ML20138E318
| ML20138E318 | |
| Person / Time | |
|---|---|
| Issue date: | 12/02/1985 |
| From: | Moran D Office of Nuclear Reactor Regulation |
| To: | Kniel K Office of Nuclear Reactor Regulation |
| References | |
| PROJECT-669A NUDOCS 8512130416 | |
| Download: ML20138E318 (17) | |
Text
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UNITED STATES C o NUCLEAR REGULATORY COMMISSION y j WASHINGTON, D. C. 20555
%, * . * * * #' December 2, 1985 MEMORANDUM FOR: Karl Kniel, Chief, SPEB, Division of Safety Review and Oversight, Office of Nuclear Reactor Regulation THRU: Thomas L. King, Section. Leader, SPEB, Divisibn of Safety Review and Oversight, Office of Nuclear Reactor Regulation FROM: David H. Moran, Project Manager Safety Program Evaluation Branch
, Division of Safety Review and Oversight
! Office of Nuclear Reactor Regulation
SUBJECT:
SUMMARY
OF OCTOBER 29-30, 1985 WORKING MEETING-0F EPRI/NRC
! PROJECT MANAGERS AND NRC STAFF TASK MANAGEBS'0F SPECIFIC GENERIC SAFETY ISSUES IMPACTING THE EPRI/ INDUSTRY ADVANCED i!_ LWR REQUIREMENTS DOCUMENT l This memorandum summarizes the working meeting held October 29-30, 1985 by EPRI/NRC project managers and the staff to discuss progress on resolution
~o f generic safety and licensing issues. The October 29 meeting was for the purpose of obtaining forecast information on issues in the process of being prioritized. The agendas for the 29th and 30th meetings are included as
, Enclosures 1 and 2 respectively; the attendees for the meetings are
- included as Enclosure 3. Due to the unavailability of four lead engineers i to provide forecasts of status on issues scheduled to be discussed on October 29, we deferred obtaining status on the~following sixteen issues
3 B22 LWR Fuel L B29 Effectiveness of Ultimate Heat Sinks D2 Emergency Core Cooling System Capability for Future Plants 27 Vibration Qualification of Equipment 57 Effects of Fire Protection System Activation on Safety-Related Equipment 73 Detached Thermal Sleeves 76 Instrumentation and Control Power Interactions -
t 95 Loss of Effective Volume for Containment Recirculation Storage
, 106 Piping and Use of Highly Combustible Gases in Vital Areas i 107 Generic Implications of Main Transfonner Failure 117 Allowable Outage Times for Diverse Simultaneous Equipment Outages 118 Tendon Anchorage Failures 119 Piping Review Committee Recommendations 120 On-Line Testability of Protection Systems 121 Hydrogen Control for Large Dry Containments 122 Davis-Besse Loss of All Feedwater Event Arrangements have been made to obtain forecasts of status of any '
prioritization action on t!.e above issues, so it can be reported at the December 3,1985 Quarterly Meeting of the EPRI LWR Steering Comittee and the NRC Policy Comittee. '
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l i The October 30 meeting was for the purpose of obtaining forecasts of elements of resolution for ten issues impacting chapter three of the
! requirements document. --
EPRI is preparing topic papers intended to provide needed information for EPRI staff to intelligently address as-yet unresolved issues in the requirements document. The issues considered for topic papers are:
! l
'! 1. 23, " Reactor Coolant Pump Seals
! 2. 29, " Bolting Degradation or Failure in Nuclear Power Plants;"
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- 3. 62, " Reactor Systems Bolting Applications;"
- 4. 67.7.0, " Steam Generator Staff Actions--Improved Eddy Current Tests;"
t 5. 79, "Unanalyzed Reactor Vessel Thermal Stress During Natural Convection Cooldown;"
- 7. 94, " Additional Low Temperature Protection Issues for Light Water Reactors;"
- 8. 104, " Reduction of Boron Dilution Requirements;"
- 9. 109, " Reactor Vessel Closure Failure;" and
- 10. 113. " Hydraulic Snubbers" t
Further Discussion of these issues is provided as Enclosure 4. Based on i staff discussion, it is evident that issues 62 and 109 should be considered
- ! part of issue 29, " Bolting Degradation or Failure in Nuclear Power l Plants." Issue 104, " Reduction of Boron Dilution Requirements" should be
[ considered a potential plant optimization issue. EPRI will probably not
,i need a topic paper on issue 104. Further information is needed on issue 113. " Hydraulic Snubbers", before EPRI can generate a cogent topic paper on the subject.
A listing of the remaining issues with currently available staff forecasts, is included as Enclosure 5. Those issues identified by an asterisk (*) need forecast detail. There are 102 items on this lists. After consideration of the drop category, not applicable category and more detailed forecast on issues asterisked, a realistic number is 50 issues remaining to be resolved and which, at this time, appear to impart the ALWR.
David H. oran, ger Safety Program Evaluation Branch 4
i Division of Safety Review and Oversight Office of Nuclear Reactor Regulation
Enclosure:
As stated i
. December 2, 1985 The October 30 meeting was for the purpose of obtaining forecasts of elements of resolution for ten issues impacting chapter three of the requirements document.
EPRI is preparing topic papers intended to provide needed information for EPRI staff to intelligently address as-yet unresolved issues in the requirements document. The issues considered for topic papers are:
- 1. 23, " Reactor Coolant Pump Seals;"
- 2. 29, " Bolting Degradation or Failure in Nuclear Power Plants;"
- 3. 62, " Reactor Systems Bolting Applications;"
- 4. 67.7.0, " Steam Generator Staff Actions--Improved Eddy Current Tests;"
- 5. 79, "Unanalyzed Reactor Vessel Thermal Stress During Natural Convection Cooldown;"
- 7. 94, " Additional Low Temperature Protection Issues for Light Water Reactors;"
- 8. 104, " Reduction of Boron Dilution Requirements;"
- 9. 109, " Reactor Vessel Closure Failure;" and
- 10. 113. " Hydraulic Snubbers" Further Discussion of these issues is provided as Enclosure 4. Based on staff discussion, it is evident that issues 62 and 109 should be considered part of issue 29, " Bolting Degradation or Failure in Nuclear Power Plants." Issue 104, " Reduction of Boron Dilution Requirements" should be considered a potential plant optimization issue. EPRI will probably not need a topic paper on issue 104. Further information is needed on issue 113, " Hydraulic Snubbers", before EPRI can generate a cogent topic paper on the subject.
A listing of the remaining issues with currently available staff forecasts, is included as Enclosure 5. Those issues identified by an asterisk (*) need forecast detail. There are 102 items on this lists. After consideration of the drop category, not applicable category and more detailed forecast on issues asterisked, a realistic number is 50 issues remaining to be resolved and which, at this time, appear to impart the ALWR, Original signed by David H. Moran, Project Manager Safety Program Evaluation Branch Division of Safety Review and Oversight Office of Nuclear Reactor Regulation
Enclosure:
As stated DISTRIBUTION:
NRC PDR ._ .,
! Central Files
'SSPB Rdg DEisenhut/HDenton DSR0:SPEB FMiraglia/HThompson DMoran:ac DCrutchfield 12/ /85 Attendees
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,f '. Enclosure 1
- ' Octcb r 29, 1985 AGENDA Working Meeting of EPRI/NRC Project Menagers for the Joint Advanced LKP Program This is the fourth such meeting for the purpose of obtaining from the staff st>tus and forecast of prioritization and resolution of generic safety '
issues which impact design of future LWR plants.
The meeting of Jan. 23, 24, 25, 1985 resulted from action items of the Dec.
5,1984 Quarterly meeting of the LWR Steering Comittee and the NRC Policy Comittee.
As a result of these meetings progress and issue status have been reported, recomerdations for improvements in handling generic safety issues have
. been reported during quarterly meetings and new action items have been assigned and executed,
- f. Several of the action items laid-on during the Sept. 12, 1985 Quarterly meeting should be addressed during this meeting and the following one
- October 30, 1985. A copy of the Sept. 12, 1985 Meeting Sumary is
( ,- enclosed; refer to agenda item 10.
Safety issues to be statused are listed below. The Task Manager or lead engineer for each issue is also listed.
Issue Title Task Mc r./ Lead Engr.
T2T " LWR Tu~eT- H. Vanc erMolen B-29 " Effectiveness of Ultimate Heat Sinks" J.Pittman(1)
[ B-32 " Ice Effects on Safety-Pelated Water J. Pittman (1)
Supplies" 8-37 " Chemical Discharge to Receiving - R. Samworth i Waters" D-2 " Emergency Core Cooling System R. Emrit Capability for Future Plants" 21 " Vibration Qualification of Equipment R. Enrit (1) 30 " Potential Generator Missiles-- J. Pittman (1)
Generator Retaining Rings" J. Pittman 57 " Effects of Fire Protection System H.VanderNolen(1) 67.7* " Steam Generator Staff Actions-- H. F. Conrad Improved Eddy Current Tests" 73 " Detached Thermal Sleeves" R.Colmar(1) 76 Instrumentation & Control' Power R. Colmar (1) i Interactions" i 95 " Loss of Effective Volume for W.Milstead(1) i Containment Recirculation Spray" 106 " Piping & Use of Highly Combustible R.Colmar(1)
Gases in Vital Are.as" 107 " Generic Implications of Main R.Colmar(1) i Transformer Failure" 110 "Eculpment Protective Devices on J.Pittman(1)
Engineered Safety Features" 112 " Westinghouse Peactor Protection J.Pittman.(1)
System Surveillance Frequencies"
.114 " Seismic Induced Relay Chatter" J.Pittman(1)
- 67.7 is to be discussed on 10/30/85-Herb Conrad ceuld not be available.
(1) Moran will provide status in the event Task Mgr/ Lead Engr. is not available.
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- Enclosure 2
[ '- October 30, 1985 AGENDA i Working Meeting of EPRI/NRR Proh et Managsrs l for the Joint Advanced LWR Program The purpose of this meeting is to obtain from Staff Task Managers their
- forecast of elements of resolution for unresolved generic safety issues i expected to impact Chapter 3 of the ALWR Requirements Document. The title of Chapter 3 is " Reactor Coolant and Non-Safety Reactor Auxiliary Systems.
Chapter 3, second level of indenture, content follows:
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Chapter 3. Reactor Coolant and Non-Safety Reactor Auxiliary Systems 3.1 PWR Primary Coolant System 3.2 PWR Steam Generator System (Including Blowdown System)
! 3.3 PWR Reactor Coolant System 3.4 Chemical and Volume Control System (PWR)
< 3.8 Leak Detection System and Process Valve Stem Leak-off Collection System (BWR)
.' 3. 9 Process Sampling System (BWR) s,_
I Issues to be discussed are listed below with the corresponding Task Manager
- providing the information.
I Issue Title Task Manager 29_ _ "BoltTng'legradation or Failure C. D. Sellers (1) in Nuclear Power Plants"
, 62 _ _ .. " Reactor Systems Bolting Applications" Notprioritized(2) i 109. . . " Reactor Vessel Closure Failure" Not prioritized (2)
[ (Note: Issues 29, 62 and 109 will be,
! discussed as a group dealing with -
! bolting USI A-12 (Resolution in hand) " Steam Generator and Reactor Coolant Pump Supports" also treats 1
bolting and may be discussed) 6.7.7 " Steam Generator Actions-Improved H. Conrad
. Eddy Current Tests" 79 "Unanalyzed Resistor Vessel Themal M. Hartzman Stress During Natural Convection Cooldown" 94 Additional Low Temperature Protection ^
E. Lantz Issues for LWR's '
104 " Reduction of Baron Dilution Notprioritized(2) l -
Requirements" 113 " Hydraulic Snubbers Notprioritized(2 84 "CE PORV's" (3 23 " Reactor Coolant Pump Seals" (4 (1) Warren Hazelton will discuss in Dave Sellers absence (2) Moran will provide information which is currently available on unprioritized issues
' (3) The resolution is available See P X NUREG-1044, this issue is held up ~
pending final resolution of A45.
(4) Resolution is available, this issue is held up pending final resolution of A44. l i
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2-Issue Title Task Mgr./ Lead Engr.
115 'PeTTability of Westinghouse M. M111 stead (2)
Solid State Protection System" 116 " Accident Management" J. Pittman (1) -
117 " Allowable Outage Times for Diverse. Simultaneous Equipment Outages" . .. . New Issue ..
118 " Tendon Anchorage Failure" New Issue 119 " Piping Review Committee Recommendations" New Issue 120 " Reactor Coolant System Pressure New Issue Isolation Valve (PIV) Leak Test Requirements" 121 " Hydrogen Control for Large New Issue Dry PWR Containments" 12? ." Davis-Besse loss of Feedwater New Issue
,_ l Event" HF.01.5.1 Man-Machine Interface- Man R. Froleich Machine Interface Guidance for
- Existing Designs HF.01.5.2 Man-Machine Interface-Man-Machine Interface Guidance '
for Designs Based on Advanced .
i Technology l HF.02.1 Maintenance and Surveillance Program (2) Tom Dunning will provide the update in Bill Milstead's absence.
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Enclosure 3 Attendees 10/29/85 D. H. Moran NRC W. Bilanin EPRI R. Engel SLI K. Kniel NRC/GIB H. Conrad NRC
, R. Samworth NRC T. Dunning NRC it 10/30/85 David H. Moran . NRC 492-9409
'I'- Dan Noble EPRI (415)855-2071 i{ Ed Lantz NRC/RSB Karl Kniel NRC/GIB 301)492-3759 Jim Lang EPRI 415)855-2038 4
Bill Layman EPRI 415 855-2013
! Warren Bilanin EPRI 415 855-2784 q Ron Engel SLI (408 377-8470 W. F. Anderson NRC/IE/DEPER 492-4819
. . Mark Hartzman NRC/MEB 492-28445
- f Dan Jones NRC/HF
- { Warren Hazelton NRC/MEB -
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Enclosure 4
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SUMMARY
- REMAINING AND NEW ISSUES FORECAST INFORMATION -
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- 1. Ice Effects on Safety-Reisted Water Supplies (B-32)
I This issue. should be considered Resolved i
Resolution documentation is available.
) 2. Chemicel DiscWgs to Remiving Waters (8-37) i This issue should be (mnsidered a Regulatory impact issue.
The current requirements in the Environmental Report Format and the Environmental Stander j
i'- Review Plans lare actmptable. Thus, the issue should be considered a Regulatory impact issue l the purposes of the ALWR. There are three perts to the issue: chlorinetton, copper and disL
- solids. Chlorinstion is no problem et current levels. Copper candenser tubes et low ph leve me/ be a problem, but normally would not be used because of corrosion problems. Dissolved solids cancerns are dependent on the type of circulating water system emploM The sta ff i
. ! considering that the Clean Water Act establishes a possibly atzeptable policy for the NRC. The s ta ff could possibly defer to EPA and the States to resolve this issue.
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- 3. L1Sild Pathway Radiological Control (lli.D.2.3( 1 ))
This issue should be considered Resolved i, A clomeout istter has been issued for this fesus.
s 4.
Screening of Sites for Liquid Pathway Conseguences (Ill.D.2.3(2))
.i This issue should be tunsidered Resolved A classaut istter has been issued for this issue.
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! 5. Liquid Pathway Interdiction (lli.D.2.3( 3))
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- I This issue should be considered Resolved A closeout letter has been issued for this issue.
6.
Summary Assessment of Liquid Pathway Consequencas (lli.D.2.4( 4))
j This issue should be considered Resolved A closecut 1stter has been issued for this issue.
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SUMMARY
- REMAINING AND NEW ISSUES FORECAST INFORM
- 7. Reactor Coolant Pump Seels (23)
No Mengein status.
Previous discussions provide ad=#a information on the status of this issue.
8.
Bolting Degradstion or failure in Nuclear Power Plants (29)
Nochange in status.
!) The offort to issue e new Standard Review Plan is currently stalled. This issue should i issues 62 and.109. The problem with the previous topic papers was an oversimplifica theissue,i.e.,takecareof theleeksandtheproblem,issolved. The staff agrees with the
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approach to closure design and maintanence to eliminate leeks as the right thing to materials that are too sensitive such as low toughness steels should not be used.
9.
Potential Generstor Missiles--Generator Retaining Rings (30)
This issue should be considered Drop Priority.
,; 10. Reactor Systems Bolting Application No change in status.
This issue me/ be superseded by Issue 29.
ii 11.
Steam Generator Staff Actions--Improved Eddy Current Tests (67.7.0)
No change in status.
lasue will probably be resolved by RES . ,
,, Changes to the ASME Code, Section Y and XI i> are likely. Suggaeted that copper be eliminated from secondary systems har=== c
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mask addr current steels. This issue could lead to new inspection tasm qualification requirements tastingare the only bemuse designofissues. differences in performance. Accessebility and capability fo
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12.
Unenelyzed Reactor Yessel Thermal Stress During Naturel Convection Cooldown (
Nochange in status.
Stresses are currently assessed as being within Code allowable. NRC has a contrac Brookhaven National Laborstory (BNL). Main canarn is how good the thermal h analysis is. The BNL offort is expectacted to be completed in June 1986. Specifyi cycles for this conmren should be an acceptable resolution.
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SUMMARY
- REMAINING AND NEW ISSUES FORECAST INFO
- 13. OE PORYs(84) "
No chen0e in status.
Previous discussions provide adequate infrmation on the status of this issue.
14.
Additional Low Temperature Protection leeues fr Light Water Reactes (94)
,, No cfienge in status.
{- This issue is based on the event et Turkey Point. Resolution is curently schedul year. Relief velves may be required on the RHR system with the cepecity of a NP change may be required to the pressure isolation system from automatic to man closed with one operation). Technical specification changes may be required to re system cepecity and on the startup of a cold loop.
'i 15.
Reduction of Baron Dilution Requirements ( 104)
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- No change in status.
I Based on the issue definition, this issue may be cxinsidered a Regulatory impact
- 16. Reactor Vessel Closure Fellure ( 109)
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Nochange in status.
s This issue may be supersedci by issue 29.
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- 17. NytteulicSnubbers(113)
No change in status.
Further infrmation is needed on this issue for a topic paper to be propered.
18.
Rellebility of Westin@ouse Solid State Protection System ( I 15)
This is should be cxinsidered not a current standardiand desip.
The current Westir$ouse micro prommear desired protection system use does not have for a diverse this concern. Tentative priority is hi$. Issue could be resolved b reactr trip.
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SUMMARY
- REMAINING AND NEW ISSUES FORECAST INFORMATI
- 19. Human Factors Program Plan (HF-01) i '
The Human Factors Program Plan is in the process of being revised There are 34 sub-iss the revised program plan, and all are currently prioritized as high priority safety issues.
, Basedondiscussionswith Diviston of Human Factors, about5of thesub-issuesshould be mnsidered as being applicable to the ALWR Program. Therefore, more information is required to almplete the forecast of these sub-issues. ,
, 20. Maintanence and Surveillana Prcram (HF.02.1 )
The Maintanence and Surveillance Proram Plan has been developed and there are 10 su j~ in the program plan. All sub-Issues are currentiv orloritized as hioh orlority safety issues.
g Basedondiscussionswiththe Division of Human Factors, none of the10 sub-issues
, should be mnsidered as being applicable to the ALWR Program. Therefore, more informst required to almplete the forecast of these sub-issues.
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l Enclosure 5 j ., October 30,1985 t REMAINING ISSUES lasue Curre<.t I
,; Number Priority NRC fygg[
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Title t
. . A-17
',; USI NoChange Systems interaction "
A-29 Nedium NoChange
- Nuclear Power Plant Design for Reduction of
.- i Vulner ebility to industrial Sebotage i; A-44 USI NoChange ii' Station Blackout A-45 USI NoChange Shutdown Demy Hast Removal Requirements i{ A-47 USl NoChange Safety implicellons of Control Systems
- _ A-48 USl NoChange Hydrogen Control Measures and Effect of Hydrogen Burns on Safety Egulpment 8-22 Later Noctangs' LWR Fuel 4
8-29 Later No Change" j i Effectiveness of Ultimets Heet Sinks
, 8-32 Later Resolved i! ice Effects on Safety-Related Water Supplies
- i 8-37 None R8guistory 6 Chemim1 Discharge to Ramtving Waters Impactissue
! D-2 Later NoChange
] Emergency Qire Cooling System Ospebility for
! FuturePlants
- l.F.1 High Nochengs QualityAssurene--Expand (M List ll.E.'4.3 ' High NoChange Containment Design--interity Check II.E.6 Medium NoChange i(
in Situ Testing of Velves--Test Adnquacy Study
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il.F.5 Medium
' ' NoChange Cleestfication of instrumentation, Control and
!' Electrim1 Equipment
lil.D.2.3( 1) Potential Resolved LiquidPathwayRadiologimlcontrol Resolution i
ill.D.2.3(2) Potential Resolved
- Resolution Screening of Sites for L iquid Pathway Conseguances i
lli.D.2.3(3) Potential Resolved LiguldPathwayInterdiction i
Resolution Further Foremst Requ! red 1
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REMAININGISSUES(continued)
Issue Current NRC Number Priority forecast Title i lli.D.2.3(4) Potential Resolved
? Summary Assessment of Liquid Pathway Resolution Consequences 2 Later NoChange
- Failure of Protective Devims on Essenttal Equipment
- 21 Later No Change
- i Vibration Quellfication of Equipment 23 High NoChange Reactor Coolant Pump Seels i
t 29 High NoChange
- Bolting Degadetion or Failure in Nuclear Power j !- Plants
! i 30 Later Drop Potentia 10enerator Missiles--Generator Retaining Rings 51 Medium No Change Proposed Requirements for improving Reliability of OpenCycleServiaWater Systems 57 Later NoChange
.j Effects of Fire Protection System Actustion on I Safety-RelatedEguipment i
No Change
- Reactor Syst3ms Bolting Applications Ij '
67.7.0 Medium NoChange l Steam Generator StaffActions--Imprwed Eddy Current Tests 73 Later NoChange DetachedThermalSleeves
- , 75 Potential NoChange" Generic implications of ATWS Events at Selem Resolution Nuclear Plant 76 Later No Change" instrumentation and Control Power Interactions 79 Medium NoChange Unenelyzed Reactor Yessel Thermal Stress During NeturalConvectionCooldown 82 Medium NoChange Beyond Design Bels Amidents in Spent Fuel Pools 84 Potential NoChange CE PORVs Resolution i
91 Potential NoChange Main Crankshaft Failure in Transemerim Delevel Resolution EmergencyDieselGenerator Further Foremst Required t
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,e REMAININGISSUES(amlinued)
- Issue Current NRC
- Number Priority Forecast Title i >
93 High NoChange
> Steam Binding of Auxiliary Feedwater Pumps 94 High No Change Additional Low Temperature Prtin: tion issues for LightWater Reactors 1 95 Later No Change
- i Loss of Effective Voluma for containment i t Recirculation Spre/
, % Medium NoChange RHR Suction VelveTesting i k 99 High No Change RCS/RHR Suction Line Velve Interlock on PWRs
,o 101 High
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NoChange BWR Water LevelRedundancy '
103 Potential NoChange Design for Maximum Probable Precipitation Resolution
- 104 Later No Change" Reduction of Baron Dilution Requirements l 105 High NoChange InterfacingSystem LOCAet BWRs 106 Later No Change' Piping and Use of HlWily Combustible Geses in YJta1[
Areas 1 s i1 107 Later No Change' '
Generic Impliations of Main,Tr.ensfoFmer failure l 109 Later NoChange' Reactor YesselClosureFellJre 1Id Later No Change' Equipment Protective Devices on Engineered Sofety Footures
' ,, 112 Later Regulatory Westinghouse Reactor Protection System
.! Impactlasue** SurveillancefrequenciesandOut-of-ServiceTimes 113 Later No Change
- HytaulicSnubbers 114 Letar No Change
- SeismicinducedReleyChetter
- 115 Later Not a Current Reliability of Westin$ouse Solid State Frctantion Stenderdized System -
Design .
116 Later No Change
- Accident Nenagement ' ~
Further Forecast Required .' c
- Resolved '
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- , t REMAININGISSUES(continued) >
- Issue Current NRC
! Number PIjgtik :
! Fracest Title '
.. 117 New issue Later*
jt Allowable Outage Times for Diverse 31multaneous
- i. ,o Egipmentoutages li 118 New issue Later* TenenAnchorageFailures 119.1 Newissue Potential Piping Review Osnmittee Rauommendations--Piping i( s i
Resolution
- Rupture Requirements and Decoupilng of Sismic and LOCA Losts
! 119.2 New issue Potential jj -
Resolution
- Piping Review Committee Rammmendstions--Piping PipingDampingValues g=
- t 119.3 Newlseue Potentiel I' Piping Review Committee Recommendelions--
Resolution
- Decoupilng of the Design Basis Earthquake (OBE) from the SafeShutdown Earthquake i.
119.4 New issue Potential Piping Review Committee Recommendations--8WR
, Resolution
- Notarisis ;
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119.5 New issue ii s -
Potential Resolution
- Piping Review Committee Recommendelions--Leek
.;s s Ddsction Requirements 120 New lseue Letar* On-Line Testability of Protection Systems
}! 121 Newissue Letar* Hy& ogen Control for Large Dry Containments 122.1 Newissus Later*
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Davis-Besse Loss of A11 Feedwater Event--Potentiel i L Inability toRemove DemyHast
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, 122.2 Newissue totar*
Devis-Basse Loss of A11 Feathvetar Event--Adesecy ii~ x '
~ of Emergency Procedures, Operator Trainin0 and l1 i
AvailablePlant MonitoringSystems j l' 122.3 New lseue Later* i
! . -,'; x -
Davis-Beses Loss of A11 Feedwater Event--Physical I Security 0anstrWnts ii
- , W.01.5.1 H1$ issue Deleted Man-Mechine Interface--Hen Nachine Interface i! Ouidance for Existing Designs
! W.01.h.2. Hi$ issueDeleted
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Non-Machine Interface--Men Machine Interface i
a Ouldena for Designs Based on Advanced Technologies I
N Further Forecent Required i
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e REMAINING ISSUES (antin'ued) issue Current NRC Number Priority Frecast Title ,
HF-01.1.1 New issue High*
I Policy Statement on Engineering ExpertNe on Shift and Evoluete Effectiveness of Policy Statement HF-01.1.2 Newissue High* Revise and Evaluete Changes to Regu1 story Guide 1.8 HF-01.1.3 New issue High"
- Develop a Means to Evolusta hxmptability of Nuclear 5 Power Plant Personne10uellfimtions Program '
HF-01.1.4 New issue High*
t .- Review and Evoluete Industry Programs HF-01.2.1 New issue High" EvaluateInchstryTraining HF-01.2.2 New lasue High* '
EvolueteINPOhx:reditetton Prorem
- HF-01.2.3 New issue High*
Revise Standard Review Plan Section 13.2.3 HF-01.3.1 New issue High* DevelopJob KnowleteCatalogue HF-01.3.2 New issue High* Develop Lkansing Examinettons Haneook
'f HF-01.3.3 New lasue High* Develop CriterieYor Nuclear Power Plant Simuletas
'I
- ' HF-01.3.4 New issue HiWi* Trainin0 Requirements Pockepe (Revise 10CFR55 and Reg. Guides 1.149 and 1.8)
W-01.3.5 Newissue High* Develop ComputertzedExem System i
T-01.4.1 New issue High* Inspection Module for 1;3greding Procaibres HF-01.4.2 New issue High* Engineering Operating Procedure Effectivensas Evaluation f W-01.4.3 Newissue High* Criteria for Sofety-Related 0perator Actions (01*B-17)
W-01.4.4 Newissue HiWi* Outdelines for Upgrading Other Procedures N-01.4.5 New issue High*
Applications of Arlificiel intelligona HF-01.5.1 Newlseue HiWi' Loos 10antrolStations HF-01.5.2 New issue HiWi" Annunciators !
s W-01.5.3 New issue High* '
EvaluateOperationalAidSystems
- Requires Forther Forecast I s
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u REMAININGISSUES(continued) i j l issue Current NRC
! Number Prkrity Foremst 6
Title
- HF-01.5.4 New issue High* Computersand0amputer Displers
.i HF-DI.6.1 New issue > High*
Development of Reguletary Position on Management j -
endorganizatist HF-01.6.2 New issue High* Evoluete CritMa for sal.P Review HF-01.6.3 New issue High*
Revise Stendero' Review Plan Section 13.1
., HF.02.1 High issueDeleted I MaintenanceandSurvellianaPrcram HF-02.1.1 New issue High* Survey of Current Maintenance Practims i HF-02.1.2 New issue High*
Neintenance and Performance Indiators ki g E-02.1.3 New Issus High" Monitor imbstryActivities HF-02.1.4 New lasue High" Participatein Standards Gra>ps HF-02.1.5 New issue Hi@*
.I Maintenens and SurveillerKc Program Integration W-02.l.6 h}. Newissue High* Analysis WJapaness/U.S. Nuclear Power Plant l
MaintenanceProrems I+
HF-02.1.7 New isme High*
Maintenance Personne10uellfications HF-02.1.8 New heue High* Human Factors in in-Service inspections HF ,02.1.9 New lasue Hi@* Human Error in Events involving Wrong Unit or
,g WrongTrain(Gl *101) '
W-02.ll.1 Newleeue Higli*
Phase il Tasks to Be Determined After Resolution of j .T.. Phasel I
l
!h* \
1
! i
- Ii
- RequiresFurtherForecast
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