ML19263E587

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Forwards IE Info Notice 79-13, Indication of Low Water Level in Oyster Creek Reactor
ML19263E587
Person / Time
Site: 05000484
Issue date: 05/29/1979
From: James Keppler
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To: Dienhart A
NORTHERN STATES POWER CO.
References
NUDOCS 7906200132
Download: ML19263E587 (1)


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UNITED STATES f

NUCLEAR REGULATORY COMMISSION,

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,( f cL EN ELLYN. ILUNOIS 60137 MAY 2 9 1979 Docket No. 50-484 Northern States Power Company ATTN:

Mr. A. V. Dienhart Vice President - Tyrone Energy Park 100 North Barstow Street Eau Claire, WI 54701 Gentlemen:

This Information Notice is provided as an early notification of a possibly significant matter.

It is expected that recipients will review the information for possible applicability to their facilities.

No specific action or response is requested at this time.

If further NRC evaluations so 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 this office.

Sincerely, k

(/ James G. Kepp er Director

Enclosure:

IE Information Notice No. 79-13 cc w/ encl:

Central Files Director, NRR/DPM Director, NRR/ DOR 22hh l((

PDR Local PDR NSIC TIC Regions I & IV

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.r-0FFICE OF INSPECTION AND ENFORCEMENT REGION III May 29, 1979 IE Information Notice No. 79-13 INDICATION OF LOW WATER LEVEL IN THE OYSTER CREEK REACTOR Su==arv A loss of feedwater transient at the Oyster Creek facility on May 2, 1979, resulted in a significant reduction in water inventory within the reactor core shroud area as measured by one set of water level instruments (triple low level), while the remaining level instruments, sensing from the reactor annulus area indicated water levels above any protective feature setpoint (Figure 1).

The water level within the core shroud area was reduced below the " triple low level" setpoint of 4-feet, 8-inches above the top of the fuel.

Subsequent analysis by the licersee 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 sa=ple analyses and offgas release rates do not indicate any fuel damage occurred.

General Oyster Creek is a non-jet pu=p BWR with licensed power of 1930 MWt. The plant was first made critical May 3, 1969.

Status Before Transient Operating at near full power with the main parameters at levels as follows:

1895 MWt power level 79" Yarway (13'4" over top of fuel) reactor water level 1020 psig reactor pressure 7.1x106 f /hr feedflow 2288 178 14.8x104 gpm recirculation flow rate (4 pumps) 12 psid core op Equipment Out of Service (OOS)

"D" recire pump OOS due to sea "B" startup transformer 00S fo DUPLICATE DOCUMENT Entire document previously entered into system under:

ANO No. of Pages:

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2 Southem Califomia Edison Company 5

R O. BOX 800 2244 WALNUT GROVE AVENUE JACK O. MOORE ROSEMEAD, CAUFORNIA 91770 TELEPHONE vice passeosse, 2&p2 2M May 1, 1979 A *.!.' i 9

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n U. S. Nuclear Regulatory Commission

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j\\Y Office of Inspection and Enforcement Region V

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1990 North California Boulevard

'G.s Walnut Creek, California 94596 Attention:

Mr. R. H. Engelken, Director Docket No. 50-206 San Onofre Unit 1

Dear Sir:

IE Inspection Report No.

50-206/79-04 The subject IE Inspection Report was forwarded by letter dated April ll, 1979, from Mr. J. L. Crews of your office. Appendix A to that letter was a Notice of Violation concerning failure of the Reactor Operator Retraining Pro-gram to review facility design changes. This letter tenders our response to that Notice of Violation.

1.

Cause of the violation Written station procedures provide for documented review of design changes and other documentation by all licensed operators.

In the case of Design Changes 78-16, 78-17 and 78-18, either the procedure for the review was not followed or documentation of the review was misplaced after the review.

2.

Steps taken to correct the violation The three design changes have been reviewed by all licensed operators and results of the review documented.

7906200134 3.

Steps taken to prevent recurrence

'Ihe written procedure governing the review has been modified to insure that all required documents are distributed to licensed operators for review in a timely manner and that documented verification of such reviews can be provided.

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U.S. Nuclear Regulatory Commission IE Inspection Repo rt 50-206/79-04 Page 2 The above corrective actions should eliminate the area of concern noted in the subject report.

Should you have any questions concerning this response, please do not hesitate to contact me.

Sincerely, 2288 180

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