ML19254C904
| ML19254C904 | |
| Person / Time | |
|---|---|
| Issue date: | 07/12/1979 |
| From: | Hunnicutt D, Oller R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML19254C903 | List: |
| References | |
| REF-QA-99900374 NUDOCS 7910180263 | |
| Download: ML19254C904 (5) | |
Text
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U. S. NUCI. EAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT REGION IV Report No. 99900374/79-01 Program No. 51400 Company:
M.E. A. Incorporated 2600 American Lane Elk Grove Village, Illinois 60007 Inspection Conducted: June 22, 1979 7/'2/?#
Inspector:
o R. E. Oller, Contractor Inspector Date Vendor Inspection Branch N'2/7/
Approved by:
2 4
D. M. Hunnicutt, Chief, ComponentsSection II Date Vendor Inspection Branch Summary n.
Special Inspection on June 22, 1979 (99900374/79-01)
Area Inspected:
Implementation of 10 CFR 50.55(e) and other NRC requirements including assessment of the cause, corrective action and generic considerations relative to the deficiencies involving the presence of metal shavings in the hydraulic system and a malfunction of the fail-safe transfer device in valve actuators for discharge valves of auxiliary feedwater pumps at Sequouah Units 1 and 2.
The inspection involved eight (8) inspector-hours on site.
Results:
In the area inspected, no deviations or unresolved items were identified.
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2 Details Section A.
Persons Contacted R. Johannson, Sales Administrative Manager T. Lasiewicz, President P. Sorsen, Chief Engineer B.
P,re-inspection Conference A pre-inspection conference was held on June 22, 1979, with Mr. T. Lasiewicz.
The NRC inspector explained that the purpose of the inspection was to follow-up on the 10 CFR Part 50.55(e), Report cf Construction Deficiencies as reported by the Tennessee Valley Authority (TVA) in their final report dated February 28, 1979, to the NRC concerning defi hydraulic valve actuators of the discharge pressure,ciencies in four (4) control valves for the motor driven auxiliary feedwater pumps on Sequoyah Nuclear Plant Units 1 and 2.
This problem is also related to the Watts Bar Nuclear Plant Units.
C.
Reported 10 CFR 50.55(e) Deficiencies 1.
Deficiencies Reported The equipment in question is four (4) hydraulic valve actuators maufactured by M.E. A. Incorporated of Elk Grove Village, Illinois.
These actuators are used to operate 4" globe valves supplied by Masoneilan for discharge pressure control of the motor driven auxiliary feedwater pumps for Sequoyah Nuclear Units 1 and 2.
The deficiencies consisted of:
(1) metal shavings left in the operating cylinders, and (2) a fail-safe transfer feature actuated by a push pull knob which can be inadvertently positioned in a midposition. Operation of the manual pump on the actuator with the knob in the midposition in conjunction with the metal shaving, permitted overpressurization of the hydraulic cylinder to the point where failure of the cylinder anchoring bolts occurred on two (2) of four (4) actuators at the Sequoyah Nuclear Station. Four (4) of these same model actuators (No. 1-19K-2) were also supplied for the Watts Bar Nuclear station.
2.
Objectives The objective of this inspection was to obtain sufficient information to assess the cause, corrective action, and generic considerations of the deficiencies in the hydraulic valve actuato:s furnished on discharge pressure control valves of the motor driven auxiliary feedwater pumps for TVA Sequoyah Nuclear Units 1 and 2 as reported by the Tennessee Valley Authority under 10 CFR 50.55(e) requirements.
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3 3.
Method of Accomplishment The preceding objectives were accomplished by:
a.
Discussions with cognizant personnel.
b.
Review of TVA's "Sequoyah Nuclear Plant Units 1 and 2 - Metal Shavings in Valve Ooerators - NRC 1354 - Final Report," dated February 28, 1979, Review of M.E.A. Drawings No. D-1841-10A, dated May 31, 1974, c.
"I HP Superthrust Valve Actuator Assembly," sheets 1 and 2, and Drawing No. B-1841-2A, dated January 31, 1974, "Model 1-19K-2 Superthrust Actuator."
d.
Observation of a new manifold type Model 1-8K-9 valve actuator.
Review of a copy of Masoneilan Purchase Order No. F-30822, e.
dated December 5,1973, to M.E. A. Incorporated to furnish four (4) Model 1-19K-2 Superthrust Valve Actuators.
f.
Review of Masoneilan Purchase Order No. F-30817, dated April 29, 1974, to M.E.A. Incorporated to furnish four (4) Model 1-19K-2 actuators (same as paragraph e above).
g.
Review of TVA's Purchase Order No. 76P-16-213663, dated May 24, 1976, to M.E. A. Incorporated to furnish a spare Model 1-19K-2 actuator for the Sequoyah project.
h.
Review of a Commonwealth Edison PO No. 213174, dated July 15, 1977, to M.E.A. to furnish one Model 1-12K-14 valve actuator for Quad Cities Station Unit No. 1.
Also, M.E. A. Incorporated proposal No. 770G29-3, Revision 2, for the above actuator.
i.
Review of a list of actuator serial numbers for the nine (9)
Model 1-19K-2 actuators furnished to TVA.
4.
Findings a.
Devia tio_n_s None.
b.
Unresolved Items None.
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4 c.
Other Findings (1) The cause and corrective action for the two (2) deficient conditions were described as follows:
(a) The presence of metal shavings in the hydraulic systems of the actuators was due to inadequate cleaning after drilling of tubing connnections during manufacture in 1974. This design was discontinued in later models.
The accumulator, cylinders and other parts are directly connected into a manifold in the new type. The corrective action with regard to the Sequoyah and Watts Bar actu-ators is to flush the hydraulic system with oil until clean and then fill with hydraulic fluid. This work is being performed under the guidance of an M.E.A. service representative.
(b) The push pull fail-safe transfer device which malfunctioned, will be replaced with a valve which utilizes a normally open solenoid. The valve remains closed with power on and opens on power failure. Eight (8) of the new Fail-safe Transfer Valve units, Model G-618-35A, have been shipped to the Sequoyah and Watts Bar sites to replace the old devices, Model G-618-84.
This replacement work is also under the guidance of the M.E.A. service representative.
M.E.A. is having discussions with TVA personnel with regard to replacing the push pull fail-safe transfer device on the spare valve actuator. Parts for the two (2) actuators which were damaged by over-pressurization, have been shipped to TVA.
(c) The information contained in the above items (a) and (b),
substantiate the conditions in TVA's final report, dated February 28, 1979, to the NRC.
(d) Review of M.E. A. records identified in paragraph C.3 and discussions, established that M.E. A. Incorporated has shipped only nine (9) valve actuators of the suspect Model 1-19K-2 type to nuclear power sites, and these were sent to TVA. The one (1) M.E.A actuator shipped to Quad Cities Unit 1 was a later model No. 1-12K-14, and was not associated with the identified problems.
D.
Exit Interview 1.
The inspector met wiq Mr. T. Lasiewicz, at the conclusion of the inspection on June 22, 1979.
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5 2.
This inspector indicated that the information provided by M.E.A.
Incorporated verified that the two (2) problems associated with valve actuator Model 1-19K-2, were being appropriately resolved as reported to the NRC by TVA in their final report dated February 28, 1979.
3.
Mr. T. Lasiewicz indicated he did not have any questions in regard to the inspection.
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