ML20012D019
| ML20012D019 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 03/19/1990 |
| From: | Taylor J NRC OFFICE OF THE EXECUTIVE DIRECTOR FOR OPERATIONS (EDO) |
| To: | |
| References | |
| TASK-PII, TASK-SE SECY-90-101, NUDOCS 9003260309 | |
| Download: ML20012D019 (3) | |
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March 19, 1990 SECY-90-101 The Commis(sionersInformation)
For:
From:
James H. Taylor Executive Director for Operations I
Subject:
INDEPENDENT SPENT FUEL STORAGE INSTALLATION (ISFSI)
TRAINING REQti1REMENTS EVALUATION
Purpose:
To respond to the Commission's question in the Staff Requirements Memorandum of January 12,(1990, about the Institute of Nuclear Power O INP0) or Nuclear Regulatory Comission (NRC) perations inspector evaluation of details of ISFSI training program process and procedures and to informtheCommissionaboutthegenericexpectatIonsor requirements for training professionals responsible for
" operation" of ISFSis.
Discussion:
Although INPO membership is voluntary for nuclear utilities, all nuclear utilities are members. Consequently, training programs at nuclear power plant sites are evaluated both by INPO evaluation and accreditation renewal teams and by NRC inspectors. Where an ISFSI is located at a commercial power reactor site, such as Duke Power Company's Oconee Nuclear Station, ISFSI training is incorporated in the reactor training program. Thus, ISFSI training also comes under evaluation both by INP0 and NRC inspectors.
(The NRC Senior Resident inspector has indicated NRC onsite staff will be attending and auditing) training to be given the new Oconee ISFSI operations staff.
Such training is expected to follow NRC guidance provided in the " Commission Policy Statement on Training and Qualification of Nuclear Power Plant Personnel" (50 FR 11147, March 20, 1985).
The generic expectations or reovirements for such training include five elements that NRC. considers essential to accept-able training programs. These elements, as endorsed in the Commission's policy statement, are:
(1)Systematicanalysis of the jobs to be performed; (2) Learning objectives derived from the analysis which describe desired performance after NOTE:
TO BE MADE PUBLICLY AVAILABLE IN 10 WORKING DAYS FROM TIIE DATE OF TilIS PAPER P
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training;(3)Trainingdesignandimplementationbasedon the learning objectives; (4) Evaluation of trainee mastery of the objectives during training; and (5) Evaluation and revision of the training based on the performance of trained personnel in the job setting.
1 Training for operations of at-reactor-site ISFSI primarily affects two groups of plant staff. These are the licensed operators who are responsible for fuel handling associated with loading the spent fuel cask and the maintenance staff who are responsible for the seal welding of the cask and the longer term monitoring. However, t,1ese additional efforts associated with ISFSI-related activities are not expected to impose significant changes to the existing training program.
A potential issue that NRC staff may be required to address in individual cases is the withdrawal of a utility from INP0. However, this eventuality is similar to the existing status of the General Electric Morris Operation in Illinois, an independent spent fuel storage installation operating on its own site. General Electric Company (GE) 4 completed its last planned receipt of spent fuel in 1989 and has 3217 assemblies (665 metric tons heavy metal) in storage. GE's training program meets the five elements required and was part of a 1989 Quality Assurance Program i
f audit by NMSS and Region 111 staff in the course of a license amendment review addressing 3roposed staff changes and qualifications associated with GE's planned termination of further receipt of spent fuel.
In instances where utilities pursuing reactor decomissioning choose to withdraw from INPO, the staff will address this issue to assure that licensees maintain a training program meeting these requirements.
The staff expects to review the first case involving the L
withdrawal issue this year.
Public Service Company of Colorado (PSC) plans to submit a license ap)11 cation for an ISFSI in June 1990, for its Fort St. Vrain ligh temperature pas reactor site. PSC also plans to proceed with full de-commissioning of the reactor. Thus, upon termination of the reactor operating license, the proposed ISFSI would reside L
on its own site and function in a fully independent manner.
NRC staff has already met with PSC and discussed the need to I
cover this transition to stand-alone status for the ISFSI.
In conclusion, the NRC staff believes that through INPO and NRC oversight, NRC can ensure that training programs for l
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ISFS! operators are adequate. For potential operators who are not members of INP0 (e.g., PSC in the Fort St. Vrain case), the NRC staff will take' care to assure that these exceptions also maintain training programs meeting the.
Comission's requirements.
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