ML19347E063
| ML19347E063 | |
| Person / Time | |
|---|---|
| Site: | Oyster Creek |
| Issue date: | 04/09/1981 |
| From: | Finfrock I JERSEY CENTRAL POWER & LIGHT CO. |
| To: | Eisenhut D Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0619, RTR-NUREG-619 NUDOCS 8104150160 | |
| Download: ML19347E063 (2) | |
Text
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1981 Mr. Darrell G. Eisenhut, Director Division of Licensing
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Office of Nuclear Reactor Regulation Co y,
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Dear Mr. Eisenhut:
Subject:
Oyster Creek Nuclear Generating Station Docket No. 50-219 NUREG-0619 This letter is in response to your letter dated November 12, 1980 concerning the implementation requirements of NUREG-0619, "BWR Feedwater Nozzle and Control Rod Drive Return Line Nozzle Cracking".
Part I of NCREG-0619 discusses feedwater nozzle cracking and the NRC staff's requirement for implementation of the technical position. Our response to the implementation requirements is as follows:
- 1. Removal of Cladding and Replacement of Interference Fit Spargers - during the spring 1977 Oyster Creek refueling outage, the feedwater nozzles were examined and the stainless steel cladding was removed from the nozzles. The originally installed feedwater spargers were replaced with an improved feedwater sparger design which is currently acceptable to the NRC staff.
2.
Implementation of Systems and Procedural Changes - NRC recommended system changes include the installation of a low flow controller to be used to control feedwater flow over a range of flows from 0.5% to 10% and the rerouting of the discharge of the reactor water cleanup system to deliver return flow to each feedwater nozzle. The GPUN Engineering Projects Department is reviewing the two proposed system changes and our determination of the action we will take will be forwarded to you by May 1, 1981 The Oyster Creek station operating procedures are designed to minimize the injection of unheated feedwater flow. We will however review our procedures against the recommended procedure improvements outlined in NEDE-21821-02 to determine if procedure changes are necessary.
- 3. Inspection and Reporting - JCP&L will follow the recommended NRC inspection program as outlined in Table 2 of NUREG-0619. This program will commence with the UT inspection during this fall 1981 (cycle 10 reload) outage. The visual inspection will be performed during the cycse 11 reload outage and the routine PT will be performed during the cycle 13 refueling outage.
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Jersey Central Power & Light Company is a Member of the General Pubbc UtMt,es System
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Mr. Darrell G. Eisenhut To meet the recommended reporting requirements, JCP&L will submit a report within 6 months of completing any outage in which an inspection was performed. This report will contain the required information as outlined in NUREG-0619 Part I, paragraph 4.4.3.1(2).
As discussed in Part ll of NUREG-0619 there is no requirement that the control rod return line at Oyster Creek be rerouted; However we are considering several modi f ications that may ef f ect this system. Our f inal decision on any changes to the CRDRL will be addressed in our May 1, 1981 submittal.
Should you have any questions concerning this letter, please contact Mr. Jim Knubel, BWR Licensing Manager at 201-455-8753.
Very truly yours, Y
Ivan R. Fin ock Jr.
Vice President h
Sworn and affirmed before me on this 9
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