ML20134G247
| ML20134G247 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 08/20/1985 |
| From: | Brons J POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | Vassallo D Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19269B593 | List: |
| References | |
| RTR-NUREG-0619, RTR-NUREG-619 GL-81-11, JPN-85-65, NUDOCS 8508230193 | |
| Download: ML20134G247 (4) | |
Text
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123 Mas Street a
WNte Plains, NewWrk 10601 914 681.6240
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& Authority
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August 20, 1985 JPN-8 5 -65 Director of Nuclear Reactor Regulation U.S.
Nuclear Regulatory Commission Washington, D.C.
20555 Attention:
Mr. Domenic B. Vassallo, Chief Operating Reactors Branch No. 2 Division of Licensing
Subject:
James A.
FitzPatrick Nuclear Power Plant Docket No. 50-333 NUREG-0619 BWR Feedwater Nozzle and Control Rod Drive Return Line Nozzle Cracking
References:
1.
NUREG-0619, "BWR Feedwater Nozzle and Control Rod Drive Return Line Nozzle' Cracking", dated November, 1981.
2.
NRC letter to All Operating Reactors, dated February 20, 1981. (Generic Letter 81-11).
3.
GE Report NEDE-21821-A, " Boiling Water Reactor I
Feedwater Nozzle /Sparger Final Report",
February, 1980.
4.
NYPA Letter, J.P.
Bayne to D.B.
- Vassallo, dated July 7, 1983 (JPN-83-64).
5.
NRC Letter, D.B. Vassallo to J.P.
Bayne, dated August 25, 1983 ([[::JAF-83-290|JAF-83-290]]).
I
Dear Sir:
This letter addresses the requirements discussed in References 1 and 2.
NUREG 0619 (Ref. 1) required the operating reactors to install a low flow feedwater controller with the characteristics described in GE Report NEDE-21821-A, Subsection 3.4.4.3 (Ref. 3),
l and to re-route the reactor water clean-up system (RWCU) return flow to all feedwater. Lines.
Generic Letter 81-11 (Ref. 2) later
~
clarified that if a fracture mechanics evaluation predicts an end of life crack size of less than one inch, a new low flow
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w controller need not be installed.
In addition, in discussing the generic letter, the NRC advised GE that the necessity of RWCU system re-route would be considered on a plant unique basis if an ASME Section III Sub-Section NB fatigue analysis showed the usage factor to be less than 1.0.
The Authority has performed these analyses for the FitzPatrick Plant as discussed below. provides a plant specific fracture mechanics assessment of the FitzPatrick feedwater. nozzle with the existing low flow feedwater controller to show-compliance with Reference 2 and Reference 3.
The evaluation considered an initial crack depth of 0.25 in. as specified in Reference 2.
The results show that stress cycling from conservative temperature and flow profiles, when added to those resulting from other crack growth phenomena, such as startup and shutdown cycles, do not result in the growth of an initial 0.25 in, crack to greater than 1" during the remaining life of the plant.
The existing controller is, therefore, acceptable based on the requirements of Reference 2.
This report (Attachment 1) contains information which the General Elecric Company customarily maintains in confidence and withholds from public. disclosure.
The information has been handled and classified as proprietary to General Electric, as indicated in the attached affidavit (Attachment 2), and we hereby request that NEDC-30799-P be withheld from public disclosure in accordance with the provisions of 10CFR 2.790. provides the results of a rapid cycling fatigue analysis for the FitzPatrick feedwater nozzle.
This analysis shows the maximum usage to be less than 1.0 with seal refurbish-ments required every sixteen (16) years.
The Authority is, however investigating alternatives to seal refurbishment, including a leak detection system. provides an. evaluation of re-routing the discharge of the RWCU to all feedwater nozzles.
This analysis indicates that the reduction in feedwater nozzle fatigue usage associated with RWCU re-route is sufficiently small that RWCU re-route is not considered to be justified.
Regarding the control Rod Drive Return Line (CRDRL), Nozzle, the Authority has opted to implement the requirements of NUREG 0619, Section 8.2(4) - Cut and Cap the CRDRL Nozzle Without Re-Routing the CRDRL.
In accordance with NUREG 0619, Section 8.1(4), this option is acceptable for FitzPatrick since it is a 218-inch BWR/4.
The Authority has cut and capped the FitzPatrick CRDRL nozzle during the 1983 refueling outage (see Refs. 4 and 5),
and has completed the following additional modifications required by this option during the 1985 refueling outage:
1.
Installation of equalizing valves between the cooling water header and the normal drive movement exhaust water header; and
- 2. Removal of carbon steel piping in the flow stabilizer loop.
e It!i.s our understanding that with the exception of the inspections required by Table 2, NUREG.0619, the actions summarized above complete conformance with the requirements of NUREG 0619 for the James A.
FitzPatrick Plant.
If you have any questions on the above, please contact Mr. J.
A.. Gray, Jr. of my staff.
Very truly yours,
.2 cIEE C.
Brons Senior Vice President Nuclear Generation J
cc:
Office of the Resident Inspector U.S.
Nuclear Regulatory Commission P.O. Box 136 Lycoming, New York 13093 l
?
T
/
t ATTACHMENT 1 -TO JPN-85-65 General Electric Report, NE DC-30799-P James A.
FitzPatrick Nuclear Power Plant Feedwater Nozzle Fracture Mechanics Analysis to Show Compliance with NUREG-0619 December, 1984 New York Power Authority James A.
FitzPatrick Nuclear Power Plant Docket No. 50-333 l
August 20, 1985}