ML19291C341
| ML19291C341 | |
| Person / Time | |
|---|---|
| Issue date: | 01/05/1980 |
| From: | Gossick L NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) |
| To: | Ahearne J, Gilinsky V, Kennedy R NRC COMMISSION (OCM) |
| Shared Package | |
| ML19260C771 | List: |
| References | |
| REF-10CFR9.7 NUDOCS 8001240251 | |
| Download: ML19291C341 (15) | |
Text
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. UNITED STATES
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NUCLEAR REGULATORY COMMISSION WASHINGTO N. D. C. 20555 s~,
January 5, 1980 MEMORANDUM FOR:
Chairman Ahearne Commissioner Gilinsky Commissioner Kennedy Commissioner Hendrie s Commissioner Bradford FROM:
Lee V. Gossick Executive Director for Operations
SUBJECT:
TMI ACTION PLAN -- PREREQUISITES FOR RESUMPTION OF LICENSING In response to the Secretary's memorandum of December 28 and the guidance of the Commission at the meeting on December 21, the TMI Action Plan Steering Group has developed a proposed definition of the actions that would be required to be taken before reactor licensing could be resumed.
This memorandum provides that proposed definition and reports on an important initial step in that effort -- the identification of the specific licensing requirements for the near-term operating license applications.
This memorandum and its attached list of near-term OL requirements were presented to and discussed with the Directors of NRR, IE, RES, and SD on January 4, and they have concurred.
The Executive Legal Director has no legal objections.
The licencing pause has been described previously, but not in the detail now needed.
It was broadly defined by the Commission in its November 9,1979 letter to Dr. Press in the Executive Office of the President.
In providing its analysis and views of the recommendations of the President's Commission, the NRC said in that letter, in part, "NRC has decided that new plants will not be licensed until the required criteria have been developed.
This approach assures that the NRC staff
,can give the necessary attention to implementation of the changes on operating plants.
NRC plans to proceed systematically in the following manner:
(1) review and correlate the recommendations of the President's Commission, those of internal lessons learned groups, those of the Advisory Committee on Reactor Safeguards, the findings of NRC Special Inquiry (when available), the findings of ongoing Congressional investigations (when available), and other inputs; (2) transform the reccmmendations in each subject area into a statement of goals (i.e., define the new or improved safety objectives to be accomplished in each area); (3) develop task action plans to transform the goals into organizational or procedural changes as they apply td NRC, 1795 074' 8 0 0124 0 cQ8 /
2 or into regulatory requirements as they apply to licensees; (4) initiate implementation of the new regulatory requirements on operating plants; and (5) initiate implementation of the new regulatory requirements on plants under construction."
The " action plans" called for in the November 9 letter have now come to be known ac the draft TMI Action Plan (NUREG-0660).
The desired format and content of the action plan in the context of the Commission's licensing pause were described in Commissioner Hendrie's memorandum of November 16, as "... essentially a matrix formed by listing the points in the November 9th paper, plus any other actions we think necessary, along one axis and the various classes of cases along the other axis." Table 1 of NUREG-0660 is the matrix of licensing and other actions developed by the staff in response to this guidance from the Commission.
The Action Plan contains what the staff presently believes constitutes the complete set of additional requirements and programs for NRC, for operating reactors, for operating license applicants, for reactors under construction, and for construction permit applicants.
In its totality the Action Plan will
' identify all actions considered to be necessary as a resu,lt of the accident at TMI.
Some will be requireo to be finished before the resumption of licensing.
Others may be required to be undertaken before resumption of licensing.
Still other, longer term actions t!.ay not be undertaken until well after licensing has been resumed.
Adoption of the Plan describing all of these actions by the NRC would constitute "getting its house in order."
We do not believe that the isolated approval of any particular subset of action items -- for example, the licensing requirements that are applicable to near-term operating licenses --
is a sufficient condition to justify the resumption of licensing.
We believ'e that Commission consideration and approval of the Action Plan in its entirety is a necessary action.
Approval of the plan would mean Commission endorsement that the total program defined in the Plan constitutes the sufficient measures to be undertaken to permit resumption of licensing.
This is important and necessary guidance for licensees, license applicants, the staff, and the hearing boards.
In this connection, the form of the Commission approval of the Plan is an inportant subject that needs further consideration.
Some preliminary thoughts by El.D on this subject are attached.
There are several deficiancies in the present draft that render it inadequate for approval at this time.
First, it is incomplete.
Recognizing that the NRC Special Inquiry report may contain additional requirements not presently identi-fied in the draft Action Plan and that there is staff review of the plan still ongoing, we are not recommending approval of the existing draft Action Plan.
Second, the plan as presently drafted is a mixture of policy objectives, program descriptions, and specific licensing criteria.
Some of this material is at a.
level of detail that is too specific for Commission approval (i.e., it is at a ' -
level of detail more appropriate for staff action and interpretation).
We anticipate furnishing to the Commission another draft of the plan within about a month of issuance of the NRC Special Inquiry Report.
It is our intent that 1795 075
3 it will correct these sorts of deficiencies.
In addition, at that time, we expect to furnish an analysis of the resource and programmatic implications of the Plan, including the identification of necessary reprogramming, future budget requirements, and effect on present programs.
We recognize that there are many action items in the present draft of the Plan that require clearer description, fuller explanation of need, development of detailed criteria, consideration of alternative approaches, and the like, before final decisions on them could be expected. We plan, for the next draft, to identify each of those actions and a proposed schedule and method for obtaining Commission approval.
We propose that those approvals can be granted external to or subsequent to Commissien approval of the Action Plan itself.
Approval of the Plan will simply mean, in these areas, that the Commissior. agrees in principal with the indicated action but intends to treat them separately and on specific schedules and according to methods or procedures outlined in the Plan.
The balance of the action items in the Plan will be sufficiently well-described that Commission approval of the o'erall Plan will constitute specific approval of those items.
Examples of the sort of detailed requirements that can be decided by Commission approval of the overall Plan are the specific near-term operating license requirements described below.
There are several subsets of requirements that could be extracted from the Plan for separate consideration and decision by the Commission.
Consistent with our understanding of the Commission's request at the December 21 meeting, we have extracted these actions that are uniquely applicable to near-term operating licenses. We have defined "near-term operating licenses" as those that would be issued before July 1980.
A longer time period would add, subtract, or modify requirements.
It is necessary to establish such a temporal definition because the subset of actions required to be accomplished by applicants before obtaining an OL differs depending on that definition.
The set of requirements for near-term OL applicants according to a July 1980 definition is attached as.
A similar listing of requirements could be extracted for other classes of activities, such as the set of short-term lessons learned already applied to operating reactors, the additional requirements for operating reactors beyond the short-term lessons learned, the actions required to be taken by holders of construction permits, and the internal actions required to be taken by the NRC that would define " putting our house in order."
It is our intent that an improved Table 1 in the next draft of NUREG-0660 will more clearly identify such subgroupings of all the actions contained in the Plan.
Besides the information discussed above, the Steering Group will be prepared at its meeting with the Commission on January 9 to discuss the status of ongoing work to revise the action plan generally, to identify the method being used to w
identify resource reprogramming candidates in the current NRC operating plan 1795 076
4 and budget submissions, and to propose a method for obtaining feedback and ideas from reactor operators and others involved in the implementation of the TMI-related requirements.
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ee V. Gossick Executive Director for Operations
Enclosures:
1.
Near-Term Operating License Requirements 2.
ELD Comments on Form of Commission Approval cc:
Office Directors Steering Group Members Task Managers o
O 1795.077
TMI ACTION PLAN NEAR-TERM OPERATING LICENSE REQUIREMENTS Requirement Already Approved When Acolicable*
I. A.1.1 Shift Technical Advisor Provide technical advisors with engineering expertise on each shift.
Yes FL I.A.1.2 Shift Suoervisor Duties Minimize administrative duties.
Yes FL I.A.l.3 Shift Mannina (1) SRO and RO in control room.
No FL (2) Administrat,ive aide to shift supervisor on each shift.
No FL (3) Restrictions on use of overtime.
No FL I.B.1.1 Organization and Management Criteria Interoffice'NRC review of licensee management to determine organizational and managerial capabilities, pending development of criteria.
No FL "FL = before fuel load FP = before full power 1795 078 1
Requirement Already Acoroved When Acolicable I.B.3.1 Safety Engineerina Groua Licensee provide onsite safety engineering group to provide supplemental engineering review and support.
Interoffice NRC review of the adequacy of this group, pending development of formal criteria.
No FL I.B.3.4 Resident Inspector NRC resident inspector at each site for new OL.
No FL I. C.1.1 Analysis and Procedure Modifications (1) Phase I - small break LOCA's.
Yes FL (2) Phase II - inadequate core cooling.
Yes FL I. C. l. 2 Shift Relief and Turnover Procedures Plant procedures for shift and relief turnover.
Yes FL I.C.1.3 Shift Personnel Resoonsibilities Plant procedures specifying responsibilities of shift personnel for safe operation of the plant.
Yes FL
'3.,
I795 079 2
Recuirement Alreadv Acoroved When Acolicable I.C.1.4 Control Room Accesc Plant procedures for limiting access to the control room.
Yes FL I.C.2 Vendor Review of Procedures NSSS vendor review of licensee emergency procedures, low power test procedures, and power ascension procedures.
No FP I.C.3 Pilot Program for Review of Selected Emeroency Procedures NRC conduct in-depth review of development and use of selected emergency procedures on NTOL plants.
No FP I.E.1 Licensee Operating Exoerience Evaluation Capability Onsite and offsite capability for evaluation of operating ~ experiences at nuclear power plants.
Partial FL I.E.2 Licensee Dissemination of Ooerating Experiences q
Procedures that assure feedback of operating experiences to operators and other personnel.
No FL 1795 080 3
Reauirement Already Acoroved When Acolicable I.G Trainino Durino Low Power Testing Conduct " hands on" training in selected plant evolutions and off-normal events for shift personnel.
No FP II.B.1 Degraded Core - Primary System Vent Provide design of remotely operable high point reactor coolant system vents.
Yes FP II.B.2 Degraded Core - Shielding Provide design of additional shielding required to provide access to vital areas and protect safety equipment.
Yes FP II.B.3 Degraded Core - Samoling Provide interim procedures and final system design for sampling and analyzing reactor coolant and containment atmosphere.
Yes FP II.B.4 Degraded Core - Training (1) Establish training program for all operating personnel in the mitigation of severe core damage using existing equipment.
No FL (2) Complete initial training.
No FP 1795 081.
4
Reauirement Already Aporoved When Acolicable II.B.8 Degraded Core - Rulemaking Issue notice of intent to conduct rulemaking on requirements for design features for accidents involving severely damaged cores.
No FP II.B.9 Interim Hydrogen Control Recuirements for Small Containments Under development.
No FP II.C.1.1 Mini-IREP No FP II.C.1.8 Reliability Assurance Establish a reliability assurance program for engineered safety features systems.
No FP II.D.1.1 Relief and Safety Valve Test Commit to performance testing of RCS relief and safety valves under the full range of nornal and accident conditions by July 1981.
Yes FL II.D.1.5 Relief and Safety Valve Position Install direct indication of relief and safety
.g w valve position.
Yes FL 1795 082 5
Reouirement Already Aporoved When Acolicable II.E.1 Auxiliary Feedwater System Reliability Perform simplified reliability analysis of A7W system and modify as necessary.
No FP II.E.1.3 Auxiliary Feedwater Initiation Install safety grada automatic start of AFW and safety grade flow indicators.
Yes FP II.E.3 Emercency Power for Decay Heat Removal Install capability to supply some pressurizer heaters and controls from emergency power supply and implement necessary training and procedures.
Yes FP II.E.4.1 Containment Penetrations Provide design of redundant dedicated containment penetrations for external hydrogen recombiner, if applicable.
Yes FL II.E.4.3 Containment Isolation Install diverse containment isolation signal.
Yes FP 795.08Y -
II.E.4.5 Containment Purce Restrict containment purge operation and demonstrate purge valve operability.
Yes FP G
Reouirement Already Anoroved When Acolicable II.F.2 Inadeouate Core Coolino Instruments (1) Install subcooling meter.
Yes FL (2) Submit design of vessel level indicator.
Yes FL II.G Emergency Power for Pressurizer Equipment Modify power supplies for the pressurizer relief valves, block valves, and level indicators to be from emergency power sources.
Yes FL III.A.1.1 Role of NRC More detailed definition of role of URC in emergencies than presently contained in Action Plan No FP III.A.1.5 Communications Install two direct dedicated telephone lines between plant and NRC.
Yes FL III.A.2.1 Technical Succort Center Establish initial onsite TSC ano provide plans, procedures, staffing, communications, and radiation monitoring equipment.
(Upgrade on s N same schedule as present OR's.)
Yes FL 1795 084 7
Reouirement Already Accroved When Aeolicable III.A.2.2 Onsite Operational succort Center Establish an OCS as described in the 10/30/79 letter to licensees.
(Upgrade on same schedule as present OR's.)
Yes FL III.A.2.3 Near-Site Emercency Operations Center Establish an EOC as a base for coordinating onsite and offsite activities and interface with State, local, and Federal agencies.
(Upgrade on same schedule as present OR's.)
Yes FL III.A.3 Uograde Licensee Emergency Precaredness Upgrade emergency plans in accordance with Regulatory Guide 1.101 and NUREG-0610.
Yes FL III.B.3.2 FEMA-NRC Concurrence in State and Local RERP Concurrence must be obtained.
Yes FL III.D.1.3.a Area Radiation Monitors (Partial)
Provide instrumentation to determine in plant
,v s.
airborne radiciodine concentrations.
Yes FL 1795 085; Attachment 1 8
Reouirement Already Aporoved When Acolicable III.D.2.1 Control Room Habitability Confirm compliance with existing regulatory requirements or establish schedule for necessary modifications to achieve compliance.
No FP III.D.2.2.b Evaluation of Secondary Side Hazards Evaluate secondary side leakage and radiological hazards which could result from major accident, and make modifications to reduce hazards.
Yes FP III.D.2.2.c Improve Auxiliary Buildino Identify improvements to control radioactive leakage from auxiliary buildings, including requirements for building exhaust filtration where it doesn't already exist, and provide schedule for modifications.
No FP III.E.1.1 Imoroved Vent Gas Systems Review vent gas and leak detection systems against new design criteria and provide schedule for modifications.
No FP
.s 1795 086 9
Recuirement Already Aoproved When Acolicable III.E.1.2.a Surveillance Testing (Filtration Systems) (Partial)
Implement surveillance testing program for non-ESF filtration systems.
No FP III.E.2.1.b NRC Monitoring NRC establish TLD surveillance network around site.
Yes FL
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1795 087 10
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