ML20041D085

Forwards Latest Update Re Generic Issues Tracking Sys as of 811217.Updated Quarterly Computer Printout Encl

ML20041D085
Person / Time
Issue date:	02/18/1982
From:	Hanauer S Office of Nuclear Reactor Regulation
To:	Eisenhut D, Mattson R, Vollmer R Office of Nuclear Reactor Regulation
References
NUDOCS 8203040246
Download: ML20041D085 (83)

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ff/f February 18, 1982

!!O100NiDIN FOR:

Darrell G. Eisenhut, Director mN Division of Licensing 4

to Richard H. Vollrer, Director P

1 Division of Engineering RECEIVED Roger J. Mattson, Director 1979826 8

Division of Systems Integration gamm e]

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Hugh Thenpson, Acting Director Division of Hunan Factors Safety 4 /

6 Victor Stello, Jr., Deputy Executive Director for Recional Operations and Generic Requirements F R0'4 -

Stephen H. Hanauer, Director Division of Safety Technology

SUBJECT:

rEMERIC ISS!!ES TRACKING SYSTE?1 (GITS) REPORT This reno transnits the latest update of the Generic Issues Trackinc System (GITS) which oives the status of all staff generic issues as of December 17, 1931. GITS does not include TMI Action Plan itens which are reported senarately in the Action Plan Tracking Systen (APTS) report.

This issue of GITS does not reflect the ongoing prioritization of cenaric, issues being conducted by the Safety Progran Evaluation Branch of DST.

Uben the prioritization is canpleted, the GITS report will be re-issuad.

with this infon-ation included.

The initial intent was to issue the GITS report quarterly, however the Icw level of activity on non-USI ceneric issues nakes it icpractical to provide complete updates quarterly.

Ilovever, the current status of any issue listed in GITS can be obtained by calling or writing the cocnizant person listed in the report or by contacting Judy Butts at (301) 492-4958.

The fomat of the GITS has been channed to group generic issues by status rather than in &erical order. The purpose of this change is to highlicht those safety issue which are active and to separately list envircnnental and licensing inprovement issues. A numerical listing of all generic issues is provided in Enclosure 1.

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I Those Listed ;

The revised fomat of GITS is as follows:

Part I Unresolved Fafety Issues l

Part II Safety Issues l

Part IIA Resolved Safety Issues Part IIB Active Safety Issues l

Part IIC Inactive Safety Issues i

Part IID Teminated or Superceded Safety Issues l

Part IIE Ongoing Safety Issues l

Part III Environmental Issues Part IV Licensing Inprover ent Issues All quistions regarding the GITS report and requests for additional copies should be addressed to Judy Butts, Generic Issues Branch, DST, j

Mail Stop 268.

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Stephen H. Hanauer, Director l

Division of Safety Technology l

Office of Nuclear Reactor Regulatiou

Enclosures:

1.

Numerical Listino of Generic Issues 2.

GITS Report cc: w/ enclosures See next page DISTRIBUTION Central Files GIB Reading NRC PDR TERA D.C.S.

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1 Those Listed cc: w/ enclosure H. Denton P. Collins E. Case D. Ziemann C. Michelson V. Moore T. f4urley L. Hule'an S. Hanauer F. Congel F. Schroeder N. Anderson fl. Ernst P. Morian P. Check PPAS T. Speis J. Butts R. Houston L. Rubenstein R. Purple H. Thanpson J. Kramer J. Knight W. Johnston D. flu 11er G. Lainas T. Novak R. Tedesco K. Kniel G. Knighton

11. Minners A. Thadani F. Rosa M. Srinivasan D. Skovholt O. Parr T. Mu nhy W. Gamill C. Berlinger LQB Acting BC B. Sheron OLB Acting BC R. Bosnak F. Schauer R. Jackson G. Lear S. Pawlicki V. Benaraya Z. Rosztoczy

11. Haass R. Ballard H. Regan S. Sk.iei

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Those Listed I The revised format of GITS is as follows:

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Part I Unresolved Safety Issues Part II jafety Issues Part IIA

\\ Resolved Safety Issues Part IIB Active Safety Issues Part IIC Inactive Safety Issues Part IID Terminated or Superceded Safety Issues Part IIE Ongoing Safety Issues Part III Environmental Issues Part IV Licensing Improvement Issues j

i All questions regarding the GITS report and requests for additional copies should be addressed to Judy Butts, Generic Issues Branch, DST, Mail Stop 268.

Stephen H. Hanauer, Director Division of Safety Technology Office of ?!uclear Reactor Regulation EnclosureM' 1. IN J GITS Report cc: w/ enclosure See next page DISTRIBUTION Central Files GIB Reading N

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TERA D.C.S.

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i Those Listed February 18, 1982 cc: w/ enclosures H. Denton P. Collins E. Case D. Ziemann C. Michelson V. Moore T. Mu rl ey L. Hulman S. Hanauer F. Congel F. Schroeder N. Anderson M. Ernst P. Nerian P. Check PPAS T. Speis J. Butts R. Houston L. Rubenstein R. Purple H. Thampson J. Krmner J. Knight W. Johnston D. Muller G. Lainas T. Novak R. Tedesco K. Kniel G. Knighton H. Minners A. Thadani F. Rosa M. Srinivasan D. Skovholt

0. Parr T. Murphy W. Gammill C. Berlinger LQB Acting BC B. Sheron OLB Acting BC R. Bosnak F. Schauer R. Jackson G. Lear S. Pawlicki V. Benaroya Z. Rosztoczy W. Haass R. Ballard W. Regan S. Skjei

t NUMERICAL LISTING OF GENERIC ISSUES 4

^Part I ssue N. Type Ti tl e 1

I A-1 USI Water Hammer I

A-2 USI Asymmetric Blowdown Loads on Reactor Primary Coolant Systems I

A-3 USI Westinghouse Steam Generator Tube Integrity I

A-4 USI CE Steam Generator Tube Integrity I

A-5 USI B&W Steam Generator Tube Integrity I

A-6 USI Mark I Short Term Program I

A-7 USI Mark I Long Term Program I

A-3 USI itark II Containment, Pool Dynamic loads - Long Term Program I

A-9 USI ATWS 7

A-10 USI BWR Feedwater Nozzle Cracking I

A-l l USI Reactor Vessel Materials Toughness I

A-12 USI Fracture Toughness of Steam Generator and Reactor Coolant Pump Supports IIA A-13 S

Snubber Operability Assurance IIC A-14 5

Flaw Detection I

IIB A-15 S

Primary Coolant System Decontamination and Steam Generator Chemical Cleaning IIB A-16 S

Steam Effects on BWR Core Spray Distribution I

A-17 USI

$ystems Interaction IIC A-18 S

Pipe Rupture Design Criteria IIB A-19 S

Digital Computer Protection System III A-20 E.

Impacts of the Coal Fuel Cycle IIC A-21 S

Main Steamline Break Inside Containment - Evaluation of Environmental Conditions for Equipment Qualification IIC A-22 S

PWR tiain Steamline Break, Core, Reactor Vessel and Containment Building Response IIA A-23 S

Containment Leak Testing I

A-24 USI Qualification of Class IE Safety Related Equipment IIA A-25 S

Non-Safety Loads ~on Class IE Power Sources I

A-26 USI Reactor Vessel Pressure Transient Protection IV A-27 L

Reload Applications IIE A-28 S

Increase in Spent Fuel Pool Capacity IIB A-29 S

Nuclear Power Plant Design for the Reduction of Vulnerability to Industrial Sabotage IIB A-30 S

Adequacy of Safety - Safety-Related DC Power Supplies I

A-31 USI RHR Shutdown Requirements IIB A-32 S

Missile Effects III A-33 E

NEPA Review of Accident Risks IIB A-34 S

Instruments for Monitoring Radiation and Process Variables During Accidents' 9

IIA A-35 USI Adequacy of Offsite Power Systems 1

A-36 USI Control of Heavy Loads Near Spent Fuel IIB A-37 5

Turbine itissiles IIC A-38 S

Tornado Missiles

. o y.

Part Issue No.

Tyge Ti tle I

A-39 USI Determination of Safety Relief Valve Pool Dynamic Loads and Temperature Limits I

A-40 USI Seismic Design Criteria Short Term Program IIC A-41 S

Long Term Seismic Program

.I A-42 USI Pipe Cracks in Boiling Water Reactors I

A-43 USI Containment Emergency Sump Performance I

A-44 USI Station Blackout I

A-45 USI Shutdown Decay Heat Removal Requirements A-46 USI Seismic Qualification of Equipment in Operating Plants I

A-47 USI Safety Implications of Control Systems I

A-48 USI Hydrogen Control Measures and Effec.s of Hydrogen Burns on Safety Equipment I

A-49 USI Pressurized Thermal Shock i

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Part Issue No.

Type Ti tle III B -1 E

Environmental Techr.ical Specifications III B -2 E

Forecasting Electricity Demand 4

IV 3-3 L

Event Categorization IV B -4 L

ECCS Reliability IIC B-5 S

Ductility of Twc Way Slabs and Shells and Buckling Behavior of Steel Containments IIA B -6 S

Loads, Load Combinations, Stress Limits IV B -7 L

Secondary Accident Consequence Modeling IIC B-8 S

Locking Out of ECCS Power Operated Valves IIA B -9 S

Electrical Cable Penetrations of Containment IIB B -10 S

Behavior of BWR Mark III Containments TV B -l l L

Subcompartment Standard Problems IV B-12 L

Containment Cooling Requirements (Non-LOCA)

IV B -13 L

Marviken Test Data Evaluations I

B -14 USI Study of Hydrogen liixing Capability in Containment Post-LOCA IV B -15 L

Contempt Computer Code Maintenance IIC B -16 S

Protection Against Postulated Piping Failures in Fluid Systems Outside Containment IID B -17 S

Criteria for Safety Related Operator Actions I

B -18 USI Vortex Suppression Requirements for Containment Sumps IV B-19 L

Thermal Hydraulic Stability IV B-20 L

Standard Problem Analysis IV B -21 L

Core Physics IV B -22 L

LWR Fuel IV B-23 L

LMFBR Fuel I

B -24 USI Seismic Qualification of Electrical and Mechanical Components IV B -25 L

Piping Benchmark Problems IIB B -26 S

Structural Integrity of Containment-Penetrations IV B -27 L

Implementation and Use of Subsection NF III B -28 C

Radionuclide/ Sediment Transport Program IV B -29 L

Effectiveness of Ultimate Heat Sinks IV B -30 L

Design Basis Floods and Probability IV B-31 L

Dam Failure tiodel IV B -32 L-Ice Effects on Safety Related Water Supplies IV B -33 L

Dose Assessment Methodology IV B -34 L

Occupational Radiation Exposure Reduction IV B -35 L

Confirmation of Appendix I Models for Calculations-of Releases of Radioactive Materials in Gaseous and Liquid Effluents from Light Water Sealed Nuclear Power Plants IV B -36 L

Develop Design, Testing and Maintenance Criteria 4

for Atmosphere Cleanup System Air Filtration and Adsorption Units for Engineered Safety Feature Systems and for Normal Ventilation Systems III B-37 E

Chemical Discharges to Receiving Waters III B -38 E

Reconnaissance Level Investigations i

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Part Issue No.

Type Ti tle III B-39 E

Transmission Lines III B-40 E-Effects of Pcwer Plant Entrainment on Plankton III B -41 E

Impacts on Fisheries III B -4?

E Socioeconomic Environmental Impacts III B-43 E

Value of Aerial Photographs for Site Evaluation III B-44 E

Forecasts of Generating Costs of Coal and Nuclear Plants III B -45 E

Need for Power - Energy Conservation III B -46 E

Cost of Alternatives in Environmental Design IIB B-47 S

Inservice Inspection Criteria for Supports and Bolting of Class 1, 2, and 3 and MC Components IIB B-48 S

BWR CRD Mechanical Faiiure (Collet Housing)

IV B-49 L

Inservice Inspection Criteria and Corrosion Prevention Criteria for Containments IV B -50 L

Post Operating Basis Earthquake Inspection IV B -51 L

Assessment of Inelastic Analysis Techniques for Equipment and Components I

. B -52 USI Fuel Assembly Seismic and LOCA Responses IIB B-53 S

Load Break Switch IIB B -54 S

Ice Condenser Containments IIC B-55 S

Improved Reliability of larget Rock Safety-Relief Valves IIA B-56 S

Diesel Reliability I

B -57 USI Station Blackout IIC B-58 S

Passive Mechanical Failures IV B -59 L

Review of (N-1) Loop Operation in BWRs and PWRs IIA B-60 S

Loose Parts fionitoring System IIC B -61 S

Allowable ECCS Equipment Outage Periods IV B-62 L

Reexamination of Technical Bases for Establishing SLs LSSS IIB B-63 S

Isolation of Low Pressure Systems Connected to the i

Reactor Coolant Pressure Boundary IIB B -64 S

Decommissioning of Reactors III B-65 S

Iodine Spiking IIA B -66 S

Control Room Infiltration Measurements IID B -67 S

Effluent and Process Monitoring Instrumentation IIC B -68 S

Pump Overspeed During LOCA 110 B -69 S

ECCS Leakage Ex-Containment IIA B -70 S

Power Grid Frequency Degradation and Effect on Primary Coolant Pumps 4

IIA B-71 S

Incident Response IV B-72 L

Development of Models for Assessing Risk of Health Effects and Life Shortening from Uranium and Coal Fuel Cycles-IIC B -73 S

Monitoring for Excessive Vibration Inside the Reactor Pressv - Vessel 4

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Part Issue No.

Tyge Title IIB C-1 S

Assurance of Continuot s Long Term Capability of

)

Hermetic Seals on Inst.umentation and Electrical Equi pnent

- IV C-2 L

Study of Containment Depressurization by Inadvertent Spray Operation I

C-3 USI Insulation Usage Within Containment i

IV C-4 L

Statistical Methods for ECCS Analysis IV C-5 L

Decay Heat Update IV C-6 L

LOCA Heat Sources IIB C-7 S

PWR System Piping IIC C-8 S

Main Steam Line Leakage Control Systems 1

IIC C-9 S

RHR Heat Exchanger Tube Failures

'IV C-10 L

Effective Operation of Contbinment Sprays in a LOCA I

C-l l USI Assessment of Failure and Reliability of Pumps and Valves IV C-12 L.

Primary System Vibration Assessment I

C USI Non-Random Failures IV C -14 L

Storm Surge Modes for Coastal Sites IV C-15 L

NUREG Report for Liquids Tank Failure Analysis III C-16 E

Assessment of Agricultural Land in Relation to Power Plant Siting and Cooling System Selection IV C-17 L

Interim Acceptance Criteria for Solidification Agents for Radioactive Solid Wastes i

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Part Issue No.

Type Ti tle IIC D-1 S

Advisability of a Seismic Scram IV D-2 L

Emergency Ccre Cooling System Capability for Future Plants IIA D-3 S

Control Rod Drop Accident O

i GENERIC ISSUES TRACKING SYSTEM (updated quarterly)

(Status of Generic Issues as of 12/17/81)

The Generic Issues Tracking System (GITS) providos the status of the staff generic issues which are not reported as Unresolved Safety Issues (USIs) or TMI Action Plan Items.

Status of USIs is reported quarterly in the AQUA Book, HUREG-0606 and TMI action plan items are reported quarterly in the Action Plan Tracking System (APTS).

This report is divided into the following sections:

Part I Unresolved Safety Issues (USI's)

Part II Safety Issues:

Part IIA Resolved Safety Issues 6

Part IIB Active Safety Issuns Part IIC Inactive Safety Issues Part IID Terminated or Superceded Safety Issues Part IIE Ongoing Safoty Issues Part III Environmental Issues Part IV Licensing Improvement Issues

]

J CONTACTS:

Judy Butts, HRR/GIB x24958 (Content & format)

Mike King, MPA/MIB x27039 (Production 8 publication) i i

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STATUS INDICATORS IN THIS REPORT ARE DEFINED AS.FDLLOWS

1. TYPE USI Issue has been designated as a USI and status is reported in the AQUA Book (NUREG-0606).

S

. Safety Issue.

E Environmental Issue.

L Licensing improvement issue; activities aimed at developing analysis or review procedures or improving understanding of phenomena, 2.

STATUS ACTIVE Item is currently under review; or the issue is technically resolved and implementation 4

i s in progress.

ONGOING Item has no clearly defined technical resolution or endpoint.

Generic work in this area will continue periodically.

INACTIVE No work is currently underway in this item.

TERMINATED Technical work on the item has been terminated.

Item has either been determined to have no safety significance or no demonstrated need for licensing improvement exists.

RESOLVED Technical resolution and implementation are complete.

SUPERCEDED.

Item has'been. superceded in scope and/or schedule by a related item i n the TMI Action Plan (NUREG-0660).

1

3. FLAG RED Trouble with item; serious slip ( > 1 year); severe resource shortage; tracking problems.

YELLOW Any slip less than 1 year; potential red item, i

GREEN Execution and/or implementation are going smoothly.

4.' PRIORITY (value)

Assigned point score.

5.

TASK A.P.

YES Task action plan has been written.

HO Task action plan doesn't exist.

6.

TECHNICAL RESOLUTION COMPLETE Issue is technically resolved but not necessarily implemented.

INCOMPLETE Issue is.not technically resolved.

7.

IMPLEMENTATION Completed Technical resolution has been implemented.

In Progress -

Implementation of technical resolution is in progress.

Not Started -

Implementation of technical resolution has been determined but not started.

Not Required -

~ Technical resolution does not require OR/0L/CP implementation.

Not Determined - Technical resolution of item is not complete.

No determination of implementation has yet been made.

8.

UPDATED

.(mm/dd/yy)

Date of information reported in current report.

1 4

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PART It UHRESOLVED SAFETY ISSUES (USI's)

ISSUE #

TYPE FLAG STATUS __

PRIORITY TASK A.P.

Tf_C H. R E_im IMPLEMENTATION TACS #

MEpt.TED

.-1 USI ACTIVE YES INCOMPLETE IH PROGRESS 12/17/81 A

HRR AL SERKIZ (492-4217) GIB/ DST TITLE: Water Hammer DESCRIPTIDH: Seo AQUA Book, HUREG-0606 SCHEDULE: See AQUA Book, HUREG-0606 CURRENT STATUS: See AQUA Book, HUREG-0606 PROBLEMS:

ISSUE #

TYPE FLAG STATUS _

PRIORL11 TASK A.P.

TECH. REi.

IMPLEMENTATION TACS #

UPDATED A-2 USI ACTIVE YES COMPLETE IH PROGRESS 12/17/81 HRR J. SHEA (492-7231) ORB-5/DL TITLE:

Asymmetric Blowdown Loads on Reactor Primary Coolant Systems DESCRIPTION: See AQUA Book, NUREG-0606 SCHEDULE: Seo AQUA Book, HUREG-0606 CURREHT STATUS: See AQUA Book, HUREG-0606 PROBLEMS:

liSUE #

TYPE FLAG STATUE _

PRIORITY TASK A.P.

TECH. RES.

IMPLEMENTATION TACS #

UPDATED A-3 USI ACTIVE YES INCOMPLETE NOT STARTED 12/17/81 RES J. STROSHIDER (443-5904) MMRB/RSR TITLE: Westinghouse Steam Generator Tube Integrity DESCRIPTION: See AQUA Book, HUREG-0606 SCHEDULE: Soo AQUA Book, HUREG-0606 CURRENT STATUS: See AQUA Book, HUREG-0606 PROBLEMS:

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111U E. #

TYPE FLAG STATUS _

PRIORITY TASK A.P.

TECH. RES.

IMPLEMENTATION TACS 8 UPDATED _

A-4 USI ACTIVt YES INCOMPLETE NOT STARTED 12/17/81 RES J. STROShlDER (443-S904) MMRB/RSR TITLE:

CE Steam Generator Tube Intecrity DESCRi? TION: See AQUA Book, HUREG-0606 SCHEDULE: See AQUA Book, HUREG-0606 CURRENT STATUS: See AQUA Book, HUREG-0606 PROBLEMS:

ISSUE #

TYPE FLAG STATU1_

PRIORITY TASK A.P.

IECH. REli IMPLEMENTATION TACS #

UPDATED A-5 USI ACTIVE YES INCOMPLETE NOT STARTED 12/ 17/8 1 RES J. STROSHIDER (443-S904) MMRB/RSR TITLE:

Blu Steam Generator Tube Integrity DESCRIPTION: See AQUA Book, HUREG-0606 SCHEDULE: See AQUA Book, NUREG-0606 CURRENT STATUS: See AQUA Book, NUREG-0606 PROBLEMS:

ISSUE #

IYPE FLAG STATUS PRIORITY TASK A.P.

TECH. REi.

IMPLEMENTATION TACS #

MPDATED_

A-6 USI RESOLVED YES COMPLETE COMPLETED 12/17/81 TITLE: MARK I Short Term Program DESCRIPTION: See HUREG-0408 SCHEDULE:

CURRENT STATUS:

PROBLEMS:

ISSUE #

TYPE FLAG STATUS PRIORITY TASK A.P.

TECH. RES.

IMPLEMENTATIDH TACS 8 UPDATED A-7 USI ACIIVE YES COMPLETE IN PROGRESS 12/17/81 NRR B. SIEGEL (492-7534) ORB 2/DL TITLE: MARK I Lona Term Program DESCRIPTION: See AQUA Book, HUREG-0606 SCHEDULE: See AQUA Book. HUREG-0606 CURRENT STATUS: See AQUA Book, NUREG-0606 PROBLEMS:

i ISSUE 9 TYPE FLAG STATUS _

PRIORITY TASK A.P.

IECH. RE}.

IMPLEMENTATION TACS 9 UPDATER _

A-8 USI ACTIVE YES COMPLETE IN PROGRESS 12/17/81 NRR CLIFF ANDERSON (492-7486) GIB/ DST TITLE: MARK II Containment Pool Dynamic Loads - Long Term Program DESCRIPTION: See AQUA Book, NUREG-0606 SCHEDULE: See AQUA Book, NUREG-0606 LURRENT STATUS: See AQUA Book, NUREG-0606 j

PROBLEMS:

i ISSUE 8 TYPE FLAG STATUi_

PRIORITY IASK A.P.

TECH. REi.

IMPLEMENTATION TACS 8 UPDATED l

A-9 USI ACTIVE YES COMPLETE NOT STARTED 12/17/81 NRR W. MINNERS (492-8342) SPEB/ DST TITLE:

ATWS DESCRIPTION: See AQUA Book, HUREG-0606 SCHEDULE: See AQUA Bock, NUREG-0606 i

4 j

CURRENT STATUS: See AQUA Book, HUREG-0606 PROBLEMS:

l ISSUE #

TYPE FLAG STATU1_

PRIORITY TASK A.P.

IECH. REL 1M.ILEMENTATION TACS 8 MP_pM_EQ_

A-10 USI ACTIVE YES COMPLETE IN PROGRESS 12/17/81 HRR PAUL O'CONHOR (492-7215) ORB-5/DL TITLE: BWR Feedwater Noz:Ie Cracking i

DESCRIPTION: See AQUA Book, NUREG-0606 i

SCHEDULE: See AQUA Book, NUREG-0606 i

CURRENT STATUS: See AQUA Book, NUREG-0606 PROBLEMS:

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ISSUE 9 TYPE FLAG STATUS __

PRIORI 11 TASK A.P.

TECH. R Ei, JMPLEMENTATION TACS 9 UPDATED _

A-11 USI ACTIVE YES INCOMPLETE NOT STARIED 12/17/81 NRR R. JOHNSON (492-471S) GIB/ DST TITLE: Reactor Vessel Materials Toughness DESCRIPTION: See AQUA Book, HUREG-0606 SCHEDULE: See AQUA Book HUREG-0606 CURRENT STATUS: See AQUA Book, HUREG-0606 PROBLEMS:

ISSUE 8 TYPE FLAG STATUi_

PRIORITY TASK A.P.

TECH. R ES2 IMPLEMENTATION TACS 8 UPDATER _

A-12 USI ACTIVE YES INCOMPLETE NOT STARTED 12/17/81 NRR R. JOHNSON (492-4715) GIB/ DST TITLE:

Fractute Toughness of Steam Generator and Reactor Coolant Pump i

Supports.

DESCRIPTION: See AQUA Book, HUREG-0606 SCHEDULE: See AQUA Book, HUREG-0606 i

CURRENT STATUS: See AQUA Book, HUREG-0606 PROBLEMS:

t ISSUE 8 TYPE FLAG STATUS _

PRIORITY TASK A.P.

If_C H. RE1.

IMPLEMENTATION TACS S UPDATEQ_

A-17 USI ACTIVE YES INCOMPLETE IN PROGRESS 12/17/81 FRANK C0FFMAN (492-7497) RRAB/ DST TITLE:

Systems Interaction DESCRIPTION: See AQUA Book, HUREG-0606 SCHEDULE: See AQUA Book, HUREG-0606 CURRENT STATUS: Responsibility for continuation of the effort is with the RRAB of DST.

P40BLEMS:

ISSUE #

TYPE FLAG

_STATUi_

PRIORITY TASK A.P.

_T EC H. RES2 IMPLEMENTATION TACS #

UPDATED _

A-24 USI ACTIVE YES COMPLETE IN PROGRESS 12/17/81 NRR A. SZUKIEWICZ (492-4713) GIB/DSI TITLE:

Qualification of Class I-E Safety Related Equipment 4

DESCRIPTION: See AQUA Book, NCREG-0606.

i SCHEDULE: See AQUA Book, HUREG-0606.

CURRENT STATUS: See AQUA Book, HUREG-0606.

j PROBLEMS:

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1 2

Y

ISSUE 8 TYPE FLAG STATUi_

PRIORITY TASK A.P.

IECH. REi.

IMPLEMENTATION TACS #

UPDATED _

A-26 USI ACTIVE YES COMPLETE IN PROGRESS 12/17/81 HRR DAH GARNER (492-9607) ORB 4/DL TITLE:

Reactor Vessel Pressure Transient Protection DESCRIPTIDH: See AQUA Book, HUREG-0606.

SCHEDULE: See AQUA Book, NUREG-0606 CURRENT STATUS: See AQUA Book, NUREG-0606.

PROBLEMS:

ISSUE #

IYPE FLAG STATU1_

PRIORITY TASK A.P.

TECH. RES.

IMPLEMENTATION TACS #

UPDATED-A-31 USI INACTIVE YES COMPLETE SEE CURRENT STATUS 12/17/81 HRR TOM HOVAK (492-7817) DL TITLE:

RHR Shutdown Requirements DESCRIPTION: See AQUA Book, HUREG-0606 SCHEDULE: Implementation not scheduled CURRENT STATUS: Implemented on cps and OLs via SRP 5.4.7, BTP 5-1 and RG 1.139. Impicmentation has not been accomplished at Operating Reactors.

FROBL Ef15 :

ISSUE #

TYPE FLAG STATUi_

PRIORITY TASK A.P.

LECH. REi.

IMPifMENTATION 'TACS #

UPDATED A-36 USI ACTIVE YES C0t!PLEIE IN PROGRESS 12/17/81 HRR BUD REQUA (492-7877) ORB-3/DL TITLE:

Control of Heavy Loads Hear Spent Fuel DESCRIPTION: See AQUA Book, HUREG-0606 SCHEDULE: See AQUA Book, HUREG-0606 CURRENT STATUS: See AQUA Book, HUREG-0606 PROBLEMS:

ISSUE 8 TYPE FLAG

_ STATUS PRIORITY TASK A.P.

TECH. REi.

IMPLEM;NTATLQM TACS #

MPDATER_

A-39 USI ACTIVE VES INCOMPLETE NOT STARTED 12/17/81 NRR NELSON SU (492-7477) GIB/ DST TITLE:

Determination of Safety Relief Valve Pool Dynamic Loads

(

and Temperature Limits 1

DESCRIPTION: See AQUA Book, HUREG-0606 SCHEDULE: See AQUA Book, HUREG-0606 CURRENT STATUS: See AQUA Book, NUREG-0606 PROBLEMS:

ISSUE 8 TYPE FLAG STATUS _

PRIORITY TASK A.P.

TECH. RES, IMPLEMENTATION TACS #

UPDATED A-40 USI ACTIVE YES INCOMPLETE NOT STARTED ~

12/17/81 NRR GOUTAM BAGCHT (492-8251)

EQB/DE TITLE:

Seismic Design Criteria - Short Term Program DESCRIPTION: See AQUA Book, NUREG-0606 SCHEDULE: See AQUA Book, NUREG-0606 CURRENT STATUS: See AQUA Book, NUREG-0606 PROBLEMS:

ISSUE 8 TYPE FLAG STATUE _

PRIORITY TASK A.P.

TECH. RES.

IMPLEMENTATION TACS 8 UPDATED A-42 USI ACTIVE YES COMPLETE IN PROGRESS 12/17/81 NRR DICK CLARK (492-7162) ORB-2/DL T1TLE:

Pipe Cracks in Boiling Water Reactors DESCRIPTION: See AQUA Book, NUREG-0606 SCHEDULE: See AQUA Book, NUREG-0606 CURRENT STATUS: See AQUA Book, NUREG-0606 PROBLEMS:

_ = _. _ __ _. _ _. _ _ _. _.. _ _ _. -

ISSUE #

TYPE FLAG STATUi_

PRIORITY TASK A.P.

TECN. RES.

IMPLEMENTATION TACS #

UPDATED A-43 USI ACTIVE YES INCOMPLETE NOT STARTED 12/17/81 NRR AL SERKIZ (492-4217) GIB/ DST TITLE:

Containment Emergency Sump Performance.

DESCRIPTION: See AQUA Book. HUREG-0606 SCHEDULE: See AQUA Book, NUREG-0606 i'

CURRENT STATUS: See AQUA Book, HUREG-0606 PROBLEMS:

ISSUE 8 TYPE FLAG STATUS _

PRIORITY TASK A.P.

IECH. RES.

IMPLEMENTATION TACS S UPDATEQ_

A-44 USI ACTIVE YES INCOMPLETE NOT STARTED 12/17/81 NRR PAT BARANOWSKY (443-5960) RRBR/RES TITLE:

Station Blackout DESCRIPTION: See AQUA Book, HUREG-0606 SCHEDULE: See AQUA Book, NUREG-0606 CURRENT STATUS: See AQUA Book, HUREG-0606 PROBLEMS:

ISSUE #

TYPE FLAG

_iTATUS__

PRIORITY TASK A.P.

TECH. R E.12 JMPLEMENTATION TACS #

UPDATED

=

A-4S USI ACTIVE YES INCOMPLETE NOT STARTED 12/17/81 NRR ANDREW MARCHESE (492-4712) GIB/ DST TITLE:

Shutdown Decay Heat Removal Requirements 4

DESCRIPTION: See AQUA Book, NUREG-0606 SCHEDULE: See AQUA Book, NUREG-0606 CURRENT STATUS: See AQUA Book, HUREG-0606 PROBLEMS:

l i'

t I

l 4

)

l i

4 9,

v v

ISSUE e TYPE FLAG STATUS PRIORITY TASK A.P.

TECH. RES IMPLEMENTATION TACS 8 UPDATED 2

A-46 USI

• • A C T Ib E YES INCOMPLETE NOT STARTED 12/17/81 NRR NEWTON ANDERSON (492-7476) GIB/ DST TITLE:

Seismic Qualification of Equipment in Operating Plants DESCRIPTIDH: See AQUA Book, HUREG-0606 SCHEDULE: Sco AQUA Book, NUREG-0606 CURRENT STATUS: See AQUA Book, HUREG-0606 PROBLEMS:

ISSUE 8 TYPE FLAG STATUS PRIORITY TASK A.P.

TECH. RES.

IMPLEMENTATIDH TACS #

UPDATED A-47 USI ACTIVE NO INCOMPLETE NOT STARTED 12/17/81 NRR ANDREW SZUKIEWICZ (492-4713) GIB/ DST TITLE:

Safety Implications of Control Systems DESCRIPTIDH: See AQUA Book, HUREG-0606 SCHEDULE: See AQUA Book, NUREG-0606 CURRENT STATUS: See AQUA Book, NUREG-0606 PROBLEMS:

ISSUE #

TYPE FLAG STATUS _

PRIORITY TASK A.P.

TECH. RES IMPLEMENTATION TACS 8 MPDATED 2

A-48 USI ACTIVE NO INCOMPLETE NOT STARTED 12/17/81 HRR CLIFFORD ANDERSON (492-7486) GIB/ DST TITLE:

Hydrogen Control Measures and Effects of Hydrogen Burns on Safety Equipment DESCRIPTION: See AQUA Book, HUREG-0606 SCHEDULE: See AQUA Book, HUREG-0606 CURRENT STATUS: See AQUA Book, NUREG-0606 PROBLEMS:

ISSUE 8 TYPE FLAG STATUS _

PRIORITY TASK A.P.

TECH. RES 1MPLEMENTATION TACS 8 UPDATED _

2 A-49 USI ACTIVE YES INCOMPLETE HOT STARTED 12/17/81 NRR ROY WOODS (492-4714) GIB/ DST TITLE:

Pressurized Thermal Shock DESCRIPTIDH: See AQUA Book, HUREG-0606 SCHEDULE: See AQUA Book, HUREG-0606 CURRENT STATUS: See AQUA Book, HUREG-0606 PROBLEMS:

ISSUE #

TYPE FLAG STATUS _

PRIORITY TASK A.P.

TECH. RE12 IMPLEMENTATION TACS 8 UPDATED B-14 USI ACTIVE NO INCOMPLETE NOT STARTED 12/17/81 NRR CLIFFORD ANDERSON (492-7486) GIB/ DST TITLE:

Study of Hydrogen Mixing Capability in Containment Post-LOCA i

DESCRIPTIDH: This task is included as part of USI A-48 SCHEDULE: See AQUA Book, HUREG-0606 CURRENT STATUS: See AQUA Book, NUREG-0606 PROBLEMS:

3 ISSUE #

TYPE FLAG STATUS _

PRIORITY TASK A.P.

TECH. RES IMPLEMENTATION TACS #

UPDATER _

2 B-18 USI ACTIVE NO INCOMPLETE NOT STARTED 12/17/81 NRR A. W. SERKIZ (492-4217) GIB/ DST TITLE: Vortex Suppression Requirements for Containment Sumps.

DESCRIPTION: This task is included as part of USI A-43 " Containment

]

Emergency Sump performance.

SCHEDULE: See AQUA Book. HUREG-0606 CURRENT STATUS: See AQUA Book, HUREG-0606 j

PROBLEMS:

.t ISSUE #

TYPE FLAG STATUS PRIORITY TASK A.P.

TECH. RES.

IMPLEMENTATION TACS 8 UPDATED B-24 USI ACTIVE NO INCOMPLETE NOT STARIED 12/17/81 NRR NEWTON ANDERSON (492-7476) GIB/ DST TITLE: Seismic Qualification of Electrical and Mechanical Components DESCRIPTION: This task is included in USI A-46 " Seismic Qualification of Equipment in Operating Plants."

I SCHEDULE: See AQUA Book, NUREG-0606 CURRENT STATUS: See AQUA Book, NUREG-0606

{

PROBLEMS:

i a

I t

i

.i 1

ISSUE #

TYPE FLAG

_ STATUS PRIORJJY TASK A.P.

TECH. RES.

IMPLEMENTATION IAgi_4 UPDATED.

B-52 USI ACTIVE YES COMPLETE IN PROGRESS 12/17/81 HRR JIM SHEA (492-7231) ORB 5/DL TITLE:

Fuel Assembly Seismic and LOCA Responses DESCRIPTION: The fuel assembly is a highly nonlinear structure which can be subjected to substantial loadings during seismic excitations and LOCA transients.

The integrity of this assembly is critical for plant safety.

Extensive work has been completed by NSSS vendors for the determination of fuel element responso during the sustained vibrations of normal operation. However, there is a need to study the behavior of these assemblies during accident conditions.

Future work will include a determination as to whether or not existing geometry can I

adequately satisfy the functional design criteria.

Vibration interaction between components of the assembly and reactor pressure vessel will be investigated.

Subsequent to its approval as a Category B task, this task has been included within the scope of Task A-2, Asymmetric Blowdown Loads on PWR Primary Coolant Systers.

SCHEDULE: See AQUA Book, HUREG-0606 for implementation schedule and status.

CURRENT STATUS:

PROBLEMS:

ISSUE #

TYPE FLAG STATUS PRIORITY TASK A.P.

IECH, RES.

IMPLEMENTATION TACS 8 UPDATED B-57 USI ACTIVE YES INCOMPLETE NOT STARTED 12/17/81 NRR PAT BARAN0WSKY (443-5960) PAS /RES 4

TITLE:

Station Blackout DESCRIPTION: This task is part of USI A-44, " Station Blackout" SCHEDULE: See AQUA Book, HUREG-0606 CURRENT STATUS: See AQUA Book, HUREG-0606 PROBLEMS:

ISSUE 8 TYPE FLAG STATUS PRIORITY T_ASK A.P.

TECH. REli IMPLEMENTATION TACS 8 UPDATED.

C-3 USI ACTIVE YES INCOMPLETE NOT STARTED 12/17/81 HRR A. SERKIZ (492-4217) GIB/ DST TITLE:

Insulation Usage with in Containment DESCRIPTION: Various kinds of insulation are being used on piping and components inside the containment of a nuclear power plant.

Of concern is its behavior under pipe break accident conditions with regard to the potential for blocking vent paths in subcompartments and impairing the effectiveness of the containment emergency sumps.

The purpose of this task will be to gain a better understanding of how insulation might behave under pipe break accident conditions. This information will then be used to assess the assumptions made regarding insulation behavior for subcompartment analysis and the need for revising containment emergency sump desian requirements.

SCHEDULE: See AQUA Book, HUREG-0606.

CURRENT STATUS: This task is included in USI A-43, " Containment Emergency Sump Performance".

j PROBLEMS:

(

h

ISSUE #

TYPE FLAG STATUS PRIORITY TASK A.P.

LFCH. RE12 IMPLEMENTATION TACS #

UPDATED C-11 USI ACTIVE YES INCOMPLETE NOT STARTED 12/!?/81 NRR ANDY MARCHESE (492-4712)

GIB/ DST TITLE:

Assessment of Failure and Reliability of Pumps and Valves.

DESCRIPTION: The operating experience of nuclear power plants indicates that a number of valves, valve operators and pumps fail to operate as specified in the techo' cal specifications either under testing conditions or when they are called upon to perform.

The operating experience is documented by the Office of Management Information and Program Control (MIPC) publications in a monthly report of LERs sorted by components which include pumps, valves, and valve operators. Most of these occurrences relate to valvo leakage, valve act-uation, and safety / relief valve operation outside their operational bounds.

The main steam isolation, safety and sole.ioid valves caused the most frequent abnormal occurrences in safety related systems.

Valve malfunctions can cause forced outage of operating plants.

It is noted that about 10% of all outage time can be attributed to the malfunction of the critical pumps and valves within the plant.

Of primary interest are outages caused by the main steam isolation and safety / relief valves.

Several adverse operating experiences concerning main steam isolation valves (MSIVs) were reported to the Office of Inspection and Enforcement following operational tests and spurious closures at various PWR plants.

This led to a staff investigation of MSIVs at all operating and near operating facilities.

This investigation has recently been completed.

The principal activity under this task will be the evaluation of active pump and valves with respect to their operability and reliability under accident loading, i.e.,

loss of coolant accident and safe shutdown earthquake.

SCHEDULE: Not developed.

CURRENT STATUS: This task is included in the scope of USI A-45, " Shutdown Decay Heat Removal Requirements" See AQUA Book for status.

PROBLEMS:

J3 SUE #

TYPE FLAG STATUS PRIORITY TASK A.P.

TECH. RES.

IMPLEMENTATION TACS #

UPDATED _

C-13 USI ACTIVE YES INCOMPLETE IN PROGRESS 12/17/81 HRR FRANK C0FFMAN (492-7497)

RRAB/ DST TITLE:

Non Random Failures DESCRIPTIDH: This is an ACRS generic concern.

It formerly was referred to as common modo failure of identical components exposed to identical or nearly identical conditions or environments.

The concern now has been expanded to include other types of multiple failures for which the consequences and probabilities cannot be predicted by application of the single failure criterion, such as use of the same sensors or components for both control and protection system, sequential multiple failures due to a domino effect, or simultaneous multiple failures due to a single fault.

This task has been included in Tasks A-9, A-30, A-35, B-56, and B-57.

SCHEDULE: See Aqua Book, HUREG-0606.

CURRENT STATUS: This task is included as part of USI A-17, " Systems Interaction".

PROBLEMS:

PART IIA: RESOLVED SAFETY ISSUES ISSUE #

TYPE FLAG

_ STATUS PRIORITY TASK A.P.

_T ECN. REi.

IMPLEMENTATION TACS #

UPDATED.

A-13 S

RESOLVED YES COMPLETE NOT REQUIRED 12/17/81 HRR RENE LEE (492-4417) MEB/DE TITLE:

Snubber Operability Assurance DESCRIPTION: A substantial number of licensee event reports have been submitted on snubber malfunctions.

This has lead to an NRC concern regarding the effect of snubber malfunctions on plant safety.

For a complete problem description of task, see NUREG-0371, November 1978.

SCHEDULE: N/A CURRENT STATUS: For operating plants, standard Technical Specification 3/4.7.9 (3/4.7.5 for BWRs) has been issued.

For CP and OL reviews, SRP 3.9.3 has been updated to include snubbers.

PROBLEMS:

ISSUE #

TYPE FLAG

. STATUS PRIORITY TASK A.P.

TECH. RES IMPLEMfMTATION TACS #

UPDATED 2

A-23 S

RESOLVED YES COMPLETE COMPLETED 20445 12/17/81 NRR JIM SHAPAKER (492-9416) CSB/DSI TITLE:

Containment Leak Testing DESCRIPTION: This task was developed to incorporate needed changes to Appendix J to reflect current understanding and licensing practice.

A complete task description can be found in NUREG-0371 SCHEDULE: Not developed.

CURRENT STATUS: A revision to Appendix J is being preparco snd will result in a rulemaking proceeding.

NRR action under A-23 is complete.

RES contact is G. Arndt.

PROBLEMS: None.

l 1

ISSUE #

TYPE FLAG STATUS _

PRIORITY TASK A.P.

IECN. REi.

IMPLEMENTATION TACS #

MPDATED l

A-25 S

RESOLVED YES COMPLETE COMPLETED 02140 12/17/81 I

HRR M. SRINIVASAN (492-7255) PSB/DSI l

TITLE:

Non Safety loads on Class IE Power Sources DESCRIPTION: The safety issue addressed by this task is whether or not 1

I the reliability of class IE power sources is significantly affected by allowing the sharing of these sources by loads that perform safety functions and loads that perform normal plant functions.

See NUREG-0371 for a complete task description.

SCHEDULE: None j

i l

CURRENT STATUS: Contractor report received.

The issue has been addressed

(

in Reg. Guide 1.75 and is considered to be resolved.

I PROBLEMS:

i l

l l

l

ISSUE #

TYPE FLAG

_ STATUS PRIORITY TASK A.P.

TECH. R.E S IMPLEMENTATIGH TACS #

UPDATED 2

A-35 S

RESOLVED VES COMPLETE COMPLETED 12/17/81 20490 NRR R.

PREVATTE (492-9491) PSB/DSI TITLE:

Adequacy of Offsite Power Systems DESCRIPTION: To assess the reliability of offsite power systems.

See H' ' EG-0 410 and i ssue 10 of HUREG-0138 for a detailed task desc-iition.

SCHEDULE-SRP 8.3.1 revised.

Backfit of requirements to all operating reactors.

Complete.

CURRENT STATUS: Resolution is form 51ized in SRP 8.3.1 All Ols since 1977 have complied with these requirements.

PROBLEMS: Hone ISSUE #

TYPE FLAG STATUS PRIORITY TASK A.P.

IECH. REE.

IMPLEMENTATION TACS #

UPDATED _

B-6 S

RESOLVED YES COMPLETE COMPLETED 12/17/81 HRR SHOU - HIEH HOU (492-8438) MEB/DE TITLE:

Loads. Load Combinations, Stress Limits DESCRIPTIDH: This task will define how design loads should be combined on components, piping systems and structures and the stress limits to be used in evaluating structural integrity and operability when subjected to these loads.

SCHEDULE: Revision of SRP 3.9.3 was completed.

CURRENT STATUS: HUREG-0484 regarding load combination methodology only has been issued.

Criteria regarding acceptability of using SRSS for combining dynamic responses is planned to be implemented on all Mark II plants as part of OL reviews. Revision of SRP 3.9.3 has been completed.

PROBLEMS:

ISSUE #

TYPE FLAG STATUS _

PRIORITY TASK A.P.

TECH. RES.

IMP (fMENTATIDH TACS #

UPDATED _

B-9 S

RESOLVED HO COMPLETE N0i REQUIRED 12/17/81 NRR AL UNGARO (492-4946) PSB/DSI TITLE:

Electrical Cable Penetrations of Containment DESCRIPTION: Reevaluate current licensing criteria for the design and qualification testing of electrical penetrations in the reactor containment.

SCHEDULE: Hone CURRENT STATUS: Complete.

ORHL evaluation determined no now requirements required.

PROBLEMS:

l l

L P

ISSUE #

TYPE FLAG

. STATUS PRIORITY TASK A.P.

TECH, REi.

IMPLEMENTATION TACS #

UPDATED _

B-56 S

RESOLVED HO COMPLETE COMPLETED 12/17/81 HRR AL UHGARD (492-4946) PSB/DSI TITLE:

Diesel Reliability DESCRIPTION: An examination of Licensee Event Reports on the experience with diesel generators (1969-1975) indicates that the emergency onsite diesel generators at operating plant have an average reliability of about 0.94 compared with the NRC's reliability goal of 0.99.

The reliability of the diesol generator is strongly dependent on the interaction of the following factors:

design, testing and operational requirements, operational history, inspections, maintenance, and the personnel qualification of operators.

The lack of detail regarding the failures reported in the Licenseo Event Reports make it difficult for the NRC to establish the causes of the reported failures.

A comprehensive review to datormine the underlying and recurring causes of the reported failures is necessary in order to enable the NRC to establish improved guidance and requirements to increase the reliability fo the emergency onsite diesel gonorators.

SCHEDULE: N/A CURRENT STATUS: Technical resolution of B-56 is described in NUREG/CR-0660.

The SRP has been updated to incorporate the staff position regarding B-56, and is being implemented routinely on now applications. A decision has not boon made on oporating reactors.

PROBLEMS:

ISSUE #

11EE FLAG STATUS _

PRIORITY TASK A.P.

TECH. REi.

IMPLEMENTATION TACS #

UPDATED B-60 S

RESOLVED H0 COMPLETE COMPLETED 12/17/81 HRR G. WEIDENHAMMER (443-5997) MSEB/RES TITLE:

Loose Parts Monitoring System DESCRIPTION: The presence of a looso (i.e., disengaged and/or drifting) object in the primary coolant system can be indicative of degraded reactor safety resulting from failure or unakening of a safety related component.

A looso part, whether it be from a failed or weakened componont or from an item inadvertently left in the primary system during construction, refueling, or maintenance procedures, can contribute to component damage and material wear by frequent impacting with other parts in the system.

A loose part can pose a serious throat of partial flow blockaqo with attendant departura from nucleato boiling (DNB) which in turn could result in failure of fuel cladding.

In addition, a looso part increases the potential for control rod jamming and for accumulation of increased levels of radioactive crud in the primary system.

The primary purpose of the looso part detection program is the early detection of looso metallic parts in the primary system.

Early detection can provide the time required to avoid or mitigate safety-related damaqo to or malfunction of primary system components.

The purpose of this task is to resolve any outstanding issues related to the proposed Roqulatory Guide, including the developmont of staff po sitions and quidance with respect to upgrading loose parts detection sy stems at operating facili ties.

SCHEDULE: N/A CURRENT STATUS: All cps and OLs under review after 1/1/78 woro required to moet privisions of RG 1.133.

CP and OL applicants after 1/1/78 are required to review their systems and determine if they comply or are equivalent.

See implementaticn section of RG 1.133 for details.

PROBLEMS:

ISSUE #

TYPE FLAG STATUS.

PRIORITY TASK A.P.

If_C H. REE, IMPLEMENTATION TACS #

UPDATED B-66 S

RESOLVED COMPLETE COMPLETED 12/17/81 HRR R. W.

HOUSTON (492-7880) AEB/DSI TITLE:

Control Room Infiltration Measurements DESCRIPTION: A key parameter affecting control room habitability under the conditions described in General Design Critoria 19 and Standard Review Plan 6.4 is the magnitude of control room air infiltration rates.

Current estimates of these rates are based on data relating to buildings that are substantially different then typical nuclear power plant control room buildings.

Additional experimentally-measured air exchange rates of operating reactor control rooms are nooded to develop an improved data base.

This task will support the following requirements:

Criterion 19 of Appendix A to 10 CFR Part 50 (General Design Criteria for Nuclear Power Plants) requires thaA control rooms be accessable and habitable under both normal and accident conditions.

Safety Standard Review Plan 6.4 Habitability Systems and SRP 9.4.1 Control Room Area Ventilation Systems specify a review of the control room habitability systems with respect to the functional performance required to maintain a habitable control room area in the event of postulated accidents.

SCHEDULE: Complete CURRENT STATUS: This program is complete.

Acceptance criteria have been incorporated into the SRP.

PROBLEMS:

ISSUE #

fYPE FLAG STATUS PRIORITY TASK A.P.

TECH. RE12 IMPLEMENTATIOE TACS #

UPDATED B-70 S

RESOLVED NO COMPLETE NOT REQUIRED 92138 12/17/81 NRR M.

SRINIVASAN (492-7255)

PSB/DSI TITLE:

Power Grid Frequency Dogradation and Effect on Primary Coolant Pumps DESCRIPTION: Offsito power system frequency decay, depending on the rate of decay, could provide an electrical brako on the reactor coolant pump motors that could slow the pumps faster than the assumed flywheel coastdown flow rates normally used in analyzing loss-of-flow accidents.

Task A-35 will determine a maximum credible frequency decay rate to be used in this task.

This task will datormine if any additional measures are necessary to protect against a frequency decay event.

SCHEDULE: Complete CURRENT STATUS: Current staff position on this task is that it is not a significant safety issue in a practical technicsl sense and should be deleted as a generic safety concern.

Branch Technical position ICSB-15 in Appendix 8A of the SRP which addressos this issue is bainq deleted.

A memorandum describing basis for resolution has been prepared by DSI.

This issue has been resolved.

PROBLEMS:

ISSUE #

. TYPE FLAG STATUS PRIORITY TASK A.P.

_T ECH. R E12 IMPLEMENTATION TACS #

UPDATED B-71 S

RESOLVED NO COMPLETE COMPLETED 12/17/81 TITLE:

Incident Response DESCRIPTION: Present NRC actions taken in response to a serious incident are directed from an Incident Responso Center (IRC).

To implement an adequate responso, it is necessary that the IRC be equipped with appropriate communications services, information handling and evaluation aids, pre-approved action quidelinos, and techncial and management personnel resources.

The present IRC, which is manned during the course of an incident by a team of NRC manaqcment and technical staff, has all of thse to some degree.

A joint NRR/IE paper dated i

July 23, 1976, addresses whether practical and useful short-term j

and long-term improvements can be made.

The paper (1) discussos the practicality and nood for various IRC resources as a function of the goals of the NRC response capability and the time sequences of a spectrum of incident scenarios judged typical of those that are at least theoretically possible, and (2) makes recommendations with regard to NRR and IE actions to improve the IRC.

The papor was reviewed and discussed by the Directors of NRR and IE, and the implementation recommendations agreed to in principle and a commitment of manpower was made by each of the Directors.

IE has had and now has work proceeding in the areas for which they i

are responsible. HMSS also has responsibility for contributing to the incident management effort.

SCHEDULE: Nono CURRENT STATUS: This issue has boon resolved by implementation of past TMI requirements for response to incidents.

PROBLEMS:

ISSUE #

IXEE FLAG

_ STATUS PRIORITY TASK A.P.

IECH. RES.

IMPLEMENTAllRH IASS #

UPDATED.

D-3 S

RESOLVED NO COMPLETE NOT REQUIRED 02038 12/17/81 NRR DAN FIEND (492-9474) CPB/DSI TITLE:

Control Rod Drop Accident DESCRIPTION: This is an ACRS generic concern.

It involves assessing the uncertainties in calculations of the control drop accident including the choice of negative reactivity insortion rate den to a scram and the potential differences between a two-dimensional j

and a three-dimensional calculation.

SCHEDULE: Complete

/

CURRENT STATUS: Completed and closed out by later to E. J. Case from R. J. Mattson i

i dated March 6, 1978

Subject:

Task No. D-3 Control Rod Drop Accident.

PROBLEMS:

,1 9

PART IIB: ACTIVE SAFETY ISSUES ISSUE #

TYPE FLAG STAlUi_

PRIORITY TASK A.P.

JECH. RES, JMPLEMENTATION TACS 8 UPDATED A-15 S

ACTIVE YES INCOMPLETE NOT STARTED 12/17/81 HRR PHIL MATTHEWS (492-8595)

CHEB/DE TITLE:

Primary Coolant System Decontamination and Steam Generator Chemical Cleaning DESCRIPTION: See HUREG-0371 for Task Description.

SCHEDULE: mid-1983.

CURRENT STATUS: Two HUREG reports (HUREG/CR-0986 and HUREG/CR-1915) have been prepared for NRC by PHL. PHL, under T.A. contract to NRR is (1) developing docontamination administration and radiological quidelines that can be in-corporated into SRP/BTP relating to ALARA and (2) identifying information that licensoos should provido for staff review of proposed system decontam-1 inations. This effort will be completed by mid-1983.

HRC is to issue a license amendment and toch spec change shortly to author-ice proceeding with decontamination at Dresden 1 The hearing is to proceed in parallel with the authorization. HRR is reviewing partial decon-. amination associated with plant modifications (e.g.,

steam generator copairs/ replace-mont) on an ad hoc basis.

PROBLEMS:

ISSUE 8 TYPE FLAG STATUS PRIORITY TASK A.P.

IECH. RE.S IMPLEMENTATIOE TACS #

UPDATED 1

A-16 S

ACTIVE YES INCOMPLETE NOT DETERMINED 12/17/81 NRR SUMMER SUN (492-9499) CPB/DSI TITLE:

Steam Effects on BWR Core Spray Distribution DESCRIPTION: During tests conducted in Europe and later confirmed by G.E.,

it was discovered that the presence of steam and pressure in and above the upper core region could adversoly affect the distribution of flow from certain types of coro spray no les.

See HUREG-0371 for a complete task description.

SCHEDULE: Task is scheduled to be completed in September 1983.

CURRENT STATUS: The final series of nor:lo tests have been conducted by GE at their facility in Lynn, Mass.

Information from this test series should provido sufficient information for the NRC to reach final conclusions on Task A-16 and to completely develop and document staff conclusions.

Test results are documented in HUREG/CR-1707.

The computer code will be modified and the data assessed to close out this issue.

PROBLEMS:

a 4

4 l

ISSUE #

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PRIORITY TASK A.P.

JECH. RES IMPLEMENTATION TACS #

UPDATED 2

A-19 5

ACTIVE YES INCCMPLETE NOT DETERMINED 02135 12/ 17/81 HRR J. JOYCE (492-9454)

ICSB/DSI TITLE:

Digital Computer Protection System DESCRIPTION: A need exists to standardize the safety review of reactor protection systems incorporating digital computers, since digital technology is considerably different from the analog technology previously used for RPS systems.

The technology is rapidly changing and needs to be assessed.

SCHEDULE: Not developed.

CURRENT STATUS: Current OL reviews are being conducted on an ad hoc basis.

A joint effort (NRR with ORNL as a consultant) and RES will be directed toward development of a Regulatory Guida and SRP revision for use in subsequent reviews.

The majority of the cost of this project is borne by T.A.

It is estimated that ICSB review of the proposed R.G. will be no greater than one person week.

Implementation will apply to cascwork only.

PROBLEMS:

l}SUF #

TYPE FLAG STATUS PRIORITY TASK A.P.

IECH. RES2 IMPLEMENTATION TACS #

UPDATEQ_

A-29 S

ACTIVE YES INCOMPLETE 12/17/81 RES JERRY ENNIS (443-5976)

TITLE:

Neclear Power Plant Design for the reduction of Vulnerability to Industrial Sabotage.

DESCRIPTION: Soo NUREG-0371 for task description.

SCHEDULE: Not established.

CURRENT STATUS: An effort to determine requirements to compartmentalize plant areas to prevent sabotaqo is underway.

LASL is conducting vital area analysis.

Results of LASL work will serve as a starting point identifying generic requirements to compartmentalize.

A proposal has been mado for a Committee of HRR/NMSS to study requirements.

PROBLEMS:

ISSUE #

TYPE FLAG STATUS PRIORITY TASK A.P.

IfCH. RES.

IMPLEMENTATION TACS #

UPDATED A-30 S

ACTIVE YES COMPLETE IN PROGRESS 04587 12/17/81 20470 HRR M. SRINIVASAN (492-7255)

PSB/DSI TITLE:

Adoquacy of safety related DC power supplies.

DESCRIPTION: Soo NUREG-0371 for task description.

SCHEDULE: Implementation schedule not established.

CURRENT STATUS: NUREG-0666, "A Probabalistic Safety Analysis of DC Power Supply Requirements for Nuclear Power Plants" was issued in April

'8i.

This report presents the technical resolution of A-30.

Impicmentation guidos are being developed. A scope of work and letter for OMB clearance will be prepared.

PROBLEMS:

ISSUE 8 TYPE FLAG STATUS.

PRIORITY JASK A.P.

HCH. RES.

IMPLEMENTATION TACS #

UPDATED _

A-32 S

ACTIVE YES EHcCMPLETE NOT STARTED 12/17/81 NRR

0. ROTHBERG (492-7864) SEB/DE TITLE: Missile Effects DESCRIPTION: This task involves development of specific licensing positions and bases for protection of nuclear plants against missile impact effects.

Soo NUREG-0371 for a complete task description.

SCHEDULE: There is no currently established schedule for this task.

CURRENT STATUS: EPRI has completed some of a series of full scale and reduced scale turbine missile impact tests and are in the process of completing the remaining tests in the series. A series of tornado missile impact tests have been completed.

PROBLEMS:

ISSUE 8 TYPE FLAG STATUi_

PRIORITY TASK A.P.

IECH. REE.

IMPLEMENTATION TACS #

UPDATED _

A-34 S

ACTIVE YES COMPLETE IN PROGRESS 04062 12/17/81 2048S HRR J. ROSENTHAL (492-7589)

ICSB/DSI TITLE:

Instruments for Monitoring Radiation and Process Variables During Accidents DESCRIPTION: Develop criteria and guidelines for functional and operational capabilities required of the different classes of instruments.

See HUREG-0371 for a complete task description.

i SCHEDULE: Not applicable CURRENT STATUS: Tech. resolution is provided in R.G.

1.97, Rev. 2 issued 12/80.

Implementation for ORS-is to be completed by 7/1/83.

PROBLEMS:

t 111JE #

TYPE FLAG STATMS_

PRIORITY IASK A.P.

TECH. RES.

IMPLEMENTATION TACS #

UPDATED.

A-37 S

ACTIVE YES INCOMPLETE NOT STARTED 12/17/81 NRR

0. ROTilBERG (492-7864)

SEB/DE TITLE:

Turbine Missiles DESCRIPTION: See HUREG-0317 for Task description.

SCHEDULE: Not developed.

i. '

CURRENT STATUS: EPRI has completed part of a series of full and reduced scale missile tests. Most of the work to date on this task has been on turbine blade cracking.

PROBLEMS:

J

ISSUE _1 TYPE FLAG STATUS PRIORITY TASK A.P.

TECH. R E5_.

IMPLEMENTATION TACS 4 UPDATED B-10 S

ACTIVE YES INCOMPLETE NOT DETERMINED 04126 12/17/81 02271 NRR MEL FIELDS (492-9717) CSB/DSI TITLE:

Behavior of BWR Mark III Containments DESCRIPTIDH: Staff evaluation of the Mark III containment and documentation of the method used to validate the analytical models and assumptions needed to predict containment pressures in the event of a LOCA.

SCHEDULE: Completion of task in mid-1982.

CURRENT STATUS: Staff position has been developed and sent to GE. GE response is scheduled for November 30, 1981 Draft HUREG is scheduled to be issued for comment February 1982. Final HUREG is scheduled to be issued June 1982.

PROBLEMS:

ISSUE 8 TYPE FLAG STATUS _

PRIORITY TASK A.P.

TEG_H - RES.

IMPLEMENTATION TACS 8 UPDATED B-26 S

ACTIVE YES IHCOMPLETE IN PROGRESS 12/17/81 NRR MTEB/DE TITLE: Structural Integrity of Containment Penetrations DESCRIPTION: This task involves an evaluation to assess the adequacy of specific containment penetration designs from the point of view of structural integrity and inservice inspection requirements.

SCHEDULE: Not developed.

CURRENT STATUS: The task involves 2 issues.

The first is structural evaluation of wolded flued head assemblies.

This part has been resolved.

The second area involves the volumetric examination as required by ASME Code,Section XI.

This issue is only partially resolved and additional independent verification needs to be performed.

The Materials Engineering Brancle is monitoring the inservice inspection at each plant.

PROBLEMS:

k

_~

ISSUE 8 TYPE FLAG STATUS PRIORITY TASK A.P.

TECH. RES IMPLEMENTATION TACS 8 UPDATED 2

B-47 S

ACTIVE YES INCOMPLETE NOT STARTED 12/17/81 HRR DAVE SELLERS (492-8968) MTEB/DE

~

TITLE:

Inservice Inspection Criteria for Supports and Bolting of Class 1,

2, and 3 and MC Components DESCRIPTION: This task is partially covered by USI-A-12 " Fracture Toughness of Steam Generation and Reactor Coolant Pump Supports".

The original task description as published in HUREG-0371 is as follows:

Results from inspections of various structural components in the torus support systems of operating BWRs have indicated several inconsistencies between the design drawings and the "as built" hardware, including missing support struts, out of tolerance weld dimensions, unwelded regions and unsupported columns.

In addition, a limited number of separate inspections have been performed on PWR steam generator supports.

The results of these inspections revealed several cracked support bolts.

In view of the above, additional investigation of BWR and PWR component support systems should be undertaken to determine if similar deficiencies and "of f design" conditons exist generally in operating plants.

This investigation should determine the extent C

of support system deficiencies, and whether the deficiencies are service induced or are the result of faulty construction.

Determination of the extent and nature of the deficiencies is necessary to define the possible safety significance and to provide quidance for further appropriate staff action regarding inservice inspection of supports.

SCHEDULE: Not developed.

CURRENT STATUS: Inservice inspection criteria for support structures is addressed by USI A-12. Criteria for high strength bolting is included in a recommended generic issue on high strength bolting.

PROBLEMS:

1 4

ISSUE 8 TYPE

_ FLAG STATUS PRIORITY TASK A.P.

TECH. RE1.

IMPLEMENTATION TACS #

UPDATED B-48 S

ACTIVE NO COMPLETE IN PROGRESS 12/17/81 HRR WARREN HAZELTON (492-8186) MTEB/DE TITLE:

BWR CRD Mechanical Failure (Collet Housing)

DESCRIPTIDH: Surface cracks have boon discovered in control rod drive internal parts at some operating BWR plants.

This cracking, although only observed to be localized in nature, if propogated could potentially affect the capability of the control rod drive to perform its design function.

Cracking has boon identified in the following control rod drive internal parts:

the collet retaining tube (CRT), the posion tubo, and the index tube.

The cracking in the collet retaining tubes was located near a transition in tube thickness approximately six inchos down the tube.

The cracks appear to have initiated on the outer tube surface and to have propoqated circumferentially in the areas betwoon the flow holes of the tube.

The cracking in the index and piston tubos have occurred in the creviced, sensitized and nor -nitridad threaded areas of these tubos.

The extent of the cracking observed at operating BWR plants to date has not been severe enough to impair the ability of the control rod drives to operate in their required capacity.

As an interim precautionary measure, additional technical specification requirements were established for operating reactors which require shutdown within 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> of detecting a rod unless investigation demonstrates that the cause of the failure was not due to a separated collet tube.

Another technical specification that has long been in effect for operating reactors requires exorcising fully or partially withdrawn rods once every week as a part of the corrosion prevention program.

This requirement also providos demonstration of CRT integrity.

SCHEDULE: General Electric is working with the affected utilities. No further staff effort is required.

CURRENT STATUS: General E1cetric is replacinq old style surface hardened colletts with new non-surface hardoned colletts, in the affected plants.

PROBLEMS:

_. _ - ~ __.

ISSUE #

IIPE FLAG STATUS PRIORITY TASK A.P.

IEC H, R ES.

IMPLEMENTATION TACS 8 UPDATED B-53 S

ACTIVE NO COMPLETE IN PROGRESS 12/17/81 NRR J. LAZEVNICK (492-9483) PSB/DSI TITLE:

Load Break Switch DESCRIPTION: Plant designs which utilize generator load circuit breakers to satisfy the requirement for an immediate access circuit stated in GDC-17 must be prototype tested to demonstrate functional capability.

This task. involves the preparation of a staff position to clarify and document the prototype testing requirements for generator load circuit i

breakers and associated circuitry used to provide an immediate access circuit in accordance with GDC-17.

This technical position, has been completed and will be' incorporated in the Standard Review Plan.

SCHEDULE: Completion of manacoment review of the BTP is expected in early 1982, at which time.it will t9 incorporated into the SRP.

CURRENT STATUS: Not applicable to operating reactors.

The first applicable plant was McGuire and the issue resolved on this docket.

Other OLs will be handled the same way.

A Branch Technical position i

has been written and is awaiting management review, after which it will be incorporated into SRP 8.2.

PROBLEMS:

4-1 L

i s

1 h

i a

s 1

4

ISSUE 8 TYPE FLAG STATUS _

PRIORITY TASK A.P.

TECH. R E_S IMPLEMENTATION TACS 8 UPDATED 2

B-54 S

ACTIVE NO INCOMPLETE IN PROGRESS 12/17/81 NRR C. TIHKLER (492-9420) CS B/ DS'I TITLE:

Ice Condenser Containments DESCRIPTION: This task involves two staff efforts associated with the ice 4

condenser containment concept.

(1) Verification of the established design margin for ice condenser containments using CONTEMPT 4 code.

Contact:

L. Ruth (492-9423)

CSB.

(2) Reviewing the surveillance programs for ice inventory and functional performance testing at operating facilities to determine whether the surveillance frequencies should be increased or other action should be taken.

Operating experience from the D. C. Cook plant has indicated that sublimation and ice melting are causing a loss of ice inventory and related functional performance problems.

Contact:

J. Shapaker (492-9416)

CSB.

SCHEDULE: Not developed.

CURRENT STATUS: EG8G, Idaho is under contract for Item 1.

Item 2 is ongoing within the staff.

PROBLEMS:

ISSUE #

TYPE FLAG STATUS _

PRIORITY TASK A.P.

IECH. RES.

IMPtEMENTATION TACS #

UPDATED 2-63 S

ACTIVE NO C0f1PLETE IN PROGRESS 12/17/81 NRR A. CAPPUCI (492-4416) MEB/DE TITLE:

Isolation of Low Pressure Systems Connected to tFn Reactor Coolant Pressure Boundary DESCRIPTIOH: There are several systems connected to the reactor coolant pressure boundary that have design pressures that are considerably below the reactor coolant system operating pressure.

The NRC staff has required that valves forming the interface between these high and low pressure systems have sufficient redundancy to assure that the low pressure systems are not subjected to pressures which exceed their design limits.

Recently, there has been discussion relative to the adequacy of the isolation of low pressure systems that are connected to the reactor coolant pressure boundary. Past revicws have concentrated on insuring isolation of the residual heat removal system, which is a j

low pressure system on almost all PWRs and BWRs.

Current reviews of license applications for new plants, that is, our CP/0L 1

evaluations, are based on guidelines set forth in the Standard Review Plan (SRP).

How ver, these guidelines were not available during the reviews of the plants which are currently operating.

SCHEDULE: Not establi.hed CURRENT STATUS: An order was issued to all operating reactors in April 4

1981 to comrly with requirements of technical resolution for event V configurations.

All other configurations are being addressed by inservice testing SERs and are being issued as license amendments.

Resolution is documented in Appendix A to Standard Review Plan

3.9.6. PROBLEMS

ISSUE e TXPE FLAG STATUE _

ERIORITY TASK A.P.

TECH. RES IMPLEMENTATION TACS 8 UPDATED 2

B-64 S

ACTIVE N0 INCOMPLETE IN PROGRESS 12/17/88 HRR PHIL MATTHEWS (492-8595) CHEB/DE TITLE:

Decomm. ssioning of Reactors DESCRIPTIDH: Establish quidance and acceptance criteria for the Decommissioning of Reactors needs to be devolaped to update Reg Guide 1.86.

A more detailed description is included in NUREG-0471 dated June 1978.

SCHEDULE: See Current Status CURRENT STATUS:

1.

Regulatory Requirements / Guidance l

The staff requirements and guidance for nucicar plant and fuel cycle facility decommissioning are undergoinq extensive review and revision by RES. The major milestones in this program are:

1) Draft Generic EIS - HUREG-0586, issued 1/81

2) Decommissioning Policy Statement originally targeted for transmittal to Commission 6/30/82. RES is considering deleting this milestone and i ssuing a Commission Information Paper in March 1982.

3) Proposed Rule Change - August, 1982

4) Final Generic EIS - August, 1982

5) Final Rule Change - March, 1983 In addition, PHL/HUREG reports have been issued which deal with the l

technology, safety, and costs of decommissioning reference nuclear facilities; e.g.

PWR's (HUREG/CR 0130),

BWR's (HUREG-0672).

Also, RES has three research projects in support of this rulemaking effort; namely, 1) Decontamination as a Procursor to Decommissioning, 2) Long lived activation products in reactor materials, 3) Characterization of radionuclide contaimination throughout LWR power stations.

Currently, the staff conducts its review of proposed decommissioning of specific plants on a case by case basis using existing applicable regulatory requirements and guidance supplemented by applicable l

HUREG reports on reference facilities as discussed above.

The existing regulatory requirements and guidance documents are:

1 1

1) 10 CFR 50.82 - Applications for termination of licenses

2) Regulatory Guide 1.86

" Termination of Operating Licenses l

for Nuclear Reactors"

3) Regulatory Guide 8.8 "Information Relevant to ensuring that Occupational Radiation Exposures at nuclear power will be as low as reasonably achievable (ALARA)

One of the major technical issues to be resolved is that of establishing uniform acceptable residual radioactivity levels of l

activated materials for unrestricted facility release.

Regulatory Guide 1.86 only provides quidance for acceptable levels of residual surface radioactive contamination.

HRR and HMSS are working l

closely.

l PROBLEMS:

i l

I

ISSUE #

TYPE FLAG STATUS _

PRIORITY TASK A.P.

TECH. RES.

IMPLEMENTATION TACS #

UPDATED C-1 S

ACTIVE NO Of1PLETE IN PROGRESS 12/17/81 HRR Z. ROSZTOCZY (492-7209) EQB/DE TITLE:

Assurance of Continuous Long Term Capability of Hermetic Seals on Instrumentation and Electrical Equipment.

DESCRIPTION: Cartain classes of instrumentation incorporate seals.

When safety related components within containment must function during post-LOCA accidentconditions, their operability is sensitive to the ingress of steam or water.

If the seals should become defective as a result of personnel errors in the maintenance of such equipment, such errors could lead to the loss of offective seals and the resultant loss of equipment operability.

The establishment of a basis for confidence that sensitive equipment has a seal during the lifetime of the plant is needed.

If current equipment and practices are found to be inadequate, critoria involving a testable design and/or quality assurance procedures adequate to assure continued seal integrity may be required.

SCHEDULE: Not developed.

CURRENT STATUS: This task is part of the environmental qualification of electical equipment which is covered by commission memorandum und order (CLI-80-21).

This work is currently underway in the EQB of DE.

PROBLEMS:

~.

ISSUE 8 TYPE FLAG STATUi_

PRIORITY TASK A.P.

TECH. RES.

IMPLEMENTATION TACS #

UPDATED C-7 5

ACTIVE NO COMPLETE NOT STARTED 12/17/81 HRR S. PAWLICKI (492-7258)

TITLE:

PWR System Piping i

DESCRIPTION: Combinations of fabrication, stress and environmental have resulted instances of stress corrosion cracking of low pressure schedule 10 type 304 stainless stool piping systems.

Although these systems are not part of the reactor coolant pressure boundary, they are safety

-related; e.g.,

the containment spray system.

The incidance of cracking has been restricted to thin wall, low pressure, low flow systems.

These cracks have occurred adjacent to the weld zones of the thin-walled piping after approximately three to five years of service and were identified by volumetric examination, by leak detection systems, or by visual inspection.

d In each of the cracking events that have occurred to date, the affected piping was determined to have been sensitized and, therefore, particularly vulnerable to corrosive attack.

Current licensing criteria preclude the use of sensitized piping in safety-related piping systems and place increased emphasis on the use of corrosion-resistant material in such systems.

The purpose of this task is to continue to evaluate operating experience to determine if augmented inservice inspection requirements should be established to fur +.her enhance the reliability of such piping systems.

SCHEDULE: Not Developed.

CURRENT STATUS: Resolution is published in HUREG-069i. DST has reviewed 4

recommendations and have prioritized recommendations concerned with j

thermal fatigue cracking. All other recommendations were referred to 9

MTEB/DE. No actions have been taken to implement. With regard to thermal i

fatigue cracking, DST recommended that DE initiate request for an augmented inservice inspection program in letter from T. Murley to R. Vollmer dated July 21, 1981 i'

PROBLEMS:

t I

1 4

1 1

l'

PART IIC: INACTIVE SAFETY IS3UES ISSUE #

IXPE FLAG STATUS PRIORITY TASK A.P.

TECH. RES.

IMPLLMENTATION TACS #

UPDATED A-14 S

INACTIVE YES INCOMPLETE NOT STARTED 12/17/81 HRR M. HUM (492-8118) MTEB/DE TITLE:

Flaw Detection DESCRIPTIOH: This problem involves assessing inservice inspection and flaw detection techniques and providing regulatory ois'Jes for use by the staff.

Input will also be provided to the ASME Code,Section XI on flaw detection techniques.

For a detailed description of task, see HUREG-0371 SCHEDULE: Not developed.

CURRENT STATUS: Work has boon suspended - no activity on this task.

PROBLEMS:

ISSUE #

TYPE FLAG STATUS _

PRIORITY JASK A.P.

TECH. RES.

JMPLEMENTATION TACS #

UPDATED A-18 5

INACTIVE YES INCOMPLETE HOT STARTED 12/17/81 NRR SHOU HOU (492-8438) ME5/DE TITLE:

Pipe Rupture Design Criteria DESCRIPTION: This task involves development of consistent pipe rupture criteria, evaluation of the break exclusion region of piping in containment penetration areas and development of composite design requirements of piping systems for abnormal events and normal operation - see NUREG-0371 for a complete task description.

SCHEDULE: Not developed.

CURRENT STATUS: No work in progress.

PROBLEMS: All work on this issue has been stopped due to lack of funds.

ISSUE #

IXEE FLAG STATUS _

PRIORITY TASK A.P.

TECH. RE12 JMPLEMENTATION IAQS #

UPDATED _

A-21 S

IHACTIVE YES INCOMPLETE IN PROGRESS 02421 12/17/81 20435 HRR JACK KUDRICK (492-7798) CSB/DSI TITLE: Main Steamline Break Inside Containment - Evaluation of Environmental Conditions for Equipment Qualification DESCRIPTION: To resolve the concerns regarding the evaluation of appropriate environmental conditions following a postulated MSLB accident inside containment.

This task supports USI A-24.

See HUREG-0371 for a complete task description.

SCHEDULE: Work on this task has been suspended to work on higher priority issues. No manpower will be available during FY82.

CURRENT STATUS: Interim criteria have been established for purposes of environmental qualifications, about three person months will be required to finalize criteria.

PROBLEMS:

ISSUE #

TYPE FLAG STATUS PRIORITY TASK A.P.

TECH. RES.

IMPLEMINTATION TACS 8 UPDATED A-22 S

INACTIVE YES INC0f1P L ET E NOT DETERMINED 04381 12/17/81 20440 HRR W. BUTLER C492-9412) CSB/DSI TITLE: ~ PWR Main Steamline Break, Core, Reactor Vessel and Containment Building Response DESCRIPTION: This task derived from issues 1 and 15 of NUREG 0318.

Issue 1 questioned operation of nonsafety grade equipment following a MSLB. -Issue 15 is concerned with the Mechanical responsa of the pressure vessel following'a MSLB.

See NUREG-0371 for a complete task description.

SCHEDULE: Not developed. No manpower will be available until FY83.

CURRENT STATUS: No work was ever initiated on this task.

Issue 15 is included in a proposed new issue "repressurization following thermal 7

shock".

r,

' PROBLEMS:

ISSUE 8 TYPE FLAG STATUS _

PRIORITY TASK A.P.

TECH. RFS IMPLEMENTATION TACS 8 UPDATED 1

A-38 S

INACTIVE YES INCOMPLETE NOT STARTED 12/17/81 HRR

0. ROTHBERG (492-7864)

SEB/DE TITLE:

Tornado Missiles DESCRIPTIDH: See NUREG-0317 for Task description.

SCHEDULE! Not developed.

CURRENT STATUS: Inactive.

PROBLEMS:

ISSUE #

TYPE FLAG STATUS PRIORITY TASK A.P.

TECH. RES.

IMPLEMENTATION TACS 8 UPDATEQ_

A-41 S

< INACTIVE NO INCOMPLETE NOT STARIED 12/17/81

- NRR N. ANDERSON (492-7476) GIB/ DST TITLE:

Long Term Seismic Program DESCRIPTIDH: This Generic Task involved long term research program on seismic' design.

SCHEDULE:

Not developed.

CURRENT STATUS:This task was never star *ed as a generic issue and is being conducted by RES as the Seismic Safety Margins Research Program (SSMRP).

PROBLEMS:

w.

i o

o f

1-1

ISSUE #

IXEE r*AG STATUS PRIORITY TASK A.P.

TECH. RES.

IMPLE.MENTATIOH TACS #

UPDATED B-5 S

INACTIVE NO INCOMPLETE NOT STARTED 12/17/81 HRR Not assigned.

TITLE:

Ductility of two way slabs and shells and Buckling Behavior of Steel Containments.

DESCRIPTION: This task includes two separate tasks.

They will be redefined and prioritized separately.

SCHEDULE: Hot developed.

CURRENT STATUS: Same work is being done on containment buckling by the Structural Engineering Branch of DE.

PROBLEMS:

ISSUE F TYPE FLAG STATUS _

PRI0lllY TASK A.P.

TECH. PES IMPLEMENTATION TACS #

UPDATED 2

B-8 S

INACTIVE NO INCOMPLETE NOT DETERMlHED 12/17/81 HRR G. MAZETIS (492-7460) RSB/DSI TITLE:

Locking out of ECCS Power Operated Values DESCRIPTION: Roovaluation of the requirement for physica1 locking out of electrical sources to specific motor operated valves using a systems approach.

Will consider such items as probability of a spurious signal, time to reactivate, status of signal lights, and other areas as nocessary.

SCHEDULE: Hot scheduled for FY82.

CURRENT STATUS: Westinghouse submitted a topical report before TMI - review of this report has not yet been completed.

PROBLEMS:

ISSUE #

TYPE FLAG STATUS _

PRIORITY TASK A.P.

TECH. RES.

IMPLEMEHTATION TACS #

UPDATED B-16 S

IHACTIVE NO INCOMPLETE NOT STARTED 12/17/8I HRR SHOU HOU (492-8438) MEB/DE TITLE: Protection against postulated piping failures in fluid systems outside containment DESCRIPTION: This task has been incorporated into task A-18

" Pipe Rupture Desi gn Cri teria" SCHEDULE: N/A CURRENT STATUS: N/A PROBLEMS:

ISSUE #

TYPE FLAG

_ STATUS PRIORITY TASK A.P.

TECH. RES.

IMPLEMENTATION TACS 8 UPDATEQ_

B-55 S

INACTIVE NO INCOMPLETE IN PROGRESS 12/17/81 HRR F. CHERHY (492-5437) MEB/DE TITLE:

Improved Reliability of Target Rock Safety-Relief Valves DESCRIPTION: Targot rock power operated relief valves are used to limit the pressure rise in boiling water reactor (BWR) transients and to automatically depressurize the primary system in the event of certain loss of-coolant accidents.

In the past, a significant number of Target Rock power operated relief valves installed in BWRs inadvertently opened and subsequently failed te rescat until the primary system was essentially depressurized.

The primary cause of valve maloperation was due to erosion of the setpoint pilot valve seat, resulting in the leakage of steam into the second and third staqos of tho valve actuator.

There is a strong corrolation between pilot leakage and the amount of " simmer margin" (SRV setpoint pressure minus system operating pressure) for the valve.

Virtually all of the SRV blowdowns occurred on valves with less than 100 psi " simmer margin."

For the short term, General Electric (GE) proposed that licensees (1) grind out the throat diameters of Target Rock SRVs which will allow the valve setpoint to be raised 35 psi and (2) monitor SRV tailpipe temperatures (from existing thermocouples) to detect valvo leakage prior to an inadvertent actuation.

For the long-term, GE (in conjunction with Target Rock) has proposed a redesigned valve actuator for Target Rock SRVs.

The most significant change would be the elimination of the second stage so that any leakage past the pilot would exhaust rather than cause a pressure buildup to the actuating pressure in the second stage.

GE and Target Rock have manufactured for prototype valves with this modification and have begun a testing prooram.

This task involves monitoring the current programs and developing generic positions for use in the review of individual plants.

SCHEDULE: Schedule for implementation not established.

CURRENT STATUS: General Electric Cat suqqestion of HRC) has developed a three pronged approach to improving target rock reliability.

(1) Replace 3 stage target rock valve with an improved 2 stage design about 2/3 have boon replaced.

(2) Increase the simmer margin on operating plants which have three stage valves.

(3) Discontinue use of target rock valves on now plants (most are Mark IIs and IIIs).

There is some data from last 2 or 3 years of BWR operation to show that inadvertant blowdown frequency has decreased.

However, there have been some additional problems with the new two stage valve which were addressed in a recent IE Bulletin.

There is very little data available on other SRVs to be used on Mark IIs and IIIs.

PROBLEMS:

ISSUE #

TYPE FLAG STAIUS_

PRIORITY TASK A.P.

TECH. RES.

IMPLEMENTATISH TACS #

UPDATED B-58 5

INACTIVE NO INCOMPLETE NOT DETERMlHED 12/17/81 HRF T I T L':

Possive Mechanical Failures DESCRIPTION: This task involves a review of valve failure data in a more systematic manner to confirm the staff's present judgment regarding the likelihood of passive mechanical valve failures, categorize these and other valve failuros as to expected frequency, specify acceptance criteria and determine if and how the results of thi s effort should be applied in licensing reviews.

SCHEDULE: Not developed.

CURRENT STATUS: This issue has recently boon evaluated by SPEB/ DST and will be prioritized in calendar 1982.

PROBLEMS:

1.SSUE #

TYPE FLAG STATUS _

PRIORITY TASK A.P.

TECH. RES.

IMPLEMENTAT10H TACS #

UPDATED B-61 S

INACTIVE NO COMPLETE NOT STARIED 12/17/81 HRR CARL BERLINGER (492-7538) CPB/DSI TITLE:

Allowable ECCS Equipment Outage Periods DESCRIPTIDH: Survoillance test intervals and allowable equipment outage periods in the Technical Specifications for safety related systems are largely based on engineering judqcmont.

Analytically based criteria are needed for the staff's uso in confirming or modifying these surveillance intervals and allowable equipment outage periode.

SCHEDULE: Implomontation not scheduled.

CURRENT STATUS: Initial work on methodology for optimizing survoillance intervals was performed under contract with SAI.

This phase of thu task was completed and four reports issued.

1.

"The Impact of Component Outages on ECCS Unavailability" dated August 1975 report no. SAI-75-550-WA.

2.

" Amendment to " Impact of Component Outaqos on ECCS Unavailability" Based on HRC Surry Power Plant ECCS Analysis" dated May 1976, report no. SAI-76-536-WA.

3.

"The Impact of Component Outages on ECCS/ECI Unavailability for a.i Operational Rosar-3 PWR" dated July 1977, report no.

SAI-76-622-WA.

4.

"A Quantitative Approach for Establishing LCOs for ECCS/ECI Components" dated March 1979, report no. SAI-78-649-WA.

An RFP and Task cescription was prepared and issued in early 1978.

Following TMI the RFP was recalled and no further action has boon taken on this task since then.

Thcro is currently no activity.

PROBLEMS:

ISSUE #

TYPE FLAG STATUS PRIORITY TASK A.P.

TECH. R ES JMPLEMENTATIOM TACS #

UPDATED B-68 S

INACTIVE NO INCOMPLETE NOT DETERMINED 12/17/81 HRR OLAN PARR (492-7483)

ASB/DSI TITLE:

Pump Overspeed During LOCA DESCRIPTION: There is a potential for BWR recirculation pumps or PWR main coolant pumps to overspeed during a LOCA, resulting in the potential for missilo generation.

This task involves the conduct of analytical

and expsrimsntal work to datsrmins wbsthnr or not dastructivs ovarspreds could be attained and to datarmina if correctivo actions are nncessary.

SCHEDULE Not developed.

CURRENT STATUS: Work has stopped on this task and nothing is planned.

Each NSSS vendor has supplied reports.

They stere unde-review for several years by the Reactor Systems Branch.

A series of audit calculations were being performed at the time of the TMI accident.

There has been no work since that time.

PROBLEMS:

.- - ~

-ISSUE'8 TYPE FLAG STATUS PRIORITY TASK A.P.

If_C H. RES.

IMPLEMENTATION TACS 8 UPDATED B-73 S

INACTIVE NO INCOMPLETE NOT STARTED 12/17/81 HRR SHOU-HIEN HOU (492-8438) MEB/DE TITLE: Monitoring for Excessive Vibration Inside the Reactor Pressure Vessel DESCRIPTION: This task involves assessing the need for and, if necessary, developing criteria for acceptable virbration monitoring systems to provide early warning of excessive vibration inside the reactor vessel.

SCHEDULE: Not developed. No effort is being expended due to higher priority work.

CURRENT STATUS: Standard ANSI /ASME OM-5, draft 3 was completed 2/15/80.

MEB has reviewed the draft and concluded that it is generally informative and needs refinement in several areas.

Details of MEB comments were delineated in memo of 4/28/80 J. P. Knight to E. L. Jordan.

PROBLEMS:

ISSUE #

IXPE FLAG STATUS PRIORITY TASK A.P.

TECH. RES.m 1MPfEMENTAT108 TACS #

UPDATED C-8 S

INACTIVE NO INCOMPLETE NOT DETERMINED 12/17/81 HRR HOT ASSIGHED ASB/DSI TITLE: Main Steam Line Leakage Control Systems DESCRIPTIDH: Operational experience has indicated that there is a relatively high failure rate and variety of failure modes for components of the main steam isolation valve leakage control systems (MSIV-LCS) in certain operating BWRs.

Experience from surveillance testing and reported in recent LERs will serve as a basis for identifying design improvements for consideration in terms of future revisions to Regulatory Guide 1.96, changes to the Standard Review Plan, and implemeni.ation on pending licensing cases.

SCHEDULE: Not developed.

CURRENT STATUS: There has been no activity on this task for several years.

This issue has recently been evaluated by SPEB/ DST and will be prioritized in calendar year 1982.

PROBLEMS:

i i

i i

2 a

u u-Y

ISSUE #

TYPE FLAG STATU1_

PRIORITY TASK A.P.

IECH. REix IMPLEMENTATION TACS #

UPDATED C-9 S

INACTIVE NO INCOMPLETE NOT DETERMIHED 12/17/81 HRR Not assigned.

TITLE:

RHR Heat Exchanger Tube Failures DESCRIPTION: RHR heat exchangers are designed to bring the reactor to a safe cold shutdown condition and to maintain the core in a coolable geometry following a postulated loss of coolant accident.

In the recent past, there have been several RHR heat exchanger tube failures at BWRs.

Since the pressure control system on the river water (shellside) piping system maintains the pressure of the river water in the shellside of the RHR heat exchanger greater than the primary coolant pressure in the tubeside of the RHR exchanger during plant cooldown operations, a Icak in the tubes would result in back leakage of river water into the primary loop.

The objective of maintaining the pressure in the shell side greater than that in the tubeside is that in the event of a tube failure there would be no leakage of radioactive fluids into the environment.

This task will investigate the cause of these tube failures and the design of the pressure control system to assure that adequate long term core cooling capability is available.

In addition, when the TAP is developed for this item it will be expanded to include Primary / Secondary System Heat Exchanger from sources such as shell fish, sludge, etc.

SCHEDULE: Not developed CURRENT STATUS: Inactive.

PROBLEMS:

ISSUE #

TYPE FLAG STATUS.

PRIORITY TASK A.P.

TECH. REli IMPLEMENTATION TACS #

UPDATED D-1 S

INACTIVE H0 INCOMPLETE NOT STARTED 12/17/81 HRR Not Assigned TITLE:

Advisability of a Seismic Scram DESCRIPTIDH: The ACRS has recommended that studies be made of techniques for seismic scram and of the potential safety advantages and potential disadvantages of prompt reactor scram in the event of strong seismic motion, say more than one-half the safe shutdown earthquake.

Various suitable techniques have been identified and exist, but thus far only limited studies have been reported on the pros and cons of seismic scram.

SCHEDULE: Not developed.

CURRENT STATUS: No activity on this issue.

ACRS still considers this to be of concern.

PROBLEMS:

4

\\

Q PART IID: TERMINATED OR SUPERCEDED SAFETY ISSUES ISSUE 8 Ilfg FLAG STATUi_

PRIORITY TASK A.P.

TECH. RES.

IMPLEMENTATION TACS #

UPDATED B-17 S

SUPERCEDED YES 12/17/81 TITLE: Criteria for Safety Related Operator Actions DESCRIPTION: Task involves the development of a time criterion for safety related operator actions and includes determination of whether or not automatic ECCS realigment will be required.

SCHEDULE: None CURRENT STATUS: This task is superceded by TMI Action Plan items I.A and I.C.

PROBLEMS:

i

ISSUE #

TYPE FLAG STATUS ERIORITY TASK A.P.

TECH. RES.

IMPLEMENTATION TACS #

UPDATED __

8-67 S

TERMlHATED YES NOT REQUIRED 02316 12/17/81 HRR RICHARD BANGART (492-7633)

ETSB/DSI TITLE:

Effluent and Process Monitoring Instrumentation DESCRIPTION: Monitoring of radioactivity in gaseous and liquid effluent streams from nucicar power plants is required for several purposes:

(a) assessment of the adenuacy of process and waste treatment systems, (b) the control of releases of radioactivity to the environment so that they do not exceed the limits of 10 CFR 20 and 10 CFR 50, Appendix I, and (c) the evaluation of environmental impact.

This task involves improving current guidance to applicants and reviewers in tho areas of radiation monitoring for processiand effluent systems and reviewing the effluent monitoring systems for selected operating BWRs and PWRs to determine their effectiveness in meeting the effluent release limits of 10 CFR Parts 20 and 50.

SCHEDULE: Not applicable.

CURRENT STATUS:

(1) Monitoring of Radioactive Materials Released in Effluents

- Proposed BTP 11-4 was incorporated into SRP 11.5 as Appendix 11.5-A.

- BHL/NUREG-24530 published June 1978.

- Reg. Guide 1.97, Rev. 2 published December 1980.

- HUREG-0592 published April 1980.

- Radiological Effluent Technical Specifications which contain LCO's on effluent monitoring instrumentation operability and detailed surveillance requirements will be implemented at all OR's during the next two years.

- HUREG-0737 item II.F.1 (1) is being implemented.

- All future work in this area will be incorporated in HUREG-0660 item III.D.1.2.

(2) Control of Radioactive Materials Released in Effluents

- HUREG-0442 issued in April 1978.

- IE Bulletin 78-03 requested operating BWR's take actions to reduce potential for offgas explosions.

- SRP 11.3 contains guidance for preventing offgas explosions.

- The staff feels there is no need for additional BTP's or Reg.

Guides; therefore, this sub-task is considered resolved.

(3) Effects of Accidental Liquid Releases on Nearby Watcr Supplies

- It is unlikely that concentrations of radioactive material in the nearest potablo water supply could exceed 10 CFR Part 20 values.

- Since this issue does not now appear to be of concern in light of experience in performing these analyses for newer plants, this sub-task has been terminated.

(4) Performance of Solid Radwaste Systems

(

- SRP 11.4 addresses potable / mobile solidification systems

- This sub-task is no Irnger appropriate and has been terminated.

PROBLEMS:

ISSUE #

TYPE FLAG STATUS PRIORITY TASK A.P.

TECH. RES.

IMPLEMENTATION TACS 8 UPDATED B-69 S

SUPERCEDED H0 12/17/81 TITLE:

ECCS Leakage Ex-containment DESCRIPTIDH: In tho event of a severe accident, such as a loss-of-coolant accident, or any other event which could lead to significant cladding failures, the levels of radioactivity in the coolant could be high.

Such a situation would require effectivo control of any resultant leakage.

Because of the inaccessibility of the equipment under post-LOCA conditions and the manual operations involved in aligning equipment for loop functions and isolating excessively leaking components, advanced planning of the steps involved in controlling the probable leakaqos for the required long-term loop configurations should be set out in emergency operating procedures.

Technical specifications governing loop boundary integrity, leak detection equipment, isolation equipment and leakaqo control equipment should be established, including limiting conditions for operation and surveillance requirements.

While existing equipment and procedures may permit a successful post-accident recovery operation, the current standard review plan does not provide an explicit basis for confirming that those objectives will be mot.

SCHEDULE: None CURRENT STATUS: This task is superseded by TMI Lessons Learned item III.D.i.1

" Primary Coolant Sources Outside of Containment," which has been implemented on all plants.

PROBLEMS:

4 9

i

PART IIE: ONGOING SAFETY ISSUES ISSUE #

JyEE FLAG STATUS PRIORITY TASK A.P.

TECH. RES, IMPLEMENTATION TACS 8 UPDATER _

A-28 S

OHGOING YES COMPLETE 12/17/81 HRR OWEH ROTHBERG -(492-7864)

SEB/DE TITLE:

Increase in Spent Fuel Pool Capacity DESCRIPTION: Develop a generic environmental impact statement and prepare for rulemaking proceeding on definition-standards and I

critoria for spent fuel pool expansion.

SCHEDULE: Schedule on an individual plant basis.

CURRENT STATUS

• Generic work completed. Fuel pool expansion reviewed on plant specific basis. SRP Section 3.8.4 includes requirements for design of fuel pools and expansions to fuel pools.

PROBLEMS:

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l 1

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l I

(

i t

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PART III: ENVIRONMENTAL ISSUES i

ISSUE #

TYPE FLAG STATUS PRIORITY TASK A.P.

TECH. RES.

IMPLEMENTATION TACS #

MPDATED A-20 E

ACTIVE YES INCOMPLETE NOT STARTED 12/17/31 NRR G. E. GEARS (492-4807)

EEB/DE TITLE:

Impacts of the Coal Fuel Cycle DESCRIPTIDH: The purpose of this task is to provide a technical basis for the detailed generic assessment of the environmental effects of using coal for generating electricity.

See NUREG-0371 for a complete task description.

SCHEDULE: Not developed.

CURRENT STATUS: ESRPs and Regulatory Guide 4.2 will be revised pending availability of staff.

PROBLEMS:

' ISSUE #

lYEE FLAG STATUS PRIORITY TASK A.P.

TECH. RES.

IMPLEMENTATION TACS #

MPDATED-i A-33 E.

RESOLVED COMPLETE COMPLETED 04658 12/17/81 NRR

.W.

HOUSTON (492-7880) AEB/DSI TITLE:

NEPA Review of Accident Risks DESCRIPTION: 500 NUREG-0371 and current calendar item SECY-80-131 of 03/11/80.

SCHEDULE: NEPA accident risk evaluations are reviewed for each current FES/ DES on OL cases.

CURRENT STATUS: In accordance with the Commission's decision on SECY-80-131, the Federal Register.Hotice FR 45.40101 of 06/13/80 announced the intention to implement an interim policy in which accidents would bo considered on a risk speci fi c basi s, and this is now being done.

PROBLEMS:

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_.m_._

ISSUE t TYPE FLAG STATUS _

PRIGRITY TASK A.P.

TECH. RES.

IMPLEMENTATION TACS 8 UPDATED B-1 E

ACTIVE HO INCOMPLETE 1H PROGRESS 12/17/81 HRR T. CAIN (492-4903)

EEB/DE TITLE:

Environmental Technical Specifications DESCRIPTION: Based on soveral years experience with facility licensing and a better understanding of EPA and HRC regulations, it was decided to develop standarized Environmental Technical Specifications (SETS).

This task is for the development of the SETS.

Final product will be either a HUREG report or as Rog. Guide 4.8.

SCHEDULE: Not developed.

CURRENT STATUS: SETS have been developed for North Anna 1,

Farley, Salem 1 and 2, Sequoyah, Trojan, Indian Point, and Palisades.

Draft SETS have been prepared for Pt. Beach, Crystal River, & Maine Yankee.

Rest of OLs will be corrected as resources permit.

PROBLEMS:

ISSUE #

TYPE FLAG STATUS..

PeIORITY TASK A.P.

TECH. RES.

IMPLEMENTATION TACS #

UPDATED B-2 E

ACTIVE ACTIVE IN PROGRESS 12/17/81 i

1 STATE PROGRAMS TITLE:

Forecasting Electricity Demand DESCRIPTION: This task involves improving the HRC staffs caoability to forecast electricity demand for the purpose of evaluating applicants nood for powcr forecasts in individual licensing cases.

SCHEDULE: Rulemaking expected in FY82.

l CURRENT STATUS: The responsibility of the rulemaking portion of the

" Head for Power" issue has been transfarred to State Programs. A propcsed rule has gone forth to the Commissioners and final rule-making is pending. HRR's responsibilities are considered resolved.

This is no longer considered a generic environmental issue.

PROBLEMS:

n.---+

ISSUE #

TYPE FLAG STATUS PRIORITY TASK A.P.

TECH. RES.

IMPLEMENTATION TACS #

UPDATED B-28 E

ACTIVE HQ INCOMPLETE NOT STARTED 12/17/81 HRR R. CODELL (492-8018) HGEB/DE TITLE: Radionuclide/ Sediment Transport Program DESCRIPTION: This task is to develop radionuclide/ sediment transport models that have been field verified.

SCHEDULE: To be completed in FY82.

CURRENT STATUS: This work is primarily performed by RES. HRR only monitors this RES program. The fate of radionuclidos released to surface waters (i.e.),

lakes, estuaries, oceans is complicated by the interaction of radionuclide with sediments.

Few analystical methods estimate the effects of sediments on the transport of radionuclides through the hydrophore.

There are many questions on sediments in the PDEIS (HUREG-0083).

Sediments effects were an important part of the Liquid Pathway Generic Study (HUREG-0440) and FES-III (Floating Huclear Power - HUREG-0502).

The staff is pursuing research leading to quantification of the effects of sedimaat.

Predictive models must be developed and verified with data obtained from actual radionuclide/ sediment environments.

Research programs have been established resulting in models applicable for tidal, non-tidal, estuaries and oceans.

Data collection is complete for non-tidal rivers and underway for estuaries and tidal rivers.

PROBLEMS:

ISSUE #

TYPE FLAG STATUS _,

PRIORITY TASK A.P.

TECH. RES IMPLEMENTATION TACS #

UPDATED 2

B-57 E

ONGOING HD 1HCOMPLETE NOT STARTED 12/ 17/81 HRR J. C. LEHR (492-4831)

EEB/DE TITLE: Chemical Discharges to Receiving Waters DESCRIPTIDH: This task will provide insight into impact of chemical discharges and provido procedures for quantifying impacts.

To provide a better defined division of responsibility between HRC and EPA.

SCHEDULE: This is an ongoing activity (monitoring RES contracts).

4 CURRENT STATUS: ESRPs and Regulatory Guide 4.2 will be modified upon completion of review of contractors work.

PROBLEMS: Work has been deferred because of lack of available staff.

4

ISSUE #

TYPE FLA STATUS.

PRIORITX TASK A.P.

TECH. RE12 IMPLEMENTATION JAQS #

UPDATED u

B-38 E

INACTIVE No INCOMPLETE NOT STARTED 12/17/81 HRR G.

E. GEARS (492-4807) EEB/DE TITLE: Reconnaissance Level Investigations DESCRIPTION: This task would develop the basis of a staff position providing guidance to applicants concerning the need, applicability, utilization and scope of an adequate reconnaissance level investigations.

SCHEDULE: Not developed.

CURRENT STATUS: ESRPs, Proposed rule on alternate sites and Regulatory Guide 4.2 is being deferred due to unavailability of staff.

PROBLEMS:

ISSUE #

JDU' g FLAG STATUS PRIORITY TASK A.P.

TECH. RES IMPLFMENTATIDH TACS #

UPDATED j

2 B-39 E

INACTIVE NO INCOMPLETE NOT STARTED 12/17/81 NRR G.

E. GEARS (492-4807)

EEB/DE TITLE: Transmission Lines DESCRIPTION: This task covers HRC participation in an interagency effort to set forth practices for siting and managing transmission line carriders for the betterment of wildlife.

Also, HRC will participate with other agencies to develop a single environmental review process 4

involving all transmission systems of joint concern.

SCHEDULE: Not developed.

CURRENT STATUS: Work has been suspended due to unavailability of staff.

ESRPs and Regulatory Guide 4.2 are being deferred pending availability of staff.

PROBLEMS:

)

r w

ISSUE #

TYPE FLAG STATUS.

PRIORITY TASK A.Ps TECH. RES.

IMPLFMENTATION TACS #

UPDATED B-40 E

INACTIVE HO INCOMPLETE NOT STARTED 12/17/81 HRR C.

R.

HICKEY (492-4677)

EEB/DE TITLE: Effects of Power Plant Entrainment on Plankton DESCRIPTION: The effects of entrainment on phyto and zooplankton populations are often minimal and occasionally beneficial. Humorous studies of the effects of entrainment on plankton organisms, phytoplankton and zooplankton, have shown impacts to be minimal and/or not significant.

Studios have also shown that even when entrainment mortaility is high, the overall impacts may be minimal due to the fast reproductivo and recovery time for many species - a few hours for some'phytoplankters to several days for zooplankton.

Utilities have undertaken exhaustivo and sometimos unnecessary preoperational and operational environmental monitoring programs.

In view of the above points, it may be possible to reduce or climinate studies of certain planktonic elements, perhaps on a site or regional basis.

A study of these matters will form the basis for a staff position on monitoring requirements of plankton and entrainment programs.

If the stato-of-the-art as defined in tho study is adequate, perhaps intensivo studios can be reduced, saving time and expense for both utilitios and the NRC staff.

SCHEDULE: Not developed.

CURRENT STATUS: Hothing has been done on this item due to insufficient manpower.

PROBLEMS:

ISSUE #-

TYPE FLAG STATUS PRIORITY TASK A.P.

IECH. RES IMPLEMENTATION TACS #

UPDATED 2

B-41 E

INACTIVE NO 1HCOMPLETE NOT STARTED 12/17/81 HRR MIKE MASHIK (492-4892)

EEB/DE TITLE: Impacts on Fisheries DESCRIPTION: This task involves studies related to the impacts of power plant operation on fishery resources, for a description of studies see HUREG-0471, pg. B-52.

SCHEDULE: Suspended until manpower becomes available.

CURRENT STATUS: ESRPs and Reg. Guide 4.2 will be modified pending availability of staff.

PROBLEMS:

i ISSUE #

TYPE FLAG STATU1_

PRIORITY TASK A.P.

TECH. RES.

IMPLEMENTATION TACS #

UPDATED B-42 E

ACTIVE HO INCOMPLETE NOT STARTED 12/17/81 NRR DONALD CLEARY (492-4875) SAB/DE TITLE: Socioeconomic Environmental Impacts DESCRIPTION: As part of the cost bonofit analysis for plant licensing, HRC is required to assess likely socioeconomic impacts of plant construction and operation on local communitics and the surrounding region.

This task is designed to improve the ability to forecast impacts for uso in preparing environmental statements and hearing testimony.

SCHEDULE: Not developed.

CURRENT STATUS: Continuing at a very low level of effort.

PROBLEMS:

ISSUE #

TYPE FLAG STATUE _

PRIORITY TASK A.P.

TECH. RES IMPLEMENTATION TACS #

UPDATED 1

B-43 E

ACTIVE NO INCOMPLETE NOT STARTED 12/17/81 NRR G. LAROCHE (492-4820)

EEB/DE TITLE: Value of Aerial Photographs for Site Evaluation DESCRIPTION: The technique of aerial photography has a long established and proven utility for earth resource inventory and evaluation.

Applicants for nuclear construction permits are becoming aware of this and are making increasing use of aerial photographs in their environmental reports.

The uncertainties with the methodology at present relate to:

(1) photo interpretation techniques and the extent to which existing regulatory quidancu can be met using this method; (2) fine tuning of the interplay between aerial photography and ground truthing needed to moet licensing requirements; (3) quantification of presumed cost advantages of this method; and (4) relative information return from different films, photographic scalos and seasons of coverago.

This task will examine existing regulatory quidance and produce a list of items which might be fulfilled in whole or in part from aerial photographic information.

Field tests on actual sites will be carried out to determino the information return from photographs in relation to regulatory requirements and in relation to conventional ground based data collection efforts.

The results will give the staff a documentary basis for accepting aerial photographic inventories and resource evaluation in environmental reports and for revising existing guidanco for making environmental surveys.

SCHEDULE: February 1982 CURRENT STATUS: A research contract is ongoing. A quality report is expected from the contractor January 1982 and a final report February 1982.

PROBLEMS:

ISSUE #

TYPE FLAG STATUS _

PRIORITY TASA A.P.

TECH. RE12 IMPLEMENTATION TACS #

UPDATED.

B-44 E

ACTIVE NO INCOMPLETE HOT STARTED 12/17/81 HRR SIDHEY FELD (492-4904)

AEAB/DE TITLE: Forecasts of Generating Costs of Coal and Huclear Plants DESCRIPTION: In the performance of HEPA obligations to evaluate alternatives to the proposed action, the staff must reach a conclusion as to the comparative costs of generating power among the feasible alternativos. Whilo alternatives other than coal are treated in the staff's analysis, coal represunts by far the most fossible alternative and requires detailed cost comparisons equivalent to those performed for nuclear.

For the several years, the staff has used a computer code known as CONCEPT to obtain forecasts of plant capital costs.

This code was developed by ORNL based upon design specifications and cost estimates done by United Engineers and Constructors.

This task involves maintaining and developing improvements to the CONCEPT code so that it remains up-to-date for use in projections of power plant capital cost, front-end cost and generating cost ferecasts.

SCHEDULE: Ongoing CURRENT STATUS: Model is being changed to reflect cost of incorporating TMI changes in plants to be constructed.

Studies are being done to improve estim:tes of scale economics by increasing the size of coal and nuclear plants. HRR only monitors RES contracts.

PROBLEMS:

ISSUE #

TYPE FLAG STATUS _

PRIORITY TASK A.P.

IfCH. RES.

IMPL EMENT AT LOM TACS 8 UPDATED B-45 E

ACTIVE HO RESOLVED IN PROGRESS 12/17/81 HRR SIDHEY FELD (492-4904) AEAB/DE TITLE:

Need for Power - Energy Conservation DESCRIPTION: This task has been included as part of B-2.

SCHEDULE: See task B-2.

CURRENT STATUS: See task B-2.

PROBLEMS:

ISSUE 4 11EE FLAG STATMS_

PRIORILY TASK A.P.

IE_C H. REli IMPLEMENTATION TACS 4 UPDATED-B-46 E

INACTIVE NO r

INCOMPLETE NOT REQUIRED 12/17/81 HRR HOT ASSIGNED SAB/DE TITLE:

Cost of Alternatives in Environmental Design DESCRIPTION: Frequently reoulatory changes are mado in the applicant's proposal for design and/or operation of systems or subsystems based on perceived needs to mitigate impacts on the environment.

Also, differences in design and/or operation are an integral part of the treatment of alternatives in the EIS.

The cost of such changes or alternatives, if calculated, are determined on an ad hoc basis.

However, this cost is not always calculated, and many timos they are not calculated on a consistent basis.

A more consistent and comprehensive analysis of the cost of various design and operating modos appears to be warranted so that there is a reasonable and documented rationale for determining such costs.

Such costs would also have to includo costs of redesign.

Once experience is gainad in this area, consideration would be given to expanding the study to the cost of making changes because of changing safety criteria, both from a redesign standpoint as well as from a "backfit" point of view, SCHEDULE: Not developed.

s CURRENT STATU3: No effort is being expended on this issue at this time. It is not anticipated that work will resume in the near future.

PROBLEM 5:

4 J

ISSUE e TYPE FLAG STATUS _

PRIORITY TASK A.P.

TECH. RE12 -. IMPLEMENTATION TACS #

UPDATED B-65 E

INACTIME NO INCOMPLETE HOT DETERMlHED 12/17/81 HRR W. PASEDAG (492-4993) AED/DSI TITLE:

Iodine Spiking DESCRIPTION: The calculated radiological consequences for some postulated design basis accidents are highly dependent on the magnitude of the iodine spike postulated to occur following the transient.

These calculations in turn determine the coolant activity limits allowed in the technical specifications.

This task will develop and confirm a model for the iodine spiking phenomena.

Procurement of data from operating plants and the development of a fuel release model for predicting the magnitude of the spikes will provide an understanding of this phenomenon which is not presently available.

Improved knowledge of this topic will allow setting of the coolant activity limits at realistic levels.

In addition, this could provide the basis for more realistic accident calculations.

SCHEDULE: Not developed.

2 CURRENT STATUS: Inactive. Work on this item may be required in the future.

This information couples with the information contained in NUREG-0772 will be utilized to reevaluate the Iodine Spiking Phenomena.

PROBLEMS:

I 4

ISSUE 8 TYPE FLAG

_ STATUS _

PRIORITY TASK A.P.

IECH. RES.

TMPLEMENTATION IACA_#

UPDATED C-16 E

ACTIVE NO INCOMPLETE MOT STARTED 12/17/81 HRR G. GEARS (492-4807)

EEB/DSE TITLE:

Assessment of Agricultural Land in Relation to Power Plant Siting and Cooling System Selection

. DESCRIPTION: Interpretations of HEPA require that environmental impact assessment

'}

include land use impacts and alternatives in nucicar power plant licensing cases.

The staff has performed both economic and non-economic land resource assessments in compliance with these HEPA requirements. Recent licensing cases have questioned

('

the adequacy of the staff's resource evaluative methods with respect to larqc land areas required for sites and cooling lakes.

The primary issue concerning the staff's assessment is that neither economic analyses nor resource assessment as currently performed provides a convincing rationale for preemption of high quality land in view of continued population pressures, predicted impending lags in world-wide agricultural food production and probable increasing international demands on the United States for exports of agricultural products.

Food and fiber production and distribution rank with energy production and utilization I

as vital world problems now and for the forreeable future.

These problems are inextri-cably linked since energy production facili'ies can be consumers of large land areas t

while energy is a prime requirement for even modest levels of agricultural production.

Thus, land use is and probably will remain a key siting issue in nuclear plant licensing.

This task will involve the conduct of a confirmatory exploration of net energy techniques to determine their suitability for application to environmental licensing assessment under HEPA.

A problem of immediate licensing consern is the conflict in land use which occurs when power plants with large cooling lakes are sited in regions of prime agricultural land.

SCHEDULE: Not developed.

CURRENT STATUS: ESRPs and Regulatory Guide 4.2 are being deferred pending availability of staff.

PROBLEMS:

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PART IV:

LICENSING IMPROVEMENT ISSUES ISSUE 8 TYPE FLAG

_ STATUS PRIORITY TASK A.P.

TECH. RES.

IMPLEMENTATIOH TACS #

UPDATED A-27 L

RESOLVED YES COMPLETE NOT REQUIRED 20455 12/ 17/81 HRR R. MEYER (492-9475) CPB/DSI TITLE: Reload Applications DESCRIPTION: Provide a comprehensive quidance document for use of Technical reviewers for the review of core reload applications.

SCHEDULE:

CURRENT STATUS: Complete PROBLEMS:

ISSUE 8 TYPE FLAG STATUS _

PRIORITY TASK A.P.

1ECH. R_Ei.

IMPLEMENTATION TACS #

MPDATED B-3 L

INACTIVE NO INCOMPLETE NOT DETERMINED 04481 12/17/81 HRR B..SHERON (492-7426) RSB/DSI TITLE:

Event Categorization DESCRIPTION: This task is to recategorize the various postulated transients and accidents in chapter 15 of the SRP using probabilitic risk assessment and to define acceptance criteria for the various categories.

SCHEDULE: Not developed.

CURRENT STATUS: Not started.

PROBLEMS:

ISSUE 8 TYPE FLAG STATUS PRIORITY TASK A.P.

TECH. RES.

IMPLEMENTATION TACS #

UPDATED B-4 L

SUPERCEDED NO 12/17/81 HRR SAMMY DIAD (492-9440)

RSB/DSI TITLE:

ECCS Reliability DESCRIP1 ION: This task involves developing and applying numerical reliability goals to the licensing process.

SCHEDULE: None CURRENT STATUS: Existing INEL contract but no work done since TMI accident.

L PROBLEMS: This item has been superceded by HUREG-0660 item II.E.3.1.

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ISSUE 8 11Eg FLAG

_1TATUS_

PRIORITY TASK A.P.

TECH. R Eit IMPLEMENTATION TACS #

UPDATED B-7 L

ACY1VE NO INCOMPLETE NOT DETERMINED 04700 12/17/81 HRR WALT PASEDAG (492-4993) AEB/DSI TITLE:

Secondary Accident Consequence Modeling DESCRIPTION: Develop more reliable models and associated computer capability for assessing radiological consequences of accidents that could result in release of radioactivity through secondary systems.

SCHEDULE: Estimated completion date - 09/30/82.

CURRENT STATUS: Los Alamos is doing TRAC calculations to see if these types of accidents could be bounded by a simple source term.

If so, case specific analysi s would no longer be required.

At present no HRR resources, other than T/A funds are being expended for this issue.

Some progress has been made.

PROBLEMS:

ISSUE #

TYPE FLAG STATUS PRIORITY TASK A.P.

TECH. R E S._

IMPLEMENTATION TACS #

UPDATED B-11 L

RESOLVED H0 COMPLETE NOT REQUIRED 12/17/81 HRR JACK KUDRICK (492-7798) CSB/DSI TITLE:

Subcompartment Standard Problems DESCRIPTION:

SCHEDULE: Complete CURRENT STATUS: Complete PROBLEMS:

ISSUE 9 11PE FLAG STATUS PRIORITY TASK A.P.

TECH, RES.

IMPLEMENTATION TACS 4 MEDATED B-12 L

RESOLVED H0 COMPLETE NOT REQUIRED 12/17/81 HRR W. BUTLER (492-9412)

CSB/DSI TITLE:

Containment Cooling Requirements (Hon LOCA)

DESCRIPTION: The rationale for normal and past accident cooling will be reviewod to determine the adequacy of the design requirements imposed on containment ventilation systems.

SCHEDULE: None CURRENT STATUS: Complete PROBLEMS: Complete 1

ISSUE #

T1EE FLAG STATUS PRIORITY TASK A.P.

TECH. R ES._

IMPLEMENTATION TACS #

UPDATED B-13 L

RESOLVED COMPLETE HOT REQUIRED 12/17/81 HRR JACK KUDRICK (492-7798) CSB/DSI TITLE: Marviken Test Data Evaluations DESCRIPTION: Correlate the Marviken containment test data and compare the results with existing computer programs.

SCHEDULE: Complete CURRENT STATUS: Complete PROBLEMS:

ISSUE #

TIPE FLAG STATUS _

PRIORITY TASK A.P.

TECH. RES.

IMPLEMENTATION TACS #

UPDATED B-15 L

ONGOING No 12/ 17/8 1 HRR LARRY RUTH (492-9423) CSB/DSI TITLE: Contempt Computer Code Maintenance DESCRIPTION: ibis is a continuing effort.

SCHELULE: N/A CURRENT STATUS: Continuing PROBLEMS:

s

ISSUE #

TXPE FLAG STATUS PRIORITY TASK A.P.

TECH. RES.

IMPLEMENTATION TACS #

UPDATED B-19 L

ONGOING NO NOT STARTED 12/17/81 HRR L. PHILLIPS (492-9472) CPD/DSI TITLE: Thermal Hydraulic Stability DESCRIPTION: This task involves the development of the analytical methods necessary for the staff to perform independent calculations to check vendor analyses of Thermal Hydraulic Stability.

This is not a safety issue.

SCHEDULE: N/A CURRENT STATUS: Vermont Yankee stability tests are in for revicu. The Browns Ferry part loop operation stability event is currently under review. This is an ongoing issue.

PROBLEMS:

i ISSUE O 11PR FLAG STATUS _

PRIORITY TASK A.P.

TECH. RES.x IMPLEMENTATIDH TACS #

UPDATED B-20 L

INACTIVE NO INCOMPLETE NOT STARTED 04003 12/17/81 RES L. SHOTKIN (427-4275)

TITLE: Standard Problem Analysis DESCRIPTION: The U.S.

1 International Standard Programs are programs in which participants predict the thermal-hydraulic behavior of experimental tests.

The tests are selected and designed to challenge certain methods, features, and/or models of accident analysis codes used in reactor design and safety evaluation.

RES (L. Shotkin) manages this task.

SCHEDULE: Ongoing.

CURRENT STATUS: An ongoing task. No work is presently being done.

PROBLEMS:

ISSUE #

Iltg FLAG STATUS PRIORITY TASK A.P.

TECH. R ES, IMPLEMENTATION TACS #

UPDATED B-21 L

RESOLVED NO RESOLVED NOT REQUIRED 02021 12/17/81 04408 HRR D.

FIEHO (492-9474) CPD/DSI i

TITLE: Core Physics DESCRIPTION: This task is not a generic safety concern.

SCHEDULE: Complete CURRENT STATUS: Not an identified issue. Considered to be complete and closed out.

PROBLEMS:

ISSUE 8 11Pg FLAG STATU3 PRIORITY TASK A.P.

TECH. RES.

IMPLEMENTATION TACS 8 UPDATED B-22 L

ONG0IdG NO 02069 12/17/81 02098 03289 04349 04366 04399 04403 05052 05089 HRR R. MEYER (492-9474)

CPB/DSI TITLE: LWR Fuel DESCRIPTION: This task is not a generic safety concern.

SCHEDULE: N/A CURRENT STATUS: Ongoing PROBLEMS:

ISSUE 8 IYEg FLAG STATUS PRIORITY TASK A.P.

TECH. RES.

IMPLEMENTATION TACS 8 UPDATED _

B-23 L

TERMINATED HD 12/17/81 NRR R. MEYER (492-9475)

TITLE: LMFBR Fuel DESCRIPTION: This task is not a generic safety concern.

4 9'

SCHEDULE: N/A CURRENT STATUS: Work in this area was terminated.

Future work in this area, if required, will be on a plant specific basis.

PROBLEMS:

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ISSUE 8 IYPE FLAG STATUS

' PRIORITY TASK A.P.

TECH. RES.

IMPLEMENTATION TACS 9 UPDATED B-25 L

ACTIVE NO COMPLETE IN PROGRESS 12/17/81 NRR M. HARTZMAN (492-8445) MEB/DE TITLE: Piping Benchmark Problems DESCRIPTION: This task consists of developing benchmark problems.for structural analysis and design of piping systems for use in reviewing applications for construction permits.

SCHEDULE: Final resolution scheduled for FY83.

i-CURRENT STATUS: Results of this task have been used to implement provisions in IE Bulletin 79-07 regarding dynamic analysis verification of structural computer programs.

Requirements in SRP 3.9.1, using.the results of this task, were specified in a revision to the SRP.

PROBLEMS:

ISSUE #

TIEE FLAG STATUS PRIORITY

' TASK A.P.

TECH. R ES, IMPLEMENTATION TACS #

MPDATED 9-27 L

ACTIVE NO INCOMPLETE NOT STARTED 12/17/81 H RP.

M. HARTZMAN (492-8445) MEB/DE TITLE: Implementation and Use of Subsection NF

. DESCRIPTION: This task is to develop a staff position with regard to use of subsection NF in licensing actions not applicable to plants which predate subsection NF.

SCHEDULE: FY83 CURRENT STATUS: Eventual goal is to endorse in 10CFR 50.5aa.

A regulatory guide on jurisdiction and design of mechanical supports

=

is being prepared.

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_ S T A T U S__

PRIORITY TASK A.P.

IECH. RES.

IMPLEMENTATION TAC 3 8 UPDATED B-29 L

ACTIVE NO INCOMPLETE 12/17/81 HRR R. CODELL (492-8018) HGEB/DE TITLE: Effectiveness of Ultimate Heat Sinks DESCRIPTION: Evaluation of the anticipated performance of Ultimate Heat Sinks under design basis conditions requires the use of predictive analytical models.

Most such models are not fully verified due to the lack of actual high-quality performance data.

The models must be used in a highly conservative mode and the analysis must firstly rest on preoperational data.

The methodology for finding the design basis condition for evaluating the Ultimate Heat Sink have previously been only vaguely defined to correct the deficiencies.

The staff has prepared HUREG-0693 for Ultimate Heat Sink Cooling Por.d Analysis and has recently issued HUREG-0733 for Spring Ponds. A draft HUREG compares the results of PHL cooling pond and Spring final performance to HRC model predictions.

These HUREG documents develop in detai.' the staff's position on what should be required for Ultimate Heat Sink cooling pond and spring pond performance appraisals.

Performance criteria for UHS may be too conservative.

Currently, there is no way to refine the early predictive estimate until the plant is essentially ready to operate.

k SCHEDULE: To be completed in 1982.

CURRENT STATUS: The staff has prepared a User Heed Letter for RES asking for validation of existing cooling pond hydraulic models against known field data so that these more advanced models can

(

be used for UHS appraisals. A RES contract has recently been initiated to accomplish this._NRR will only monitor this program.

PROBLEMS:

(

a

ISSUE 8 IXEE FLAG STATUS __

PRIORITY TASK A.P.

TECH. R ES.

IMPLEMENTATION TACS 8 UPDATED B-30 L

INACTIVE NO INCOMPLETE NOT STARTED 12/17/81 HRR M. FLIEGEL (492-8117) HGED/DE TITLE: Design Basis Floods & Probability DESCRIPTIDH: The purpose of this task is to quantify to the extent possible, the probability of design basis flood events.

Adequacy of the existing deterministic method for estimating design basis floods is not in question.

i

~

SCHEDULE: Not developod.

CURRENT STATUS: Casework has taken priority over this generic issue. Handled by RES, but no contracts are in effect on this issue due to lack of T.A. funds.

PROBLEMS:

ISSUE #

TYPE FLAG STATUS _

PRIORITY TASK A.P.

TECH. REi.

IMPLEMEt?TATION TACS S MPDATED B-31 L

ACTIVE NO INCOMPLETE h0T STARTED 12/17/81 1

HRR G. STALEY (492-8003) HGEB/DE TITLE: Dam Failure Model DESCRIP.IIDH Assessment of dam failure usually requires use of emperical time-failure rate models or instantaneous failure models.

The time failure models are unverified and the instantaneous failures model is possible unnecessarily conservative.

The issue is that significant over conservatives may require otherwise unwarranted flood protection or execute cortain sites.

SCHEDULE: No schedule has been developed. This task provides a forum for continued assessment of the issue.

l CURRENT STATUS: Current State-of-the-Art has not progressed i.

sufficiently to warrant realistic assessments.

f PROBLEMS:

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ISSUE 8 11EE FLAG STATUS =

PRIORITY TASK A.P.

TECH. R(1, IMPLEMEN?ATIO # TACS 8 UPDATED _

B-32 L

ACTIVE NO 3HCOMPLETE

,EH PROGRESS 12/17/81 NRR REX WESCOTT (492-8476) HGEB/DE TITLE: Ice Effects on Safety Related Water Supplies DESCRIPTION: Not an identified safety issue.

The operating experience during recent severe winters identified physical phenomena which might advarsely impact the proper operation of safety related systems

(

(i.e.,

the utlimate heat sink) and impair the ability to obtain r

sufficient cooling water to safely shut the plant down.

Typical s

e icinq conditions (e.g.,

surface ice) appear lesstimportant than subsurfaca frazile ice as a flow blockage mechanssm.

r Pack ice on packed surface ice has, in the past, been assumed sufficiently porous to pass the relatively low flows necessary for UHS operations.

Frazile ice may not be as porous and may, under rare conditions, reduce the flow below acceptable levels.

Also, forces produced by expanding ice sheets could damage safety-related equipment and structures and impair the -ability of the UHS to function.

The object of this task is to ensure that operating reactors have the ability to circulate warm water to the intake (or have other processes) *: 'i~it ice buildup.

SCHEDULE: Not dev;1oped.

CURRENT STATUS. Issue serves as a forum for staff to monitor progress in the area.

PROBLEMS:

ISSUE 8 TYPE FLAG STATUS.

PRIORITY TASK A.P.

TECH. R ES, IMPLEMENTATION IACS 8 UPDATED B-33 L

RESOLVED NO COMPLETE COMPLETED 12/17/81 NRR FRANK CONGEL (492-7321) RAB/DSI TITLE: Dose Assessment Methodology DESCRIPTION: Not a saf$ty issue.

This task involves the maintenance of I

calculational capab.lities for assessing doses to individuals from radiation and radioactive effluents from normal operation and from radioactive releases from postulated accidents.

SCHEDULE: Complete CURRENT STATUS: Updated models are included in Rcnalatory Guide 1.109 and are used for SER, DES and FES sections concerned with public l

exposure to radioactive materials and effluents, PRDBLEMS:

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ISSUE 8 IXEg FLAG STATUS _

Pr,IGRITY TASK A.P.

TECH. RES.

IMPLEMENTATION IACS 8 UPDATED B-34 L

SUPERCEDED YES 02234 12/17/31 NRR D. M.

COLLINS (492-7614) RAB/DSI l

TITLE: Occupational Radiatico Excosure Reduction DESCRIPTION: This task is superceded by TMI Action Plan item III.D.3.1,

" Radiation Protection Plans."

' SCHEDULE: N/A CURRENT STATUS: Superceded by TMI Action Plan item III.D.3.1, " Radiation Protection Plans".

l PROBLEMS:

m ISSUE 8 11PE FLAG STATUS PRIORITY TASK A.P.

TECH. RES.

IMPLEMENTATION TACS 8 UPDATEQ_

B-35 L

ACTIVE YES INCOMPLETE NOT DETERMlHED 03091 12/17/81 HRR RICHARD BANGART (492-7633)

ETSB/DSI TITLE: Confirmation of Appendix I Models for Calculations of Releases of Radioactive Materials in Gaseous and Liould Effluents from Light Water Sealed Nuclear Power Plants DESCRIPTION: This is not an identified safety issue.

The task involves revision of models for calculating releases of radioactive materials to improve the accuracy of current staff models for appendix I calculations.

1 SCHEDULE: Completion dependent on manpower and priorities. Completion of this task is expected by FY83.

CURRENT STATUS: All research programs described in the action plan have been completed except for the source term measurement program which is still underway and is due to be completed in late FY32 or early FY33.

HUREG-0016, Rev. I was published January, 1979.

NUREG-0017, Rev. 1 is in early draft stage.

INEL will complete draft on FY81 funding.

PROBLEMS:

ISSUE #

TYPE FLAG

_ STATUS.

PRIOill!

TASK A.P.

T_ECH. RE1.

IMPLEMENTATION TACS 8 UPDATED B-36 L

RESOLVED NO COMPLETE COMPLETED 12/17/81 NRR RICHARD BANGART (492-7633)

EISB/DSI TITLE: Develop Design, Testing and Maintenance Criteria for Atmosphere Cleanup System Air Filtration and Adsorption Units for Engineered Safety Feature Systems and for Normal Ventilation Systems.

DESCRIPTION: Title is self explanatory.

SCHEDULE: Complete CURRENT STATUS: Completed - resolution is documented in Regulatory Guides 1.52. Rev. 2, dated March 1978, 1.140 Rev. 1 dated Oct. 1979.

PROBLEMS:

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TECH. RE12 IMPLEMENTATION TACS 8 UPDATED B-49 L

INACTIVE NO INCOMPLETE NOT (4 TARTED 92/17/81 HRR Not Assigned TITLE:

Inservice Inspection Criteria and Corrosion Prevention Criteria for Containments DESCRIPTION: General Design Criterion 53, " Provisions for Containment Testing and Inspection," requires in part that the reactor containment be designed to permit:

(1) periodic inspection of all important areas, and (2) an appropriate surveillance program.

10 CFR 50, Appendix J,

" Primary Reactor Containment Leakage Testing for Water-Cooled Power Reactors," requires a general inspection of the surfaces of the containment prior to any Type A test to uncover any evidence of structural deterioration.

Containment designs typically utilize any one of the following structural materials:

steel, steel lined reinforced concrete, steel I

i lined prestressed concrete.

To date the only detailed criteria that have been developed for inservice inspection of containments relate to tendon surveillance for pre-stressed concrete containments.

These i

l criteria are contained in Regulatory Guides 1.35 and 1.90 which address ungrouted and grouted tendons respectively.

These Regulatory Guides deal primarily with the pre stressing hardware; no detailed inservice i

inspection criteria exist for the steel liner or other portions of the containment.

Similarly, there are no criteria for inservice inspection of steel containments or steel lined reinforced concrete containments.

In view of this, detailed and comprehensive criteria need to be j

developed for perforr.ing inservice inspections of all type of

\\

containments.

l

.i In addition, the long term corrosion problems of reinforcements and of the steel liner in contact with concrete in concrete containments, or the corrosion of the steel surface in contact with the water in BWR suppression chambers, have yet to be adequately analyzed.

Long

{

term studies of these corrosion phenomena need to be undertaken to develop criteria and requirements to prevent corrosion in all types i

of containments.

SCHEDULE: Not started.

CURRENT STATUS: Considered to.be low priority. There is currently no activity in this area.

PROBLEMS:

)

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_ STATUS PRIORITY TASK A.P.

IECH. REi.

IMPLEMENTATIDE TACS 8 UPDATED B-50 L

INACTIUE NO INCOMPLETE NOT STARTED 12/1F/881 NRR

0. ROTHBERG (492-7864) SEB/DE TITLE:

Post Operating Basis Earthquake Inspection DESCRIPTION: Section V9a)(2) of Appendix A to 10 CFR Part 100 states that licensees will be required to chut down their plants in the event of an earthquake if vibratory ground motion exceeds that of the OBF.,

Prior to restart the licensee must demonstrate to the NRC that no functional damage has occurred to those features necessary for continued operation without undue risk to the health and safety of the public.

In order to determine the capability of a plant to resume operation following an OBE an adequate inspection of the plant and site area must be performed.

The roquirements for this post-0BE inspection are stated in Section 3.7.4.11.4 of the Standard Review Plan.

Since neither the Regulations nor the Standard Review Plan provide details on the extent of such inspections, this task will develop an acceptable inspection procedure.

SCHEDULE: Not developed.

CURRENT STATUS: Inactive PROBLEMS:

ISSUE 8 11PE FLAG STATUS PRIORITY TASK A.P.

I_ECH. REiz IMPLEMENTATION TACS 8 UPDATED _

B-51 L

ACTIVE NO INCOMPLETE NOT STARTED 12/17/81 NRR M. HARTZMAN (492-8445) MEB/DE 4

TITLE: Assessment of Inelastic Analysis Techniques for

]

Equipment and Components

{

DESCRIPTION: In the design of nucicar power plants, inelastic response of equipment and components due to severe transients from low probability events is permitted in the ASME Boiler and Pressesre Vessel Code,Section III Subsection NA, Appendix F.

Local inelastic response is also permitted for structures under severe impact loads due to low probability events.

Assessment of inelastic analysis techniques applicable to equipment and components is the basic objective of this task.

Inelastic analysis techniques for structures are under study as a part of HRR Category A Task No. A-40, " Seismic Design Criteria - Short Term i

Program."

.4 Since inelastic analysis procedures acceptable under Appendix F of the ASME Boiler and Pressure Vessel Code permit Level D Service Limits and since Level D Service Limits allow large inelastic strains, it is particularly important that properly qualified analysis techniques are used, and that their limitations are properly understood.

2 I

SCHEDUL E: Low level of effort (FY34).

CURREN1 STATUS: Work is progressing under contract with Brookhaven National Laboratory.

PROBLEMS:

4 1

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1 k

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ISSUE 8 TvPE FLAG

_ STATUS _

E_RIORITY TASK A.P.

T E_CH. PJS.

IMPLEMENTATION TACS 4 UPDATED B-59 L

ACTIVE YES INCOMPLETE 1N PROGRESS 12/17/81 NRR JACK GUTTMANN (492-9439) RSB/DSI - PWR GEORGE THOMAS (492-9445) RSB/DSI - BWR TITLE:

Review of (N-1) Loop Operation in BWRs and PWRs DESCRIPTION: The majority of operating BWRs and PWRs are designed to l

operate with less than full reactor coolant flow.

If a PWR reactor coolant pump or a BWR recirculation pump becomes inoperat?ve, the flow provided by the remaining (N-1) loops is sufficient for steady state operation at a power level less than full power.

Although FSARs for the licensed BWRs and PWRs present (N-1) loop calculations showing allowable power and protective system trip setpoints, the staff has disallowed this mode of operation for most plants primarily due to insufficient ECCS analyses.

Some Babcock & Wilcox (B&W)

PWRs are authorized for long term operation with one reactor coolant pump out of service since they have submitted and the staff has approved the necessary ECCS, steady state, and transient calculations.

The remaining BWR and PWR licensees have Technical Specifications which require shutdown within a fairly short time if one of the reactor coolant 1seps becomes inoperable.

The purpose of this task is to develop a set of acceptance criteria and review quidelines for the (N-1) loop authorization requests.

SCHEFULE: Not developed.

CURRENT STATUS: All R8W plants have been approved for N-1 operation.

Contractor reports on Westinghouse plants N-1 operation are under staff review.

Combustion Engineering has submitted analyses for Calvert Cliffs.

The review of BWRs has been suspended pending review of the incident at Browns Ferry when core vibrations occurred during single loop operation.

A meeting was held with a GE owners group to discuss the incident, and the issue was resolved.

Staff positions for BWR's is that for single loop operation, plants are restricted to 504 power. SER's are being written for eleven BWR plants which have applied for N-! operation, No manpower is being expended by RSB for work on PWR's at the present time.

4 PROBLEMS:

4 ISSUE 8 TYPE FLAG STATUS _

PRIORITY TASK A.P.

TECH. RES.

IMPLEMENTATION TACS #

UPDATED B-62 L

RESOLVED NO COMPLETE NOT REQUIRED 12/17/81 NRR DAN FIENO (492-9474) CPB/DSI TITLE:

Reexamination of Technical Bases for Establishing SLs LSSS.

DESCRIPTION: The methods used to establish safe operating limits for reactor cores were developed about ten years ago.

At present, safety margins are reviewed utilizing previous staff judgments i

based on individual plant reviews.

A uniform staff positien needs to be developed for application to core performance reviews of new plants and to reloads and core modifications of operating plants.

SCHIPULE:

CURkGiT STATUS: This is not a safety issue.

There is no activity in this area, nor is there any planned. This issue is considered to be resolved.

PROBLEMS:

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ISSUE #

TYPE FLAQ_

STATUS PRIORITY TASK A.P.

_T EC H. RES.

IMPLEMENTATION TACS #

UPDATED.

B-72 L

ACTIVE NO COMPLETE IN PROGRESS 12/17#81 HRR F. CONGEL (492-7321) RAB/DSI TITLE:

Development of Models for Assessing Risk of Health Effects and Life Shortening from Uranium and Coal Fuel Cycles DESCRIPTION: Current practice in health impact assessments is to convert radiation exposure estimates into estimates of health effects, such as cancer deaths, illness, and life shortening.

However, the models presently being used, such as those in WASH-1400, GESMO, current NRC case realted testimony, and EPA assessments, all suffer from similar weaknesses. A major common weakness, which appears amendab.te to solution, is related to the correct treatment of competing risks among populations with life expectancies, ago, and sex distributions that vary with time.

Since the staff is currently attempting to assess health effects in the future (e.g.,

Year 2000 and beyond),

it is reasonable to expect significant changes in currcnt population statistics.

To make such an assessment, a demographic model is required which extrapolates the current population into the future, correctly allowing for competing risks of mortality from various causes (e.g.,

accidents, heart disease, and cancer).

Failure to do so results, for example, in hypothetical cancer deaths for people who would statistically die from other causes.

In the absence of better predictive models, it is not possible to even evaluate the uncertainty associated with the use of the current simplified methods for estimating health effects and conscquent life shortening.

Uncertainties in the use of current models are greatly magnified when attempting to make comparisions of health effects for the coal and nuclear fuel cycles.

Current health effects models generally are used for estimating long-term impacts.

Chronic exposure may be the primary determinant of the number of deaths for a given period for a given pollutant.

However, in the case of non radiological pollutants from the coal fuel cycle, short-term fluctuations leading to acute exposures may determine the time of death and consequent life shortening.

Current evaluations of the coal fuel cycle generally fail to account for short-term mortaility, disease and illness.

In addition, short-term effects from chemical pollutants are generally dependent on the prior history of chronic (long-term) exposure.

Current models generally assume linear dose-response relationships even when evidence exists for real or practical thresholds, or where experimental data support a non-linear dose response relationship.

This task involves the development of models to address these problems so that health effects (morbidity and mortality) can be assessed for both the coal and uranium fuel cycles as completely as current data permit and on a comparable basis.

SCHEDULE: Final HUREG-0332 is due to be issued in January 1982.

CURRENT STATUS: Information contained in the Draft HUREG is being used in Draft and Final environmental statements regarding comparisons of coal and nuclear impacts.

PROBLEMS:

ISSUE 9 11EE FLAG

_iTATUS PRIORITY TASK A.P.

TECH. RES.

IMPLEMENTATID_H TACS 8 UPDATED-C-2 L

IHACTIVE NO ENCOMPLETE NOT DETERMINED 12/17/81^

HRR J. KUDRICK (492-7798) 'CSB/DSI TITLE:

Study of Containment Depressurization by Inadvertent Spray Operation.

DESCRIPTION: Inadvertent operation of containment sprays can result in a rapid depressurization of the containment building. Where containment external design pressure may be exceeded many plants have been provided with vacuum breakers or control system interlocks to prevent the containment external design pressure from being exceeded.

The depressurization of the containment is a transient behavior and can take place in a short time period.

This task involves the developement of a code to be used for the analysis of containment pressure response (both with ar.d without the effects of vacuum breakers or control systems) for the inadvertent spray accident.

SCHEDULE: Expected to be completed in FY-83.

CURRENT STATUS: There has been no work on this activity because of low priority.

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lygg FLAG STATUS _

PRIORITY TASK A.P.

TECH. RES.

IMPLEMENTATION TACS #

UPDATED C-4 L

TERMlHATED 12/17/81 HRR B.

SHERON (492-7626) RSB/DSI TITLE:

Statistical Methods for ECCS Analysis DESCRIPTION: Appendix K 10 CFR 50 specifies the requirements for LWR ECCS analysis.

These requirements presently call for specified conservatisms to be applied to certain models and correlations used in the analysis to account for data uncertainties at the time Appendix K was wrtten.

The resulting conservatism in the calculated peak clad temperaturc however, has never boon compared against the uncertainty in peak clad temperature obtained from a realistically calculated (bost estimate) LOCA.

In ordor to assess the safety margin in the Appendix K requirements, the peak clad temperature requirement (2200 daqrco F) will be equated to an uncertainty level of a realistic calculation.

This will be accomplished by analytical analysis utilizing best estimate LOCA analysis codes in which cortain input parameters are simultaneously varied about their uncertainty distribution functions such that a resulting uncertainly distribution functions in peak clad temperature is obtained.

It is then possible to express the conservatism of the 2200 degree F cladding temperature limit in terms of probability or standard deviations from the most probable peak clad temperature.

The statistical methods for ECCS analysis will provide a probabilistic quantification of the safety margin imposed by 10 CFR 50 Appendix K ECCS safety evaluation requirements.

The results of this program will be used to aid the staf f in the review of changes to vendor ECCS models and.in performing staff audit calculations of ECCS parformance.

SCHEDULE: None.

Program terminated.

CURRENT STATUS: This task is not an identified safety concern.

RES completed certain parts of this program prior to TMI; however, due to the deemphasis of the LBLOCA and the establishment many higher priority items, this program has been terminated.

PROBLEMS:

ISSUE 8 TYPE FLAG

_ STATUS PRIORITY TAS$ A.P.

TECH. RE12 IMPLEMENTATION TACS B UPDATE 2_

C-5 L

RESOLVED NO COMPLETE NOT REQUIRED 02039 12/17/81 NRR H. RICHINGS (492-9465) CPB/DSI TITLE:

Decay Heat Update DESCRIPTION: This task involves following the work of research groups in determining best estimate decay heat data and associated uncertainties for use in LOCA calculations.

The results of this task could be incorporated in future ravisions of the current regulations regarding ECCS performance.

SCHEDULE: Not established.

CURRENT STATUS: NRC has followed the development of ANS standard 5.1 proposed quidelines.

ANS 5.1 applies to Appendix K type calculations.

The staff does not interst to propose rulemaking to charge 10 CFR 50, Appendix K.

This issue is considered to be resolved.

PROBLEMS:

ISSUE #

TYPE FLAG STATUS _

PRIORITY TASK A.P.

TECH. RES.

IMPLEMENTATION TACS 4 UPDATED _

C-6 L

RESOLVED NO COMPLETE NOT REQUIRED 02037 12/17/81 NRR DAN FIENO (492-9474) CPB/DSI TITLE:

LOCA Heat Sources DESCRIPTION: The contributors to LOCA heat sources, along with their associated uncertainties, and the manner in which they are combined have an impact on LOCA calculations.

An evalution of the combined effect of power density, decay heat, stored energy, fission power decay and their associated uncertainties with regard to calculations of LOCA heat sources is needed.

This task will involve the review of vendor's data and approaches for determining LOCA heat sources and developinq staff positions as needed.

SCHEDULE: Not established.

CURRENT STATUS: This issue was intended to be an open item to cover work to improve predictions of heat sources for LOCA calculations.

It is not an identified safety issue.

It is cosidered to be resolved.

PROBLEMS:

ISSUE 8 TIEE FLAG STATUS._

PRIO92TY TASK A.P.

IECH RES2 IMPLEMENTATIDH TACS 8 UPDATER _

C-10 L

INACTIVE NO INCOMPLETE NOT DETERM1HED 12/17/81 HRR T. QUAY (492-7159) AEB/DSI TITLE:

Effective Operation of Containment Sprays in a LOCA DESCRIPTION: This task will respond to a conern of the ACRS about the effectiveness of various containment sprays to remove airborne radioactive materials which could be present within the containment following a LOCA.

This concern has been expanded to include the possible damage to equipment located insido containment due to an inadvertent actuation of the sprays.

This task involves assisting the industry in writing an ANSI Standard on the design of containment spray systems, developing a topical report on the techiological bases for spray washout models, and in managing contract to evaluate the ability of different spray solutions to remove the radiciodines and radioactive particulates released to containment during a postulated LOCA.

Draft 7 of ANSI H581, "BWR and PWR Containment Spray System Design", has been

?

reviewed by the staff.

Following resolution of U.e NRC comments and issuance of this standard by ANSI, a regulatory quide endorsing this standard will be developed by RES.

SCHEDULE: Not developed.

CURRENT STATUS: Iask largely completed although not completely documented.

Needs re-evaluation to determine if additional work needs to be done.

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IHACTIVE NO INCOMPLETE NOT STARTED 12/17/81 HRR Hot asrigned TITLE:

Primary System Vibration Assessment DESCRIPTION: Structural damaqo to the primary system, including the reactor pressure vessel and internals, associated piping and steam generator tubing in PWR's, can be caused by vibrations of sufficient magnitude.

These vibrationss can be either flow-induced or the result of operation of the pumps to which primary system piping is attached.

There have been a number of instances where components internal to the ractor coolant pressure boundary have come loose as the result of flow-induced vibration and been carcied through the pri-mary system by the coolant flow.

Excessive core barrel movement, caused by flow-induced vibration, may lead to many detrimental effects including damage to reactor internals and interference with control rod movement.

Problems resulting from excessive core barrel movement have been encountered at Palisades and possibly other operating plants.

Structural damage due to flow-induced vibration of steam generator tubing has also been encoutered. Anti-vibration bars are currently utilized to minimize tube vibration.

Howeser, fretting has occurred due to deficient design and material selection for the anti-vibration bars.

Piping systems are also susceptible to forced vibration as a result of pump vibration during operation.

If a natural frequency of the connected piping is very nearly the same as the driving frequency of the pump there is then the possibility, depending on the amplituod of vibration, for fatique failures in the system, particularly at the no:=le where the stresses will be highest.

Prooperational testing of reactor internals, piping systems and mechanical equipment conducted during startup functional testing to assure structural and functional integrity per section 3.9.2 of the Standard Daview Plant and Regulatory Guide 1.20.

However, vibration frequency shifta are possible during operation as a result of component and/or component support wear or degradation.

Also, vibration effects for the long term may not have been pro-perly assessed during startup testing.

Inservice inspection during the life of the plant and possible visual and audible deiection of vibreation during plant operation may be necessary in order to arrest structural damage already incurred or, if the vibration were to continue, might occur at some future time.

This vibration assessment could lead to modifications in the design of system components or component support arrangements of system operation sequences.

SCHEDULE: Hot developed.

CURRENT STATUS: Inactive PROBLEMS:

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INACTIVE NO INCOMPLETE NOT STARTED 12r 17/81 HRR M. FLIEGEL (492-81i7)

HGEB/DE TITLE:

Storm Surge Modes for Coastal Sites DESCRIPTION: The primary tool used by the staff for estimating storm surge has been the bathystrophic model developed by the US Army Corps and Engineers, Coastal, Engineering Research Center.

The model has served its intended purpose will, but biqqor, faster computers can handle multidimensional, multivariability models.

These mode) s can be used in a less conservative mode to account for irraqular shoreline and shape facters ignored by the bathystrophic.

This issue is not an identified safety problem.

However, more complex models would allow single step solution of coastal flooding problems.

SCHEDULE: Hot developed.

CURRENT STATUS: Currently the technical community is developing and attempting to verify more complex model. However, limitation of data defining both the storm and surge in '..mo and space impede validation.

The NRC is cosponserinq data aquisition proposed and is cooporating in model assessment.

This task provides the forum for NRR staff activities in this area.

This task provides for continous tracking and assessment of model evalution and data acquisition pro-grams. There is no work currently in progress on this task due to its low priority.

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IHACTIVE YES INCOMPLETE NOT DETERMINED 12/17/81 HRR R. BANGART (492-7633)

ETSB/DSI TITLE:

NUREG Report for Liquids Tank Failure Analysis DESCRIPTION: Standard Review Plan 15.7.3 requires an analysis of the consequences of failure of tanks containing radioactive liquids outside containment.

This task involves the development of a NUREG report that wil! describe a consistent and accepSable method for analyzing the effects of a failure of a redioactive liquid waste tank.

SCHEDULE: Not developed.

CURRENT STATUS: No action has started on this items due to low priority.

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ISSUE 8 11EE FLAG STATUS PRIORITY TASK A.P.

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RESOLVED NO CONPLETE NOT REQUIRED 02311 12/17/01 NRR RICHARD BANGART (492-7633)

ETSB/DSI TITLE:

Interm Acceptance Criteria for Solidification Agents for Radioactive Solide Wastes.

DESCRIPTION: There are no current criteria for acceptability of solidification agents.

This task involves the development of criteria for acceptability of radwaste solidification agents to properly implement a process control program for the packaging of diverse plant waste for shallow land burial.

SCHEDULE: N/A CURRENT STATUS: Resolution is documented by 10 CFR Proposed Part 61.

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ACTIVE YES INCOMPLETE NOT STARTED 12/17/81 NRR B. SHERON (492-7626) RSB/DSI TITLE:

Emergency Core Cooling System Capability for Future Plants e

DESCRIPTIDH: This is an ACRS generic concern.

It involves exploration of diverse means of obtaining ECCS capability.

This item is incorporated in USI A-45.

SCHEDULE: See AQUA Book, HUREG-0606 CURRENT STATUS: See AQUA Book, HUREG-0606 PROBLEMS:

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