ML19221A699
| ML19221A699 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 05/29/1979 |
| From: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | Stampley N MISSISSIPPI POWER & LIGHT CO. |
| References | |
| NUDOCS 7907030102 | |
| Download: ML19221A699 (1) | |
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UNITED STATES
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[o7, NUCLEAR REGULATORY COMMISSION REGION 11
$ g ~k. I 101 MARIETT A ST.. N A, sUtTE 3100
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AT LANT A, GEORGI A 3o303
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MAY 2 91979 In Reply Refer To:
RII:JPO O O-416, 50-417~,
Mississippi Power and Light Company Atto:
N. ". Stampley Vice President of Production P. O. Box 1640 Jackson, Mississippi 39205 Gentlemen:
This Information Notice is provided as an early notification of a possibly It is expected that recipients wil' review the significant matter.
No specific inf ormation for possible applicability to their f acilities.If further NRC evaluations action or response is requested at this time.
ao indicate, an IE Circular or Bulletin will be issued to recommend or request specific licensee actions. If you have questions regarding this matter, please contact the Director of the appropriate NRC Regional Office.
Sincerely, d
Q James P. O'Reilly Director
Enclosure:
Inforr.ation Notice No. 79-13 w/F.nclosures 273 122 7 907 03 0l0V Q
Mississippi Power and Light Coc:pany 2
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C. K. McCoy Plant Manager Post Office Box 756 Port Gibson, Mississippi 39150 G
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UNITED STATES f[. 'h NUCLEAR REGUIATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT f @.',T.q)L P WASHINGTON, D.C.
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b y 29, 1979 1,4 IE Information Botice No. 79-13 INDICATION OF IJDW WATER 1EVEL IN THE OYSTER CREEK REACTOR Suasaary A loss of feedvater transient at the Oyster Creek facility on b y 2, 1979, resulted in a significant reduction in water inventory within the reactor core shroud area as sensured by one set of water level instruments (triple lov level), while the remaining level instruments, sensing from the reactor==1us area indicated water levels above any protective feature setpoint (Figure 1).
The water level within the core shroud area was reduced below the " triple lov level" setpoint of 4-feet, 8-inches above the top of the fuel.
Subsequent analysis by the licensee has determined that the minimum collapsed water level (solid, without steam voids) over the top of the fuel was 1 to 1-1/2 feet.
Coolant sample analyses and offges release rates indicate no fuel damage occurred.
General Oyster Creek is a non-jet pu=p BWR with licensed power of 1930 W t.
The plant was first made critical b y 3, 1969.
Status Bet ve Transient Operating at near full power with the main parameters at levels as follows:
1895 We power level 79" Yarvsy (13'4" over top of fuel) reactor water level 1020 psig reactor pressure 7.1x106 f/hr feedlov 14.8x104 gpm recirculation flow rate (4 pus:ps) 12 paid core p m,
Eqolpment Out of Service (005 DUPLICATE DOCUMENT 273 124 "D" recire pump 005 due to e Entire document previously entered "A" startup transformer 00S i into system under:
D &&D [(ON ANO No. of pages:
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