IR 05000271/1981021
| ML20040B146 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 01/06/1982 |
| From: | Mcbrearty R, Lester Tripp NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20040B142 | List: |
| References | |
| 50-271-81-21, NUDOCS 8201250209 | |
| Download: ML20040B146 (8) | |
Text
l
.
.
U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT Region I Report No. 50-271/81-21 Docket No. 50-271 License No. DPR-28 Priority Category A
Licensee: Vermont Yankee Nuclear Corporation 1671 Worcester Road Framinoham, Massachusetts 01701 Inspection at: Vernon, Vermont Inspector:
[8- [F C [%h
/ - 1* * J'l R. A. M Brearty, Reagtor Inspector date signed Approved by:
h l!h!/3 L. E. T p, Chief, Materials and date signed Processes Section, DE&TI
_ Inspection Summary:
Inspection on November 16 - 20, 1981 (Report No. 50-271/81-21]
Areas Insgected: Routine inspection of inservice inspection data; reactor water cleanup system piping replacement, including review of welding and NDE activities; feedwater nozzle bypass leak detection system installation activities.
The inspection involved 37 inspector-hours on site by one regional based inspector.
Results:
No items of noncompliance or deviations were identified.
8201250209 820108 PDR ADOCK 05000271
_.
_ ____ ____________________ _ ______-____
.
.
Details 1.
Persons Contacted Vermont Yankee Nuclear Power Corporation (VY)
R. Jeffrey, Engineer - Data Control
- R. J. Kenney, Engineer - Assessment Coordinator
- W. M. Limberger, Plant ISI Coordinator
- W. Murphy, Plant Manager J. P. Pelletier, Assistant Plant Manager D. Phillips, Technical Assistant
- D. Reid, Engineering Support Supervisor Yankee Atomic Electric Company (YAEC)
L. Bozek, QA Coordinator M. Gilmore, Associate Engineer
- J. Lance, Senior NDE Engineer - YNSD
- T. Rennell, Engineer - ISI Mercury Company of Norwood J. J. Duquay, Site QA Supervisor P. McAuliffe, Welding Supervisor M. Trombley, Project Manager Hartford Steam Boiler
- R. L. Lane, Authorized Nuclear Inspector
- Denotes those present at exit interview.
2.
I_nservice Inspection (ISI) Data Revi_ew The inspector reviewed selected ISI data to ascertain that the data were complete and that indications were properly recorded, evaluated and dispositioned by the licensee.
Data associated with the following were included in the inspector's review:
Recirculation System Weld N2BSE
- Data Sheet #1-H, Liquid penetrant examination on 10/24/81.
- Data Sheet #1-I, visual examination on 10/30/8. _.
.. - -
_ _ _
- - _.
-
.
-
.
.
.
i
'
\\leld 24A
.
- Data Sheet #VT-11A, visual examination on 10/26/81
- Data Sheet #11-B, straight beam (0' ) ultrasonic examination on
,
i 10/26/81
- Data Sheet #11-E, Shear wave (45' ) ultrasonic examination on 10/27/81
,
Weld 40
.
- Data Sheet #12-8, O' ultrasonic examination on 10/26/81
- Dzta Sheet #12-C, O' ultrasonic examination on 10/26/81
- Data Sheet #12-D, 45' ultrasonic examination on 10/26/81
. Weld 40A
- Data Sheet #13-A, visual examination on 10/24/81
- Data Sheet #13-E, 45' ultrasonic examination on 10/26/81 Weld C-7A g
- Data Sheet #37-B, liquid penetrant examination on 11/6/81
- Data Sheet #37-B Supplement, liquid penetrant examination on 11/9/81 C_ ore Spray _ System
'
Weld MF6A
,
- Data Sheet #7-H sheet 1 and 2, liquid penetrant examination on 10/23/81 and 10/26/81 respectively
- Data Sheet #7-I, ultrasonic thickness measurement on 10/23/81 Mainsteam System Hanger MS-2, Mainsteam "A"
.
- Data Sheet #45-A, visual examination on 10/26/81
- Data Sheet #45-B, visual reexamination on 11/9/81 Hanger MS-13, Mainsteam "3
.
- Data Sheet #46-A, visual examination on 10/26/81
- Data Sheet #46-B, visual reexamination on 11/9/81 Hanger MS-30, Mainsteam "D"
,
Data Sheat #47-A, visual examination on 10/26/81
-
- Data Sheet #47-B, visual reexamination on 11/9/81 feedwater System Hanger FW-12, Feedwater "B" i
.
- Data Sheet #50-A, visual examination on 10/22/81 l
Data Sheet #50-B, visual reexamination on 11/9/81
'
-
..
W i
_
l
, - - _,.
--- y
-
.-
. -, _
_ _ -. _ _ _.. - _ _ _.. _ _ _ _ _ _ _.. _. _ _
-
-
_
-. _ __
.
j
.
.
i
Vessel Stabilizer Brackets Bracket "A" at O' azimuth position
.
- Data Sheet #220-A, visual examination on 11/2/81 Bracket "B" at 90' azimuth position
,
.
!
Data Sheet #3-1A, visual examination 10/31/81
-
- Data Sheet #3-1C, visual reexamination on 11/9/81 Bracket "C" at 180' azimuth position
.
- Data Sheet #221-A, visual examination on 11/2/81
,
Data Sheet #221-8, visual reexamination on 11/9/81
-
a Bracket "D" at 270' azimuth position
.
- Data Sheet #3-2A, visual examination on 11/2/81
,
- Data Sheet #3-2C, visual reexamination on 11/9/81 CRD Scram Discharge Volume Header Hcnger H-17
.
- Data Sheet #97-A, visual examination on 10/20/81
- Data Sheet #97-A Supplement, visual reexamination on 11/9/81 Service Water Piging Hanger H-59
.
- Data Sheet #117-A, visual examination on 10/20/81
- Data Sheet #117-B, visual reexamination on 11/11/81 Residual Heat Removal Sy_ stem Hanger HD-188D
.
- Data Sheet #212-A, visual examination on 10/28/81
- Data Sheet #212-B, visual reexamination on 11/12/81 Reactor Core Isolation Coolin_g_ System Weld F-1C
- Data Sheet #34-B, O' ultrasonic examination on 10/30/81
- Data Sheet #34-C and #34-0, 45' ultrasonic examination on 10/30/81
- General Electric data form number 1418 dated 11/21/74 i
The inspector's review of the above indicated that the recorded indica-tions were properly evaluated and dispositioned.
In the case of visual examinations which disclosed loose parts, a reexamination verified that the unacceptable condition was corrected.
The inspector noted that SUS dual element transducer, S/N E42 was used.
- to perform the 45' shear wave examination of weld number 40 on the recirculation system 12 inch diameter ring header in which a flaw indication was detected and evaluated by the licensee.
The transducer's
.
.-
-
-. -. - -
-
-
-
.-
_
.
_ =,
- - _ _
-_
-
-. _ -
-
_ -
.
.
sound entry angle was measured and found to be 42' in a carbon steel i
IIW standard test block. At the inspector's request, the licensee l
measured the sound entry angle in the stainless steel calibration
'
block S/N VY-7, which was used to calibrate the ultrasonic equipment for the original weld examination.
The entry angle in the stainless steel block was found to be 45', a 3' difference when compared to the carbon steel results.
The licensee calculated the location of the flaw indication source in weld 40 and found that, because of the short metal path involved, the 3' difference made no significant difference in the flaw location in the weld.
The licensee considered the original evaluation and disposition as valid and the inspector stated that he agreed with that judgement.
The licensee stated at the exit interview i
!
on November 20, 1981, that he would procure a stainless steel standard
!
test block to measure the sound entry angle of transducers which were l
to be used on stainless steel material.
No items of noncompliance were identified.
3.
Feedwater Nozzle Bypass Leak Detection System Installation l
NUREG-0619 requires that interference fit feedwater spargers be replaced with a new design double or triple sleeve piston ring sparger thermal sleeve by July 1983 to preclude reinitiating cracks in the feedwater nozzle blend radius area.
In his response to the NRC regarding the NUREG requirements on feed-water sparger replacement, the licensee presented arguments for the retention of the present interference fit spargers at Vermont Yankee.
The spargers were installed in 1976 af ter feedwater nozzle cracking was detected.
Liquid penetrant examination of the irner blend radius surface of all four nozzles was performed in 1977, 1979 and in 1981.
The records indicate that no significant penetrant indications were detected by any of the examinations.
The licensee is presently installing a leak monitoring system to monitor leakage past the thermal sleeve seal into the annulus area between the thermal sleeve and feedwater nozzle.
i The monitoring system will consist of the following:
Four thermocouples welded to the outside of each feedwater nozzle using a low heat input capacitive discharge welding technique.
One thermocouple will be mounted at the top of the nozzle (O' )
.
and the remaining three thermocouples will be attached at the bottom (180') of each nozzle.
The thermocouple lead wire will be routed from the nozzles to a
.
junction box to be located at the top of the shield wall.
e i
-. - -
-
-
.,- ~--.-.-- --
_
-.
--
.
-
_
.
_
__. _.
______ _ _ _
-. _ _
_
. _ _ _ _
_.
_
_ _ -
..
_ _
.
.
i
.
'
Cables from the junction box will go to an existing drywell electri-
.
i cal penetration out to a recorder to be placed in the reactor building outside the drywell.
i
.
The inspector reviewed licensee records, reports and documentation
]
related to the leak detection system installation to ascertain that
'
ASME Code and regulatory requirements were met.
i
The inspector's review included the following:
!
]
Engineering Design Change Request (EDCR) No. 81-27
.
EDCR 81-27, Change 3
.
I Memorandum dated 11/19/81 from K. R. Willens to R. E. White
.
i Welding procedure no. XYA-01-101, Revision 0, dated September 1981
.
Metallurgical report no. ADV-13-001, Revision 1, dated October 1979,
.
prepared by Nutech, Incorporated.
!
Code Case N-252 permits the use of the low energy capacitive discharge
method of welding for temporary or permanent attachment of strain
gages, thermocouples and similar instrumentation to ASME Section III,
'
Division 1, and Section XI components and supports providing that certain conditions are met.
Regulatory Guide 1.147 states that the use of the code case is acceptable to the NRC, but imposes an additional
ccndition on the user.
Change 3 to EDCR no. 81-27 was issued to
'
comply with the regulatory guide.
In addition to the above the inspector performed a visual inspection j
of thermocouples welded to feedwater nozzle number N4B and of the
junction box mounted above the nozzle in the drywell.
l The inspector found that three of the required four thermocouples were i
welded in place, one at the O' location and two at the 180' location.
The nozzle attachment surface was properly prepared for the spot welding operation and the three thermocouples were attached in compliance
with applicable sections of procedure no. XYA-01-101.
The thermocouple
,
leads were routed from the nozzle, up the reactor vessel wall to the junction box to preclude interference with the performance of future nozzle inservice inspection activities, j
No items of noncompliance were identified.
4.
Reac_ tor _ Water Clean-up_ System (RWCU) Piping 3 placement During the 1930 refueling outage a leak was observed in RWCU piping inside the drywell.
Ultrasonic examination of some of the 4 inch dia-meter piping welds in the system disclosed indications of probable intergranular stress corrosion cracking (IGSCC) of the heat affected
.
-
.
!
-
,-.
,
,-c
--~~..,._--c,,,mn-
-~
.. ~. - -. -. _ - - - -. -, - _ -
-
.. - -
-
- _.
._
_. _ _.
-______
____
_ -. __
_ _ -. -
__ __
_
_
.
.
j l
!
The licensee elected to replace most of the piping in the system and commenced the work during the present refueling outage.
a I
!
The inspector reviewed the applicable welding procedure, welding procedure qualification records, selected welder qualification records,
QC records for selected welds, inspection personnel certification records, material certification records and, additionally, performed a walk-through inspection of the work areas.
l The above was done to ascertain compliance 'with ASME code and regulatory requirements.
.
The following were included in the inspector's review:
i Material certification records for a 3" schedule 160 90" elbow,
.
heat code E-1183 j
.
Quality control records for welds 2A-7, 2A-8, 2B-9A and 28-10 i
Welder qualification records for welder stamp number 135, 194 and
.
i 276
)
Nondestructive examination personnel certification records i
. Welding Procedure Specification (WPS) number AZ Procedure Qualification records for WPS AZ
.
]
As part of the walk through inspection of the "A" and "B" pump room the inspector examined the above listed welds for surface finish, j
appearance, weld reinforcement, undercut and obvious defects.
l
!
The records indicated that the Guyon Alloys supplied material met the j
applicable requirements of the material specification, ASME SA 403 WP 304 Seamless,Section III, Class 1,1977 Edition through Summer 1979
'
Addenda, with a 0.025"4 maximum carbon content An applicable intergranular
,
a corrosion test, in accordance with ASTM-A-262, Practice E, Copper -
Copper Sulfate Sulfuric Acid Test, was done on the material by Spectrum
"
Laboratories, Inc.
,
The weld QC records verified that inspections were done as required
~
during weld fabrication and that liquid penetrant examination of the root pass and of the final surface vas satisfactorily completed by a
,
j properly qualified individual.
At the exit interview on Novembs.r 20, 1981, the inspector advised the licensee that an update of the status of the Battelle Laboratory
'
reports on the RWCU, and an update of LER 81-16 dated 7/22/81 would j
complete licensee actions on unresolved item 50-271/81-12-03.
J
.
- -
-
_.
.
. _.
-__ _...
--
. -. - _
_
.
_
.
.
No items of noncompliance were identified.
5.
Exit Interview At the conclusion of the inspection on November 20, 1981, the inspector met with licensee representatives.
In addition to those denoted in paragraph 1, the meeting was attended by Messrs. W. Raymond and S.
Collins, NRC Senior Resident Inspector and NRC Resident Inspector respectively.
The inspector summarized the purpose and scope of the inspection and the findings, t