ML20154G427

Responds to NRC Bulletin 88-007, Power Oscillations in Bwrs. Current Operating Procedures Address Reactor Stability Concerns & Operator Actions to Mitigate Initiating Conditions for Power Oscillation Problems

ML20154G427
Person / Time
Site:	Oyster Creek
Issue date:	09/14/1988
From:	Fitzpatrick E GENERAL PUBLIC UTILITIES CORP.
To:	Office of Nuclear Reactor Regulation
References
IEB-88-007, IEB-88-7, NUDOCS 8809200361
Download: ML20154G427 (2)

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l GPU Nucleat Corporation NggIgf Post Office Box 388 Route 9 South Fotked Rwer New Jersey 08731-0388 609 971 4000 Writer's Direct Dial Nurr%r, September 14, 1988 Director of Nuclear Reactor Regulation U.S. Nuclear Regulatory Comission Hail Scatinn PI-137 Washingun, DC 20535

Subject:

Oyster Creek Nuclear Generating Station Docket No. 50-219 NRC Bulletin No. 88-07 "Power Oscillations in Boiling Water Reactors (BWRs)"

l l General Public Utilities Nuclear, (GPUN) has briefed licensed reactor operators and Shif t Technical Advisors (STAS), assigned to shif t duties.

l regarding the March 9,1988 LaSalle Unit 2 event described in the subject I bulletin. This was acconiplished within 15 days of the receipt of the tsulletin as required.

SLbsequently, GPUN conducted a review of this event as it pertains to the Oyster Creek design. This review included an engineering evaluation of reactor stability, a review of the capabilities of the installed nuclear instrumentation to detect power oscillations which included a specific Lest, a review of the operator training program, and a review of operating procedures. As a result of these reviews, it has been concluded that althnugh the Oyster creek design is less susceptible to power oscillations due to lower power deasity, oscillations can occur during operation at high 3 power and low flow conditions. Furthermore, it was found that if power oscillations similar to those at LaSalle Unit 2 were to occur at Oyster Creek, the oscillations would be terminated by scram at a lower power level.

Information relative to the LaSalle events has been included in the applicable training program files (both operator and STA) which are consulted prior to presentation of the training progr4 4 ;dule. Permanent inclusion of this information into the couru outline will be accomplished within the established schedule for revision of the training program module.

Additionally, plant simulator training includes operator response to power oscillations.

A review of operating procedures was conducted. These procedures had addressed most aspects of reactor stability and operator .*esponse to events and conditions which could result in power oscillations. However, as a result of the engineering evaluation, it was concluded that these procedures can be improved and revisicns are currently in the preparation and review process. Following revision of the procedures, they will be included in the operator and STA training program.

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{DR g fl GPU Nuc'e v Ccrtef ation a a subsdary of the Geretal Pothc Utd t.es Corporat.on I

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In summary, all licensed reactor operators and STAS have been formally briefed on the event.s which occurrad at LaSalle Unit 2 by the Oyster Creek Training Department. Infonnation relative to this event and its applicability ta the Oyster Creek design has been included in training presentations. Current operating procedures address reactor stability concerns and operator actions to mitigate initiating conditions for power oscillation problems. Improvs wnts in these procedures are being implemented and are expected to be completed by December 15, 1988. This will complete ,

GPUN's response to NRC Bulletin 88-07.  !

Very truly yours, E. E. Fitzpat' rick Vice President and Director Oyster Creek Sworn to and Subscribed before me this /#% day of 4ps,j n 1988.

Am hr4&o A Notary P .DTic of NJ h psHVn l

EEF/GB/smz i 0545A cc: Mr. William T. Russell, Administrator l 1 Region I  !

i U.S. Nuclear Regulatory Commission l 475 Allendale Road '

King of Prussia, PA 19406 fir. Alexander W. Dromerick, Project Manager U.S. Nuclear Regulatory Commission Division of Reactor Projerts I/II Washington, DC 20555 NRC Resident Inspector Oyster Creek Nuclear Generating Station Forked River, NJ 08731 1 I

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