ML19224B010
| ML19224B010 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 04/03/1979 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| To: | |
| References | |
| OLS-790403, NUDOCS 7906130422 | |
| Download: ML19224B010 (7) | |
Text
.
50-320 NRC Actions re other BSW plants from IE files 3/28/79 - 4/3/79 i
t 181 076 7006130 Q,1
I.
Imn.ediate Staff Work A.
Obtain best available preliminary technical evalua-tion of the significance of the TMI accident for i
the sister plants.
The focus should be on whether presently available information indicates a
.4 generic design or procedural problem.
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B.
Determine current operating status of sister plants --
'1 e.g.,
Davis-Besse is not presently operatin6-I C.
Determine probable practical effects of the follow-
.3 ing regulatory options:
a) aft fik
-b *
.A 1.
Provision of resident inspector and other mens-ures already adopted.
2.
Increased inspection and surveillance above current levels.
3.
Operation at reduced power levels.
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Precautionary shutdown pending more definite identification of TMI problem.
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181 078 i
TASK GROUP ON GENERIC REVIEW 0F FEEDWATER TRANSIENTS IN B&W REACTORS g // }]
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Members:
S. Israel, Group Leader f C '/ ',i </ )
5 P. Check, RSB R. Satterfield, ICSB u
G. Lainas, PSB Z. Rosztoczy, AB A. Oxfurth, IE Given the operating experience with feedwater transients Charter:
in operating B&W designed reactors, assess whether reactor and plant systems at these plants provide adequate protection from design basis feedwater transients.
This assessment should re-confinn whether these plant designs meet the requirements of NRC regulations, using appropriate staff guidelines for acceptable means of meeting these regulations.
This should include an evaluation of the safety margins of these plant designs to assure that specified acceptable fuel design limits are not exceeded as a result of feedwater transients.
181 079 9
- J n,v Preliminary Notifications are being transmitt'ed to each B&W facility to keep them appraised of the Three Mile Island licident daily.
These documents were verified to have been facsim. lied except for Arkansas which was overnite mailed due to equipment problem.
The PNs were discussed with the Vice President of Arkansas Power and Light on i
March 31, 1979 and are being updated daily.
The PNs also being sent to other licensees for information.
An expedited Bulletin has been prepared for issuance on April 2, 1979 to all B&W facilities for action and to other facilities either in operation or under construction for information.
An inspectisA.has been dispatched or is on site at each of the B&W facilities.
The following personnel have been assigned:
Site Status Inspector Arkansas I Refuel not identified (Monday)
Crystal River Full Power Don Quick Rancho Seco Full Power Al Johnson Davis Besse 9 day maintenance Tom Tambling (Monday) outage Oconee Unit 1 Full Power Bill Cottle Oconee Unit 2 Full Power Oconee Unit 3 Full Power r
e 181 080
RESPONSE TO INQUIRIES REGARDING DRAFT 4/2/79 IE BULLETIN N0. 79-05 Riesland:ecw 1.
The bulletin is addressed to utilities listed below and includes pertinent facilities, sources of cooling water, and the dates the operating licenses were issued.
l Utili_tv Facility Cooled By Operating License Sacramento Rancho Seco 1 Air, CA 08/16/74 Municipal Utility District e
Florida Power Crystal River 3 Gulf of 01/28/77 Corporation Mexico, FL Toleds Edison Davis Besse 1 Lake Erie, OH 04/22/77 Company Duke Power Company Oconee 1, 2 & 3 Lake Keowee, SC 1 - 02/06/73 2 - 10/06/73 3 - 07/14/74 Duquesne Light Beaver Valley 1 Ohio River, PA 07/02/76 Company Metropolitan Three Mile Susquehanna River, 1 - 06/24/74 Edison Company Island 1 & 2 PA 2 - 02/08/78 Arkansas Power Arkansas 1 Lake Darderelle, 05/21/74 AK Arkansas 2 Arkansas River, AK 09/01/78 1R1 031
. t 2.
The bulletin is directed to the above utilities be ause, like Metropolitan Edison Company, they operate Babcock & Wilcox (B&W) designed facilities.
It appears on very preliminary review of limited data that these facilities may be more susceptible than other pressurized water reactor (PWR) facilities to some of the malfunctions that appear to have been invoked at Three Mile Island.
The Davis Besse event described in Enclosure 1 to the Belletin has some superficial similarities to the event at Three Mile Island, although there are also significant differences.
As more information is developed, the cause of the occurrence will be fully assessed and appropriate corrective measures taken.
3.
The purpose of Bulletin No. 79-05 is to obtain information from
)
licensees who are operating B&W designed facilities.
To assist the licensees in their development of the requested information, we are providing updates on the Three Mile Island Ur.it 2 occurrence.
Information developed by the licensees should lead to additional conservatism in the protection of the public in the event a transient, such as occurred at Three Mile Island Unit 2, is repeated at a B&W designed facility.
i81 082