ML19224C098
| ML19224C098 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 04/20/1979 |
| From: | Jennifer Davis NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| To: | Gilinski V, Hendrie J, Kennedy R NRC COMMISSION (OCM) |
| Shared Package | |
| ML19224C097 | List: |
| References | |
| NUDOCS 7906290003 | |
| Download: ML19224C098 (8) | |
Text
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s w-5 April 20,1979 F.E!DPA"DUM FOR:
Chairman Hendrie Commissioner Gilinsky Commissioner Kennedy Commissioner Bradford Comnissioner Ahearne THRU:
Lee V. Gossick ISTI""'"Y""
Executive Director for Operations FROM:
John G. Davis, Acting Director Office of Inspection and Enforcement
SUBJECT:
INVESTIGATION OF THREE MILE ISLAND ACCIDENT SY THE OFFICE OF INSPECTION AND ENFORCEMENT This is to confirm our discussion of April 13, 1979, concerning the T.hree Mile Island accident investigation underway by the Office of Inspection and Enforcement (IE).
The investigation performed by IE has two basic goals:
1.
To establish, in a comprehensive manner, the facts concerning the Three Mile Island accident.
The parameters of this effort are further described in Attachment A.
2.
To evaluate the performance of the licensee in association with the Three Mile Island accident as a basis for corrective action or enforcement action as appropriate.
The Offic:: of In:pdction and Enforce. tent investigacion does not include, under our current plans, the following:
1.
Any evaluation of the actions of the NRC or any of its organiza-tional components during the course of this accident or recovery period.
2.
Any evaluation of the actions of other agencie; during the course of the accident, or during the recovery period of the accident.
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APR 2 01979
- The Connissione
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3.- Any revie and evaluation of the NRC regulatory process as it relates to the Three title Island accident for " lessons l e a rned."
IE is not callecting information concerning nor d
eval uating:.
Legislative authority of the !!RC I'ules and reguiations of the frdC 1 -
j Safety research 3
Licensing process l
Inspection and enforcement process I' -
The Office of Inspection and Enforcement will expand its investigation l
i as directed by the Co..nission or the EDO.
In the absence of such direction, IE is proceeding with its investigation as outlined in this tmorandum.
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John G. Davis Acting Director Office of Inspection and Enforcement
Enclosure:
IE/TMI Conceptual Outline DISTRIBUTION:
LVGossick, ED0 DThompson, IE EXCornell, EDO IE Division Directors TRehm, EDO Regional Directors HRDenton, NRR VStello, fiRR ECase, URR HVShapar, ELD JJCummings, OIA SECY EDO Reading JGDavis, IE i'Cl'osel ey, IE FLIngram, PA IE ELD EDO Davisti Shapar Gossick 4/20/79 4/ /79 4/
/79 258 117
OFFICE OF I::SPECTIO:i AT?D EliFORCEMEliT t
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ThREE MITE ISLAND ACCIDE!!T I!;VESTIGATIO; Conceptual Outiiae 1.
The IE investigation of the Three Mile Island accident is directed toward:
a.
Within the time period of the investigation, establishing the facts concerning the imediate causes of the accident and the actions of the plant and the licensee staff during the course of the accident.
b.
Within the time period of the investigation, establishing the facts concerning the actions cf the licensee, the tiRC, other Federal agencies, and appropriate state agencies.
Evaluating the perfomance of the licensee during and in c.
response to the Three Mile Island accident as a basis for corrective action or enforcement action as appropriate.
2.
The investigation consists of two parts conducted in parallel:
Operational - The inplant, reactor operations situation.
a.
This will cover the time period from the closing of the auxiliary Feedwater System valves (or other earlier immediate cause of the accident) to the restart of reactor coolant pump 1 A (about 3:00 p.m., March 28, 1979).
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Radiological - The inplant and environmental radiological conditions.
This will cover the time period from the beginning of the accident until about midnight on March 31, 1979.
1 The Office of 'Inspec. tion and Enforcement will. develop factual in' formation concerning the condition of the plant and the environment and the performance of the licensee for the time periods subsequent to those described in Item 2, above.
However, this information will not be included in the IE Three Mile Island Accident Investigation.
(?!ote that this does not include development of information concerning !;RC activities.
The information will include the licensee's reaction and response to i?RC activities but will nct develop, for example, how an !?RC position or recommendation was formulated.)
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The investigation will include:
Sequence of Events.
a.
(1) Operational Identify the sequence of events in relation to facility Determine licensee actions or lack of actions operation.related'to operation of the facility within licensed Determine the parameters, constraints and limits.
participation of licensee supervision, management and engineering support.
Determine causes of the event.
(2) Radiological Identify the sequence of events in relation to licensee activities in radiation control on site and off site.
Determine licensee actions or lack of actions related to controlling and monitoring on site exposures, protection of workers, and control and monitoring of off site releases.
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b.
Intnediate Cause of Accident (1) Equipment
- and maintenance history of important Trace the performance equipment which malfunctioned at the beginning or during the early phases of the incident.
Define the s_ignals or other intelligence provided to operators concerning serviceability and availability of equipment.
Identi fy the serviceability of equipment required for operation.
(2) Procedures, Determine the requirements contained in surveillance and maintenaace procedures and the appropriateness of procedures.
Determine appro-Identify failures to follow procedures.
priateness of communications between plant groups on plant Determine v;hether emergency operating and equipment status.
procedures were appropriate and were followed.
(3) Staff Performance L -s and other licensee Describe the performance of the ope.
Review t-aining of operators personnel during the accident.
particularly training concerning response to off-normal limits.
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Licensee Management of Accident Describe the response of the licensee from the standpoint of canagement and supervision of the accident.
Identify the engineering and radiciogical support reouested and received and its source.
Catermine the licensee's. reaction to and analysis of the accident as it unfolded with particular emphasis on engineering analysis of alternative modes of accident recovery.
d.
Emergency Plan Ac'_ivation Examine the licensee's emergency plan implementation to include preplanning and tests.
Develop a detailed chronology of the implementation of the emergency plan with particular emphasis on timeliness of notification.
5.
This investigation is being managed by the NRC Region I Office.
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ATTACHMENT 3 A number of professional staff personnel have been detailed to the Special Inquiry Group investigating the accident at the Three Mile Island Nuclear These individuals were detailed only after agreements were reached Plant.
with their Office Directors, and each individual had evidenced a willingness to participate in the inquiry and had no reservations concerning the nature of the detail.
The total number of professional personnel presently detailed to the Special With one exception participation will be on a full-time Inquiry Group is 47.
The exception is J. Fitzgerald of OGC who will devote about one-third basis.
time to the Group.
The assignments of the personnel within the Group are provided in Attachment 1. provides a summary of the manpoaer contributions from various offices.
We believe that the present detailed staff is sufficient for our purposes; however, unexpected developments in the coming months could impose a need for additional individuals with special talents for specific tasks. We will regtest such additional personnel if and when the need develops.
As specific tasks within the Group are completed we expect to terminate the detail of individual participants and return them to their offices for reassignment.
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STAFF ASSIG:!MENTS TO NRC TMI INQUIRY E. Kevin Cornell, ED0 - Interim Director
.C.
O. Miller, Consul tant Bernard Doyle, Consul tant Richard DeYoung, NRR' - Interim Deputy Director Patricia Norry, ADM - Administrative Coordinator Robert Budnitz, RES - Technical Coordinator James Fitzgerald, OGC - Counsel (About one-third time)
TASK TASK LEADER SUPPORT STAFF 1.
Pre-accident Background William Parler, ELD Harold Orns tein, EDO David Evans, ELD Thomas Cox, NRR Frederick Hebdon, NRR Wayne Lanning, RES 2.
Description of Accident William Johnston, RES Mark Cunningham, RES Gordon Chipman, NRR Sequence - Reactor Marion Picklesimer, RES Plant Performance Evangelos Marinos, SD Donald Quick, IE 3.
Description of Accident Frank Miraglia, NRR Shlomo Yaniv, RES Oliver Lynch, flRR Sequcoce-Radioactive Re-Ronald Bellamy, NRR leas s and Exposures Louis Battist, SD.
4.
Emer 2ncy Response Ronald Haynes, IE Dennis Allison, NRR Hartmut Schierling, NRR of U ility Harry North, IE 5.
Emergency Response of Robert Bernero, SD Ralph Page, NMSS George Rivenbark, SD NRC Joseph Scinto, ELD 6.
Emergency Response of MalcolmErnst,ilRR tarry Crocker, NRR Robert Schamberger, RES Federal and State Donovan Smith, SD Agencies ALL 7.
Lessons and Implications 8.
Information Support Patricia Norry, ADM Richard Hartfield, MPA Larry Vardenberg, MPA Myrna Steele, ADM Additional Mecaer, ADM Additional M2rber, ADM Additional Marner, ADM 9.
Investiga tive James Cutmings, OIA Frederick Herr, OIA Peter Sicilia, 01 A In te rviews Milliam Foster, OI A Paul Murray, OIA 58 122 vid Gamble, 01A
f Secretarial Staf f Ann Haikalis Patricia LaGrange Susan Cavanaugh Kathy Motley Diane Passero Kathy Ruifrock Eileen Tel ford Ann Bowden Mary Potter s
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