ML20133G663

Forwards Schedule for Meeting Requirements of 10CFR50.62(c)3 & (c)4 Re Reduction of Risk from ATWS Events for Light Water Cooled Nuclear Power Plants

ML20133G663
Person / Time
Site:	Oyster Creek
Issue date:	10/09/1985
From:	Fiedler P GENERAL PUBLIC UTILITIES CORP.
To:	Harold Denton Office of Nuclear Reactor Regulation
References
NUDOCS 8510160072
Download: ML20133G663 (3)

Text

r GPU Nuclear Corporation Nuclear  ::',ggr388 Forked Rwer New Jersey 087310388 609 971-4000 Writer's D rect Dial Number:

October 9,1985 Office of Nuclear Reactor Regulation Attn: H. R. Denton, Director U.S. Nuclear Regulatory Comission Washington, DC 20555

Dear Mr. Denton:

Suoject: Oyster Creek Nuclear Generating Station (OCNGS)

Docket No. 50-219 10CFR 50.62 As you are aware,10CFR 50.62 concerns requirements for reduction of risk from anticipated transients without scram events for light-water-cooled nuclear power plants. Pursuant to 10CFR 50.62(d), please find attached a schedule for meeting the requirements of 10CFR 50.62(c)(3) and (c)(4).

Very truly yours,

. Tiedler Vice President & Director Oyster Creek PBF:gpa 2281 f/001 Attachment cc: Administrator, Region 1 U. S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406 NRC Resident Inspector Oyster Creek Nuclear Generating Station Forked River, New Jersey 08731 J. Donohew U.S. Nuclear Regulatory Comission 7920 Norfolk Avenue Bethesda, Maryland 20014 su 2288H Bi!8!h' 3 6 l

\

GPU Nuclear Corporation is a wtasdary of the General Pubhc Utihties Corporation

ATTACHMENT 10CFR 50.02 OCNGS Requirement (d); Implementation - By 180 days af ter the issuance of the QA guidance for non-safety related components each licensee shall develop and submit to the Director of the Office of Nuclear Reactor Regulation a proposed senedule for meeting the requirements of paragraphs (c)(1) through (c)(5) of this section. Each shall include an explanation of the senedule along with a justification if the schedule calls for final implementation later than the second refueling outage after July 26, 1984, or the date of issuance of a license authorizing operation above 5 percent of full power. A final schedule shall then be mutually agreed upon by the Commission and Licensee.

Discussion; Subsequent to the issuance of 10CFR 50.62, tne BWROG fonned a committee to genes ically address the hardware aspects of the ATWS rule.

General Electric, under the direction of the BWROG, assessed the various alternatives available to meet the requirements of the ATWS rule. GPUN has evaluated the BWROG assessment and has detennined that the modifications indicated below are responsive to the requirements of 10CFR

, 50.62. The schedules provided are based on the extent of hardware cnanges, equipment availability and refueling outage work load.

Requirement (c)(3) - Each boiling water reactor must have an alternate rod injection (ARI) system that is diverse (from the reactor trip system) from sensor output to the final actuation device. The ARI system must have redundant scram air header exhaust valves. The ARI must be designed to perform its function in a reliable manner and be independent (from existing reactor trip system) from sensor output to the final actuation device Response - An ARI system shall be provided by no later than the Cycle 12 refueling outage. The ARI system shall have valves redundant to the backup scram valves and may be initated on the same parameters as the existing recirculating pump trip system.

Requirement - (c)(4) - Each boiling water reactor must have a Standuy Liquid Control System (SLCS) with a minimum flow capacity and boron content equivalent in control capacity to 86 gallons per minute of 13 weight percent sodium pentaborate solution. The SLCS and its injection location must be designed to perfonn its function in a reliable manner.

The SLCS initiation must be automatic and must be designed to perfonn its function in a reliable manner for plants granted a construction pennit after July 26, 1984, and for plants granted a construction permit prior to July 26, 1984, that have already been designed and built to include this feature.

Response - It is our belief that the existing isolation condenser

, instalfation negates the need for an increased boron initiation rate because it allows sufficient time for the existing SLCS to bring the plant subcritical. However, we also feel that going to a higher injection rate can improve overall ATWS mitigation. Therefore, SLCS providing the desired equivalency in control capacity shall be provided l

I by no later than the Cycle 12 refueling outage.

l

Requirement - (c)(5) - Each boiling water reactor must have equipment to trip the reactor coolant recirculating pumps automatically under conditions indicative of an ATWS. This equipment must be designed to perform its function in a reliable manner.

Response - The OCNGS presently has an ATWS reactor coolant recirculating pump trip (RPT) which is actuated on High Reactor Pressure and/or Low-Low Reactor Water Level.

In light of the statement contained in the supplementary information associated with the Rule's appearance in the Federal Register dated June 26,1984, " Existing recirculation pump trip equipment installed in BWRs in accordance with previous staff requirements for the mitigation of anticipated transients without scram need not be modified", GPUN has determined that its existing ATWS RPT is responsive to the rule and no modifications will be made with respect to 10CFR 50.62 (c)(S).