ML17223A487
| ML17223A487 | |
| Person / Time | |
|---|---|
| Site: | Saint Lucie  |
| Issue date: | 01/23/1990 |
| From: | Julian C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML17223A486 | List: |
| References | |
| 50-335-89-29, 50-389-89-29, NUDOCS 9001310263 | |
| Download: ML17223A487 (2) | |
Text
ENCLOSURE 1
NOTICE OF VIOLATION Florida Power and Light St.
Lucie Docket Nos.
50-335 and 50-50-389 License Nos.
DPR-67 and NPF-16 During the Nuclear Regulatory Commission (NRC) inspection conducted on November 27 December 1,
- 1989, a
violation of NRC requirements was identified.
In accordance with the "General Statement of Policy and Procedure for NRC Enforcement Actions,"
10 CFR Part 2, Appendix C (1990), the violation is listed below:
Title 10 Code of Federal Regulations, Part 50, Appendix B Criterion V
- requires, in part, that activities affecting quality shall be prescribed by documented instructions or procedures of a
type -appropriate to the circumstances.
Instructions, and procedures shall include appropriate quantitative or qualitative acceptance criteria for determining that important activities have been satisfactorily accomplished.
Florida Power and Light procedure PR/PSL-l, Revision 13, "Control of Purchased
- Material, Equipment, and Services,"
paragraph
- 5. 10. requires the St.
Lucie Plant Site Coordinator to approve material used on safety related work performed by contractors to ensure proper quality level, and to provide adequate supervision of the work.
Florida Power and Light Administrative Procedure No.
- 0010432, Revision 39, "Nuclear Plant Work Orders,"
paragraph 8.6 requires, in part, "When parts or materials are
- used, attach all ROS forms and/or gC tags, to the NPWO package...."
Contrary to the above, the following was found as listed below:
Unit 2 Limitorque actuators MV-09-09, and MV-09-10 failed to operate as designed when called upon to do so September 23, 1989, following a manual reactor trip and the subsequent receipt of an Auxiliary Feedwater Actuation System (AFAS) signal.
Valves MV-09-09 and MV-09-10 are at the discharge of the Unit 2 motor driven auxiliary feedwater
- pumps, 2a and 2b, respectively.
MV-09-09 failed to operate as designed because of severe galling between the upper stem and stem nut, due to inadequate lubrication.
The valve went full-open following receipt of the AFAS signal,
- however, operators could not close the valve remotely or locally.
General Maintenance Procedure Number 2-M-00180, revison 5
PM File 10500 covers the 18 month inspection and lubrication of Limitorque actuators.
Valve stem.lubrication is covered in section 4.8 of the procedure, and the instructions are to "Clean the valve stem with kerosene and rags; apply a coat of anti seize lubricant."
These instuctions are inadequate because they do not ensure an even coating of lubricant will be applied to the entire valve
- stem, including the portion of the valve stem in contact with the actuator stem nut.
PDR AGCJCK 05000 9
Florida Power and Light St.
Lucie Docket Nos.
50-335 and 50-389 License Nos.
DPR-67 and NPF-16 MV-09-10 failed to operate as desigried due to a worn limit switch pinion drive gear.
The result was the valve could only move in the closed direction, after initially being opened by the AFAS signal.
The root cause was due to the installation of an unauthorized handwheel cover gasket which was 0. 116" thick, resulting in improper meshing of the limit switch pinion and drive sleeve bevel gear s.
The proper gas'ket thickness should have been 0.015".
The licensee was unable to determine when the unauthorized gasket was installed, or account for the use of the gasket material it was cut
- from, in violation of the requirements to account for materials and parts used on safety related work.
The licensee did not provide adequate and complete work procedures for proper Limitorque disassembly/assembly, and the vendor technical manuals in use at the time were not updated.
The most recent vendor technical manual for Limitorque actuators, SMBI-82C was available in 1982.
The SMBI-82C technical manual contains instructions for determining the proper thickness of the handwheel cover gasket; the SMBI-170, issued in 1979, and in use during the time, the unauthorized handwheel gasket was installed (between 1984 and 1989) did not contain instructions for determining proper handwheel gasket thickness.
Pursuant to the provisions of 10 CFR 2.201, Florida Power and Light Company is.
hereby required to submit a written statement or explanation to the Nuclear Regulatory Commission, ATTN:
Document Control
- Desk, Washington, DC
- 20555, with a copy to the Regional Administrator, Region II, and a copy to the NRC Resident Inspector, St. Lucie, within 30 days of the date of the letter transmitting this Notice.
This reply should be clearly marked as a "Reply to a
Notice of Violation" and should include:
( 1) admission or denial of the violation, (2) the reason for the violation if admitted, (3) the corrective steps which have been taken and the results
- achieved, (4) the corrective steps which will be taken to avoid further violations, and (5) the date when full compliance will be achieved.
Mhere good cause is shown, consideration will be given to extending the response time.
If an adequate reply is not received within the time specified in this Notice, an order may be issued to show cause why the license should not be modified, suspended, or revoked or why such other action as may be proper should not be taken.
FOR THE NUCLEAR REGULATORY COMMISSION Caudle A. Julian, Chief Engineering Branch Division of Reactor Safety Dated at Atlanta, Georgia this 23rd day of January 1990