ML19322E914
| ML19322E914 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 03/28/1980 |
| From: | Tauber H DETROIT EDISON CO. |
| To: | Varga S Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19322E915 | List: |
| References | |
| EF2-48-374, NUDOCS 8004040278 | |
| Download: ML19322E914 (10) | |
Text
Detroit ury t w ee, w
March 28, 1980 EF2 - 48,374 Mr. Steven A. Varga Acting Assistant Director for Light Water Reactors Division of Project Management Of fice of Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C.
20555
Dear Mr. Varga:
Reference:
Enrico Fermi Atomic Power Plant Unit 2 NRC Docket No. 50-341
Subject:
Preservice Examination of Pipina Welds Detroit Edison has not yet completed the work necessary to complete our respor.se to NRC Staff question 121.13 provided in Appendix E.5 to the FSAR.
Provided below, however, is a part of the informat ion r eques ted.
Upon cor.pletion of the preservice inspection, a complete response i) question 121.13 will be provided.
Detroit Edison requests that this item be carricJ ao an "Out-standing Review Item" in the Safety Evaluation Rops.rt which is scheduled to be published in September, 1980 Data to support UT examination impracticality on the welds in Category 1 are given in the attached table and (5) figures.
The welds all f all under Section XI Examination Cate;ory B-J.
Item B4.3.
The alternate examination proposal is PT.
Note that by the choice of materials, none of these is subject to internal cracking due to interaranular stress-assisted cor-rosion cracking (ICSCC).
The design of high energy primary containment penetrations have very limited spac-between the process pipe and guard pipe which makes it impossi'.e to perform an examination on the process f\\, a t pipe-to-flued head weld af ter the penetration is completed.
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Mr. Steven A. Varga March 28, 1980 EF2-48,374 Page 2 FSAR Figure 6.2-2 showing these penetrations is attached.
A preservice UT examination using ASME Code Section XI criteria was performed on these welds in the shop prior to final assembly.
Fermi 2 needs relief from inservice examination of these welds.
The impact of th:s relief on the overall level of plant quality and safety is negligible because a.
The process pipe in the penetration was designed to have low stress and usage factor limits, b.
The design basis of the pipe support system prevents loss of containment integrity and pipe whip damage should a break occur.
(See FSAR Section 3.6),
c.
None of the penetrations are made of material sub ject to IGSCC.
The preservice examt m.
Hon (PSI) of piping welds on Fermi 2 complies to the extent practicable with the requirements set forth in 10 CFR 50.55a(g). The basis for the Ferni 2 PSI is the 1974 Edition of Section XI through Summer 1975 of the ASME Boiler and Pressure Vessel Code.
To determine the exceptions for which relief needs to be requested, Detroit Edison engaged Southwest Research Institute (SwRI) to review isometric drawings of all Class 1 systems for feasibility of UT examination of all shop and field welds.
That survey is reported in SwRI Project 17-4992.
A copy of that report is attached to this letter.
The survey found that there are approximately 40 welds which have configurations s'ich limit examination.
These welds are i
all fitting-to-fitti ; welds, and can be divided into two major categories <
(1) weld. that cannot be examined ultrasonically and for which relief f rom the NRC must be obtained, and (2) welds that probably can be examined ultrasonically, but which may require modifications to procedures or the construction of special calibration blocks. There are 9 welds in Category 1 which SwRI believes cannot be examined ultrasonically because of the physical configuration of the fittings. These welds are listed on Table 1 (attached). The remainder of the welds are included in Category 2.
Of the'se welds, approximately 20 are between fittings whose geometry allows only a partial ultrasonic examination.
About 40 move welds probably can be exam,ined at least from one side, but may require calibration blocks separate from those of associated piping. About 20 welds involve an ultrasonic examination which may be performed from the penetration side of these welds.
Mr. Steven A. Varga March 28, 1980 EF2-48,374 Page 3 The isometrics used as the basis for this study should show all problem areas due to piping configuration.
As the actual examination of these welds gets underway, additional requests for relief will likely be required due to access limitations.
The number of these additional requests should be small because accessibility to welds was a design requirement for Class 1 systems.
Very truly yours, Attachments cc:
D. E. Howell L. L. Kintner i
1 1
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= - _ -
March 28,19m j
'EF2-48,374 1
TABLE 1 - i:XAMINATION EXCEPTIONS FOR CLASS 1 WEI.DS SURVEY REPORT ISOMETRIC ALTERNATE WELD NUMBER SYSTEM PACE (1)
FIGURF (2)
!!ATI:R I Al.
LOCATION (3)
DESCRIPTION EXAMINATION FH-ii21-2336-llWG Feedwater, 093 A-14 Carbon 0.C.
Weld between two 20" PT Loop A Steel check valves FW-N21-2336-lWK Feedwater, 125 A-15 Carbon 0.C.
Weld between two 20" PT Loop 11 Steel check valves FW-N21-2336-lWO2 Feedwater/
123 A-15 Carbon 0.C.
Weld between valve from PT RCIC Steel RCIC and 12" x 6" reducer FW-E51-2192-4WO RCIC 323 A-25 Carbon I.C.
Weld between steam PT Steel supply valve to RCIC and 6" x 4" reducer SW-633-3096-6WJ RWCU 331 A-26 Carbon I.C.
?!" tee with reducers PT
-6WF 331 Steel welded to two ends FW-613-3096-0W10 RWCU 340 A-26 Carbon I.C.
Weld between 6" valve.
-0W12 336 Steel to recire line and 4" x 6" reducer SW-C41-2340-(27)
SLCS 373 A-28 Type 316L I.C.
Welds to special 2" PT St ainless Adaptor Sleeve for Steel RPV Nozzle HlO (1) Scuthwest Research Project 17-4992, Table 2 (2) These figures from the (preliminary) inspect ion plan are att ached to this letter; wells requiring relief have been highIighted.
(3) OC=outside primary containment; IC=inside primary containment
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