ML20010G360
| ML20010G360 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 09/10/1981 |
| From: | Bayne J POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | Ippolito T Office of Nuclear Reactor Regulation |
| References | |
| REF-GTECI-A-10, REF-GTECI-RV, RTR-NUREG-0619, RTR-NUREG-619, TASK-A-10, TASK-OR JPN-81-68, NUDOCS 8109150619 | |
| Download: ML20010G360 (3) | |
Text
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POWER AUTHORITY OF THE STATE OF NEW YORK 10 CoLUMeus CIRCLE NEW YORK. N. Y.10019 (212) 397.6200 CEORGET. BERRY OPE R 4 TI N G OFFICER TRUSTEES JOHN S.DYSON JOHN W. BOSTON P
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oEORoE L.iNorttS JOSEPH R. SCHMIEDER viC E CMalR M AN PRE DE
& CHIEF RICH ARD M. FLY N N nosERri.MittONzi September 10, 1981 IEDo!'"*CE^1 iu=1 r R E D ERiC x R. c'^"
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& GENERAL COUNSEL Director of Nuclear Reactor Regulation N
U.S.
Nuclear '.egulatory Commission Washington, D.C.
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T b(bu Attention:
Mr. Thomas A.
Ippolito, Chief N
Operating Reactor Branch No. 2 7
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Division of Licensing g1 4
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Subject:
James A. FitzPatrick Nuclear Power P$ ant
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Docket No. 50-333 C
Implementation of Unresol'ied Safety Isdtio/ 4 t A-10, BWR Nozzle Cracking
References:
1.
Bayne (PASNY) to D.G. Eisenhut (NRC) 2.
July 13, 1981 letter T.A.
Ippolito (NRC) to G.T.
Berry (PASNY)
Dear Sir:
Reference 1 provided to the Commission information regarding the implementation of NUREG-0619, ("BWR Feedwater Nozzle and Control Rod Drive Return Line Nozzle Cracking' issued by letter dated November 13, 1980) at tne Authority's James A.
FitzPatrick Nuclear Power Plant.
In Reference 2 you approved the basic approach outlined in Reference 1 and requested the clarification of one item, and additional information.
This letter responds to these requests.
Low Flow Controller Evaluation The evaluation of the existing low flow controller was performed during a January 25, 1981 plant start-up.
As a l
result, the Authority has determined that in order to meet.he l
six characteristics described in General Electric's NEDO-21821-A report (BWR Feedwater Nozzle /Sparger Final Report, February j
1980), a finer degree of flow control would be required.
By o[
changing the internal trim of the flow control valve, the y
/ D 8109150619 810910 PDR ADOCK 05000333 P
. Authority has determined that the required degree of flow control should be obtained.
The Authority plans to make this change in the upcoming outage and to verify the adequacy of this modification with a preoperational test during subsequent plant start-up.
Control Rod Drive (CRD) Modifications The Authority has re-evaluated its position regarding CRD return line re-routing and now plans to operate the system with the return line valve closed as described in Section 8.2(3) of NUREG-0619.
Required modifications will be completed during the 1983 refueling outage as per Reference 1.
Interim Methods of Operation During the period before modifications are complete, the Authority has incorporated, as part of the start-up procedure following a refueling outage, a program to flush the exhaust header.
The program also includes cleaning of the insert /
withdrawal line filters when there are indications of slow control rod movement.
These interim measures are sufficient because, compared to tne assumptions made by the General Electric Co. in their Service Information Letter (SIL) No. 200, j
the path of CRD water at the James A. FitzPatrick Plant between the exhaust header, stabilizing valve discharge and cooling water pressure control station discharge uses significantly less carbon steel piping.
i NUREG-0619, "BWR Feedwater Nozzle and CRD Return Line Nozzle Cracking" NUREG-0619 requires an ultrasonic inspection of the feedwater nozzle blend radii, safe ends, and bores every two outages.
Initial inspections were scheduled for the Spring, 1980 outage.
Extremely high radiation levels at the nozzles prevented these inspections from being conducted as planned.
The Authority is currently evaluating two alternate means for conducting this examination - decontamination of the space between the inner thermal sleeve and nozzle wall, and the use of remotely operated examination equipment.
The evaluation must consider the high radiation fields previously experienced, the ALARA program, other equipment scheduled for installation in this area during the 1983 refueling outage, and if existing clearances are adequate to accomodate remote inspection equipment.
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i If, as a result of this evaluation, it is determined that inspection is not feasible.tnis refueling outage, preparations will be made to ensure that it is conducted during the 1983 refueling outage.
Should you have any questions, do not hesitate to contact us.
Very truly yours, s
P.
e Senior Vice President Nuclear Generation' cc:
Mr.
J. Linville Resident Inspector P. O. Box 41 Lycoming, New York 13093 1
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