ML19276E335

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Forwards Revision 2 of Task Action Plan A-27,reload Applications.Completion Requires Approx 0.07 man-yrs. Completion Projected for June 1979
ML19276E335
Person / Time
Issue date: 02/16/1979
From: Stello V
Office of Nuclear Reactor Regulation
To: Case E
Office of Nuclear Reactor Regulation
References
REF-GTECI-A-27, REF-GTECI-FU, TASK-A-27, TASK-OR NUDOCS 7903120401
Download: ML19276E335 (5)


Text

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i February 16, 1979 i

Generic Activity A-27 MEMORANDUM FOR:

E. G. Case, Chaiman Technical Activities Steering Cormittee FROM:

Victor Stello, Jr., Director i

Division of Operating Reactors

SUBJECT:

REVISED TASK ACTION PLAN FOR A-27 RELOAD APPLICATIONS Enclosed is Revision 2 of the Task Action Plan for A-27, Reload i

Applications, which I have recently approved. Since this Task was assigned only 90 points by the Steering Corm 11ttee, we have requested NRR Directors approval to complete this reduced scope task. Of the three original major milestones, the two which are almost complete (issuance of a BTP and a Reg. Guide) have been retained and the one which has not yet been started (modification to the SRP) has been rieleted. To comphte the two remaining milestones approximately 0.07 manyear ir required

($10 days for 00R and s10 days for PSS). The projected completion date is June 1979.

Victor Stello, Jr., Director Division of Operating Reactors

Enclosure:

TAP - Task A-27, Rev. 2 79031209'd/

Task A-27 RELOAD APPLICATIONS Lead NRR Grganization:

Divisio., of Operating Reactors (D0R)

Lead f1RR Supervisor:

D. G. Eisenhut Deruty Director Divisicn of Operating Reactors Task Manager:

J. Giannelli, PSS/f4RR Applicabi? ity:

Light Water Reactors Projected Completion Date:

June 1979

Task A-27 Rev. No. 2 Feb. 1979 1.

DESCRIPTION OF PROBLEM By letter dated June 18, 1975, licensees of operating reactor facilities were sent a preliminary copy of a staff paper, " Guidance for Proposed License Amendments Relating to Refueling," and " Refueling Information Request Form." The purpose was to provide guidance, although preliminary, to licensees as to information the staff considers to be essential for the conduct of its review of core reload submittals.

In order to add more predictability to the review process and to improve the staff scheduling of such reviews, licensees were asked to submit the Refueling Information Request data within 30 days af ter receipt of the letter and were requested to update the information annually thereafter (or more often if appropriate).

In 1978, this information request was revised and sent to the licensees by MPA.

The revision underscored our interests in the spent fuel storage capacity at the plants.

A further revision, currently being prepared will call for the early identification of non-reload related activities which often take place during refueling outages and which require Commission review.

The purpose of Task A-27 is to update the preliminary guidance issued to licensees in the June 18, 1975 letter to assure conformance with the latest staff technical positions that relate to core reloads.

Providing licensees with uniform and up-to-date infonnation on our criteria will help to make the review process more orderly and predictable. We would like to encourage licensees to plan reloads which do not reouire prior NRC approval and thus reduce our staffing commitment to reload reviews.

2.

PLAN FOR PROBLEMS RESOLUTION Updated guidance on reload applications will be made available to licensees in two phases. The first phase involves preparation of a D0R Branch Technical Position (BTP) to revise the preliminary guidance issued to licensees. The revisions that have been made will (a) ensure completeness of the safety analyses performed by the licensee, (b) ensure completeness of the application for license amendment relating to core refueling, (c) provide sufficient time for NRC review of proposed license amendments and/or unreviewed safety questions, and (d) improve efficiency and scheduling of NRC review of proposed license amendments. The draft BTP, DOR-1, was presented to the Regulatory Requirements Review Committee (RRRC) and was approved in January 1978.

A-27/1

Task A-27 Rev. No. 2 Feb. 1979 Completion and issuance of the BTP will provide updated interim guidance to the licensees until completion of the Regulatory Guide.

The second phase of the task, already underway in the Office of Standards Development, involves preparation of a Regulatory Guide on reload reviews which will incorporate the~BTP.

Following approval by the RRRC, the draft BTP-DOR-1 was sent to the Office of Standards Development as our response to their Request for Technical Assistance dated April 9, 1976. The April 9,1976 reouest transmitted a copy of their draft Regulatory Guide on refueling for our comments.

In addition, upon completion of the BTP, it will be sent to licensees as discussed above.

NRR will continue to support this effort as reouired.

It is estimated that the Regulatory Guide will be issued for comment in June 1979.

3.

BASIS FOR CONTINUED PLANT OPERATION AND LICENSING PENDING COMPLETION OF TASK The results of this Task Action Plan (TAP) will be applicable to all operating reactor facilities.

Continued operation of licensed facilities, pending completion of this TAP, does not present an undue risk to the health and safety of the public for the following reasons:

The TAP does not include the development of new technical positions and, as such, is generally administrative in nature with the intended objective of improving the overall efficiency and effectiveness of core reload reviews.

Currently existing licensing acceptance criteria which are utilized in the staff's review of proposed core reloads provide adequate assurance that plants will be operated safely without undue risk to the health and safety of the public.

4.

NRR TECHNICAL ORGANIZATIONS INVOLVED The Reactor Safety Branch, Division of Operating Reactors is responsible for providing the technical input necessary (1) to obtain RRRC approval of BTP-DOR-1, and (2) to support the preparation of the Regulatory Guide by the Office of Standards Development.

A-27/2

4 Task A-27 Rev. No. 2 Feb. 1979 The Core Performance Branch and the Reactor Systems Branch, Division of Systems Safety, participated in the above areas by providing review and comments as requested.

We estimate that 0.07 manyear of NRR technical effort is required for the completion of this Task.

5.

TECHNICAL ASSISTANCE REQUIREMENTS None.

6.

INTERACTION WITH OUTSIDE ORGANIZATIONS None.

7.

ASSISTANCE REQUIREMENTS FROM OTHER NRC 0FFICES None.

8.

POTENTIAL PROBLEMS No potential problems can be foreseen at this time.

A-27/3