ML19320D561
| ML19320D561 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 07/03/1980 |
| From: | Pasternak R POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| IEB-80-08, IEB-80-8, JAFP-80-540, NUDOCS 8007210526 | |
| Download: ML19320D561 (4) | |
Text
rn POWER AUTHORITY OF THE STATE OF NEW YORK
- ~ james A. FITzPATRICK NUCLEAR Pt*v? HR PLANT A
RAYMOND J. PAsTERNAK P.O. BOX 41 1
Resident Menager Lycoming.New York 13093 315-342-3840 July 3, 1980 SERIAL:JAFP 80-540 Boyce H. Grier, Director United States Nuclear Regulatory Commission i
Region I j
631 Park Avenue King of Prussia, PA.
19406
SUBJECT:
NRC I&E BULLETIN N0. 80-08 Examination of Containment Liner Penetration Welds
Reference:
Letter from PASNY, Paul J. Early to Director of Nuclear Reactor Regulation, Thomas A. Ippolito, Dated September 10, 1979 (Serial No. JPN-79-57)
Dear Mr. Grier:
The FitzPatrick Plant staff has completed a review of the subject Bulletin. Presented below is the response to each of the reoutred actions in the same order as presented in the Bulletin.
1)
The FitzPatrick Plant utilizes a number of containment pene-trations of the flued head design as described in the subject Bulletin.
2) a)
With respect to the applicable ASME Code, inspection of the field welds joining the assembled penetration internals and the penetration sleeve was governed by ASME III,1968 with Sumer 1968 addenda.
b)
The welds of concern joining the assembled penetration internals and the penetration sleeve were tested by using an approved liquid penetrant procedure with the exception of the main steam line penetrations (X7A through X7D), which were magnetic particle examined.
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July 3, 1980
.,Boyce H. Grier, Director United States ~ Nuclear Regulatory ' ommission
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Subject:
NRC I&E BULLETIN 80-08 Page 2) c)
For each of the nineteen (19) containment penetrations of concern, the weld joints are butt type and no packing rings were used. With respect to pipe material, as indicated in the JAFNPP FSAR, Section 5.2.3.1 indi.ates the pipe material conforms to ASME SA-333, Grade 1 except as modified by drop weight or Charpy V-no~ch impact tests as required by sub-section B of the ASME Boiler and Pressure Vessel Code,Section III, Nuclear Vessels. All material for pressure parts meets the Code NDTT requirement as determined by drop weight testing per ASTM E 208 or Charpy V-notch testing per ASME SA-370.
Tabulated below are the nineteen (19) penetrations, the service description and nominal OD of the penetration sleeve (pipe):
Penetration Nominal Size Number Service Description (Inches 00)
X7A Main Steam 37 X78 Main Steam 37 X7C Main Steam 37 X7D Main Steam 37 X8 Condensate Drain 14 X9A Feedwater 31 X98 Feedwater 31 X10 Steam to RCIC Turbine 14 X11 Steam to HPCI Turbine 22.75 X12 Shutdown Supply to RHR Pumps 32.5 X13A RHR Return 37.1 X13B RHR Return 37.1 X14 RWCU Supply to Recirc Pumps 18 X16A Core Spray Pump Discharge 20 X16B Core Spray Pump Discharge 20 X17 RPV Head Spray 10.79 X36 CRD Return 6.625 X41 Recirc Loop Sample 4.5 X42 Standby Liquid Control (Poison Injection)4.5
r Boyce H. Grier, Dir:ctor July 3, 1980 United States Nuclear Regulatory Commission JAFP 80-540 N 2
Subject:
c NRC I&E BULLETIN N0.-80-08 Page '
2) d)
As indicated in paragraph 2) b) above, non-destructive exam-inations of the welds of concern were completed.
- However, review of QA and construction records concerning the extent of repairs and description of defects encountered during examination or repair continues. The plant staff expects this review to be completed and an updated response submitted within 30 days.
3)
As noted in paragraph 2) a) above, examination of the weld joints of concern was governed by ASME III,1968 with Summer 1968 addenda.
A review of the governing code has been conducted by the architect-engineer. As a result of this review, it is noted that the architect-i engineer considers the welds of concern to be Category D welds as definediin paragraph N-461 (d). The architect-engineer also notes that pDagraph N-1350 of the code states:
" Welded joints of Categories C and D as defined in N-461 shall be fully radiographed if a radiographab'e joint detail is used.
If a nonradiographable joint detail is used, it shall be examined by the ultrasonic method in accordance with N-625, or by a magnetic particle method i
in accordance with N-626, or by a liquid penetrant method in accordance with N-627."
As a result, the FitzPatrick Plant considers that the liquid penetrant and the magnetic particle examinations of the weld joints of concern met the applicable code requirements.
In addition, a Level III radiographer of the architect-engineer's staff reviewed the drawings associated with the welds of concern and concurs that no meaningful radiographic examination was possible as a result of the geometric configurations and the restricted access to the weld ID.
In general, access to this area is eitner extremely limited or the weld is totally inaccessible due to the installation of thermal insulation and/or the presence of pipe anti-whip rings.
The FitzPatrick Plant staff further notes that in the Authority's transmittel of September 10, 1979, referenced above, concerning the ISI program, that primary containment penetration welds associated with high energy steam or water containing piping greater than 3 "
nominal pipe size would be subjected to a surface examination. As noted in the' ISI program submittal, this examination exceeds the code requirements in some cases but is considered necessary because of the importance of the integrity of the primary containment boundary.
Very truly yours, [/
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RJP:VC:brp RAYM0ND J. PASTEPNAK RESIDENT MANAGER Attachment - Distribution List I
July 3, 1980 qAFP80-540
- -DISTRIBUTION:
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Director, Division of R'eactor Construction Inspection
. George T. Berry, PASNY, NY0 G. M. Wilverding, PASNY, NY0 J. P. Bayne, PASNY, NY0 J. F. Davis, PASNY, NY0 A. Klausmann, PASNY, NYO M. C. Cosgrove, PASNY, JAF R. Baker, PASNY, JAF W. Fernandez, PASNY, JAF Document Control Center 1
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