IR 05000315/1979006
| ML17317B316 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 05/16/1979 |
| From: | Danielson D, Key W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML17317B315 | List: |
| References | |
| 50-315-79-06, 50-315-79-6, NUDOCS 7907180335 | |
| Download: ML17317B316 (17) | |
Text
U.S.
NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
Report No. 50-315/79-06 Docket No. 50-315 License No. DPR-58 Licensee:
American Electric Power Service Corporation Indiana and Michigan Power Company 2 Broadway New York, NY 10004 Facility Name:
D.
C.
Cook Nuclear Power Plant, Unit 1 Inspection At:
D.
C.
Cook Site, Bridgman, MI Inspection Conducted:
April 12-13 and May 1-2, 1979 Approved By:
D.
. Danielson, Chief Engineering Support Section
J /s Ins ection Summar Ins ection on A ril 12-13 and Ma 1-2 1979 (Re ort No. 50-315/79-06)
Areas Ins ected:
Review of ISI program and procedures, observation of ISI work activities, and review and evaluation of collected ISI data.
The inspection involved a total of 28 inspector-hours onsite by one NRC inspector.
Results:
No items of noncompliance or deviations were identified.
q9Qy'180
4) P>>
DETAILS Personnel Contacted Indiana and Michi an Power Com an (I&M)
"D.
A.
- H.
-R.
V. Shaller, Plant Manager A. Svensson, Assistant Plant Manager P. Papai, ISI Supervisor H. Bolinger, ISI Assistant Supervisor F. Stietzel, equality Assurance Supervisor S. I,ease, Operations Superintendent Facto Mutual En ineerin D.
C. Young, Authorized Inspector Southwest Research Institute (SWRI)
R. P.
Simkus, Quality Assurance Engineer F. Mengden, Inspection Engineer C. Trout, Team Leader
="Denotes those present at the exit interview.
Functional or Pro ram Areas Ins ected l.
Inservice Ins ection Pro ram Review The inspector reviewed Final Plan No. 17-3378, developed by SWRI and titled 10 year Inservice Examination Plan for Class I Components at D.
C.
Cook Nuclear Power Plant, Unit l.,
This examination plan has been upgraded to meet the require-ments of ASME Code,Section XI, 1974 Edition through Summer 1975 Addenda.
The inspector reviewed SWRI Final Plan, 17-4662, 1979 Inservice Examination Plan for the D.
C.
Cook Nuclear Power Plant, Unit l.
Items selected for examination during this outage are from the 10 year plan, and include the following systems and components.
a.
Reactor Pressure Vessel and Closure Head b.
Pressurizer
c ~
d.
e.f.
g.
h.
Regenerative Heat Exchangers Steam Generators Reactor Coolant System Chemical and Volume Control System Residual Heat System Safety Injection System Waste Disposal System Reactor Coolant Pump The long term ISI examination plan for Class 2 systems and components has not been completed by SWRI for D.
C.
Cook, Units 1 and 2, and only a few items have been scheduled for exami-nation during this outage.
The inspector was informed, that Class 2 and 3 items will start being examined beginning with the second inspection period of the first inspection interval.
Technical Specification 4.4.10, Table 4.4-6, does not reflect upgrading of the ISI Program to ASME Section XI, 1974 Edition through Summer 1975 Addenda.
The inspector was informed, that this was in progress.
No items of noncompliance or deviations were identified.
2.
Inservice Ins ection Procedure Review The inspector reviewed the following SWRI procedures for perfor-mance of ISI examinations.
IX-FE-101-1.
Titled:
Deviations to Nuclear Field Services Section Operating Procedures.
b.
IX-FE-103-1.
Titled:
Weld Joint Identification Marking on Nuclear Power Plant Piping.
C.
IX-FE-104-1.
Titled:
'Measuring and Recording Search Unit Location, and Maximum Signal Amplitude Data during Ultra-sonic Weld Examination.
d.
IX-FE-105-0.
Titled:
Recording Data from Direct Visual, Liquid Penetrant and Magnetic Particle Examination of Welds.
e.
IX-FF-109-1 ~
Titled:
Measuring and Recording Search Unit Location and Signal Amplitude Data during Ultrasonic Examination of Pressure Vessel Welds.
-3"
f.
IK-FE"110-0.
Titled:
Black Light Intensity Measurement.
g.
X-FE-101-0.
Titled:
On Site NDT Record Control.
h.
XIII-AG-101-0. Titled:
Control of Nuclear Inspection Equipment.
i.
XVIII-AG-101-0. Titled:
Data Storage and Retrieval.
The following SWRI procedures have been reviewed and approved by the licensee for performance of examinations in accordance with Project Plan 78-IMP - D.
C.
Cook 1/2 - 1-1, Units 1 and 2.
a.
200-1/46.
Titled:
Liquid Penetrant Examination, Color Contrast Method.
b.
300-1/16.
Titled:
Dry Powder Magnetic Particle Exami-nation.
C.
300-1/25 'itled:
Fluorescent Magnetic Particle Exami-nation.
d.
600-3/52.
Titled:
Manual Ultrasonic Examination of Pressure Piping Welds.
e.
600-6/20.
Titled:
Manual Ultrasonic Examination of Reactor Coolant Pump Flywheel.
600-11/28.
Dev.
1.
Titled:
Manual Ultrasonic Examination of Vessel to Nozzle Inner Radius Sections.
go 600-15/39.
Titled:
Manual Ultrasonic Examination of Pressure Vessel Welds.
h.
600-16/21.
Titled:
Manual Ultrasonic Examination of Vessel Support Skirt Attachment Welds.
600-18/26.
Titled:
Manual Ultrasonic Examination of Pressure Retaining Studs and Nuts 2 inches or Greater in Diameter Containing Access Holes.
600-19/26.
Titled:
Manual Ultrasonic Examination of Pressure Retaining Round Nuts, 2 inches or Greater in Diamete k.
800-17/19.
Titled:
Special Procedure for Manual Ultra-sonic Examination of Austenitic Steel Components with High Acoustic Attenuation Properties.
l.
800-36/22.
Titled:
Manual Ultrasonic Examination of Thru Wall Piping Welds.
m.
900-1/42.
Titled:
Visual Examination of Nuclear Reactor Components by Direct or Remote Viewing.
No items'f noncompliance or deviations were identified'.
Observation of Work Activities a
~
E ui ment Certification and Calibration The inspector verified certification and calibration of the following SWRI equipment intended for use in the performance of ISI examinations and personnel certifications.
Ultrasonic Instruments Sonic MK-1 - S/N-780417 Sonic MK-1 - S/N-774101 Sonic MK-1 - S/N-774224 Sonic MK-1 - S/N-774222 Ultrasonic Cou lant Ultragel-II - Batch No.
4378 Glycerine - Lot No. TB-12137-2 Ultrasonic Search Units S/N I03851 013619 013633M 016263H 15493 15496 013718 120049 512 Size
.250" 3/4tl 3/4 II
.500" 250 250 1/2" x 1" 1/2tl 3/8tl 2.25 2.25 2.25 2.25 2.25 2.25 2.25 2.25 M 015762 1tl
. 250'I 2.25 2.25 Li uid Penetrant Materials Magnaflux Cleaner, SKC-S, Batch No.
78H015 Magnaflux Penetrant, SKL-HF/S, Batch No.
78B032 Magnaflux Developer, SKD-S, Batch No.
78H005 Ma netic Particle Materials Electro Magnetic Particle Probes S/N-WL-1-1 and WL-1-2 Magnetic Powder, Magnaflux Type No.
14AM Prepared Maglo, Batch No.
78F020 b.
Personnel Certification and ualifications The inspector verified certification and qualification of the following SWRI and I&M examination personnel.
Name SWRI Level of Qualification UT PT MT VT ET RT C. E. Trout L. C. Reaves F.
C. H. Mengden J.
P. Melendez D.
W. Fournell F. J. Carruth III I Ltd.
IIIII II I Ltd. I I Ltd. I I Ltd. I III I
II Ltd. I Ltd.
Ltd. I Ltd.
Ltd. I Ltd.
II II I
I Ltd.
I Ltd.
R. E. Kernosky G. R. Montenegro R. L. Otte L. F. Vanzandt D. I. Hickcox IIIIIIIIII IIIIIIIIII c ~
Feedwater S stem Two (2) Class II welds in the Feedwater System were selec-ted for radiographic examination this outage, one field
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and one shop weld, identified on isometric No.
1-FW-15, Revision 12, as weld No.
04S Shop, and No. 05F Field welds.
The inspector was informed that the separation between Class II and Class III or balance of plant was the check valves located 8'r 10'eet outside containment, not the M.O. isolation valves located some 80'o 100'eet away from the check valves.
It appears that the system design is in violation of 10 CFR 50, Appendix A, Criterion 57, which states that an isolation valve must be as close as possible, and that a
simple check valve cannot be an isolation valve.
The feedwater flow diagram shown on Drawing No. 1-2-5106-16 shows the check valves as being the boundary.
The inspector examined the four feedwater lines on Unit 1 and discussed the arrangement with licensee representatives.
The inspector reviewed radiographs of the following welds taken at the request of the licensee when defective con-ditions were detected in the shop weld selected for exami-nation.
Since these welds were classified as Class III during construction the shop welds were not examined, however, the field wel'ds reviewed were of acceptable quality.
(1)
Shop weld No. 04S, Isometric 1-FW-15, Revision 12.
Position, 0-11, Nonpenetration of backing ring.
Position, 11-22, Mismatch of backing ring, melt through, and nonpenetration.
Position, 33-0, Nonpenetration (2)
Shop weld No. 035, Isometric 1-FW-15 Position, 11-22, Nonpenetration Position, 22-33, Nonpenetration Position, 33-0, Nonpenetration
(3)
Shop weld No.
02S, Isometric 1-FW-15 Position - 0-11 11-22 nonpenetration of backing ring and slag.
22-33 nonpenetration of backing ring and slag.
33-0 nonpenetration of backing ring and slag.
(4)
Shop weld No. 05S, Isometric 1-FW-17 Position, O-ll, Nonpenetration and slag Position, 11-22, Melt through at'2-13 Position, 22-33, Burn through Position, 33.0, Nonpenetration and slag (5)
Shop weld No. 04S, Isometric 1-FW-12 Position, 0-11, Nonpenetration Position, Position, 11-22, Burn through at 12-15 nonpenetration 22-33, Nonpenetration Position, 33-0, Nonpenetration The location of check valves and other information gathered by the inspector was forwarded to NRR on May 1, 1979, by phone, and to the Region III Operations Branch for further review and evaluation.
No items of noncompliance or deviations were identified.
Record Review and Evaluation The inspector reviewed the following substitutions and records of examinations performed during this outag a.
1-PRZ-18 and 19, middle shell weld.
Examine 13 inches, rather than 30" inches.
b.
1-PRZ-26, skirt weld added c.
1-S1-29-04F, substituted for weld 1-Sl-29-05F due to inaccessibility.
d.
1-RC-2-12F, substituted for weld 1-RC1-06S due to inaccessibility.
e.
1-S1-31-18S, substituted for 1-Sl-31-19S due to inaccessi-bility.
f.
1-CS-96-51F, substituted for 1-CS-96-50F.
g.
1-CS-777-02S, substituted for 1-CS-767-07S.
h.
1-RC15-02S, substituted for 1-CS-92-28S will be rescheduled.
i.
Closure head lifting lug 1-LL-2 added per I&M request.
j.
1-RC7-06S and 1-RC8-05S deferred until next outage.
k.
Sheet No.
130120 1-CS-99-23F l.
Sheet No.
110003 1"CS-763-05S m.
Sheet No.
140029 1-RH-28-01S No items of noncompliance or deviations were identified.
Exit Interview The inspector met with licensee representatives (denoted in Persons Contacted) at the conclusion of each portion of this inspection.
On May 2, 1979, the inspector summarized the scope and findings of the inspection and of the concerns for design and weld conditions in the Feedwater System.
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