ML20128H258
| ML20128H258 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities |
| Issue date: | 05/21/1985 |
| From: | Thompson H Office of Nuclear Reactor Regulation |
| To: | Norelius C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| NUDOCS 8505300479 | |
| Download: ML20128H258 (1) | |
Text
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May 21, 1985 MEMORANDUM FOR:
, Charles E. Morelius, Director Division of Reactor Projects Region III FROM:
Hugh L. Thompson, Jr., Director Division of Licensing Office of Nuclear Reactor Regulation
SUBJECT:
ISI AND IST PROGRAMS AT OUAD CITIES STATION, UNITS 1 AND 2 (TIA 83-90)
In your memorandum of April 22, 1983 you requested NRR to clarify what ISI/IST program the license should follow, in that the first 10-year program period had expired and the second 10-year program had been submitted by the licensee but had not yet been approved by NRR. Task Interface Agreement (TIA) 83-90 was issued July 9, 1983 to task NRR with this undertaking.
By letter of March 20, 1985 (enclosed) following our preliminary review of the licensee's program as proposed in letters dated February 17, 1983, September 7,1984 and January 1,1985, we instructed the licensee to follow the licensee-proposed program, subject to conditions described in our letter on the subject, until our review is complete and final approval is given.
This complete NRR action on TIA 83-90.
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Hugh L. Thompson', Jr., Director Division of Licensing Office of Nuclear Reactor Regulation
Enclosure:
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WASHINGTON D.C.Sette March 20.1985 Docket Nos. 50-254/265 Mr. Dennis L. Farrar Director of Nuclear Licensing Comonwealth Edison Company Post Office Box 767 Chicago, Illinois 60690
Dear Mr. Farrar:
SUBJECT:
INSERVICE INSPECTION AND TESTING PROGRAM -
SECOND 10-YEAR INTERVAL Re:
Quad Cities Nuclear Power Station Units 1 and 2 By letters dated February 17, 1983 September 7, 1984 and January 9, 1985, you submitted a proposed inservice inspection and testing program description and requests for relief from selected ASME Code requirements pursuant to 10 CFR 50.55a(g). Although we have not completed our detailed review of your submittal, our preliminary revfew makes clear to us that your proposed srogram to implement those ASME Code requirements that you have found to le practical would increase the scope of inservice inspection and testing'for your facility beyond that currently required by your Technical Specifications. We have concluded that this upgrading of your inservice inspection and testing program will further enhance safety.
Based on our preliminary review, we agree with the detemination that it is impractical within the limitations of design, genmetry and materials of construction of component, for you to meet certiin of the specified ASME Code requirements and that imposition of those requirements would result -
in hardships or unusual difficulties without a compensating increase in the level of quality of safety. Therefore, pursuant to 10 CFR 50.55a(g)(6)(1),
we hereby grant reitef until the staff has completed its detailed review or until December 31,1o85, whichever comes first, from those inservice inspection and testing requirements of the ASME Code that you have requested. Moreover, since the scope of the inservice inspection and testing will be increased by your proposed program, and the eranting of l
this relief is based only on the impracticality of selected ASME Code requirements, we have detemined that the relief granted neither increases the probability or consequences of accidents previously considered nor decreases safety margins and that, therefore it does not involve a significant hazards consideration. Therefore, you are authortred to, and should proceed to, implement your proposed program (except where your current Technical Specifications are more restrictive).
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Mr. Dennis L. Farrar,
During the period between now and the date we complete our detailed review of your submittal, you must comply with both your existing Technical Specifications and your proposed inservice inspection and testing program.
In the event conflicting requirements arise for some components, you must comply with the more restrictiv4 requirements (e.g., shorter inspection intervals, increased number of parameters measured).
In other words, the granting of this, relief from ASME Code requirements, should not be interpreted to give you relief from any of the requirements in your existing Technical Specifications.
When our detailed review of your submittals is complete we will:
(1) issue final approval of your program (which may contain modifications resulting from the staff's review) and (2) grant relief from any ASME Code requirements that are detemined to be impractical for your facility for the duration of the inspection interval.
Sincerely, Domenic B. Vassallo, Chief Operating Reactors Branch #7 Division of Licensing cct See next page 6
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W. Dennis L. Farrar Comonwealth Edison Company Ouad Cities Nuclear Power Station, Units 1 and 2 cc:
tir B. C. O'Brien James G. Keppler President Regional Administrator lowa-111inois Gas and Region !!! Office Elect'rfc Comoany U. S. Nuclear Regulatory Comission 206 East Second Avenue 799 Roosevelt Road Davenport, Iowa 52801 Glen Ellyn, Illinois 60137 Robert G. Fitzgibbons, Jr.
Susan N. Sekuler 1 sham, Lincoln A Beale Assistant Attorney General Three First National Plaza Environmental Control Division Suite 5200 188 W. Randolph Street Chicago, Illinois 60602 Suite 2315 Mr. Nick Kalivianakis Plant Superintendent The Honorable Tom Corcoran Guad Cities Nuclear Power Station United States House of 22710 - 206th Avenue - North Representatives
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Cordova, Illinois 61242 Washington, D. C.
20515 i
1 Resident Inspector fir. Gary N. L'right U. $. Nuclear Repulatory Comission Nuclear Facility Safety 22712 206th Avenue North 1111rois Department of Cordova, Illinois 61242 Nuclear Safety 1035 Outer Park Drive, 5th Floor Chaiman Springfield, lilinois 62704 P,ock Island County Roard of Supervisors Rock Island County Court House Rock Island, Illinois 61201 l 1 bf X -- - ----- - -
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