IR 05000329/1980033
| ML19340E926 | |
| Person / Time | |
|---|---|
| Site: | Midland |
| Issue date: | 12/30/1980 |
| From: | Danielson D, Erb C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19340E925 | List: |
| References | |
| 50-329-80-33, 50-330-80-34, NUDOCS 8101160259 | |
| Download: ML19340E926 (5) | |
Text
. - _ _
. _ _ _
..
.
.
.
__..
.
l O
.
U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT i
REGION III
Reports No. 50-329/80-33; 50-330/80-34 Docket Nos. 50-329; 50-330 Licenses No. CPPR-81; CPPR-82 Licensee:
Consumers Power Company 1945 West Parnall Road Jackson, MI 49201 Facility Name: Midland Nuclear Power Plant, Units 1 and 2 Inspection At: Midland Site, Midland, MI Inspection Conducted: December 1-4, 1980
,,k r
~'
Inspector:
C. M. Erb h,dsff /fff lYw Approved By:
D. H. Danielson, Chief
/
30 /t
'
/
Engineering Support Section 2 l
Inspection Summary Inspection on December 1-4, 1980 (Reports No. 50-329/80-33; 50-330/80-34)
Areas Inspected: Observation and documentation of modifications to pressurizers and steam generators Units 1 and 2; examination of Guide Blocks and lower inter-nals Unit 1; quality documentation of certain safety related components; obser-vation of hardness results of embedded bolts for lateral snubbers attached to primary coolant pumps. This inspection effort involved 19 inspector-hours onsite by one h3C inspector.
Results: No items of nonc6mpliance or deviations were identified.
s101160 25 9
.
_
.
.
... -
. - _.
.
-
..
.
.
DETAILS Persons Contacted Consumers Power Company Personnel
- T. C. Cooke, Project Manager's Office
- D. Turnbull, MPQAD
- H. P. Leonard, MPQAD
- R. Whitaker, MPQAD
- L. R. Howell, MPQAD Other Company Personnel
- A. McClure, Quality Assurance, Bechtel
- P. C. Lahoti, Quality Assurance, Bechtel
- R. W. Shope, Supervisor, Babcock & Wilcox
- T. W. Davis, Jr., Asst. Supervisor QC, Babcock & Wilcox
- Denotes those present during the exit interview conducted on December 4, 1980.
Functional or Program Areas Inspected 1.
Steam Generator and Pressurizer Modifications, Units 1 and 2 Each of the four generators will have four level sensing nozzles installed at three different heights on the generator for a total of 12.
The work is being done by B&W Construction Company to Procedure 284A, Revision 1.
The weld is a groove weld with some fillet and is made from the outside of the vessel.
'
A half bead technique is used which eliminates the 1100 F post weld heat treat and replaces it with a two hour 400 F-500 F post weld heat treat.
The half bead technique involves one weld layer on the generator weld preparation and a weld layer on the fitting to be inserted. This level is ground so that only 50% of the layer remains. Then the fitting is inserted in the weld preparation and welding is performed. Magnetic test is performed at various times during the weld. The entire weld is made by the manual metal process using E7015A1 electrode with 350 F-450 F preheat.
The process sheets and procedures used were examined and found to be accept-able to ASME Section III and IX.
Each of the two pressurizers will have six level sensing nozzles installed by B&W Construction Company to Procedure 278, Revision 4.
The weld design is similar to the steam generator weld except that it is made from the inside of the pressurizer and involves different materials.
This weld is a dissimilar weld and an Inconel filler is used to weld the stainless fitting to the carbon steel base material.
Gas tungsten arc welding is the process used and liquid penetrant test is the NDT method-2-
.
'
unless checking the base metal when magnetic particle testing is used.
A UT test is also utilized for base material. The process sheets and procedures were found to be acceptable to the applicable ASME Section XI, 1977 Edition, Summer 1978 Addenda.
No items of noncompliance or deviations were identified.
2.
Observation of Guide Blocks on Lower Internals - Unit 2 Storage and cleanliness conditions of the lower internals were noted and found to be acceptable. A clean room and controlled access with shoe covers and coveralls were in place. Welding on Guide Block 11-450-2012-60-22 was examined. This weld, a large stainless fillet weld which established the location of the Guide Block in the core barrel, was made using the tungsten inert gas method. The weld appearance was smooth and clean indicating excellent control of the inert atmosphere while the weld was being made.
No items of noncompliance or deviations were identified.
3.
QA Documentation on Safety Related Components, Units 1 and 2 a.
A Reactor Building Spray Pump, No. 2P-64A, receiving inspection information was examined. This pump was bought to Specification 7220-M-54. An Allis-Chalmers 200 HP induction motor powers the unit.
There were three deviation requests included fcr the pump. The devia-tions were signed off by B&W Canada, the manufacturer and Bechtel who purchased the unit for Consumers Power Company. This pump is in ASME Class 2.
b.
A Makeup and Seal Injection Pump, No. 2P-58A, receiving information was examined. This Class 2 pump was manufactured by B&W to Specifica-tion 08-1130000009-05 and bore Serial No. 70360.
It also was marked National Board No. 40 and was built to ASME Section III, 1971 Edition, 1971 Winter Addenda. The material certifications, certificate of design, and tests were included in the package which appeared to be acceptable to the above ASME Code, c.
Documentation on a component cooling water heat exchanger was examined.
This heat exchanger No N-011-1B is a Class 3 item and was manufactured by Yuba Heat Transfer Corporation. The tubes in this exchanger are Cupro Nickel and were purchased to the latest revision of SB-111. The documentation included Mill Test Reports, NU.s, Travelers, Heat Treat welder qualifications, and sheets showing Authorized Inspector release.
The information included was complete and there was no evidence of noncompliance.
No items of noncompliance or deviations were identified.
.
-3-m
O
4.
Embedded Bolts for Attachment of Primary Coolant Snubbers to Concrete Wall A problem has arisen with subject bolts of various sizes, which af ter installation were hardness checked as a result of the licensee'r ontinuing investigation caused by the high hardness of the reactor pressure vessel hold down studs. Embedded bolts in sizes 2-1/4", 2-1/2", 3" and 3-1/2" bought to ASTM Specification A354, Grade BD, have shown hardness results both below and above the specified hardness range.
Tabulated below are the results to date on embedded bolts.
Heat No.
Readings Reading No. High Highest No.
Size" Bolts No. Low Lowest Readings Reading Material Spec Comments 63315 2k
17 531 L
686 L 4145 A354 BD Spec reqd Hardness 63575
164
535
675 4145 A354 BD RC 32-38 62609
24
557
688 4145 A354 BD 50415
6
571
Not given A354 BD Actual low RC 23-30 61951R1 3
16 538
693 Not given A354 BD 91196R1 3
7 522
4140 A354 BD Actual high RC 43-45 655A196 3
0
636 Not given A354 BD 51980
24
518
4142 A354 BD Total __
346 132
Below are tabulated results to date on through wall bolts.
97847
10
569
E4340 A-540 Spec Hard-B-23 Cl-3 RC 31-39 115544 2\\
0
E4340 A-540 Actual low B-23 Cl-3 range 91039 2k
6 559
E4340 A-540 RC 28-29 B-23 Cl-3 From the above table, it is evident that the material specified to ASTM A354, Grade BD, has twice as many low readings to the specified 32 - 38 RC as high readings.
.
-4-
_..
_
_ _
.
. _ -
__
_ _ _ _ -. -
.
. _ -.
-. -
..
-
1.
i e
The material to ASTM A-540 has no bolts over the maximum hardness range
.
but has 7 bolts below the minimum specified hardness of 31 - 39 RC.
The above results are being studied by the licensee and their consultant APTECli to ascertain what corrective action should be taken.
,
^
This is an unresolved item for both units and will be examined in future inspections (329/80-33-1; 330/80-34-1).
Unresolved Matters
'
,
Unresolved items are matters about which more information is required in order to ascertain whether they are acceptable items, items of noncompliance, or deviations. One unresolved item affecting both plants disclosed during the l
inspection is discussed in paragraph 4.
t Exit Interview l
The inspector met with site representatives (denoted in Persons Contacted
paragraph) on December 4, 1980, at the conclusion of the inspection. The
!
inspector summarized the scope and findings of the inspection, which were acknowledged by the licensee.
i
!
,
I I
l i
i I-5-L.