ML20108E317

Provides Updated Schedule for Licensing Actions Necessary to Support Transition of Plants to Fuel Supplied by Siemens Power Corp

ML20108E317
Person / Time
Site:	Quad Cities, LaSalle
Issue date:	05/01/1996
From:	Hosmer J COMMONWEALTH EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9605100155
Download: ML20108E317 (5)

Text

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Commonwealth Edison Company a ,

1400 0 pus Place

, Downers Grove. IL PALM 701 ,

l May_1,1996 U.S. Nuclear Regulatory Commission Washington, DC, 20555 Attn: Document Control Desk

Subject:

LaSalle County Nuclear Power Station Units 1 and 2 Quad Cities Nuclear Power Station Unite 1 and 2 Fuel Vendor Transition Schedule Update NRC Docket Nos. 50-373/374 and 50-254/265 Referencc~ 1. Conference Call on Sept. 15,1994 between Comed (G. Benes, J. Silady, et al.), NRR (R. Pulsifer, L. Phillips, et al.),

and SPC (R. Copeland, et al.)  ;

1

2. Letter, G. Benes to USNRC dated Nov. 14,1994, on " Fuel Vendor Transition for Post-1995 Reloads" for LaSalle and )

Quad Cities Nuclear Power Stations (Docket Nos. 50-373, 374, l 254, and 265) l

3. Letter, R. Querio to USNRC dated April 8,1996 submitting the  ;

preparatory license amendment to support the fuel vendor transition for LaSalle Units 1 and 2 (Docket Nos. 50-373, 374)

4. Letter, G. Benes to USNRC dated March 8,1996 submitting SPC report EMF-96-021(P) Revisien 1, February 1996 This letter provides an updated schedule for the licensing actions necessary to support the transition of the subject units to fuel supplied by Siemens Power Corporation (SPC). These actions were initially outlined for the NRR Project Manager, Reactor Systems Branch staff and a representative of Region lli during the Reference 1 conference call. Both the technical and scheduler considerations of the licensing plan were discussed and it was viewed as a reasonable approach.

1 The tentative schedule was also subsequently transmitted for the Staff's l information and resource planning purposes in Reference 2. As indicated in the conference call and follow-up letter, the dates shown were subject to chaga due to the Comed system-wide outage scheduling requirements. The company % Overhaul Scheduling Committee subsequently made several changes, for example, as a result of the extended outages at Dresden and Quad Cities. The originally scheduled Fall 1996 refuel outage for the initial SPC reload for Quad Cities Unit 2 Cycle 15 has been rescheduled to begin in February 1997 with a targeted restart date in early April 1997 (i.e. start-up five months later than original tentative schedule). In contrast, the initial start-up with SPC fuel for LaSalle Unit 2 Cycle 8 is now targeted for late November 1996 (one month earlier than originally anticipated).

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USNRC May 1,1996 i

The preparatory amendment for the LaSalle units was recently submitted in l 4

Reference 3. A similar amendment for Quad Cities is targeted for submittal to the NRC in June 1996. As discussed in References 1 and 2, cycle-specific analyses are performed by SPC to confirm the value of the Minimum Critical Power Ratio (MCPR) j safety limit . The potential need for a supplemental change to the safety limit value is '

not likely, but remains as a scheduled confirmation following the preparatory amendment. The cycle-specific MCPR safety limit confirmation was completed for LaSalle Unit 2 prior to the Reference 3 submittal. )

In response to generic questions from the NRR Reactor Systems Branch to the itel vendors concerning mixed core Critical Power Ratio (CPR) treatment of co-resident fuel, Siemens supplemented the Licensing Topical Report on their CPR methods in November 1995. In a meeting early this year, NRR also requested plant j specific submittals concerning this topic for reactors undergoing fuel vendor transitions in the near term. This was provided for LaSalle Unit ? in Reference 4 with a similar submittal planned for Quad Cities Unit 2 by June 1996. i This letter also confirms the tentative plans discussed in Reference 1 for  ;

transitioning to Siemen's POWERPLEX core monitoring system from the current General Electric CMC software. Attachment 1 summarizes the approach that is being used to accomplish this transition, which has not changed since the Reference 1 interaction.

Finally, Attachment 2 provides the status of the licensing plan in tabular form with updated targets for tbc remaifdag by milestones. Commonwealth Edison plans to apply 10CFR50.59 to other aspects of the reload transition a4 discussed in Reference 1.

Comed appreciates the support required from the NRR Staff in reviewing the preparatory amendments on the needed schedules.

Please contact Gary Benes of the corporate Nuclear Licensing Staff if additional information is required. Meetings or conference calls can be arranged at your Staff's convenience to facilitate the necessary reviews.

Sincerely, John B. Hosmer j Vice President - Engineering Attachments: 1. Core Monitoring Transition Plan

2. Lead Unit Transition Schedules I

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USNRC May 1,1996 3

i cc: R. M. Pulsifer - Project Manager, NRR D. M. Skay - Project Manager, NRR 1

H. J. Miller - Region lil Administrator 1 R. C. Jones - Reactor Systems Branch Chief  !

, L. E. Phillips - BWR Reactor Systems Section Chief '

i C. G. Miller - Senior Resident inspector, Quad Cities P. G. Brochman - Senior Resident inspector, LaSalle Office of Nuclear Facility Safety - IDNS l

4 k

I

T Attachment 1 .

Core Monitorina Trans; tion Plan for Quad Cities and LaSalle

. Use SPC Core Monitoring Code (POWERPLEX-II) already in cae at Dresden

. Perform thorough testing, including parallel operation with current GE Core Monitoring Code, to assure acceptable performance and validate results prior to fuel transition

. Monitor both the SPC transition (mixed) core and the sister unit's (all GE) core with POWERPLEX beginning with the transition unit's start-up at each site in 1996/1997 Lead Transition Unit (mixed core)

O Licensed and monitored with SPC ANFB correlation starting at BOC 0 input to ANFB for GE fuel conservatively determined per Reference 4 0 Operating CPR limits based on SPC methods Sister Unit (still all GE fue_l}

O Last half cycle uses POWERPLEX for power distribution calculation and GE's CPR correlation for MCPR determination

! O Operating CPR limits based on GE methods

. Simultaneous switch to POWERPLEX on both units avoids human factor concerns with dual 4 software /surveillances as well as more complex hardware cont!guration and support I

i _ _ _ _ _ . . _ _ _ _ _ _ _ . . _ . _ . . _ _ _ _ _ . _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ . _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ___

Attachment 2 -

, Lead Unit Transition Schedules .-

L2C8 Q2C15

SER on SPC Advanced Channel Topical Complete Complete Core Monitoring Transition Information Complete Complete Pceparatory Amendment (PA) Submittal Complete June 1996 i

Cycle Specific Mixed Core CPR Submittal Complete June 1996 Shipping Container Certificate Amended June 1996 June 1996 Confirm SLMCPR (or supplement PA) Complete Aug.1996 SER on PA and Mixed Core CPR Oct.1996 Feb.1997

, Current Shutdown Date 9-21-96 2-1-97 COLR / 50.59 Summary / 50.46 Report Nov.1996 March 1997 Current Estimated Start-Up late 11-96 early 4-97 Start-Up Test Report 90 days after start-up

UFSAR Update Per 10 CFR 50.71 (e)

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