ML19309G449
| ML19309G449 | |
| Person / Time | |
|---|---|
| Site: | Midland |
| Issue date: | 04/17/1980 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19309G448 | List: |
| References | |
| 50-329-80-08, 50-329-80-8, 50-330-80-08, 50-330-80-8, NUDOCS 8005060305 | |
| Download: ML19309G449 (2) | |
See also: IR 05000329/1980008
Text
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DETAILS
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Persons Contacted
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Consumars Power Company Personnel
D. Miller, Site Manager
B. Peck, Construction Supervisor
M. Shaeffer, Group Supervisor
D. Keating, QA Group Supervisor
P. Kyner, QA Eluctrical Supervisor
B. Horn, Group Supervisor QAE
- E. Evans, Field Electrical Engineer
Bechtel Power Corporation Personnel
- E. Smith, Head QA Engineer
EuW Personnel
R. Shope, QC Supervisor
- W. Willman, QC Engineer
Numerous other principal staff and other personnel were contacted during
the recording period.
- Denotes those present during the exit interview conducted during the
reporting period.
Licensee Action on Previous Inspection Findings
(Open) Unresolved Items No. (329/78-19-05; 330/78-19-05): During the
reporting period the Resident Inspector witnessed pull tests on four
grouted anchor-bolts which had exhibited a voided area around the ex-
posed bolt ends. The pull tests were conducted as per a procedure
documented on Bechtel Corporation Field Engineer's Report Form dated
December 20, 1979 signed by Mr. J. Betts. The bolts tested were nomi-
nally 5/8" diameter. Specification No. 7220-C-306 Revision 3 states
that, "5/8" diameter anchor bolts in 4,000 psi concrete should with-
stand a 2.2 kips longitudinal load and withstand a similar 2.7 kips
load when used in 5,000 psi concrete. Bolts for hangers designated
3-1HPC-145-H3 (2 bolts) and 2 1/2 - ICCB-2-H4, sketch nos. 616-4-11
and 603-7-14 respectively were pulled at 2.2 kips using hydraulic
piston no. JSH-123-0A6 and held for one minute.
One bolt for hanger
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designated 12-2GCB-25-H8 (one bolt), sketch no. 611-3-29 was pulled
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st 2.7 kips and held for one minute using the same hydraulic cylinder.
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The area at the hydraulic piston used was v.ertified to be 2.761i .003
square inches. The pressures maintained for load tests of anchors in
4,000 psi concrete were 800 psi and 1,000 psi for the anchors used on
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5,000 psi concrete. Calibrated gauge no. N-4 was used for determining
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the hydraulic pressure. The gauge pressure calibrated on September 21,
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1979 by Indland Ryerson Construction Products Company. After the pull
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test, each of the bolts was examined for any bolt pull-out and/or con-
crete spaulding. None was detected.
Reportable Deficiencies - 50.55(e) Item
Failure of Reactor Vessel Anchor Bolts
As a result of spontaneous failure of reactor vessel anchor studs no.
3 (inside) and no. 36 (outside) for Unit I which were discovered on
September 14, 1979 and December 19, 1979, Teledyne Engineering Services
was contracted to evaluate the cause of these failures. As a part of
this evaluation, Teledyne Engineering Services, performed hardness
tests of all the installed intact anchor studs for both Unit I and Unit
2 reactor vessels. There were originally 96 studs for each reactor
vessel. Teledyne Engineering Services used an Equo-Tip Portable Hard-
ness Tester for these measurements.
A cursory review of the data revealed that six bolts of Unit I were
within the specification tolerance of 32-38 R De Q and 18 bolts in
Unit 2 show hardness values greater than 38 R Dc Q.
In addition to the reactor vessels anchor studs, Teledyne Engineering
Services performed hardness tests on five steam generator anchor bolts
of each steam generator for both units. Each unit has two steam genera-
tors. The steam generator studs tested showed localized hardness values
between nominally 28.5 and 42.5 R Dc Q.
Stress corrosion cracking is attributed as being the most probably cause
for spontaneous failure with a small critical flaw size.
Regional based inspectors are following this matter.
Functional or Program Areas Inspected
1.
Site Tours
At periodic intervals during the report period, tours of randomly
selected areas of the site were performed. These tours were in-
tended to assess the cleanliness of the site; storage conditions of
equipment and piping being used in site construction; the potential
for fire or other hazards which might have a deleterious effect on
personnel and equipment and to witness construction activities in
progress.
It was noted that the licensee was improving control of
extraneous welding materials such as welding stubs and placement
of five blankets.
2.
Unit 1 Reactor Vessel Internal Assembly
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During the reporting period the Resident Inspector examined and
witnessed selected portions of fitting the core support assembly
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guide blocks. B&W was having some difficulty in maintaining the
0.03 inch levelness requirements specified in B&W Procedure No.
FCP-132, Initial Fit-Up of Internals Core Support Assembly, when
the core support assembly was engaged with the reactor vessel
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