID USNRC PERMIT NO. G-67 PRNTED ON RECYCLED PAPER}}


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Revision as of 13:55, 17 September 2018

Quality Assurance Program Requirements (Operation)
ML13350A365
Person / Time
Issue date: 01/31/1977
From:
NRC/OSD
To:
References
RG-1.033, Rev. 1
Download: ML13350A365 (8)
v • d • e


Revision 1 January 1977 U.S. NUCLEAR REGULATORY

COMMISSION

  • REGULATORY

GUIDE OFFICE OF STANDARDS

DEVELOPMENT

REGULATORY

GUIDE 1.33 QUALITY ASSURANCE

PROGRAM REQUIREMENTS (OPERATION)

A. INTRODUCTION

Appendix B, "Quality Assurance Criteria for N2 r P~nis.'s, Ph:nl nr anfl Fns't R nrncetcinr'

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.

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.

' cWhere conformance to the

B. DISCUSSION

reconimendatiotns-`.

of this regulatory puide is in-dicaited inn :.application without further qualifica- Subcommittee ANS-3. Reactor Operations.

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.

along with.\ANS1'" S

  • .... 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 !

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 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-

Copic% ma. hbe obtained from American Nucle:r Sriciety.

244 IVa.st 3.2. "Administrative Controls and Quality Assurance Ogden Avenue. Htinsdale.

Illinoi 60521 USNRC REGULATORY

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.

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'.

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.

to ACCOMniUSjtIA

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'

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.

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.

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.

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:

a. The results of actions taken to correct deficiencies that affect nuclear safety and occur in facility equipment.

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.

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

.,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.

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.

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.

except for the guidelines that address (I) a separate state-ment of applicability in Section 5.3.2(2).

(2) inclusion of references in procedures, as applicable, in Section 5.3.2(3).

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):

the inclusion of svmploms to aid in iden-tificaltion in Section 5.3.9.1(2):

automatic actions in Section 5.3.9.1(3):

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

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.

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

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)

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)

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

(2) Sampling and Monitoring

(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

(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

(4) Protective Clothing (5) Radiation Work Permit Procedure r, Area Radiation Monitoring System Operation g. Process Radiation Monitoring System Opera-tion h. Meteorological Monitoring

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.

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.

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):

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

(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.

Skills normally possessed by qualified maintenance personnel may not require detailed step-by-step delineation in a procedure.

The following types of activities are among those that may not require detailed step-by-step written procedures:

(1) Gasket Replacement

(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

'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.

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

(3) Draining and Refilling Recirculation Loop (4) Draining and Refilling the Reactor Vessel (5) Draining and Refilling Steam Generators

(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.

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.

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.

These procedures should specify laboratory instructions and calibration of laboratory equipment.

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.

and ade-quacy of analyses.1.33-7 UNITECV STATES NUCLE~AR REGUiLATORY

COMMISSION

WA%.INGTON, D. C. 20555 OFFICIAL BUSINESS I'( NALTY IFOR PRIVAITE USE. $300 POSTAGE AN40 PIES PAID U.S NUCLEAR REGULATORY

COMMISSION

1.33-8


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