ML20211Q048

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Requests Dates for NRC Review & Approval of BWR Topical Repts to Support Facility Application.Brunswick Driven Schedule Would Require SER for Final Topical to Be Moved Forward Several Months to Jan 1989
ML20211Q048
Person / Time
Site: Brunswick Duke Energy icon.png
Issue date: 12/11/1986
From: Rahe E
WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
To: Haughey M, Lainas G
NRC OFFICE OF ADMINISTRATION (ADM), Office of Nuclear Reactor Regulation
References
NS-NRC-3188, TAC-66529, TAC-66539, NUDOCS 8612190185
Download: ML20211Q048 (2)


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Westinghouse PowerSystems Rn"3}l5 Eh Pennsylvania 15230-0355 Electric Corporation Ns-Nac-3188 December 11, 1986 Mr. Gus C. Lainas, Assistant Director go'31Y Division of BWR Licensing Office of Nuclear Reactor Regulations U.S. Nuclear Regulatory M== ion Washington, D.C.

20555

SUBJECT:

Westinghouse Need Dates for NRC Review and Approval of Boiling Water Peactor (NR) 'Ibpical Espurts to Support a Brunswick Unit 2 Application

REFERENCE:

1.

Istter from Mary F. Haughey (NRC) dated May 2,1986 and titled

" Meeting Summary for April 24, 1986 Meeting with Westinghouse to Discuss Westinghouse core Reloads in BWRs Specifically, Nine Mile Point 2" 2.

Istter NS-NRC-86-3141 frt:rn E. P. Rahe, Jr. (W) to Jim Lyons (NRC) dated June 12, 1986 and titled " Westinghouse Need Dates for NRC Review and Approval of Boiling Water Reactor (NR) Topical Reports" (copy attached)

ATIENTION: DOCUMENT CCNIBOL DESK Mary F. Haughey, Project Manager Division of BWR Licensing Wayne Hodges, Chief Reactor Systems Branch

Dear Mr. Iainas:

In the above Reference 2, Westinghouse (W) specified the required need dates for each of the (W) topical reports being subnitted for NRC review and approval to support (W) core reloads in Boilirq Water Reactors (BWRs). R ese dates were driven by the Niagara Mohawk Nine Mile Point 2 plant. Westinghouse is currently in active negotiation with Carolina Power and Light ocxnpany for a Brunswick Unit 2 application. 'Ihe Brunswick cycle in question is currently scheduled for startup in April 1989. 'Ihe Niagara Mohawk driven schedule results in the submittal of approximately 12 generic topicals with the final Imc SER being issued in the spring of 1989.

To allow for the required 90-day NRC review time for the Brunswick cycle-specific submittal, the Brunswick driven schedule would require the NRC SER for the final topical to be moved forward several months to January 1989.

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Mr. Jim Lyons NS-NRC-86-3188 nansunhar 11, 1986 Please note that in Referenos 2, only cna topical is currently scheduled for an SER after Jamlary 1989, Wilch is the Westinghouse IMR fuel Basic Safety Report (BSR) to be submitted in June 1987.

For Brunswick Unit 2, W11ch is a IMR-4 plant, Westinghouse plans to amend a portion of the June BSR (less than 50%) for submittal to the NRC in MWr 1987.

'Ihus, for Brunswick, the schedule is moved forward several months for the review of the BSR and a second smaller BSR supplement has been aMad.

Given the early notification of the above needs, it is requested that the NRC evaluate their review resources to support the Brunswick aparatirq plant application haamd on the assunption that Westinghouse adheres to their subaittal schedule.

All of the above is predicated on Westinghouse receivirq the CP&L Brunswick contract which will be awarded by April 1987.

We would appreciate receiving your ocrifirmation that the Brunswick schedule can be acitieved.

If you have any questions, or should you desire any additional information, please contact Mr. Douglas G. Bevard at (412)-374-2319.

Very truly yours, h4%

p

. Rahe, Jr., Manager Nuclear Safety Deparbnent EPR:vyb Attachment

Westinghouse PowerSystems gylppennsytvania is230.osss Electric Corporation NS-NRC-86-3141 June 12, 1986 Mr. Jim Lyons, Chief Technical and Operations Support Branch Office of Nuclear Reactor Regulations U.S. Nuclear Regulatory Commission Washington, D. C.

20555

SUBJECT:

Westinghouse Need Dates for NRC Review and Approval of Boiling Water Reactor (BWR) Topical Reports

REFERENCE:

Letter from Mary F. Haughey (NRC) dated May 2, 1986 and titled " Meeting Summary for April 24, 1986 Meeting with Westinghouse to Discuss Westinghouse Core Reloads in BWRs Specifically, Nine Mile Point 2" ATTENTION:

DOCUMENT CONTROL DESK Mary F. Haughey, Project Manager Division of BWR Licensing Wayne Hodges, Chief Reactor Systems Branch

Dear Mr. Lyons:

In the above reference Westinghouse (W) was requested to specify the required need dates for each of the (W)(W) core reloads in Boiling Water topical reports being submitted for'NRC review and approval to support Reactors (BWRs). The enclosed Table 1 specifies these requested SER dates in addition to the corresponding submittal dates for each topical report.

These dates reflect several considerations, which are:

1.

A need for final issuance and receipt of all SERs by the spring of 1989 to support Nine Mile Point Unit 2.

2.

A need to smooth the schedule for SER issuance to obtain a workable process; i.e., not to require 11 SERs due at one time.

3.

The interdependence between the various topicals and their upcoming apolications.

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4.

Historical data on NRC review times for comparable (W) PWR topical reports.

If you have any questions, or should you desire any additional information, please contact Mr. Douglas G. Bevard at (412)-374-2319.

Very truly yours, c_

h~.y %W p Nuclear Safety Department P. Rahe, Jr., Manager EPR/vyb e

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TABLE 1 SCHEDULE FOR WESTINGHOUSE BWR TOPICAL REPORTS REQUESTED TOPICAL SUBMITTAL DATE SER DATE NUCLEAR DESIGN CODES 6-82 COMPLETED (WCAP-10106)

THERMAL-HYDRAULIC CODE 6-82 COMPLETED (WCAP.10107) 8X8 CPR CORRELATION 1-86 IN ACTIVE REVIEW (WCAP-10972)

NUCLEAR QUALIFICATION 6-85 2-88 (WCAP-10841)

CHANNEL STABILITY 6-86 4-88 BISON QUALIFICATION 8-86 8-88 9-86 3-88 QUAD + CORRELATION LOCA METHODOLOGY 9-86 9-88 RAMONA QUALIFICATION 1-87 11-88 LOCA SENSITIVITY 6-87,

1-89 BWR FUEL ROD DESIGN 6-87 10-88 LOCA CALCULATION 6-87 1-89 BASIC SAFETY REPORT 6-87 3-89 i

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