ML20029D690
| ML20029D690 | |
| Person / Time | |
|---|---|
| Site: | Quad Cities  |
| Issue date: | 05/03/1994 |
| From: | Dyer J Office of Nuclear Reactor Regulation |
| To: | Farrar D COMMONWEALTH EDISON CO. |
| Shared Package | |
| ML20029C517 | List: |
| References | |
| GL-89-04, GL-89-4, TAC-M85762, TAC-M85763, NUDOCS 9405090285 | |
| Download: ML20029D690 (3) | |
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.A UfelTED STATES 1
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WASHINGTON. D.C. 20555-0001 May 3, 1994 Docket Nos. 50-254 and 50-265-Mr. D. L. Farrar, Manager Nuclear Regulatory Services Commonwealth Edison Company Executive Towers West III, Suite 500 l
1400 OPUS Place l
Downers Grove, Illinois 60515 l
Dear Mr. Farrar,
SUBJECT:
SAFETY EVALUATION OF THE INSERVICE TESTING PROGRAM RELIEF REQUESTS FOR PUMPS AND VALVES FOR QUAD CITIES STATION, UNITS 1 AND 2 (TAC NOS. M85762 AND M85763)
By letters dated January 7, 1993, and October 28, 1993, Commonwealth Edison i
Company (the licensee) submitted the third 10-year interval inservice testing l
(IST) program and associated requests for relief for the Pumps and Valves at j
Quad Cities Nuclear Power Station, Units 1 and 2.
The third 10-year intervals for both units began February 18, 1993.
The IST program was submitted for review and evaluation of its compliance with the requirements of the 1986 Edition of Section XI of the American Society of Mechanical Engineers (ASME)
Boiler and Pressure Vessel Code (the Code), and the plant Technical Specifications.
The staff, with technical assistance from Idaho National Engineering Laboratory (INEL), has reviewed the IST program plan, and adopts the evaluations and recommendations for granting relief or authorizing alternatives contained in the Technical Evaluation Report. (TER) prepared by INEL. The recommendations from the TER are reflected or modified in the enclosed Safety Evaluation (SE).
Relief is granted from or alternatives are authorized for the testing requirements which have been determined to be impractical to perform, where compliance would result in a hardship without a J
l compensating increase in safety, or where the proposed alternative testing l
provides an acceptable level of quality and safety.
In particular, the staff's evaluation of the proposed alternative to extend the " alert" range vibration limits for the Unit 2 high-pressure coolant injection (HPCI) pump has been modified from the TER evaluation. The alternative " alert" limits l
have been approved on an interim basis pursuant to 10 CFR 50.55a(a)(3)(ii), as l
detailed in the SE.
Certain relief requests have been approved pursuant to l
10 CFR 50.55a (f)(4)(iv) where it has been determined that the proposed alternative is in accordance with the requirements of the 1989 Edition of ASME Section XI.
A summary of relief requests and the NRC actions is provided in Table 1 of the SE.
The TER is provided as an attachment to the SE.
The IST program relief requests which are granted, authorized, or approved are acceptable for implementation provided the action items identified in Appendix A of the TER are addressed within one year of the date of this letter or by the end of the next refueling outage, whichever is later, unless another l
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Mr. D. L. Farrar period is specified.
The granting of relief is based upon the fulfillment of any commitments made by the licensee in the basis for each relief request and the alternatives proposed.
Where interim relief has been granted, the licensee should resolve the issues before expiration of the interim period.
The licensee should respond to the NRC within one year of the date of this letter, describing actions taken, actions in progress, or actions to be taken to address each of these items.
Program changes involving new or revised relief requests should not be implemented prior to approval by the NRC except as authorized by GL 89-04.
New or revised relief requests that meet the positions in GL 89-04,, should be submitted to the NRC but may be implemented provided the guidance in GL 89-04, Section D, is followed.
Program changes that add or delete components from the IST program should also be periodically submitted f
to the NRC.
This completes our review of your IST plan under TAC Numbers M85762 and M85763.
Sincerely, Original signed by James E. Dyer, Director Project Directorate III-2 Division of Reactor Projects - III/IV s
Office of Nuclear Reactor Regulation
Enclosure:
Safety Evaluation cc w/ enclosure:
See next page DISTRIBUTION:
Docket File J. Dyer E. Greenman, RIII NRC & LOCAL PDRS C. Hawes B. Dean, ED0 RIII PDIII-2 R/F C. Patel J. Zwolinski W. Russell /F. Miraglia 0GC J. Roe L. Reyes E. Jordan OPA E. Rossi G. Hill (4)
OC/LFDCB J. Lieberman ACRS (10)
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Mr. D. L. Farrar Quad Cities Nuclear Power Station Comonwealth Edison Company Unit Nos. I and 2 cc:
Mr. Stephen.E. Shelton Vice President Iowa-Illinois Gas and Electric Company P. O. Box 4350 Davenport, Iowa 52808 Michael I. Miller, Esquire Sidley and Austin One First National Plaza Chicago, Illinois 60690 Mr. Richard Bax Station Manager Quad Cities Nuclear Power Station 22710 206th Avenue North Cordova, Illinois 61242 Resident Inspector U. S. Nuclear Regulatory Commission 22712 206th Avenue North Cordova, Illinois 61242 Chairman Rock Island County Board of Supervisors 1504 3rd Avenue Rock Island County Office Bldg.
Rock ~ Island, Illinois 61201 Illinois Department of Nuclear Safety Office of Nuclear Facility Safety 1035 Outer Park Drive Springfield, Illinois 62704 Regional Administrator U. S. NRC, Region III 801 Warrenville Road Lisle, Illinois 60532-4351
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