ML20064M618
| ML20064M618 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 08/31/1982 |
| From: | Rausch T COMMONWEALTH EDISON CO. |
| To: | Eisenhut D Office of Nuclear Reactor Regulation |
| References | |
| 4767N, NUDOCS 8209080049 | |
| Download: ML20064M618 (3) | |
Text
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'O Commonwrith Edison 3 ' one First National Plaza. Chicago, Illinois (s
Address Reply to: Post Ofhce Box 767 v
Chicago, Illinois 60690 Augus t 31, 1982 Mr. Darrell G.
Eisenhut, Direc to r Division of Licensing U.S. Nuclear Regulatory Commission Washington, DC 20555
Subject:
Quad Cities Station Unit 2 Refueling Dutage Schedule Change NRC Docket No. 50-265 Dea r Mr. Eisenhu t:
Due to a lengthy forced outage early in the Quad Cities Unit 2 current cycle, Commonwealth Edison has had to reschedule the forthcoming Quad Cities 2 refueling outage so that acceptable fuel utilization will be maintained.
The next refueling outage (end o f cycle 6) is now scheduled to begin on approximately September 10, 1983 (was February 27, 1983) and the Cycle 7 outage is now scheduled to begin on approximately March 2, 1985 (was September 30, 1984).
Although these schedules are not subject to NRC approval, we are providing this information at this time in order to document the schedule effect this change will have on certain outage related projects.
A.
Mark I Containment Modifications The revised Orders transmitted in the January 19, 1982 D.
Vassallo letter to L.
DelGeorge require the completion of major modifications and all remaining modifications prior to the start o f Cycle 7.
We intend to comply with this requirement, and no revision of the order is neeeded.
We do wish to point out that the start of Cycle 7 date is now approximately November 1983, not April or May 1983 as noted parenthetically in the respective April 6, 1982 and December 16, 19 81 T. J. Rausch letters to D.
Vassallo and H. R. Denton.
The plant unique analyses are also scheduled for submittal by the start of Cycle 7.
B.
Reactor Protection System (RPS) Power Monitoring System Modifications In the December 11, 1980, R. Janecek letter to T.Ippolito, we indicated that we expected to install this modification during the Ma rch, 1983 outage.
This date should now be noted to be December, 1983, as already docketed in the T. Rausch letter to D. B. Vassallo letter dated July 23, 1982 concerning this subject.
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C.
Barrier Fuel Ramp Tes t t
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The end of Cycle 6 barrier fuel demonstration test now may tre held at a later date due to the earlier forced outage.
We will provide the June, 1982 information committed to in the December 3,
1981 L. De1 George letter to D.
Eisenhu t (items 1 and 4) by l
Oc tobe r, 19 82.
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D.
Control Rod Drive (CRD) Insert - Withdraw-Line Seismic Supports (Inside'Contalment) i l
The remaining inside-drywell CRD Insert-withdraw Line seismic support modification will still be completed by the next l
refueling outage as described in the T. Rausch letter to J.
Keppler dated December 17, 19 81.
1 i
E.
Repair of Non-Isolable IGSCC-in 'the Clean-up System In the January 26, 1982 meeting with the NRC at the Region III Offices, Commonwealth Edison presented the report entitlted
" Quad Cities Station Unit' 2 Reactor Water Clean-up System Temporary Repair of Non-Isolable IGSCC".
We have reviewed the i
modifications associated with this temporary repair and have i
determined that our conclusions regarding safe operation with I
this repair remain completely valid, considering the increased operating cycle time.
We also believe that this outage schedule l
change does not alter the conclusions of the February 19, 1982, NRC SER concerning this repair.
I The following additional items scheduled for the next refueling outage' are also related to NRC requirements and i
commitments and are listed below for your information-1 1.
Environmental Qualification o f Electrical Equipment --
Component Replacement.
2.
4 KV Degraded Voltage Relays.
3.
FW Sparger and CRDRL Investigations -- FW Nozzle Temperatures; CRDRL Valve Leak Tests and Piping Inspection s.
j.
4.
125 VDC Panel Separation -- Long-term. fix.
5.
Fire Protection Saf e-Shutdown Modifications. -- RHR,
RHRSW, DG Mods and Associated Circuits.
6.
TMI Items --
a.
Finish HRSS (non-essential items).
b.
New Hydrogen Monitors (Gas Chromatographs).
7.
IE Bulletin 79-14 hangers and supports.
8.
Inspect Core Spray Spargers.
9.
Insepet Core Spray Piping in the Drywell.
- 10. Integrated Primary Containment Leak Rate Test.
i 1
a.- By copy of this letter, Region III is also being notified o f this change in refueling outage schedule, and our conclusions concerning item E.
Please' address-any questions you may have concerning this matter to.this office.
One (1) signed original and thirty-nine (39) copies of this letter are provided for your use.
Very truly yours, 24== / A~=<
- Thoma s J. Raus ch Nuclear Licensing Administrator cc:
J.
G.
Keppler, Regional Administrator RIII Inspector - Quad Cities 4767N