ML19290E653
| ML19290E653 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse  |
| Issue date: | 03/05/1980 |
| From: | Stello V NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| To: | TOLEDO EDISON CO. |
| Shared Package | |
| ML19290E655 | List: |
| References | |
| NUDOCS 8003140337 | |
| Download: ML19290E653 (7) | |
Text
UNITED STATES OF AMERICA h'JCLEAR REGUL% TORY COMMISSION In the Matter of
)
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THE TOLEDO EDISON COMPANY AND
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Docket No. 50-346 THE CLEVELAND ELECTRIC ILLUMINATING
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COMPANY
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Davis-Besse Nuclear Power Station,
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Unit No.1
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ORDER PODIFYING LICENSE EFFECTIVE IMMEDIATELY I
The Toleco Ecisor. Company and the Cles elard Elec.ric Illuminating Company are holders cf Facility Operating License No. NPF-3 which authorizes the cperation cf the Da/is-sesse Nuclear Power Statien, Unit No. 1 (the facility or Davis-Besse 1), at steadj state power levels not in excess of 2772 megawatts thermal (rated power).
The Toledo Edison Company is the lead licensee, (the licensee). Tne f acility is a Babcock & Wilcox (E&W) designed pressurized water reactor (PR) located at the licensee's site in Ottawa County, Ohio.
II Davis-Eesse Unit No. 'l was the first nuclear power reactor built and operated by the licensee.
The facility, which began commercial operation November 21, 1977, experienced a higher than normal number of operating events during early operaticn and testing.
Many of these events were caused by personnel errors and procedural deficiencies.
A meeting with 800314033 7
. licensee corporate management was held during August 1978 in which the operating staff weaknesses were noted along with the related problem of untimely evaluation and resolution of facility change requests.
III The facility, being of B&W design, has undergone a significant number of pro-cedural, ecaiprent and operational changes as a result of lessons learned from the investigation of the Three Mile Island accident which occurred on March 28, 1979.
An crder issued to the licensee on May 16, 1979 and several NRC Bulletins have required r3for additional effort on the licensee's corporate and plant staffs.
IV A series of managerent meetings was initiated by Region III to address the licensee's enfercement history, number of pe sonnel errors, breakdown in managerert centrols, equipment problems ar.d lack of management's effectiveness in dealing sith identified problems.
The orfmary thrust of the first meeting in this series neld on April 14, 1979, was to address the need for immediate action by the licensee to irprove management controls and plant operations.
In the second meeting held on May 31, 1979, the licensee presented a program, based upon its assessnent of prcblem areas, to improve the level of management control, staffirg, training, the correction of equipment problems and plant operations.
During meetings held on July 17 and September 19, 1979, the licensee presented
. schedules and progress reports on their program for corrective action.
At the September 19, 1979, meeting, it appeared that licensee management had made progress in its control of licensed activities.
Personnel errors were declining and organizational changes were underway.
V A recent evaluation of the licensee's operation shows that the staffing, while improved, is not yet at the desired level.
Tinely resolution of problems is still a catter of concern.
The changes required by the TMI investigations and related studies and bulletins continue to place an additional burden on the cperating staff causing extended use of overtime.
During the week of February 18, 1980, the Resident Inspector, upon direct questicning cf plar,t operators, was told by One Operator that staffing problems were so significant that the plant was unsafe to operate.
On February 25, 1980, the Directcr, Region III, and the Director, Division of Reactor Operations Inspection, IE, interviewed several plant workers including senior licensed operators, licensed operators and nonlicensed personnel.
Perceived problems of excessive work hours and inadequate training were identified during these inter-views.
Sore of those interviewed, including two senior licensed operators stated their view that some shifts did not have adequately qualified people to successfully handle an emergency.
None of those interviewed rated the plant as being any better than marginally safe.
Additional investigation was conducted
. onsite on February 26 and 27,1980.
These investigations showed that while the licensee meetc the staffing requirements of its license, concerns remain regarding the adequacy of training of nonlicensed personnel, the ability to respond to emergency conditions, and the overall depth of the staff.
Specifically:
1)
Six of the more experienced equipment operators have been effectively removed from regular shif t work to train to become licensed operators; 2)
S me cf the remaining equipment operators have been trained on the e:uiprert only in certain zones.
While this is adequate for routine s-if t operaticns, these equipment cperators are not trained on all safety re'atec equipment such that they could be relied upon if neecec in other work zones during an erergency.
3)
Trere is 'ittle flexibility to acccmmocate the loss of staff because of sickress or other work leave.
Such problems result in additional osertime work requirements.
A reeting was held wi.th licensee managetent in the Region III office on Februa ry 29, 1930, to discuss the above concerns and to consider corrective actions.
. VI The past experience of plant operations, the observation by plant operators as to the adequacy of the operating staff, and the above NRC findings, demonstrate that changes ir the plant operating staff are required to provide reasonable assurance that the facility can be safely operated under emergency conditions.
Therefore, in \\iew of the above, I have determined that the public health, safety and interest recaire License No. NPF-3 be modified as stated in Part VII below, effective irrediately.
VII Accordingly, pt sua,t to the Atomic Energy A:t of 1954, as amended, and the Cormissicn regulations in 10 CFR Parts 2 and 50, IT IS HEREBY ORDERED THAT:
1.
Tre licensee snall:
a)
Fetur, six experienced and fully qualified equipment operators, whc t$ve been involved in operator license training, to regular shif t work to provide two fully qualified equipment operators for each operating shift.
The additional qualified individuals will remain on shift duty until such time as they are relieved from duty by other fully qualified individuals who are appropriately trained and certified by the licensee's training department.
_ b)
Prov'de ene additional person for each day shif t to relieve the shift forecan of nonlicenued admir.istrative responsibilities.
c)
Expecite the cn-the-job training schedule for existing equipment cperators whc are not yet fully qualified.
This program shall be acccmplishsd by personnel from Toledo Edison Company or an cutside contract crganization and shall continue at least until the ref ueling outage.
Or in tre alte nat've to items a), b) and c) above, place and maintain the facil#ty
'1 a :old sr.u:dcan or refuelir;. ode of operation.
2.
Pricr tc retar, of tre station tc cperations from the scheduled April 198C ref ueling oJtige, each cperating 57if t shall have a corplete ccmplement of full,. trair.ed perscnr.el 17 accordance with the staffing and qua'ification ~es e's set fcrth in c a't ANSI Standard 3.1.
VIII The licensee, cr any ot er person who has ar interest affected by this Order, nay, within twe7ty-five days of the date of this Order, request a hearing.
Any recuest for a hearing srall be addressed to the Director, Office of Inspection and Enforceme nt, U. S.N. E.C., Washington, D.C. 20555.
If a hearing is requested, the Cor.missica sill isste an order designating the time and place of hearing.
Such a request for nearing SHALL NOT STAY THE IMMEDIATE EFFECTIVENESS OF THIS twsER.
.- IX In the event t.e licensee or any other persca requests a hearing as provided above, tne isstes to be considered at such a hearing shall be:
(1) -hether the facts set forth in Section II, III, IV and V are true; and (2)
-hether this Order should be sustained.
FOR HE !.UCLEAR REGULATORY COMMISSION 7..
' N., ! >- f:
Vict:r Stello, Jr.
Dire: tor Of fi:e o' Inspection ar: En'orcement
- ated at Bethesda, Maryland this eo ca;. of March 1930.