ML19209A085
| ML19209A085 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 09/10/1979 |
| From: | Economos N, Herdt A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19209A078 | List: |
| References | |
| 50-269-79-21, 50-270-79-19, 50-287-79-21, NUDOCS 7910020211 | |
| Download: ML19209A085 (5) | |
See also: IR 05000269/1979021
Text
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION
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$
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REGION 11
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101 MARIETTA ST., N.W., SUITE 3100
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ATLANTA, GEORGIA 303o3
.....
Report Nos. 50-269/79-21, 50-270/79-19 and 50-287/79-21
Licensee: Duke Power Company
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4
422 South Church Street
Charlotte, North Carolina 28242
Facility Name: Oconee
Docket Nos. 50-269, 50-270 and 50-287
Inspection at Oconee, Seneca South Carolina
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Inspector:
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N. Eco om s
D(te Signed
Approved by:
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A. R. Herdt, RC&ES Branch
P'.'( Signed
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SUMMARY
Inspection on August 7-9, 1974
Areas Inspected
This routine, unannounced inspection involved 19 inspector-hours onsite in the
areas of IE Bulletin 79-17 related ultrasonic examination of pipe welds in
stagnant borated water systems - Unit 3; once through steam generator (OTSG)
"1B" tube leak repair record review - Unit 1; reactor vessel internal vent valve
exercise record review - Unit 3.
Results
No items of noncompliance or deviation were identified.
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DETAILS
1.
Person Contacted
LijpnseeEmployees
- J. E. Smith, Station Manager
- J. D. Norton, QA Engineer
- R. T. Bond, Technical Services Engineer
- T. C. Matthews Technician Projects
Other Organizations
Babcock and Wilcox Construction Company (B&W)
F. J. Sattler, Manager Inservice Inspection
II. W. Stoppelman, Coordinator
C. E. Thompson, Level II Examiner
- Attended exit interview
2.
Exit Interview
The inspection scope and findings were summarized on aagust 9,1979 with
those persons indicated in Paragraph I above. The inspector summarized the
scope and. findings of tbe inspection which included; observation of UT
examination relative to IE Balletin 79-17; record review of steam generator
"1B" tube leak repair; record review of Unit 3 reactor vessel internal valve
exercise. The licensee acknowledged unresolved item nuaber: 50-287/78-21-01
RPV vent valve test results.
3.
Licensee Action On Previous Inspection Findings
Not inspected.
4.
Unresolved Items
Unresolved items are matters about which more information is required to
determine whether they are acceptable or eay involve noncompliance or
deviations. New unresolved items identified during this inspection are
discussed in paragraph 5.a.
5.
Independent Inspection Effort
a.
Reactor Pressure Vessel (RPV) Internal Vent Valve Exercise 'Iest Record
Review - Unit 3
Paragraph 4.2.12 of the Oconee Technical Specification (TS) requires
that all RPV internal vent valves be inspected / tested durin'g each
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refueling outage to confi
...that each valve operates freely. This
test was performed during .ae last fuel outage on Unit 3 under main-
tenance procedure MP/0/A/3000/20. This procedure provides acceptance
criteria including limits on the amount of vertical lift force to open
the valve - 335 lbs. max. A review of the test data, documented on
g enclosure 13.1 to the aforemented procedure, disclosed that valve No.
4 required 370 lbs.
force to open or 35 lbs.
in excess of of the
maximum specified.
In response to questioning the licensee could not
provide a satisfactory explanation for this procedural deviation but
agreed to investigate the matter further and report findings on a
subsequent inspection. The inspector identified this as unresolved
item 287/79-21-01, RPV Vent Valve Test Results.
b.
Steam Generator "1B" Tube Leak Repair - Unit 1
On July 24, 1979 the licensee reported to RII an apparent tube leak in
OTSG "1B".
In discussing the matter, the licensee stated that the
leak was the result of a crack in OTSG "1B" tube 73/130 at the 14th
support and that it had been repaired.
The repair procedure required
that the tu a be stabilized and plugged under station modification
number 1256 R/2 which refererced maintenance procedures: MP/0/A/1130/11
"0TSG Tube Stabilization" and MP/0/A/1130/01 "0TSG Tube Plugging".
B&W'S replacement parts specification 08-1001892-05 dated 2/7/79
provided material, design, fabricatica testing, cleaning and shipping
requirements for the hr.rdware used in the repair.
Sections III and IX
(77S.78) of the ASME Code were listed as applicable to materials and
welding respectively. The inspector reviewed the aforementioned
documents along with related QA/QC records including work request
package S/N 96773, inspection requirement recard (QCF-1A), NDE inspec-
tion record (QCI-IA, R/2) material quality records, welder qualifica-
tions, weld consumable certificatious and receiving reports. The
inspector noted that the number of SG tubes out of service at this
time includes 50 in SG "1A" and 131 in SG "1B".
Within the areas
inspected, no items of noncompliance or deviations were identified.
6.
IE Bulletins
(0 pen) IE Bulletin 79-17, P Se Cracks in Stagnant Borated Water
a.
Systems-(Unit 3)
In accordance with IE Bulletin 79-17, the licensee was conducting a UT
examination of certain suspect pipe welds in critiet.1 (non-isolatable)
systems in Unit 3.
Welds selected for this inspection program were in the
high and low pressure injection systems. A total of 18 pipe welds were
selected. The selection included various thickness sizes, pipe diameters
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and configurations e.g., pipe to valve, pipe to elbow, etc.
Following is a
list of welds selected.
Low Pressure Injection System (53B)
Wehd
ISO Description
Size
Comments
7
46
Pipe to Ell
14" X .250"
Clear
8
46
Pipe to Ell
14" X .250"
Clear
12
46
Pipe to Pipe
14" X .250"
Clear
43
39
Pipe to Value
8" X 1.60"
35% of CRT screen height
intermitent 360
41
39
Pipe to Ell
8" X .160"
35% of CRT screen height
intermitent 360
40
39
Pipe to Ell
8" X .160"
45% of CRT screen height
intermitent 360
4
52
Pipe to Pipe
8" X .148"
Clear
4A
52
Pipe to Elbow
Clear
High Pressure Injection System (51A)
ISO Description
Size
Comments
37A
61
Pipe to Ell
2 " X .375
Clear
38A
61
Pipe to Ell
2\\" X .375"
Clear
43
. 61
Pipe to Valve
2 " X .375"
Clear
44
61
Pipe to Valve
2 " X .375"
Clear
16AB
62
Pipe to Ell
2\\" X .375"
lea r
20A
62
Pipe to Ell
2 " X .375"
Clear
21
62
Pipe to Ell
2 " X .375"
Clear
22
62
Pipe to Ell
2 " X .375"
Clear
25
62
Pipe to Valve
2 " X .375"
Clear
26
62
Pipe to Nozzle 2 " X .375"
Clear
The UT examination of the area in question was performed by B&W with a UT
procedure / technique designed to pickup intergranular corrosion type attack
within the HAZ of the weld. The examination was performed with a USM-2
Krautkramer-Branson instrument using a 1/4", 50 degree shear wave, 5 MHz
trans 'ucer.
Amplitude cabibration was accomplished using a pipe calibration
standard with an I.D. circumferential notch 1" X 1/8" and a depth equal to
5 percent of wall thickness. Maximum signal response was obtained from the
notch on the first half of the "V" path and the signal amplitude was set at
80% of CRT acreen height.
The inspector observed system calibratian, weld examination and recording
of discernable reflectors in weld 20A and 40 above. Personnel, equipment,
material certifications and examination results were reviewed for completeness
and accuracy.
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In a telephone conversation with the licensee's representative on August 14,
1979, the inspector learned that discernable reflectors had been found in
welds 41 and 43 of the low pressure injection system. The licensee stated
that all reflectors will be evaluated in order to determine their nature.
During this conversation the inspector stated that (a) a followup information
notice or supplement to IE Bulletin 79-17 would be forthcoming from IE:HQ
and (b) examination of walds as stated in part two of IEE 19-17, will have
to be performed on stagnant water pipe systems with UT procedure ISI-129
Rev. O, or one comparable.
Within the areas inspected, no items of noncompliance or deviations were
identified.
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