ML17297A379

Forwards List of Reg Guides Effective as of Feb 1981,in Response to .Guides Are Not Regulations & Compliance Is Not Required

ML17297A379
Person / Time
Site:	Palo Verde
Issue date:	04/21/1981
From:	Tedesco R Office of Nuclear Reactor Regulation
To:	Van Brunt E ARIZONA PUBLIC SERVICE CO. (FORMERLY ARIZONA NUCLEAR
References
NUDOCS 8104270462
Download: ML17297A379 (34)

Text

APR 2 I

)98)

Docket Nos.:

STN 50-528/529/530 Mr. E.

E.

Van Brunt, Jr.

Vice President -,Nuclear Projects Arizona Public Service Company P. 0.

Box 21666

'hoenix.

Arizona 85036 (p

,'; a<g(h, j Ar.'1221991~

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~o(X DISTRI 8UTION:

Docket File 50-528/529/530 LPDR PDR NSIC TERA LBA'3 Files RLTedesco FJMi ragl i a JDKerri gan JLee RBaer

SUBJECT:

NRC CRITERIA FOR REGULATORY GUIDES UPGRADES In response to your letter dated March 9, 1981, we have enclosed, a list of NRC Regulatory Guides which were effective as of February, 1981.

As you stated fn your-letter, the possibility does. exist that you will be requested to upgrade Palo Verde to a different Regulatory Guide or revision than listed fn your FSAR.

The decision on whether'or not a particular Regulatory Guide is to be made applicable to OL's fs normally contai ned in the "Implementation" section of each Guide.

The categorization referred to in your letter was pj'fmari~ly used as an abbm'vfated method of referring to these fmplementation requirements.

Therefore, reading the "Implementation" section of the f.,'ufdes is a more accurate method of determining if the guide is applicable to your facility.

Regulatory Guides are not substitutes for regulations, and compliance with them is not required.

If you have been requested to implement a Regulatory Guide and the "Implementation" section of the guide does not prohibit this request, you may request t)at the staff re-evaluate its position.

However, since Regulatory Guides delinate methods acceptable to the staff for complying with Commission regulations, a basis for substituting alternate methods must be provfded.

If you have any additional questions on this matter, please contact us.

Sf ncerely,

+%oat e>gaea Sy.

Robert 'L. Tedesco la;ze42v II<~

A cc:

See next page.

Robert L. Tedesco, Assistant Director for Licensing Division of Licensing OFFICE/

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UNITED STATES t

NUCLEAR REGULATORY COMMISSJON LVASHINGTOhf D C 20~05 APR 2 i 198',

Docket Nos.:

STN 50-528/529/530 Mr.

E.

E.

Van Brunt, Jr, Vice President

- Nuclear Projects Arizona Public Service Company P.

0.

Box 21666 Phoenix, Arizona 85036 Dear Mr.

Van Brunt:

SUBJECT:

NRC CRITERIA FOR REGULATORY GUIDES UPGRADES In response to your letter dated March 9, 1981, we have enclosed a list of NRC Regulatory Guides which were effective as of February, 1981.

As you stated in your letter, the possibility does exist that you will be requested to upgrade Palo Verde to a different Regulatory Guide or revision than listed

-in your FSAR.

The decision on whether or not a particular Regulatory Guide is to be made applicable to OL's is normally contained in the "Implementation" section of each Guide.

The categorization referred to in your letter was primari ly used as an abbreviated method of referring to these implementation requirements.

Therefore, reading the "Implementation" section of the Guides is a more accurate method of determining if the guide is applicable to your faci'lity.

Regulatory Guides are not substitutes for regu')ations, and compliance with them is not required.

If you.have been requested to implement a Regulatory Guide and the "Implementation" section of the guide does not prohibit this request, you may request that the staff re-evaluate its position.

However, since Regulatory Guides delinate methods acceptable to the staff for complying with Commission regulations, a basis for substituting alternate methods must be provided.

If you have any additional questions on this matter, please contact us.

Sincerely, Robert L. Tedesco, Assistant Director for Licensing Division of Licensing

t f

Mr. E.

E.

Van Brunt, Jr.

Vice President - Construction Projects Arizona Pub]ic Service Company P. 0. Box 21666

Phoenix, Arizona 85036 CC:

Arthur C. Gehr, Esq.

Snell 6 Wilmer 3100 Valley Center

Phoenix, Arizona 85073 Charles S. Pierson Assistant Attorney General 200 State Capitol 1700 West Washington Phoenix, Arizona 85007 David N. Barry, Esq.,

Senior Counsel Charles R. Kocher, Esq., Assistant Counsel Southern California Edison'ompany.

P. 0.

Box 800

Rosemead, California 91770 Margaret Walker Deputy Director of Energy Programs Economic Planning and Development Office 1700 West Washington Phoenix, Arizona 85007 William Primm Assistant Attorney General Bataan Memorial Building Santa Fe, New Mexico 87503 Resident Inspector Palo Verde/NPS U.S. Nuclear Regulatory Commission P. 0. Box 21324 Phoenix, Arizona 85001 Hs. Patricia Lee Hourihan 6413 S. 26th Street Phoenix, Arizona 85040

I l

l

US. NUCLEAR REGULATORYCOMMISSION REGULATORY GUIDE SERIES DIVISION 1 - POWER REACTORS TABLE OF CONTENTS This table of content lists every revision of each regulatory guide in Division I arith the date it was issued.

If the la(est version of a guide (as of the date of this tab)e of contents) was issued for early comment, this is so noted.

Division 1, one of tcn broad divisions in which regulatory guides are issued, contains those guides that were developed I'or power reactors.

There may also be some guides issued in other divisions that would be of interest to those whose primary concern is in the area of power reactors.

Accordingly, this issue of the table of contents includes, for the first time, a listing of regulatory guides issued in the other divisions that the NRC staf'f has identified as possibly of interest to rrcipicnts nf Disision I guides.

This listing vrill be uprlatr1 from time to time, and suggestions for additions to it,are encouraged.

IIost regulatory guides contain a section headed "Implementation" that is intended to provide informatron to applicants and licensees regarding the NRC stai'f's p)ans for using the guide.

If a guide does not contain such a section orif detailed information is needed on the staff's plans for using a regulatory guide with respect to a specific permit or license or application therefor, requests for such information should be addressed to the appro-priate licensing project manager in the Office of Nuclear Reactor Regulation or Office of Nuclear Material Safety and Safeguards.

At an appropriate point in the devclopmcnt of a new regulatory guide or a proposed revision to an existing

guide, the guide and the associated value/impact statement are issued in draft form to involve the public in the early stages of the development of a regulatory position.

These drafts have not received complete staff review and do not represent an official NRC staff position.

They are temporarily identified by their task number and issued to the same distribution list that is used for pubHshed guides in each division.

Draft guides issued in this division are listed in this issue of the table of contents.

All regulatory guides, including draft guides, proposed revisions, and all published revisions, may be examined at the Commission's Public Document Room at 1717 H Street NW., Washington, D.C.

Regulatory guides are not copyrighted and Commission approval is not required to reproduce them.

Requests for single copies of draft guides and proposed revisions should be made in writing to the U.S. Nuclear Regulatory Commission, Washington, D.C.

20555, Attention:

Director, Division of Technical Information and Document Control.

Copies of active guides may be purchased at the current Government Printing Office (GPO) price.

A subscription serv-ice for future guides in specific divisions is available through the Government Printing Office.

Information on subscription service and current GPO prices may be obtained by writing to the U.S. Nuclear Regulatory Commis-sion, Washington, D.C. 20555, Attention: PubHcations Sales Manager.

R

'Is Guides Number 1.1 Net Positive Suction Head for Emer ency Core Cooling and Containment Heat Removal System Pumps (Safety Guide 1) 1.2 Thermal Shock to Reactor Pressure Vessels (Safety Guide 2) 1.3 Assumptions Used for Evaluating. the Potential Radiological Consequences of a Loss-of-Coolant Accident for BoIHng Watet Reactors Issued Year/Month e

70/11 VO/11 VO/11 V3/06 74/06 Qi 1.4 Assumptions Used for Evaluating the Potential Radiological Consequences of a Loss-of-Coolant Accident for PressurLted Water Reactors 1

2 70/11 73/06 V4/06

~ +

C

Isxurct You/Month 1.5 1.6 l.'7 Ass~onons Used for Evaluating the Potential Radiological Consequences f a St.

L~fa Br eak Accident for Boiling Water Reactors (Safety Guide 5)

Indcpcndcncc Between Redundant Standby (Onsftc) Power Sources and Between Their Distribution Systems (Safety Guide 6)

Contro] of CombustLble Gas Concentrations in Contaiament Following a Loss'-Coolant Accident 1

2 Tl/03 Tl/03 71/03 76/09 78/ll Personnel SeIectioa aad Training I 9 Sel~d n Desig

~d QuaLrl~doa of Dfescl-Generator Uaf Used as Standby (Onsite) E1ectric Power Systems at NIIc1~ar Power Plants 1.10 Mechanical (Cadweld) SpUces in Reinforciag Bars of Category I Con-crete Structures 1.11 Instr~eat Lines Penetrating Primary Reactor Containment (Safety Gufde 11)

Supple=eat to Safety Guide 11, Backfftthg Corsiderations

1. 12 Instrumentatioa for Earthquakes 1.13 Spent Fuel Storage Facility Design Basis (For Comment) 1.14 Reactor Coolant Pump Flywheel Integrity (For Comment) 1.15 Testing of Reinforcing Bars tor Category I Concrete Structures 1.16 Reporting of Operating InformationAppendh A Tcchnical Specfffcatfoas (For Comment) 1.17 Protectfon of Nuclear Power Plants Against Industrial Sabotage 1.1d Structural Acceptance Test for'oncrete Primary Reactor Contafnmcnts I

1-R I

2 1

2 3

4 71/03 75/09 77/05 TI/03 78/11 79/12 Tl/03 T3/01 71/03 72/02 Tl/03 74/04

'Tl/03 75/12 71/10 75/0d TI/10 72/12 71/10 T3/10 74/09 75/01 TS/08 71/10 73/06 Tl/10 72/12 1.19 1.20 NondestructLve Exaraiaatfon of Prfmary Containment LLner Welds (Safety Guide 19)

Comprehensfve Vibration hssessmeat Program for Reactor Internals During PreoperatLoaal aad InitialStartup Testing Tl/12 72/0$

71/12 T5/06 76/Im 1.21 Measuring, Evaluating, and Reportiag Radfoactfvfty fa Soud Wastes and Releases of Radioactive Naterfals ia Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants 1.22 PeriodLc Testing of Protectfoa System Actuation Functions (Safety Gufde 22) 1.23 Onsfte Meteorological Programs (Safety Guide &)

Tl/12 74/I 1.24 Assumptfoas Used for Evaluating the PotentfaI RadfoIogical Consequences of a Pressurized Water Reactor Radfoactive Gas Storage Tank FaQure (Safety Guide 24) r 2

TM=

I rrr5 Ass um ptfons Used for Evaluating the potentfal Rad' rr'f Consequences ot - F i Fmdffag Accident fn the Fuel Haadffag aad Stor"ge Fac"'uty tor BoQLag aad Pressurfaed Water Raa.-mrs (3&cay Cu'"c 25)

Rcv.

tc=~

Year/Meed 1.25 I 2T Oluaffty Croup C~sfifcatfoas and Standards fot Water-, Steam-,

acct Radioactive-Waste-Coatai ing Components of Nuclear Power Plants (For Comment)

Ultimate Heat Sfnlt tor Nuclear Power PLats (For Comment)

Qua1fty Assurance Mgram Requirements (Design aad Consmuc~c)

I 2

3 I

2 V2/03 T4/09 T5/Od Td/02 T2/03 T4/03 Vd/Ol V2/Od TS/03 V9/02 I.K Seismic Design ClassftLcatfoa 1.30 Quaffty Assurance Requirements tor the IastaQatfon, Iaspection, aad Testfag of'nstrumeatation and Electric Zqufpmeat (Safety Gufcfe 30) 1.3I Control ot Ferrite Coateat in Stainless Steel Weld Metal I

2 3

V~Od Ti/OS Vd/0" T8/09 V2/06 T3/06 TT/05 T8/04 1.32 Criteria tor Satety-Related Electric Power Systems tor Nuclei" Power Plants I

2 VIVOS Td/03 TT/02 1.33 Quality Assurance Program Requfrements (Operatfon) 1.34 Conttol cif Electroslag Weld'Pzapertfes 1.35 Iaservfce Iaspec~ ot Uagrouted Tendons fa Prestressed Conc".ete Contafa-meat Structures C

1.35 Noametallfc Thermal Insula&a tor Austenftfc Stainless Steel I;3V Quaffty Assurance Requfremeats.tor C~cg of Fluid Systems ancl Associated Components of Water Coolecf Nulcear Power Plants I 38 Quaffty Assurance Requfremeats tot Packaging,

Shfppfag, Receivwg,

Storage, and HaacQLag ot Items tor Water-Cooled Nuclear Power P~ts I

2 T2/ll VT/02 i8/02 TQI2 T3/02 T4/06 Td/01 V3/03 Td/10 VT/05 1.39 Housekeeping Requirements for Water Cooled Nuclear Po~er Plants 1.40 Qualftfcatfoa Tests of Continuous-Duty Rotors Installed Inside the Coatafa-ment of Water-Cooled Nuclear Power Pfaats 1.4l Preoperatfonal Testing of Redcuufant On Sita Recmic Power Systems to Verity Proper Load Gsoup Assfgameats 1.42 (WithdrawnSee 41 FR 11891, 3/~5) 1.43 Conttol ot Stainless Steel Weld Claddfag of'ow-ALLoy Steel Components 1.44 Control ot the Use of Sensitized Staialess Steel 1.45 Reactot'oolant Pressure Boundary Leakage Detect~a Systems 2

T3/03 Td/10

- ~.,Pi/09 i3/05 T3/05

, T3/05

Number Title issued Ye~/htcoth 1.46 Protection Against Pipe Whip Inside Containment I.47 Bypassed and Inoperable Status Indication for Nuclear Power Plant Safety-Systems 1.48 Design Limits and Loading Combinations for Seismic Category I Fluid System Components 1.49 Power Levels of Nuclear Power Plants 1.50 Control of Preheat Temperature for Welding of Low-Alloy Steel I.SI (Withdraws--See 40 FR 30510, 7/21/75) 1.52 Design, Testing, and Maintenance Criteria for Post Accident Engineered-Safety-Feature Atmosphere Cleanup System Air Filtration and Adsorption Units of Light-Water-Cooled Nulear Power Plants 1.53 Appncation of the Single-Failure Criterion to Nuclear Power Plant Protection Systems 1.54 Quality Assurance Requirements for Protective Coatings Applied to Water-Cooled Nuclear Power Plants 73/05 V3/05 73/05 V3/12 73/05 V3/06

?6/07 78/03 73/06 73/06 1.55 Concrete Placement in Category I Structures 1.56 Maintenance of Water Purity in Boiling Water Reactors (For Comment) 1.57 Design Limits and Loading Combinations for Metal Primary Reactor Contain-ment System Components 1.58 Qualification of Nuclear Power Plant Inspection, Examination, and Testing Personnel 1.59 Design Basis Hoods for Nuclear Power Plants 1.60 Design Response Spectra for Seismic Design of Nuclear Power Plants 1.61 Damping Values for Seismic Design of Nuclear Power Plants 1..62 Manual Initiation of Protective Actions 1.63 Electric Penetration Assemblies in Containment Structures for Light-Water-Cooled Nuclear Power Plants 73/06 73/06 78/OV

?3/05 V3/08 80/09 73/08 V6/04 77/08 V3/10 73/12 i V3/10 73/10 V3/10 77/05 V8/07 1.64 Quality Assurance Requirements for the Design of Nuclear Power Plants 1.65 Materials and Insoections for Reactor Vessel Closure Studs 1.66 (Withdrawn-See 42 FR 54478, 10/06/77) 1.67 Installation of Overpressure Protection Devices 1.68 Inithl Test Programs r Water-Cooled Reactor Power Plants 1.68.1 Preoperational and Initial Startup TesMg of Feedwater and Conden-sate Systems for BoQing Water Reactor Power Plants 1

2 73/10 75/02 V6/06 S/Io 73/10 73/11 77/01 V8/08 V5/12 VV/01

Th>

1.68.2 Initial Startup Test Program to Demonstrate Remote Shutdown Capability for Water-Cooled Nuclear Power Plants 1.69 Concrete Radiation Shields for Nuclear Power Plants 1.70 Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants 1.71 Welder Qualification for Areas of Limited AcccssibQity 1.72 Spray Pond Piping Made from Fiberglass-Reinforced Thermosetting Resin 1.73 Qualification Tests of Electric Valve Operators Installed Inside the Containment of Nuclear Power Plants 1.74 Quality Assurance Terms and Definitions 1.75 Physical Independence of Electric Systems 1.76 Design Basis Tornado for Nuclear Power Plants 1.77 Assumptions Used for Evaluating a Control Rod Ejecuon Accident for Pressurized Water Reactors inc~

Year/t.toad 77/Ol V8/07 V3/12 72/02 72/10 75/09 78/11 73/I 2 73/12 78/01 78/11 74/01 74/02 74/02 V5/Ol 78/09 74/04 74/05 1.78 1.79 1.80 1.81 Assumptions for Evaluating the Habitability of a Nuclear Power Plant Control Room During a Postulated Hazardous Chemical Release Preoperational Testing of Emergency Core Cooling Systems for Pressurized Water Reactors Preoperational Testing of Instrument Air Systems Shared Emergency and Shutdown Electric Systems for Multi-Unit Nuclear Power Plants 74/06 74/06 75/09 V4/06 74/06 75/01 1.82 Sumps for Emergency Core Cooling and Containment Spray Systems

/'.

1.83 Inservice Inspection of Pressurized Water Reactor. Steam Generator Tubes 1.84 Design and Fabrication Code Case AcceptabilityASME Section Ill, Division I I

2 3

5 6

7 8

9 10ll 12 13 14 15 16 17 74/06 74/06 VS/07 74/06 V5/04 V5/06 75/09 75/11 76/02 76/OS 76/08 V6/11 V7/08 77/Il

. V8/03 78/07 78/11 79/05 80/05 80/12 1.8S Materials Code Case AcceptabilityhSME Section III, Division 1 1

2 V4/06 VS/04 VS/06

" 'S/09

t f

I

Nsrmb r Rev.

4r 6

7 8

9 10ll 12 13 14 15 16 17 lsstr~

Yerrr/Montts 75/ l l 76/02 76/Ss.'G/05 76/11 77/03

'V7/08 77/11 78/03 78/07 78/11 79/05 80/05 SO/12 1.86 Tcrttsination of Operating Licenses for Nuclear Reactors 1.87 Guidance for Con truction of Class I Components in Elevated-Temperature Reactors (Supplement to ASME Section Ill Code C ises

1592, 1593,

1594, 1595, and 1596) 1.88 Collection, Storage, and Maintenance of Nuclear Power Plant Quality Assurance Records 1.89 Qualification of Class IE Equipment for Nuclear Power Plants 1.90 lnscrvice Inspection of Prestressed Concrete Containment Structures with Grouted Tendons 1.91 Evaluations of Explosiosss Postulated to Occur on Transportation Routes Near Nuclear Power Plants (For Comment) 1.92 Combining Modal Responses and Spatial Components in Seismic Response Analysis 74)06 74/06 75/06 74/08 75/12 76/10 74/11 74/1) 77/08 75/01 78/02 74/12 V6/02 1.93 AvaiiabiUty of Electric Power Sources 1.94 Quality Assurance Requirements for Installation, Inspection, and Testing of Structural Concrete and Structural Steel During the Construction Phase of Nuclear Power Plants 1.95 Protection of Nuclear Power Plant Control Room Operators Against an Accidental Chlorine Release 1.96 Design of Main Steam Isolation Valve Leakage Control Systems for BoiTing Water Reactor Nuclear Power Plants 1.9V Instrumentation for Light-Water-Cooled Nuclear Power Plants To Assess Plagt and Environs Conditions During and Following an

~

Accident 1.98 Assumptions Used for Evaluating the Potential Radiological Consequences of a Radioactive Offgas System Failure in a Boiling Water Reactor (For Comment) 1.99 Effects of Residual Elements on Predicted Radiation Damage to Reactor Vessel Materials 1.100 Seismic Qualification of Electric Equipment for Nuclear Power Plants 1.101 (ttithdrawn--See 45 FR 69610, 10/21/80) 1 2

74/12 75/04 76/04 VS/02 77/01 75/05 76/06 75/12 77/08

.30/12 V5/07 77/04 76/03 VV/08,.",.

'.102 Flood Protection for Nuclear Power Plants 1.103 Post-Tensioned Prestressing Systems for Concrete Reactor Vessels and Containments

.75/10 76/09 75/11 V6/10

f4urnber TitIe 104 (withdrawn--see 44 FR 49321, 8/22/v9) See NUREG-0554, "Single-Failure-Proof Cranes for Nuclear Power Plants."

1.105 instrument Setpoints 1.106 Thermal Overload Protection for Electric Motors on Motor-Operated Valves Rev.

Issued Year/Month 75/11 76/11 75/11 7V/03 1.107 Qualifications for Cement Grouting for Prestressing Tendons in Containment Structures 1.10S Periodic Testing of Diesel Generator Units Used as Onsite Electric Power Systems at Nuclear Power Plants 1.109 Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, A>pendix I.

1.110 Cost-Benefit Analysis for Radwaste Systems for light-Water-Cooled Nuclear Power Reactors (For Comment)

Methods for Estimating Atmospheric Transport and Dispersion of Gaseous Effluents in Routine Releases from Light-Water-Cooled Reactors 1.112 Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents from Light-Water-Cooled Power Reactors 1.113 Estimating Aquatic Dispersion of Effluents from Accidental and Routine Reactor Releases for the Purpose of Implementhxg Appendix I 1.114 Guidance on Being Operator at the Controls of a Nuclear Power Plant 1.115 Protection Against Low-Trajectory Turbine l4ssiles 1.116 Quality Assurance Requirements for Installation, Inspection, and Testing of Mechanical Equipment and Systems 1.117 Tornado Design Classification 1.118 Periodic Testing of Electric Power and Protection Systems 0-R 0-R 75/11 77/02 76/08 77/OS 76/03 77/10 76/03 76/03 77/07 76/04 77/05 76/05 77/04 76/02 76/11 4

V6/03 77/07 76/06 77/05 76/06 78/04 76/06 77/11 V8/06 1.119 (WithdrawnSee 42 FR 33387, 6/30/77) 1.120 Fire Protection Guidelines for Nuclear Power Plants (For Comment) 1.121 Bases for Plugging Degraded PWR Steam Generator Tubes (For Comment) 1.122 Development of Floor Design Response Spectra for Seismic Design of Floor-Supported Equipment or Components 1.123 Quality Assurance Requirements for Control of Procurement of Items and Services for Nuclear Power Plants 1.124 Service Limits and Loading Combinations for Class 1 Linear-Type Component Supports 1.125 Physical Models for Design and Operation of Hydraulic Structures and Systems for Nuclear Power Plants 1.126 An Acceptable Model and Related Statistical Methods for the Analysis of Fuel Densification 76/06 77/11 0

76/08 76/09 78/02 V6/10 77/07 V6/ll.'; s, 78/01 77/03 V8/10 77/03 V8/03

Number Title I Laved Year/Montir 1.127 inspection of Water-Control Structures Associatcrl with Nuclear Power Plants 77/04 78/03 1.128 installation Design and Installation of Large Lead Storage Batteries for Nuclear Power Plants 1.129 Maintenance, Testing, and Replacement of I urge Lead Storage Batteries for Nuclear Power Plants 1.130 Service Limits and Loading Combinations for Class I Plate-and-Shell-Type Component Supports 1.13l Qualification Tests of Electric Cables, Field Splices, and Connections for Light-Water-Cooled Nuclear Power Plants (For Comment)

I. I32 Site Investigations for Foundations of Nuclear Power Plants 7V/04 VS/10 77/04 78/02 77/07 VS/10 7?/08 V7/09 V9/03 1.133 Loose-Part Detection Program for the Primary System of Light-Water-Cooled Reactors (For Comment) 1.134 Medical Evaluation of Nuclear Power Plant Personnel Requiring Operator Licenses 1.135 Normal Water Lcvcl and Discharge at Nuclear Power Plants (For Coramcnt) 1.136 Material for Concrete Containments 1.137 Fuel-Oil Systems for Standby Diesel Generators 1.138 Laboratory Investigations of Soils for Engineering Analysis and Design of Nuclear Power Plants (For Comment) 1.139 Guidance for Residual Heat Removal (For Comment) 77/09 77/09 79/03 V7/09 77/11 78/10 78/0) 79/10 VS/04 ZS/05 1.140 1.141 Design, Testing, and Maintenance Criteria for Normal Ventilation Exhaust System Air Filtration and Adsorption Units of Light-Water-Cooled Nuclear Power Plants Containmcnt Isolation Provisions for Fluid Systems (For Comment)

VS/03 79/10 78/04 1.142 Safety-Related Concrete Structures for Nuclear Power Plants (Other Than Reactor Vessels and Containments)

(For Comment)

VS/04 l.143 Design Guidance for Radioactive 'Waste Management

Systems, Structures, and Components InstaIled in Light-Water-Cooled Nuclear Power Plants 78/07 79/10 1.144 Auditing of Quality Assurance Prograras for Nuclear Power Plants 1.145 Atmospheric Dispersion Models for Potential Accident Consequence Assessments at Nuclear Power Plants (For Comment)

V9/01 80/09 V9/08 1.146 qualification of Quality Assurance Program Audit Personnel for Nuclear Power Plants BO/OB 1.147 Inservice Inspection Code Case Acceptabil ity ASME Section XI, Division 1

81/02

)

I l

TM Number EN 805-5 Dratt Regulatory Guider Nuclear Analysis and Design of Concrete Radiation Shielding for

-Nuclear Power Plants lrsuert Year/I tooth

'79/02 SC 704-5 SC 807-4 (Proposed R.G. 1.35.1)

SC 705-4 RS 809-5 Functional Specification for Safety-Related Valve Assemblies in Nuclear Power Plants Determining Prcstressing Forces for Inspection of Prestressed Concrete Containments Ultrasonic Testing of Reactor Vessel Welds During Inservice Examination Qualification Test for Cable Penetration Fire Stops for Usc in Nuclear Power Plants 79/02 79/04 79/05 79/07 RS 705-4 FP 811-4 SC 521-4 Lightning Protection for Nuclear Power Plants Safety-Related Permanent Dcwatering Systems for Nuclear Power Plants LWR Core Reloads; Guidance on Applications for Amendments to Operating Iicenses and on Refueling and Startup Tests 79/08 79/09 79/09 RS 110-5 SC 708-4 81/02 Nuclear Power Plant Simulators for Use in Operator 80/07 Training qualification and Acceptance Tests for Snubbers Used in Systems Important to Safety

Tesss end R.G.

(cumbers as eoz-5 1.8 sc e]0-4 1.35 Proposed Revisions so Reaulatory Guides Title Personnel Sel etio and Training Personnel

))calcification and Training (Second)

Inservice inspection of Ungrouted Tendons in Prestressed Concrete Containments Proposed Revision 2

2 issued Ye er/h1onth 79/02 80/09 79/04 Rs 050-2 1.131 Rs 902-4 1.33 as 9oe-5 1.94 SC 814-5 1.136 Qualification Tests oi'lectric Cables and Field Splices for Light-Water-Cooled Nuclear Power Plants Quality Assurance Program Requirements (Operation) 3 (Second) 3 Quality Assurance Requirements for Installation, inspection, 2

and Testing of Structural Concrete, Structural Steel, Soils, and Foundations During the Construction Phase oi'uclear Power Plants l1aterials, Construction, and Testing of Con-2 crete Containments (Article CC-1000,

-2000 and -4000 through -7000 of the "Code for Concrete Reactor Vessels and Containments" 79/08 79/08 80/11 79/09 79/11 SS 926-4 1.23 RS 709-4

1. 80 (to be renumbered

l. 68.3}

Meteorological Programs in Support of Nuclear Power Plants Preoperational Testing of Instrument and Control Air Systems 80/09 80/10 10 are e

R letorv Guides Under Oewlooment later'uide oa Toraado NfssQes Sfngfe FaQure C~w for Idght-Water Reactox Plants Fluid Systems Earthquake Instzumeatatfoa Data Baadlfng for Nucleax Power Plaats Press~wed Wate. Reactor and BoQfng Watez Reactox'ontainment Spray Design Czfterfa Crfte;- for E!ec~, Iastrumeazatfoa, aad Control Portions of Safety Systems Design and Coastraedoa Def~ Reporaxzg Requirements Qualfffcatfon of Hectrfc Nodules for Nucleaz Power Plants Quality Assurance Requirements for Packa~g, Shipping, Receiving, Storage, aad Bandog of items for Nuclear Power Plants Meteorological Extreme Afr Temperatures for Design and Operation of Nuclear Power Plants Extreme Wfndspeeds in Coastal Areas for Design and Operation of Nuclear Power Plants Qeochronologfc Techniques Applied to Nuclear Powex Plant Sftfag Procedures and Cziterfa for Assessiag SoQ Lfquefactfoa Potential at Nuclear FacQfty Sites Foundation aad Earthwork Coastructfon for Nuclear Power Plants Scow and Ico Accumulations fox the Desiga and Operation of Nuclear Powex Plants GeofogfcaI Dlappfag of Excavatioas for Nuclear Powe; Plants Fracazre Analysis of riaws at Structural Dfscoatfauftfes Iaservfco >Ioaftoring of Core aad Cora Suppor. S~cture Natfoa Via Neutron-Flux Measurement Requfremeats foz'uaifffcatfoa Tests aad Productfon Tests tor Pfping aad Equipment Saubbers UItrasoafc Testfng (UT) of ~IE Code Class I aad 2 Austeaftfc Pfpiag Systexzs Methods of Analysis and Desiga of Reinforced Concrete Containment Struc~s Recommendatfoas for Iaservfce Testing of Valves Requfred to Perform a Safety Fuacaoa fn Ught-Water Reactors

Regulat Gudcs Being Revised Revision 2 to Regulatory Guide 1.12, "Instrumentation for Earthquakes" a

Revision 2 to Regulatory Guide 1.14, "Reactor Coolant Pump Flywheel Integrity Revision 5 to Regulatory Guide 1.16, "Reporting of Operation Information--Appendix A Technical Specifications" Revision I to Regulatory Guide 1.25, "Assumptions Used for Evaluating the Potential Radiological Consequences of a Fuel Han~g Accident in the Fuel Handling an.

Storage Facility for Boiling and Pressurized Water Reactors" Revision I to Regulatory Guide 1.50, "Control of Preheat Temperature for Welding of Low-Alloy Steel" Revision 2 to Regulatory Guide 1.56, "hlaintcnance of Water Purity in Boiling Water Reactors"

/

Update of Revision 3 to Rcgu!story Guide 1.70, "Standard Format and Content of Safety Analysis Reports for Nuclear Power'Plants" Revision ) to Regulatory Guide 1.71, "Welder Qualification for Areas of Limited Accessibility" Revision I to Regulatory Guide 1.80, "Preoperational Testing of instrument and Control Air Systems" Revision j8 to Regulatory Guide 1.84, "Design and Fabrication Code Case AcceptabilityAShIE Section III, Division 1" Revtsionl8 to Regulatory Guide 1.85, "Materi& Code Case Acceptability-ASME Section III, Division 1" Rewmion 1 to Regulatory Guide 1.89, "Qualification of 1E Equipment for Nuclear Power Plants" Revision 2 to Regulatory Guide 1.101, "Emergency Planning for Nuclear Power Plants" Revision 1 to Regulatory Guide 1.133, "Loose-Part Detection Program for the Primary System of Light-WaterCooled Nuclear Power Plants" Revision 1 to Regulatory Guide 1.135, "Normal Water Level Discharge at Nuclear Power Plants" Revision 1 to Regulatory Guide 1.139, "Guidance for Residual Heat Remov Revision 1 to Regulatory Guide 1.141, "Containment Isolation Provisions for Fluid Systems" Revision 1 to Regulatory Guide 1 ~ 142, "Safety-Related Concrete Structures for Nuclear Power Plants (Other Than Reactor Vessels and Containments)"

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Radfation Symbol Guide !or Admfnfstrative Practices fn Radhioa Nnnitorfng FQm Badge Performance Criteria Direct-Reading and Indirect-Reading Pocket Dosfmeters Standard Tc=.~edure for Gefgex MQDe." Counters f

Occupational Radfatfon Exposure Reco&m Systems Inlotmanon Relevant to Ensuring That Occupational Radiation Ex~ ures at flicker Power Stains WQl Be As Low As Is Reasonably Achievable Rev.

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$.13 8.14 8 15 Acceptable Concepts, Models, Equations, and Assumptfons !or a Bfoassay

'Program Operatfng PhQosophy for Maintaining OccupatfonaI Radiatfon Exposures As Low As Is Reasonably Achievable Instruction Concernfng Prenatal Radfatfon Exposure Personnel Neutron Dosimeters Acceptable Pro~ tor Respiratory ~tech 1-R TS/il TT/08 Td/10 8.19 10.1 Occupa&cal Radfa5m Dose Assessment fn Light-Water Reactor Power Paints-Des' Stage Man-Rem rmnmates Applfca&ns of Bfoassay !or 1-125 and I-131 CompQatfon oI Reporting Requfrements for'Persons Subfect to NRC Regulatfons T9/08 1

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