ML19341B793
| ML19341B793 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 02/20/1981 |
| From: | Bayne J POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | Eisenhut D Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0619, RTR-NUREG-619 JPN-81-12, NUDOCS 8102270598 | |
| Download: ML19341B793 (2) | |
Text
POWER AUTHORITY OF THE STATE OF NEW YORK to COLUMaus CIRCLE NEW YORK. N. Y. too19 (212) 397 6200 G ECR,G,E T stamv one=avn.a o,, ice, rausters
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THOM AS R FREY Director of Nuclear Reactor Regulations "lC;'* 'c;",'.',',"
U. S. Nuclear Regulatory Commission Washington, D. C.
20555 Attention:
Mr. Darrell G. Eisenhut, Director Division of Licensing Office of Nuclear Reactor Regulation
Subject:
James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 NUREG-0619, "BWR Feedwater Nozzle and Co.itrol Rod Drive Return Line Nozzle Cracking"
Reference:
NRC letter from Darrell G. Eisenhut dated November 13, 1980
Dear Sir:
This letter is submitted in response to your letter dated November 13, 1980 transmitting the subject document.
The Power Authority of the State of New York (Authority) has reviewed NUREG-0619 and intends to meet the implementation dates as set forth therein, except as noted below.
The triple-sleeve spargers have been installed and the associated cladding has been removed at the FitzPatrick plant.
The Authority is currently evaluating on-line leak detection systems and the need for a low-flow controller (present installed system may_already meet the characteristics described in NEDE-21821-A).
Barring any difficulty in obtaining the required equipment,these modifications, including the re-route of the RWCU, should be completed by June 30, 1983.
Of present concern is'the ultrasonic testing (UT) require-ment in section 4.3.2.3 of the subject document.
During FitzPatrick's 1980 refueling outage, an attempt was made to UT the feedwater nozzles and safe ends. At this time high radiation fields were discovered, thus preventing examination.
The Authority is investigating this problem for possible solutions in order to perform the required examination by the next refueling outage.
However, alternate examination techniques and schedules may.be presented to the Commission.
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+ " Regarding P.rt 2 of NUREG-0619, the Authority adopts the option of re-routing the Control Rod Drive Return Line with continuous flow.
This modification would have to be completed during the next refueling outage (currently scheduled for Fall 1981) which would be the only scheduled outage of sufficient duration prior to June 1982.
However,the time available to support installation during the next refueling outage is not sufficient for engineering, design and procurement.
This problem is compounded due to the long lead time for qualified equipment and the limited manpower available as a result of the various other requirements currently being implemented (e.g.;
TMI, RPS Power Supply, Fire Protection, Mark I Long Term Pro-gram, Scram System Modifications, Equipment Qualification).
. Consequently the CRD modifications will be completed during the subsequent refueling outage tentatively scheduled for the first quarter of 1983.
In the interim, the Authority will J
attempt to install the modifications as soon as possible and will continue to perform 100% ultrasonic testing of the stainless steel portion of/the CRDRL in accordance with NUREG-0313.
t, should you have any questions, please do not hesitate to contact us.
Very truly yours, h.k.
J.
P. Bayne Senior Vice President Nuclear Generation i
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