ML13333A779
| ML13333A779 | |
| Person / Time | |
|---|---|
| Site: | San Onofre  |
| Issue date: | 12/19/1980 |
| From: | Brunet R, Curran J SOUTHERN CALIFORNIA EDISON CO. |
| To: | |
| Shared Package | |
| ML13310B151 | List: |
| References | |
| SO1-V-2.17, NUDOCS 8401240151 | |
| Download: ML13333A779 (4) | |
Text
ENCLOSURE 2 SAN ONOFRE NUCLEAR GENERATING STATION ENGINEERING PROCEDURE SOI-V-2.17 UNIT 1 DEC 0
REVISION 2 Page 1 REACTOR COOLANT PUMP FLYWHEEL INSPECTION 1.0 OBJECTIVE 1.1 Regulatory Guide 1.14, Revision 1, recorrmends that inservice inspection of reactor coolant pump flywheels be conducted to insure that the probability of a flywheel failure is small.
This procedure is intended to implement the recommendations of that guide to the maximum extent practical, considering the as-built condition of the reactor coolant pumps and flywheels.
1.2 All three reactor coolant pump flywheels were inspected during the 1970 refueling outage.
No significant indications were noted on the flywheels from A and B pumps. However, C pump flywheel did exhibit a laminar flaw indication when ultrasonically tested. It was determined that this indication was a fabrication
-flaw. and did not develop-in-service. However, -the flywheel was replaced with a spare that was examined ana founo acceptable for use. This new flywheel on C pump was examined during the 1972 refueling outage and was found to have no indications.
1.3 During the 1976 refueling outage, all three flywheels were examined. C was found clear, with no indications, while both A and B did exhibit liquid penetrant indications in the bore ana keyway areas.
These indications were re~moved through grinding, re-examined and found acceptable.
1.4 During the 1980 refueling outage, all three flywheels were examined. C was found clear, with no indications.
Both A and 8 did exhibit unacceptable indications. It was determined that the linear flaws were a result of welds in the bore of the wheels.
An annular area was removed at the parting of the flywheel plates. The groove is U shaped with no sharp corners (Ref.
SPPE-262 EDM NA10-308).
2.0 REFERENCES
2.1 American Society of Mechanical Engineers (ASME), Boiler and Pressure
- Vessel Code,Section XI, 1974 Edition, including Addenda through Sumer, 1975.
2.2 USNRC Regulatory Guide 1.14.
RECEIVED DEC 1 9 8 EDM-SITE 8401240151 840119 PDR ADOCK 05000206, P
SAN ONOFRE NUCLEAR GENERATING STATION ENGINEERING PROCEDURE SO-V-2.17 UNIT 1 DEC 12 1940 REVISION 2 Page 2 3.0 PREREQUISITES 3.1 The provisions of this procedure remain effective for a period of 40 months commencing on January 1, 1978. Prior to the expiration of this initial forty month period this procedure shall be revised to meet the code edition and addenda that are in effect per paragraph (6) of 10CFR 50.55a six months prior to the start of the next forty month interval.
4.0 PRECAUTIONS 4.1 None.
5.0 CHECK-OFF LISTS 5.1 None.
6.0 PROCEDURE
- 6.
REQUIREMENTS An ultrasonic volumetric examination of the areas of higher stress concentration at the bore and keyway of the pump flywheels shall be conducted at approximately three year intervals.
A surface examination of all exposed surfaces and complete ultra-sonic volumetric examination of the pump flywheels shall be conducted at approximately ten year intervals.
Examination shall be in accordance with the requirements of Reference 1 to the extent practical.
6.2 IMPLEMENTATION 6.2.1 The attached table defines the reactor coolant pump flywheel examination schedule for the ten year inspection interval commencing on January 1, 1978 and terminating on December 31, 1987. The examinations specified shall be conducted during the refueling outage occurring in the year under the column "Inspection Dates", or nearest refueling outage.
6.2.2 Examinations shall be conducted in accordance with the requirements of Reference 1 to the maximum extent practical.
SAN ONOFRE NUCLEAR GENERATING STATION ENGINEERING PROCEDURE SO-V-2.17 UNIT 1 pEC 1 2 1980 REVISION 2 Page 3 7.0 RECORDS 7.1 Should the examination and evaluation of any indications indicate an increase in flaw size or growth rate greater than predicted for the service life of the flywheel, the results of the examination and evaluation should be submitted to the NRC for evaluation.
7.2 The results of all inspections shall be documented in writing anG submitted to EOM for retention under Encode NA1O.
8.0 ATTACHMENTS 8.1 Inspection Schedule, Reactor Coolant Pump Flywheels.
R. R. BRUNET APPROVED:
SUPERINTENDENT UNIT 1 M. CURRAN PLANT MANAGER JTR:dh
AN ON0FRE NUCLEAR GENERATING STATION ENGINEERING PROCEDURE SO1-V-2.17 NIT I DEC 1 2 1900 ATTACHMENT 8.1 INSPECTION S DULE REACTOR COOLANT PUMP FLYWHEELS INSPECTION PRIMARY MODE DESCRIPTION DATES OF EXAMINATION REMARKS FLYWHEEL -
PUMP A Bore and Keyway 1980, 1982 Ultrasonic All Exposed Surfaces 1987 Surface, Ultrasonic Complete ultrasonic and including Bore and Keyway surface examination of all accessible areas FLYWHEEL -
PUMP B Bore and Keyway Areas 1980, 1982 All Exposed Surfaces 1987 Surface, Ultrasonic Complete ultrasonic and surface including Bore and Keyway examination of all accessible areas FLYWHEEL -
PUMP C Bore and Keyway Areas 1980, 1982, 1987 Ultrasonic All Exposed Surfaces 1987 Surface, Ultrasonic
- Complete ultrasonic and surface inicuding Bore and Keyway examination of all accessible a areas
.