ML19322D359
| ML19322D359 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 05/31/1979 |
| From: | Floyd, Lewis NRC - NRC THREE MILE ISLAND TASK FORCE, NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| To: | |
| References | |
| TASK-TF, TASK-TMR NUDOCS 8002110687 | |
| Download: ML19322D359 (16) | |
Text
{{#Wiki_filter:7_ Ill ok.}-) QS[3, OM4ppamp, Qq 5 209 ) I i b~ t i 1 C0!stISSIONER LEWIS: Mr. Floyd, I'd like to go back bi/ n ro q p~4 2 to before the accident. According to Richard Hartfield, {. n^lil g p3 Director of the NRC's Management and program Analysis Office, t 3 39 y.- )4 Unit 2 has had 50 percent more reportable occurrences than the si.t i j ' [5 natiom ide average for nuclear reactors. That was before Y Q 6 Unit 2 went on line and went commercial. What does that say yp j7 to you about the readiness of Unit 2 to go into operation? ] !!O p8 MR. FLOYD: I need to know if he is quoting the . ?i:M, n i 9 national average for nuclear reactors today, or if he is quot- @M M v .t: m; 10 ing the national average for reactors in their first year ' j ! *,1 before commercial operation. It could make a great big ""y ,. o, e. g difference to how I respond to your question as to which QT g J,.. ! 13 average he is comparing us to. u( C0!ellSSIONER LEW15: He is comoaring you to the n' l .[ g'j L first year of operation for all nuclear reactors. 1 MR. FLOYD: Okay. This is not quite a fair compari-(
- 37l, son becuase we were in a test program during that year and not WJ pp;;j in ur first year of operation.
vpf '18 F 0; t, -4 F But assuming it were a fair comparison: The number ,'issM ,19 e v.a of reportable occurrences that a station has or a unit has is gf; ny rq some kind of an index to what kind of an operation is being hy 1 3 4 When you look behind just the number and at the conse-iij run. cy j 5, m Id5d'? quences of what was wrong, the two occurrences might be much 1 ? b. ,k ' more imoortant than 10 or 20. 'Mt ~ blN l ^ There are many things which I have to put myself on fi l ..'3 ol l bp] u l' 8002110 b87 ".4 I m k ~ c--.-.
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i Question II. How many incidents or events have. occurred at TMI-2 before the accident? Answer During the period from license issuance (February 8,1978) through March 30, 1979 a total of 69. licensee events were reported to the Nuclear Regulatory Comission. These included the following causes and types of reports. CAUSE TITLE
- NUMBER OF REPORTS 14 Day **
30 Day ** Total Component Failure 0 13 13 Defective Procedures 2 8 10 Design / Fabrication Errors 9 13 22 External Cause 0 0 0 Other 1 8 9 Personnel Error 6 9 15 Total 18 51 69 *
- These causes are defined on pages 13-15 of the enclosed NUREG-0161, Instrettions For Preparation of Data Entry Sheets for Licensee Event Report (LER) File.
- The.4 day and 30 da'y reports are described on pages 1,16-3 through 1.16-5 of Regulatory Guide 1.16 (Revision 4, August 1975).
Copy attached. Question How does the frequency and type of event cornpare with other facilities? ~ Answer During 1978 there were 1765 licensee events reported to the NRC by the 42 pressurized water reactors that had operating licenses during that period. The THI-2 reports are included in this table and a copy of the printout of all events reported by THI-2 is attached. 's e N w o e-p
c. ~ -2 CAUSE TITLE NUMBER OF REPOP.TS 14 Day 30 Day Total Component Failure 72 847 919 Defective Procedures 25 58 83 Design / Fabrication Error , 70 105 175 External Cause 3 18 21 Other 38 212 250 Personnel Error 83 234 317 . Total 291 1474 1765 4 The following table lists the number of reports submitted by TMI-2 during this period. CAUSE TITLE NUMBER OF REPORTS 14 Day 30 Day Total Component Failure 0 13 13 Defective Procedures 2 5 7 Design / Fabrication Error 9 11 20 Other 0 0 0 External Error 1 6 7 Personnel Error 6 7 13 Total 18 42 60 Additional data listed below shows the number of licensee events reported by two unit sites for the first year after initial criticality for the second unit at the site and for the first unit during the same time period. 'i
Er w b 8 a h i s s. 8 0 8 E e 't a i S o e 8 3 t 88! 8 t E u V e' 3 .? C Plant Time Period O S 5 f Totals o TMI-1 3/28/78 - 3/28/79 9 1 3 0 5 4l 22 TMI-2 3/28/78 - 3/28/79 13 5 14 0 10 10 52 Calvert Cliffs-1 12/01/76 - 12/01/77 43 8 4 1 38 14 108 Calvert Cliffs-2 12/01/76 - 12/01/77 67 1 6 1 14 12 y 101 D. C. Cook-1 03/10/78 - 03/10/79 22 5 8 0 12 17 64 m D. C. Cook-2 03/10/78 - 03/10/79 39 5 10 1 21 28 ] 113 The following data provide a breakdown of the licensee events reported by each of the other Babcock & Wilcox (B&W) facilities during the one year period immediately following license issuance. This will provide some correlation between the events experienced at TMI-2 and other B&W facilities for somewhat similar periods of operation. 8 EE '5 5 x 8E 's 4 15 2 E R3 88 .Pt b b$ b 8% t2 Ott ta 5 t t u. u u. a n. a u. w wu o a. s Other B&W Facilities - One Year Period Immediately Following License Issuance Arkansas 1 4 2 3 19 21 2 51 Crystal River 34 7 7 3 35 16 102 Davis Besse 51 14 18 4 21 22 130 Oconee 1 11 7 4 0 1 11 34 Oconee 2 7 6 1 0 2 9 25 Oconee 3 12 2 7 0 0 12 33 Rancho Seco 9 5 4 1 0 11 30 TMI-1 27 - 18 20 5 5 11 86 B&W Average 19.4 7.6 8.0 6.4 14.1 11.7 61.4
e' -4 Care should be exercised in comparing these data, rince some of these facilities do not have the more complex systems and components utilized in newer f6cilities. In addition, the significance of individual LERs varies. Question What guidelines does the Commission have to determine when the frequency of incidents constitute a problem? P Answer Though the Commission has identified the types of incidents lirtnsees are to report, reviews the information reported, end takes action as it deems appropriate, the Commission at cae present time does not have specific guidelines to determine when the frequency of a jiven type of reported incident constitutes a problem. Engineering judgments, applied by knowledgeable. people on an ad hoc basis, have been used to initiate actions to reduce the frequency of events cauring safety concerns. The recurrent of some events has, for example, led to the identification of generic safety issues. The resolution of these issues has resulted in changes in the licensing and review process, as well as in plant nodifications and in technical specification changes, yielding safer operations. This process for reviewing and analyzing licensee event reports is now being reviewed to establish more formal and systematic evaluation procedures. A copy of SECY 79 371 is attached for your information, however, this document has not received Commission approval yet. Icprovements should lead to earlier discovery and correction of potential safety problems. M O
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