ML20207N393

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Forwards Memo Assessing Impact of Current Reporting Requirements (10CFR50.72) on Facility
ML20207N393
Person / Time
Issue date: 03/19/1985
From: Norelius C
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To: Jordan E
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
Shared Package
ML20204G677 List:
References
FOIA-86-729 NUDOCS 8701140188
Download: ML20207N393 (2)


Text

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f 799 ROOSEVELT RO AD CLEN ELLYN, ILLINOl$ 60137 IMAR 19 G85 MEMORANDUM FOR: E. L. Jordan. Director, Division of Emergency Preparedness and Engineering Response IE

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FORM: C. E. Norelius,LDirector, Division of Reactor Projects ,

SUBJECT:

POTENTIAL OPERATIONAL' IMPACT FROM 10 CFR 50.72 REPORTING

REQUIREMENTS ,

Attached for your review and consideration is a memorandum prepared by a 'DRP Section Chief assessing the impact of current reporting requirements on the .

LaSalle Station. The evaluation of 102 events reported from September 1, 1984 through January 14, 1985 indicated that only 23 percent of the reports involved matters considered to have safety significance. Further, of the remaining reports, the regional staff did not need the information within the time constraints imposed by 10 CFR 50.72 to properly evaluate and provide followup.

Our concern focuses on the impact that voluminous numbers of reportable events may have on the licensee's ability to provide the necessary attention to the control room environment, off-nonnal conditions, and matters which may have more innediate safety significance. Region III licensees are very sensitive to time clocks associated with 50.72 reporting.

Additionally, I have been concerned for some time with the substantial increase in reports coming from more recently licensed plants and the more complex technical specifications. Our analysis of 50.72 reports over the past quarter indicates we received, evaluated, and followed up almost twice as many reportable events as in the previous quarter. With the addition of Fermi, Perry -

Clinton and Byron Unit 2 projected within the next.12. months, I would anticipate a significant increase in workload for the Events Analysis, Headquarters Duty Officer, and regional office staffs to communicate, track and, follow up events which have little operational significance. From a

! regional perspective. I would also add that the handling of many of the 50.72 l

calls by our regional duty officer and project management and staff also takes time which could be more profitably spent dealing with more significant safety matters.

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E. L. Jordan 2 MAR 19 085-l Region III is cognizant of initiatives underway concerning the review of Technical Specifications and the analysis of 50.72 reporting requirements. We would be happy to work with you to assure that 50.72 reporting requirements factor in the potential impact on control room and plant operations and result in reporting at a level consistent with safety significance. Should you have any questions on the detailed listing of Attachment A of the enclosed memorandum, the details of the reported events, or our bases in determining operational i significance, please have your staff contact N. Chrissotimos directly: ,

(FTS388-5716).

M.DM C. E. Horelius, Director l

Division of Reactor Projects 3

cc: J. M. Taylor, IE H. L. Thompson..NRR C. J. Heltemes, AE0D A. B. Davis, RIII E. G. Greenman, RIII DRP Division Directors, RI, RII, RIV RV

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