ML19309B008
| ML19309B008 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 03/12/1980 |
| From: | Mattson R Office of Nuclear Reactor Regulation |
| To: | Dircks W, Donoghue D, Shapar H NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO), NRC OFFICE OF THE EXECUTIVE LEGAL DIRECTOR (OELD) |
| References | |
| NUDOCS 8004020476 | |
| Download: ML19309B008 (37) | |
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UNITED STATES f'
NUCLEAR REGULATORY COMMisslON PDR fy i
WASHINGTON. O. C. 20555 f
March 12, 1980 MEMORAl4DUM FOR:
W. Dircks, Acting Director for Operations D.J. Donoghue, Director, ADM H. Shapar, Director, OELD L. Barry, Director, CON J. Shea, Director, IP R. Ryan, Director, SP N. Haller, Director, MPA R. Minogue, Director, OSD J. Davis, Acting Director, NHSS H. Denton, Director, NRR R. Budnitz, Director, RES V. Stello, Director, IE FROM:
Roger J. Mattsen, Director TMI-2 Action Plan Steering Group
SUBJECT:
TRANSMITTAL OF REPLACEMENT PAGES TO DRAFT 3a 0F THE ACTION PLAN Attached are replacement pages I.A.2-3, I.A.2-1L.
I.D.-4, I.D.-5, I.D.-11, I.G.-1, and I.G.-2 to Draft 3a of the Action Plan to reflect a change in Task I.D.3 from Decision Group B to C; to clarify that tne education requirements pcrtion of Task I.A.2.1 is Decision Group C; and to incluce missing Task I.G.2.
Also attached are revised Tables 1 and B.2 to reflect the above changes and other corrections.
Please include these replacement pages in your copy of Draft 3a of the Action Plan.
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Roger J..Mattson', Director 4
TMI-2 Action Plan Steering Group
Enclosure:
7 revised pages Tables 1 and B.2 cc: PDR Task Managers Steering Group Offices of the Commissioners 8004020 Q %
Task I.A.2 Draft 3 - 3/5/80 (2) Training (a) Shift supervisor - Training programs for shift supervisors shall emphasize and reinforce the responsibility for safe operation and the management function to assure safety (NUREG-0578, Recommendation 2.2.1.a).
Those individuals applying six months after the requirement issue date* shall have thr se months shift training (Recommendation 3 of SECY 79-330E).
(b) Senior operator *: Applicants shall have three months of shift training six months after the date of the requirement (Recommendation 3 of SECY 79-330E).
(c) Control room operators *:
Individuals applying six months after the requirement issue date shall have three months training on shift as an extra person in the control room (Recommendation 3 of SECY 79-330E).
conce u 9 w d'"] ^"d L4*"
b.
Schedule: The requirements 4will be issued by April 1, 1980. Th e Rc G o'* **""
C o~ce a n unc} B d o us v.o a wor L be add ae.::.ed ns p A u o F Tum Z. A 3 h ge s <, a,tct ; de L.n ed To ESTnhinsbo AgQ a,ge,e u ( *. (a4 Tan,Nong Add her%t'NCe Resources:
FY80 - $3,000, FY81 - 0.1 my and $3,000; IE FY80 - 1.0 my and $9,000. See Tass I. A..;t 6 Co A Res ou ac a R e u re.L ia e s r,e 6 Li sh o aq Ed s e.n.o,4 de a u, o<am a.v -s 2.
Training and qualification of other operations personnel.
a.
==
Description:==
Each licensee will be required to review its training program for all operations personnel, including maintenance and technical
" Precritical applicants will be required to meet unique qualifications designed to accommodate the fact that their facility has not yet been in operation.
I.A.2-3
t Task I.A.2 Draft 3 - 3/5/80 NRC approaches to accreditation of training institutions, coordinate'with INPO to include thorough discussion and assessment of INP0 programs.
b.
Schedule:
RR will complete study by April 1.80.
NRR will complete information paper by June 1980.
SD will complete a Commission action paper by January 1982.
c.
Resources: NRR FY80 - 0.4 my and $80,000, FY81 - 0.2 my; SD FY80 -
0.6 my, FY81 - i.0 my; ADM FY80 - 0.1 my and $7,000, FY81 - 0.2 my and $7,000.
C.
' LICENSEE ACTIONS 1.
Immediate upgrading of training and qualifications.
a.
==
Description:==
All operating license applicants and operating reactor licensees must recruit and train personnel to meet the new requirements [x 7,(4 e,"$
An d E yfe :t r es c e ( S ac TA5 m Z. A. O. 6 !a e. RC C J.R e s ed n A L,*r e s
~a EJaca r, o s )
b.
' Implementation:
Licensed operators must meet the requirements for licensingandrelicensingontheschedule{tkough4985asdefinedinNRC
)
item I.A.2.1.
c.
Resources: $300,000 per year per plant for increased salaries and increased time in training.
I l
l I.A.2-10
t Task I.D Oraft 3 - 3/5/80 c.
Resources:
NRR FYSO - 2.0 my and $160,000, FY81 - 5.8 my and $110,000, FY32 2 my/yr and $50,000/yr; IE FY80 - 1 my and 59,000, FY81 - 1 my and 59,000; ACM FY80 - 0.1 my and $10,000.
2.
Plant safety parameter display console.
a.
==
Description:==
NRR will require all licensees and applicants to install a safety parameter display system that will display to the operator a minimum set of parameters ' safety state vector) which define the safety status of the plant.
The system must have the capability of permitting the operator to display a full range of important plant parameters and data trends on demand.In addition, the system must provide indication to the operator that process limits are being approached or exceeded.
NRR will review the proposed designs in conjunction with other control room design modifications to ensure that the needs of the operator are met b.
Schedule:
NRR requirements will be issued by June 1980, c.
Resources:
NRR FY80 - 2.0 my, FY81 - 2.0 my.
3.
Safety system status monitoring.
NRR will(A deneed $*K sr a.
==
Description:==
quirc thajt all licensees and applicants not presently committed to the requirements of Regulatory Guide 1.47, " Bypassed and Inoperable Status Indication for Nuclear Power Plant Safety Systems,"
{s4es+ the we]4 to monitor and verify operations, test, and maintenance l
l I.0-4
Task I.D Draft 3 - 3/5/80 activities by means of an automatic status monitoring system, such as that cescribed in Regtlatory Guide 1.47.
This ab$dat-is to be performed following a review of precedures and other nonautomatic actions to verify y
,,s m.,.va er ~ u M 2 r 8 % M C...:. u CD a these activities, ar. required in item I.C.6 In addition, consideration should be given to the impact of other control room modifications on establishing the need for automatic status monitoring.
<e po c-Re.s u tn o b S -n i k Siu dy NRR wilf[somplete r-edews_.of licensee-assessments b.
Schedule:
[dmTuary-1982[
$c.
-S c.
Resources: NRR h80 D.4 mj FY81 -
my; (ABM-FYSI -Or2-my-snd Sr'r9,00]G r
D 4.
Control room design standard.
h f
.S
?
a.
==
Description:==
SD will issue for comment a proposed regulatory guide g
based on an evaluation of industry standards (IEEE 566 and 567) that includes
<-W consideration of the applicability of standards to plants under construction.
x SD will urge prompt revision of IEEE 566 and 567. NRR will require compliance Q
O with the regulatory guide as required.
k 5.
Schedule:
50 will issue regulatory guide for comment by July 1981.
SD will develop implementation schedule and will issue regulatory guide effective by May 1982.
NRR will ensure compliance (or commitment to comply) by May 1983.
c.
Resources: SD FYS1 - 0.5 my, FY82 - 0.5 my.
I.0-5
Task 1.D Draft 3 - 3/5/80 2.
Plant safety parameter display console.
a.
==
Description:==
Design and install safety monitor console.
b.
Implementation:
Licensees and applicants will submit the system design for NRR review by January 1981 or 12 months prior to issuance of an operating license, whichever is later.
Licensees and applicants for operating licenses will complete implementation by January 1982 or prior to issuance of operating license, whichever is later.
c.
Resources (per reactor):
$1,000,000.
3.
Safety system status monitoring.* AJO L Cea Jeo A C 7, cd kd QC / dd h.-Oescription:
Submit for NRc_ review a-r4 port describing-an-asessment of-the-need for-an autmatic status-monitarii.s sy ster l
&Impicmantetion:
L!weasees and applWnts for-operating 44c-enses.
ui cc:pletc their asses...enLa by Septcmbe.1981 or grior i.o issuouve-of-en--
operstTrity license, wMchevar is later. Thcy iii4nstali Uie automai.iu = Lh men:tering syste.a wi thin 12 moiiUi= chereafte., i f i-t--is r;;;uir:d.
les m was (;cr reav er):
0.5 my, 250, c-4.
Control room design standard.
I.0-11
Tash X.G Oraft 3 - 3/5/80
}_ RAINING-GURINGf PREOPERATIONAL AND LOW-POWER T TASK I.G A.
OBJECTIVE:
Increase the capability of the shift crews to operate facilities in a safe and competent manner by assuring that training for plant evolutions and off-normal events is conducted.
Near-term operating license facilities will be required to develop and implement intensified training exercises during the low power testing programs.
This may involve the repetition of startup tests on different shifts for training purposes.
Based on experiences from the near-term operating license facilities, requirements may be applied to other new facilities or incorporated into the plant drill requirement (item I.A.2.5).
Review comprehensiveness of test programs.
B.
N,RC ACTIONS 1.
Training requirements.
a.
==
Description:==
NRR will require new operating licensees to conduct a set of low power tests to accomplish the objective. The set of tests will be determined on a case-by-case basis for the first few plants.
Then NRR will develop acceptance criteria for low power test programs to provide " hands on" training for plant evaluation and off-normal events for each operating shift.
b.
Schedule: NRR will develop criteria in conjunction with initial near-term operating license reviews.
This work will be completed by September 1980.
l I.G-1
Task Z.G Oraft 3 - 3/5/80 c.
Resources: NRR FY80 - 1.5 my, FY81 - 0.5 my.
7 C.
LICENSEE ACTIONS 1
1.
Training requirement 1.
i l
a.
==
Description:==
Licensees will (1) define training plan prior to
' loading fuel, and (2) conduct training prior to full power operation.
i b.
Implementation:
Oces not apply to operating reactors. Applicants for operating licenses will define plans prior to fuel loading and conduct training prior to full power operation.
c.
Resources:
Does not apply to operating reactors.
Applicants for i operating license - 0.1 my; plants with ~ construction permits 0.1 my.
.3. S c. a ga e c i-TE S T pro a Aan. Aj 6 L a c ~ ~ : e L Acrcn N::' 6 a. R v cf D.
OTHER ACTIONS: None i
i E.
REFERENC55:
None 5 Cops cG I EST
- p. aoc em a.
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h p q,tt w Rgis.sr cz em u r ek SKP 0'*dM%
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-} a e d ow l s ~~ o l]e ve,< in," e
-[0 ( [a'L L w h e~h e il N EG.' > R L r e. - M C,..,p ae he~ s u e y ac owe
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[u l y I, I N l c se c co nc e = ' A AA ftEA-0Dny IE f'Il ~O. I A /, 50 ff b'I ~C'I"I I.G-2
AW8D IAlltE 1 - PRIORilitS AND SIAlll5 Of litMS IN IMI-2 ACil0N PIAN Decision Priority lead Implementation Complete Action item Group Group Office Operating Reactors Plihti Ui.deFConstruction 1.
Operational Safety I.A.I Operatliig PersonsieI asid StariIsig 1.
Shift lethnical Advisor A
I NRR On duty - 1/1/80 On duty --ti fully trained - 1/1/81 f ully tralsied - 1/1/88 2.
Shift Supervisor Admin. Duties A
I NRR 1/1/80 IL 3.
Shift H.anning A
I NNR Personnel req. - 7/1/81 fl overtime req. - 1/l/80 4.
long-term upgradisig 0
5D NA NA 1.A.2 Iraining ased Quellfications of Operatinu Personnel 1.
Immediate Upurade of Ro and $RO qual.
.&ep = A I
NRR Experience 4/1/88 Same as OR ru..r i n <nt 2.
Iraining and Qualifications of Ottier 8
2 NRR S/1/81 5/1/81 Personnel 3.
NRR Audit freining 8
2 NRR NA NA 4.
NRR Participation in IL Inspector 8
3 If NA NA Iraining S.
Plant Drills B
1 NRR Short-tera - 1/1/81 Short-term I/l/81 6.
Long-tesa Upgrading C
I SD NA NA 7.
Accreditation of 1 raining C
2 NEW NA NA Institutions.
I A8t t I (continued)
Decision Priority lead Implemesitatiosi Complete Action item Group Group Office DperatIWheactors
~ Plants UniEr ConstruciIiin 1.A.3 Licensing and Nequalificatiosi of Operating Persusinel I.
Nevise Scope and Criteria for Exams A
2 NNW 4/1/80 il 2.
NNC Operator iicensisig Neforms C
3 NNN NA NA 3.
Operatur Iitness B
$D HA NA 4.
L icensing of Additional Operations Persosuie l C
2 NNN NA NA h.
NHC/ DOL /INPO Statement of Understanding 0
NNN NA NA
!.A.4 Simulator use and Development I.
Initial Simulator leprovement 8
- /
NNN 1/1/81 1/l/81 2.
long-term $1mulator upgrading 8
A*d 50
//l/82 7/l/82 J.
NNC Iraining Simulator D
NES NA NA 4.
NNC Engineering Computer D
NE5 NA NA 1.8.I Management for Operations 1.
Orgentiation and Manauement C
1 NNN 6/8/82 6/1/82-fL tong-lerm Improvements 2.
[ valuation of NI0l Orgenlistion A
I IE NA IL and Nanagement leprovements
)
3.
loss of Safety function C
A-(
50 NA NA j
9 I AHi t I (continued)
Decision Priority lead laplementation Complete Action item Group Group Office Operating Reactors Plinks undeFConstructio~n 1.B.2 Inspection of Og*vating iteactors 1.
Pevise IE Inspection Progros 0
IE NA NA 2.
Resident inspector at operating A
L IE 4/80 IL Reactors 3.
Neutonal Evaluations 0
IE NA NA 4.
Overview of 1icensee Performance 0
IE NA NA 1.C Operatlag Procedures I.
Sluirt-Iern Accident Assalysis and A
I NRR Small Break - 1/1/80 Small Break - Il Procedure Revision Cure Cooling - 1/1/80 Core Cooling - it Iransients/ Accidents -
Iransients/ Accidents -
7/1/80 7/1/80 2.
Stillt ami Relief furnover A
I NRR 1/1/80 ft 3.
Shift Supervisor Responsibilities A
I NRR 1/1/80 (L
4.
Control Room Access A
I NRR 1/1/80 ft 5.
feedback of Operating imperience A
I NRR 9/l/80 (L
f>.
Verification of Operating Activities B
2 NRR 1/1/81 1/1/81 7.
NS$$ Vendor Review A
I NRR NA low Pbwer lest - it leergency & Power Ascension - FP 8.
Pilot Program - NIDI A
2 NRR NA IP i
9.
toau-lerm Progree Plan C
1 NRR NA NA
-3_
I A8t f 1 (continued) l l
Decision Priority lead Implement imihaple te Action item Group Group Office Operating Reactors dants ilmler Construction I.D Control Nous Design I.
Design Neview Niet - A I
HNN Short-tera - 3/1/81 Interim - ft Nemainder - 8 tong-tern - 3/l/82 Sliort-tera - 3/1/81 tung-ters - 3/l/02 2.
Sately Parmacter Console 8
I NNR 6/1/81 6/l/81 3.
System Status N nitoring
- C 2
NkN 12/1/81 12/1/81 4.
Design $taswfard 8
I
$D NA NA 5.
Research C
2 RLS MA NA 6.
Iechnology transfer Cosiferesica A
g3 RES NA NA 1.E Analysis and Dissemisiation of Operatisia txperience 1.
Office for Analysis and A
I ALOD NA NA Evaluettosi of Operational Data 2.
Office Programs A
I (DO NA NA 3.
Data Analysis A
I Rf5 MA NA 4.
Coordination of Programs B
I
$D NA NA S.
Nuclear Plasit fjellatallity Data i
System D
50 NA NA i
6.
Reporting Nequiremen'ts C
1 Af00 NA NA i
4
I A881 1 (continued)
Decision Priority lead Implementation Cag le g _ _
Action Iten Group Group Office Operating Reactors Plants under Constructi_on J.
foreign Sources B
- d IP NA NA 8.
Ihaean trror Analysis A
2 RL5 NA NA l.I Quality Assurance 1.
Expand QA list 8
2 50 NA NA 2.
Detailed Criterie D
50 NA NA I.G Irainlag During low-Power lasting 1.
Iraining Requirements A
2 NRR NA Plan - FL Irain - IP 2.
Scope of Iest Progree 8
/(
NNN NA NA II.
Siting and Design II.A Siting 1.
5fting Policy Rulemaking C
3 NNN HA NA 2.
Site tvaluation C
2 NRR NA NA 11.8 Degraaled or Melted Cores l.
Primary System Vents A
2 NRN Design 1/1/80 Design IP Installation I/1/81 Installation 1/1/81 2.
Plant Shielding A
2 NRR Design 1/1/80 Design IP Hodifications 1/1/81 Modifications 1/1/81 3.
Postacclitent $4epting A
2 NAN Design & Procedures Design & Procetlures - IP I/1/80 Hodifications 1/1/81 Modifications 1/1/81 I ABt 1 1 (continued)
I)=c i s ion Priority lead Iglementatiosi Causplete Action item Grongs Groegs Office Operating Reactors Plants Uniler Const:uction 4.
Iraining A
I NNR Program - 1/1/88 Issill41 Program - Il levelement - 4/1/81 Implement - iP 5.
Research A
2 NL5 NA NA 6.
Nisk Reduction for Operating A
I NNN Selected $ltes -
NA Reactors at Sites wille liigh 10/1/80 Populatica Density l.
Contalausent Isierting A
I NNR ilWN NK I & II NHC decide on Cont 41sunents -
Interim laydrogen control As Ordered measures - IP 8.
stulemaking on Degraded Core A
2 50 NA NHC issue interim rule - IP Accidents 11.0 Neliability is gineering and Nisk Assessment 1.
Inittel Integrated Neliability A
I R[5 Crystal Nlver - 7/80 NA Lwaluatiosi Program (IREP) 6 plants - 10/80 2.
Continuatiosi of INEP C
2 R[5 All - 1983 lladecided 3.
Systems Interact losi A
W NRR Inallan Point 3 - 1981 Distilo Casiyon - IP 4.
Heliability ingineering 8
- Q NRR Beyond l'J82 NA II.D Neactor Coolant System Nellet asus Safety Velves 1.
lest Neipsirements A
I NRR Program - 1/l/80
' engram - #1 lestisig - 7/1/81 lasting - 7/1/81 i
f IABLE 1 (continued)
Decistun Priority lead Implementation Complete Action item Group Group Office Operating Reactors Plants UnM r Construct Wn 2.
Reseas ch A
23 RES NA NA 3.
Position Indicatiosi A
I NRR 1/1/80 Il II.E
System Design
ll.L.I Auxiliary f eedwater System 1.
Evaluation A
i 16RR Siior t-tere
$hort-term - fl.
W & CE - 6/1/80 tong-ters - IP B&W - 9/1/80 long-tern - 1/1/81 2.
Auto Initiation and flow Indication A
I NRR Control Grade - 6/1/80 Control Grade - Il Safety Grade - I/1/81 Safety Grade - 1/1/81 3.
tipdate SkP and issue Regulatory Guide D
NRR NA NA II.E.2 Emergency Core Cooling System 1.
Reliance on LCCS
,[8 Ad NRR 1/1/82 1/1/82 2.
Research A
I RES NA NA 3.
uncertainties in Performance G
2 NRR 1/1/80 1/1/80 Predictions II.E.3
!)ecay lleet Removal 1.
Natural Circulation A
1 NRR 1/1/80 fP 2.
Systems Reliability,
8 I
NRR NA NA
-y-
I A8t t I (continued)
Decision Priority lead Implemengtlon Complete Action Iten Group Group Office Operating Reactors Plants linder Construction 3.
Alternate Concepts Nemearch D
Nt5 NA NA 4.
Negulatory Guide 0
$D NA NA II.E.4 Contalonent Design 1.
Dedicated Penetrations A
I NNR Design - 1/1/80 Design - it install - 1/1/81 Install - t/1/81 2.
Isolation Dependatallity A
I NNN Signals - 1/1/80 Signals - I'P Plan - 6/1/80 Plan - f r N d - 11/1/80 Nd - I P 3.
Integrity Check 8
2 NNN 6/1/81 6/l/81 4.
Purging A
I NNN 1/1/80 - Staged IP - 5 49est i
II.E.5 Design Senaltivity of 84W Neactors A
2 NNN 4/1/81 4/1/81 11.E.6 In Situ lesting of Valves 0
NNN NA NA II.f instrumentation and Controls 1.
Additional Accident Mnitoring f
Instrumentation A
I NNN 1/1/81 1/1/81 2.
Inaalcaguate Core Cooling A
I NNN Sidicool - 1/1/80 5 diccol - il level Design - t/1/80 level Design - IL level Install - 1/1/81 level Install - 1/1/81 3.
41 50 6/8/82 6/1/82 4.
Control and Protection Actions C
3 NNN NA NA
IAllil I (continued)
Decislon Priority lead Implementetlon Complete Action Ites Group Groaqi Office OperatlWileactors
~ flants Under Construction ll.G flectrical Power for PONV, Bluck Valve asal level Indication A
I NHR 1/1/80 IL 11.11 INI-2 Cle4susp and [maanisiation 1.
INI-2 Safety A
I NRR NA NA 2.
Obtain Information A
- 4 NES HA NA 3.
Evaluation asul f eediaack A
NRM NA
~
NA 4.
Socioeconomic Effect and Property Values A
3 NE5 NA NA II.J General Implications of INI for Design and Constructian Activities II.J.I Vendor Inspection Progras I.
Inspection Priority D
IE NA NA 2.
Hudify fuisting Program D
IE NA NA 3.
Expand Negulatory Control D
IE HA NA 4.
Resident Inspectors at N555 0
IE NA NA Vendor 6 and Afs II.J.2 ConstrutLlon inspectlon Program 1.
Reorient Program A
3 IE NA NA 2.
Imlepesulent Heasureme'nt A
- ,3 IE NA NA 9
I AulE I (continued)
Decision Priority lead laclementation Cong_ilete Action item Group Group Office OperatlWReactors flants liniteFConstructIE 3.
Nesident Inspectors D
IL NA NA I1.J.3 Nan 49ement ior De6 ion and Construction I.
Organization aml Staf fing C
- 1 NRR NA NA 2.
Regulatory Guide C
3 50 NA NA II.J.4 Revise Deficiency Reporting Requirements C
2 IE NA NA II.K Small-Ilreak 10CAs and loss of feedwater Accidents 1.
IE Bulletins A
I NHR 3/31/80 lable C.I Appendix C 2.
Commission Orders on 81W Plants A
I NRR 1/1/81 lable C.2, Anoendix C 3.
Iinal RecoamienJ4tions of B&O 8
I NNN I4ble C.3, Appendix C lable C.3, Appendix C Iask force 111. Leergency Preparations and Radletion Protection Ill.A.I improve licensee Emergency Preparedness Short-term I.
Upgrade [mergency Preparedness A
1 NRR Phased I/l/80 - 1/1/85 Phased: FL-l/l/81 2.
Upgrade Support f acilities A
I NNR Infllal - 1/1/80 lattial - IL i
Upgrade - l/l/81 Upgrade - 1/1/81
- 10 ' -
l
- - ^ - -
lanst 1 (continned)
Decision Priority
!=ad Implementation CM ete Action item Group Group Office Operati _ng Reactors Plants under Construction 3.
Ihyroid Blocking Agent C
3 MN Workers - 3/1/81 Workers - 3/1/81 Public - NA Public - NA Ill.A.2 Improving licensee Emergency Preparedness - tong-tern I.
Rule Change C
/,3 SD NA NA 2.
Guidance and Criteria C
3 MH HA NA lit.A.3 Improving MC f aergency Preparedaiess 1.
NRC Role A
1 100 NA MC de f ine i t s role - I P 2.
Improve Operatlens Center [
B 2
IE NA NA 3.
Communications Telephones-A 2
IE Islephones - Y/l/80 lelephones - ti l
Sackup-C 4.
Nuclear Data Link C
3 IE NA NA 5.
Iraining Drills, and lests 0
IE NA NA 6.
Interaction with Other Agencies C
2 100 NA NA Ill.B toergency Preparedness of State and local Governments 1.
Iransfer of Responsibilities to FENA A
- /
LDO NA NA 2.
legalementation of MC and ilNA A
I
[D0 NA NA Responalbilities
, 11 -
IA8tE I (continued) i Decision Priority iend Implementation C mple_te 2
Action lies Group Group Office Operating Reactors Plants under Construction III.C Padslic Information I.
Information Availability C
3 OPA NA NA 2.
A ency Policy asul Training C
3 OPA NA NA 0
Ill.D.I Nadiation Source Control l
1.
Source Outside Containment A
2 NNN 1/3/83 IP 2.
Radioactive Gas Management B
3 NRR NA NA 3.
Vent System and Nadiolodine B
2 NNN Evaluation - 4/15/80 Evaluation - 4/lb/80 j
Adsorber Criteria Modifications -
Modifications -
e late 1983
!ste 1983
{
4.
Nadweste System Design features C
3 NRR NA NA l
III.D.2 Public Radiation Protectiosi Improienent 1.
Effluent knitoring 8
3 NNN 12/1/81 12/1/81 2.
Radiolodine, Cashon-14, and Irltius B
3 NNN NA NA Path Dose Analysis 3.
Lispaid Patieway Radiololical Control C
3 NNR NA NA 4.
Offsite Dose N asurementa NIOL - A 3
NNR 6/1/81 6/1/81 Remalader -
NHC install itDs - fP 5.
Dose Calculation Manital B
3 NRR 6/1/81 6/1/81 6.
Independent massarements D
IE NA NA I
IABIE i (continued)
Decision Priority lead Implementatism Cong!kte Action iten Group Group Office Operating Reactors flents usuler Construction Ill.D.3 Worker Nadiation Protection impsovements 1.
Nadiation Protection Plens a
2 NNil 9/1/88 9/l/88 2.
Ilealth Physics leprovements D
SD HA NA 3.
Inplant Monitoring Short-3 NNN Nadiolodine - 1/1/80 Nedlolodine - Il ters - A long-Addl. E nitors - 6/1/82 Addl. Nonitors - 6/1/82 ters - 8 D s
l 4.
Control Noon liahitability A
2 NNN Neview - 5/1/80 Neview - IP Hod - 3/l/81 N d - 3/1/81 5.
Radiation Worter Emposure Data Base D
50 MS NA IV.
Practices asul Proceduces
~
IV.A Strengtl.en inforcement Authority 1.
Seek teulstative Authority A
2 DGC MA NA
[
If NA NA 2.
Nevise inforcement Policy D
I IV.8 Nevise Practices for Providing i
g Instructions and Information D
G-NNN NA NA to Iicensees l
I IV.C Extend lessons learned to licensed C
/{
NN55 NA NA l
Activities other lhan Power Neactors IV.D Assess NNC Irdining Needs C
2 AllH NA NA i
i ~
l l
l
l 1
\\
l IA8tE I (continued)
Decision Priority. tead laisilementat ton Cogilete Action lien Group Group Office Op Val W Reactors Plaiits Under Construct I~on l
IV.E Safety Decision-Haking 1.
Espand Research on Quantification D
RES NA NA of $4tely DecisinerNaking 2.
Plan for Resolving issues at C
3 50 NA NA Construction Permit stage 3.
Resolve Generic issues by Rulemaking C
E.3 Comm.
NA NA I
4.
Assess Currently Operating Reactors C
g/
NRR NA NA
{
IV.f firaancial Disincentive to Safety 1.
Increased il Scratiny of Power A
3 IE NA I L-Ascension test Program 2.
Evaluate tapact of financial C
3 NRR NA NA f
Disincentives to Safety of Nuclear Power Plants IV.G Improve safety Rulemaking Procedures 1.
Develop Public Agenda D
SD NA NA 2.
Periodic and Systematic 0
[-
ELD NA NA Reevaluation of Existing Rules 3.
Improve Rulemaking Procedures D
[-
E!D NA NA
{
4.
Study Alternative for leproved D
[
EID NA NA Rulceakinu Process
. )
IA8tt I (continued)
Decislan Priority lead Implementation Esqlete Action Iten Group Group Office bperatin0 Reactors Plants Under Construction V.
MC Policy Organization, and Nasiegement 1.
NNC Policy Statement on Safety NA NA Come NA NA 2.
Study Elimination of Housafety NA NA Comm.
NA NA l
m Responsibilities I
e 3.
Strengthen Nole of ACNS NA NA Comm.
NA NA 4.
Study Need for Atkillional NA NA Comm.
NA NA Advisory Cuemittees S.
Improve Pahlic and Intervenor NA NA Comm.
NA NA Participation ist Hearing Process j
i 6.
Study Construction-Daring-NA NA Comm.
NA NA Adhalication Rules 7.
Study Need for INI-Related NA NA Comm.
NA NA le0lstation 8.
Study Need to Establists an NA NA Comm.
NA kA Independent Nuclear Safety Board 9.
Study Reform of ticensing Process NA NA Comm.
NA NA 10.
Study NNC Top Management Structure NA NA Comm.
NA NA and Process Reexamine Organizatiosi and NA NA Comm.
NA NA functions of NRC Offices IAllit I (continued)
Decision Priority lead Implementation C_oatilete Action Iten Group Grou;n Office Operall5g Reactors flants under Construct Gn
.f
- 12. Revise Delegations of Authority NA NA Comm.
NA NA to Staff 13.
Rules of Chairman, Commission, NA NA Comm.
NA NA and (00 14.
Delegate 1mergency Nesponse NA NA Comm.
NA NA i
f unctions to a Single Commissioner 15.
Achieve Slagle location - Long-tern NA NA Comm.
NA NA
- 16. Achieve Single location - Interim NA NA Comm.
NA NA
- 17. Reexamine Commission Note in NA NA Comm.
NA NA AJjiulicatlen
3 /11/ 5'0 IABif 8.2 (continued)
NAC Alf implementation Priority list and lille Points Priority ACRS Niot Dates Decision GRA, I*
- 1. A. 2.1 Immediate lipurade of NO and Sko keq.
210 I, II, Ill 5/I6/19 19fst-1985 (Parts)
II. D. 3 Position laulication 210 Il I/l/bH II.I. !
Addillonal Accident Monitoring Instrimentation
?!0 4/1/19, 5/16/79 1/1/80 8/13/19 11.1.2 Inadeilisate Core Cooling 210 4/7/79, 5/16/19 ft 1/1/ou asul 1/1/81 4
I. A. I. 3 5tilft Hanning 200 (II)
Il I/1/01
- 1. 8.1. 2 Evalisetion of Nint orgasitzation asul two 12/13/79 iL 3/1/01 Mastauemesit insis ovesiesits I.C.5 feeissack of Osserating taperiesme 200 1
12/13/19 ft 2/1/bu I.C.?
NS$$ Vendor Neview 200 II 8/14/19 ft&IP (Part) 11.B.4 Iraisiino 200 I
ft & IP 2/1/60 I I. E.1. 2 Auto initiation asul flow Isidicatiosi 200 lL fi/80 11.1.3.1 Natural Circulatiosi 200 5/16/19 IP I/1/80 II.E.4.2 Isulation ikpensialallity 206 8/14/79 IP I/1/u0 I
II.K.I It Bulletins 200 1
it 3/31/80 II.K.2 Commission orders od B&W Plants 200 t/1/81 11 - 1 1 I
i
IAunt B.2 (continued) i HNC Alf Priority list and fille laplementation Points Priority ACNS Niot Dates I
N I. A. I. !
$hift fet.hnical Advisor 190 8/13/19, 12/13/19 fl 1/l/80 1.D.2.2 Resident inspector at Operating Nedctors 190 il 10/80 f.D. I Design Neview 190 11 12/13/19 in HA I.L.!
Office for Analysis and fvaluation of 190 5/16/19 7/tio Operatiosi Data I.L.2 Office Programs 190 5/16/19 6/80 II.D. !
lest Nequirements 190 It 1/1/80 - 7/1/81 II.L. I. I tvaluation 190 I
IP I/l/81 II.E.4.1 Dedicated Penetrat losis 190 It 1/l/til ll.f.4.4 Purging 190 1
12/81 lit.A.3.1 NHC Mule 200 5/16/19 iP 2/80 (complete)
O Ill.D. I fransfer of Nesponsibilities to ffMA
.weRoo -
5/16/19 II 6/80 p
I.L. )
Data Analysis 1t10 5/16/J9 Onuuin9 I I. L. 2. 2 Nesedich 180 4/1, 4/10, 5/16 NA and 8/14/19 II.G.!
PONV, Glo<.k Valve, level Ind.
1110 5/16/19 18 t/1/80 lit.A.I.2 upgrade Sispport facilities 180 5/16/?9 ft & I/1/81 1/1/80 - 1/1/31 til.B.2
',lementatiosi of NHC asul f1HA Nesponsibilities 180 5/16/19 NA li. C 3
.S.s rem zaw c:rsoa
/t0 y
9M, n/ost19 PunSeccu B-12 l
t
IABit 8.2 (continued!
NRC All' Priority list and Iltle laplementation Points Priority ACNS Hl01 Dates Y
.C.1 1
Short-tere Accident Anelysis and 110 5/16, 8/14, and II&IP I/1/80 - 7/1/80 Peacedure Revision 12/13/79 i
11.8.6 Nisk Neduction for Operatind Reactors at 110 12/13/19 Selected sites -
e Sites with liiuh Population Density l
M 10/1/80 Ill.A.I.! Ilpurade tenergest(y Preparedness 170 5/16/19 it & 1/1/81 Phased I/l/80 -
1/1/85 e
I. A. I. 2 5til!L $upervisor Adeln. Dullas 160 Il 1/1/80 i
I. C. 2
$hitt and Relief lussiever 160 Implicitly fl I/1/80 l.C.3 Shift Supervisor Nesponsibilities 160 Il 1/l/60 I.C.4 Cositrol Noam Access 160 Il 1/1/80 11.8./
Contaisionesit Inerting 100 (II) 12/13/79 IP As ondered II.C.!
Initial Inteursted Reliability Evaluation Jefr /S4 (1) 8/14, 12/13/19 Plant specific Program (IRIP) 1 1. 11. 1 IMI-2 Safety 14,ts-/ $ -
NA f l. il. 2 Obtaise Inforenallon 160 NA I f il 3
[valuallun and feetNaack 160 5/16/79 NA 11.8.3 Postas cident Sangiling 150 12/13/19 IP & 1/1/81 1/1/M - 1/l/M
{
IV.A.I Seek legislative Atathority 150 NA 8-13
\\
l l
i l
IA81[ 8.2 (continued)
NRC Alf laplemefilat ion Priority 1ist anal litle Points Priority ACR5 Hlot Dates l. A. 3.1 Revise Scope and Crlieria for Exams 140 1, 111
- 1 4/1/80 (Parts)
- 1. C. 8 Pilot Program - NIOl 140 til implicitly IP l
1.E.8 ihman Error Analysis 140 5/16/79 NA II.B.!
Primary System Vents 140 4///79 IP & I/l/81 1/1/80 & 1/1/81 1 1. 11. 2 Plant Shielding 140 12/13/19 IP & I/1/81 1/1/80 & 1/1/81
-:!. C. 2
', ;;; '..:: r _; ; n..
- ;^.
- ,/;4, ;;
- /;;/;';
ii..a,ym a;e-II.L.5 Deslun Sensitivity of B&W Reactors 140 4/1/85 lit.A.3.3 Communications 140 111 5/16/19 f t.
2/1/80 III.D.I.! Source Outside Contaisiment 140 IP I/1/80 l
I.G.1 Irminling Respiliements 130
, Il 12/11/19 11 & IP t1.8.5 Researtta 130 12/13/19 NA II.B.8 kulemaking on Degraded Core Accidents 120 12/17/79 IP HA
.E. D..*L RcSt A nte.it 13 0 AA
~
I I I.D. 3. 4 Control Room liabitability 120 II IP & 3/1/81 5/1/80 & 3/1/81
~
1.D.6 lethnolouy Iransfer Coasterence 110 Complete i
B-14
o i
l IABIL B.2 (continw.:d)
NGC Alf Implementation Priority i nst aiul litle Points Priority ACNS NIOL Dates
' L L'. 2
": _ _ _ :d
.;0 e
I I..l. 2. 2 Imiepesulent &45uresnent 110 NA I I. J. 2.1 Neurtent Program 100 NA 111.18.3.3 Inplant Honitoring (ITen s}
100 II Il I/1/80 IV. f. I increased IL Strutiny of Power Ascension 100 II until I
lest Progr completion j
l 1 1. 11. 4 Soclueconomic Ef fect ami Property Values 90 18A
{
lil D.2.4 Of f site Dose Measurements (Meg 3) 90 Ill IP NA t
I B-15
I IABit 8.2 (continued) t NNC Ali implementatlose Priunity list and lille Points Priority ACNS NIot Dates l
Decisiuse Groege B N.L.4 I
l'ourdination of Progrees 200 11 5/16/19 6/80 f. A. 2. 5 Plant Drills 190 III 5/81 1.D.1 Deslun Neview 190 Il 12/13/19 1/15/80 1.D.2 Safety Parameter Console 180 II 12/13/19 6/1/81 i
I.D.4 Deslun Standarna 180 12/13/19 NA II.L.3.2 System Hellatellity 180 12/11/19 8/81 II. K. 3 Iinal Necommendations of 810 lasit force 180 See letale C. 3 See table C 3 1.A.4.2 tonu-tesa Simulator tipgrades llo II t/l/82 11.1.2.1 Neliante osi ICCS 110 11 t/1/82 II.f.3 Neuestatory Guide 1.91 110 11 8/14/19 6/82 1.E.1 loscion Soarces 160 5/I6/19 NA l
l.A.4.1 inillal Simulator Improvement MM 11 1/1/81
- 8. 2'. 2 ij_ t : n t i&_ !L.. 'i_. '..;
lic
!?/!2/?e
!?!!A!
II.t.4.3 luteurity Cl.eck
!$a 131 6/1/81 I
Ill.A.3.2 Improve Operat.sna Centers 140 5/16/19 B-16
I I
'l 1.
I I
l IA81[ 8.2 (continued) e NRC Alt laplema*nt al lost i
Priority list seul litle Points Priority ACRS N101 Dates l
I.A.2.2 f raining 4:ut Qisatificatiosis of Ottier Personnel 130 II 5/81
- 1. A. 2. 3 NkR Atulit trainisig 130 HA J 1-9 111.11.3.1 Radiation Protection Plasts 130 III 9/til I.C.6 Verification of Operating Activilles 120 1/1/81 I.I.I impasused Quality Assiarance list 120 8/14, 12/17/79 NA III.D.I.3 Vent System asul Nadiciodine Adsortaer Criteria 110 til Late l*Jul ll.C.4 Neliability ind neering 100 1
10/19, 12/13/79 i
Beyond 1982 Inplasit Nonitorisig bh I I l. D. 3. 3 100 1I 6/1/62 l
i 1.A.2.4 NNM Participate in If Inspector Training 90 NA l
'fI.G.2 Scope of lest Program
.ekr/VO NA
!!!.9.2.'
'" 4 "
9-__"
2.
- E ee t/3/"!
Ill.D.2.5 Dose Celtistation Manisal 80 lit 6/1/01 I i I. D.1. 2 RadinactIwe Gas Nassagenesit 70 10/9/19 NA i
i III.D.2.1 triluent Honitoring Jer4D III 12/1/81 III.D.2.2 Radiolodine C-14 Tritins Dose Analysis 50 IIA 8-11
1
) !
.I l
IAnt[ B.2 (continued)
I NitC Alf laplementation Priority list asul litle Points Priority ACRS NIOL Dates M iston Grun I
gC f
- '.2.:
- _ mut,..a _:=_.2:= m.
2:e v:u s see: :et M
i
_.2 i
u.. i _ c..
,,m
<,u,m z,m,m.
l.A.2.6 long-ters tapurade 190 2/1/82 I.L.6 Reporting Neguirements 190 I
5/16/19 HA
'e
.K.3.3. 8 DRGMozaro*4 sd4 S,AFF *q f$e (BD AA
~
~
- 1. 8.1.1 Organisat ion asul H.anagement long-tern 170 III 12/13/19 6/82 leprovement>
l.C.9 lom,1-tere Program Plan 110 Ill laplicit.ly NA
- 1. 8.1. 3 loss of Safety f unction 160 Ill 8/13/19 NA 1.D.h Hesearch 160 12/13/19 NA I.D 3 Sysreens Srnros Mod rad odg
/SD f
skh3 /71 NA
~
II.L.2.3 Uncertainties in Perturmance Predictions the II 4///79, 8/14/19 1/1/80 II.J.4 Newise Detitlency Reporiing Requirement >
150 HA 54 A. ?
A = h _...; L; " ' z' h; L'.
flV.f.4 Assess Currently Operating lleactors 19e/SO 10/11/19 NA i
I 8-18
a I
IA8it B.2 (continued) i
(
l NNC All laglementaliaan Priority List and title Paints Priority ACNS N101 Dates s
li.C.2 Contisusation of INIP W '50 l
8/14. 12/13/79 1983 til.A.3.3 Communicationis Bacitup 140 (Ill) 5/16/19 NA I. A. 2.1 Accreditation of Irdining Institutions 130 NA I.A.3.4 licensing of Additional operations Personnel 130 NA ll.J.3.!
'h ;;..':2i::n 2nd E1:SHn;;
- 20 (I&I; "t
II.A.2 Site ivaluatiosi 120 12/14/19 MA IV.D()# Assess Iraining Needs 120 h/16. 12/13/79 NA III.A.3.6 Interaction with Other Agencies 110 5/16/19 NA fl.J.3.2 Regulatosy C.uide 100 NA III.A.1.3 Ihysold Diocking Agent 100 11 as. A.b.I Rate Ch A ng e.
5//bMt 3/1/81 oao III.A.3.4 Nuclear Data 1. Ink 100 4 /a n D HA Ill.D.2.3 liquid Pall.way Nadiological Control 100 HA ZY.E.3 Resolet. Gennec.rssess 9 EwenAmHQ soo NA i.C lxtend lessons learned A /30 NA LET.D.3.'s OGCsors bass Atensateneans Qven o) to RC AIA Ill.C.I Info mation Availability 90 12/110 8-19
e l
l l
l IA8t[ B.2 (continued)
NNC Alt laple ntation Priority list asul lille Points Priority ACNS N101 Dates I.
IV.E.2 Plan tur Nesolving lasues at CP Stage 90 NA lit.C.2 Agency Policy asul training 80 NA
- 1. A 3. 2 NNC Operator Iicensing Reforms 70 NA III.D.I.4 Na& aste System Design features 10 NA IV.I.2 Lvalisate letsact of finastcial Disincentives 70 NA to Safety of Nuclear Power.?lants ll.A.!
Siting Policy Rulemaking 60 12/j7/19 NA II.f.4 Control anal Protection Action 60 NA Ill.A.2.2 Gulilance and Criteria 60
$/16/19 NA 5
8-20
IA8tf b.2 (continued)
INIC All laplementation Priority list and litle Points Priority ACR$
NI0t D. ale s I
gIJ M Iston Gron
- 1. A.1. 4 Iam.8-lerm L4 grading
- 1. A. 3. 3 Operator titness
- 1. A. 3. b NHC/lW)(/INPO Statement of Understanding 1.A.4.3 MC l raining Simulator 1.A.4.4 MC Engineering Computer 1.8.2.1 Revise IE Inspection Program
- 1. 8. 2. 3 Regional Evaluations 1.8.2.4 overview of licentee Performance 1.E.S Nuclear Plant Nellalallity Data System S/16/19 t
i I.f.2 Detailed Criteria 8/14, 12/17/73 11.1.1.3 tip< late $NP and lasue Segulatory Guide I I. E. 3. 3 Alternate Conceris Nescarch 4/18/JS II.f.3.4 Negulatory Guide II.L.6 In Situ lestiql of Valves II.J.l.1 Inspection Priority II.J.I.2 Hudify Existind Program E i
e l
l I A8tl B.2 (s'ontinued)
NHC Alt Priority 1.lst osal linle implementation.
Points Priority ACNS N101 Dates II.J.l.3 tapasid Negulatary Control II.J.l.4 Nesident luspectors ai N555 Vendors and Afs II.J.2.3 Nesideset inspectors III.A.3.h f reinisag, Drills, asul f ests 5/16/79 Ill.D.2.6 Indepesulent Hedsuremesits l i t. D. 3. 2 lleditti Playsics leprovesisesits M. D.3.3.1NPtsar RAdanses nonsisto4QTC%\\*l* &
~
~
~
Ill.D.3.5 Nadiatiosi W.stSer Exposure Data Base IV.A.2 Nevise inforcement Policy IV.8 Nevise Practices for Providind Instructions 5/16, 12/13/J'3 and Informatiosi to Lia:esisees IV. t.1 Expostal Nesearcia osi Quasitification of 12/13/J9 54iety Decislost-Making IV.G.I Develop Pidslic Auesuld 12/13/J9 IV.G.2 Periodic and Systematic Neevalasation 12/13/19 of [xisting Nules IV.G.3 Improve Mulemaking Procedures 12/17/JS IV.G.4 Stuity Alternative for improved 12/13/19 kulemaking Process 8
8-22
e a
l IABit 8.2 (tuntinued)
HNC All Implementdtion Priority Iist anal lille Pulnts Priority ACNS N101 ilates V.
NHC Policy. Orgasil:4Llon, and Handgement 1.
NNC Pulity Stelement on Safety 2.
Sluily Elimination of Nonsafety Nesponsitellities 3.
Strengthen Nole of ACNS t/15/80 4.
Study Need for Additional Advisory Committees 5.
Improve Putilic and Intervenor Participation in licering Process 6.
Stasdy Construction-During-Adjudication Nules 1.
Study Need for lHi-Neleted legislation 8.
Stanly Need to Estatslisle an Independent Nuclear Safety lluesd 9.
Study Nelorm of Licensing Process
- 10. Stauly NHC lop H.snagement Structiere elMI Process II. Neen.neine organizat lose asial f usictions of NNC Offices
- 12. Nevise helegatiosas of Aesthority to Staff I/15/80
- 13. Noles of Chaleman. Commission, asul 1110 B-21
--.