IR 05000382/1987020
| ML20235G551 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 09/23/1987 |
| From: | Jaudon J, Skow M, Staker T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20235G512 | List: |
| References | |
| 50-382-87-20, NUDOCS 8709300101 | |
| Download: ML20235G551 (7) | |
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APPENDIX U.S. NUCLEAR REGULATORY COMMISSION i
REGION IV.
NRC Inspection Report:
50-382/87-20 License:
NPF-38 Docket:
50-382 Licensee:
Louisiana Power & Light Company (LP&L)
142 Delaronde Street New Orleans, Louisiana 70174 Facility Name:
Waterford Steam Electric Station, Unit 3 Inspection At:
Taft,_ Louisiana Inspection Conducted:
August 16 through September 15, 1987 Inspectors:
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'R. Staker, Acting Senior Resident Inspector Sffd/
1At/rr M.~ E.~ Skow, Project Inspector Date'
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Approved:
fp4 P.gudon, Chief,ReactorProjectSectionA gatd a
870'.300101 070923 PDR ADOCK 0500
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i Inspection Summary
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Inspection Conducted August 16 through September 15, 1987 (Recort 50-382/87-20)
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. Areas Inspected:
Routine, unannounced inspection of:
(1) followup of previously identified items, (2) licensee event report followup, (3) allegation
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followup, (4) plant status, (5) monthly maintenance, (6) monthly surveillance, and (7) routine operational safety inspection.
l Results:
Within the areas inspected, no violations or deviations were identified.
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DETAILS 1.
Persons Contacted Principal Licensee Employees J. G. Dewease, Senior Vice President, Nuclear Operations
- R. P. Barkhurst, Vice President, Nuclear Operations
- N. S. Carns, Plant Manager, Nuclear
- P. N. Backes, Corporate QA Manager
- S. A. Alleman, Assistant Plant Manager, Plant Technical Staff J. R. McGaha, Assistant Plant Manager, Operations and Maintenance l
J. N. Woods, Quality Manager, Nuclear
- A. S. Lockhart, Nuclear Operations Support and Assessments Manager R. F. Burski, Engineering Service Manager
- G. E. Wuller, Onsite Licensing Coordinator T. H. Smith, Maintenance Superintendent, Nuclear
- J. M. O'Hearn, Technical Support Training Superintendent
- W. T. LaBonte, Radiation Protection Superintendent
- J. A. Ridgel, Assistant Superintendent, Health Physics
- T. F. Lerrets, Acting Nuclear Services Manager
- D. A. Rothrock, Operational Licensing Engineer
- H. C. Lesan, Health Physics Engineer
- L. W. Laughlin, LP&L Public Relations D. E. Baker, Event Analysis and Reporting Supervision M. P. Bermingham, Personnel Representative
- Present at exit interview conducted on August 21, 1987.
- Present at exit interview conducted on September 16, 1987.
In addition to the above personnel, the NRC inspectors held discussions with various operatior,s, engineering, technical support, maintenance, and administrative members of the licensee's staff.
2.
Followup of Previously Identified Items (Closed) Violation 382/8710-02, " Failure to Adhere to the Technical Specification Required Action For An Inoperable Fire Penetration Seal."
The NRC inspector has reviewed both of the licensee's letters, dated July 7 and August 24, 1987, concerning this violation. Additionally, the NRC inspector verified implementation of the corrective action:, addressed in these letters.
Specifically, the NRC inspector found that personnel had been retrained and that the firs seal's status was clarified. This item is closed.
(Closed) Unresolved Item 382/8714-01, " Backlog of PORC Final Reviews of PRES." The NRC inspector verified, by review of the plant potentially reportable event log, that the backlog has been reduced to a level which was approximately 20 percent of the backlog noted in NRC Inspection Report 50-382/87-14. This item is closed.
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LicenseeEventReport(LER) Followup
The folloeing LERs were reviewed and closed.
The NRC inspectors verified that reporting requirements had been met, that causes had been identified, that corrective actions appeared appropriate, that generic applicability had been considered, and that the LER forms were complete. Additionally, the NRC inspectors contirmed that no unreviewed safety questions were involved, and that violations of regulations or Technical Specification (TS) conditions had been identified.
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(Closed) LER 382/85-057, "Both Charging System Trains Inoperable Due to i
Inadequate Shift Turnover." This LER, which was dated July 30, 1987, reported an event' that occurred on December 16, 1985. The NRC inspector found, as stated in the LER, that the event was documented when it l
occurred and that the initial determination that the event was not reportable was not reviewed by the licensee. The licensee stated in the
cover letter accompanying the LER that event analysis and. reporting had
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been reorganized and strengthened, and that one of the responsibilities of the. new organization was to review potentially reportable event (PRE)
reports. The review included those PRES that had not yet received final review and closure.
It was through the efforts of this group that this event was identified and reported. The NRC inspector found that although this report was not timely, the licensee had recognized a systematic weakness and had taken corrective action. The NRC inspector concluded that the LER resulted from the licensee's efforts to perform event analysis and reporting tasks in a more prompt and effective manner, as well as reduce the backlog of outstanding PRES. The NRC inspector also found that the corrective action discussed in the LER had been completed.
This item is closed.
(Closed)LER 382/86-014, "Due to Inadequate Work Instructions, Maintenance Personnel Inadvertently Opened Safety Injection Tank 1B and 28 Isolation Valves." The NRC inspector found that the corrective actions described in the LER had been completed. A memo dated September 18, 198ii, had been issued to caution personnel against lifting both power supply common wires
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simultaneously from the bus bar. A similar caution was found in Technical
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Manual 45700403. This item is closed.
(Closed)LER 382/87-007, Revisions 0 and 1, " Reactor Trip on High i
Pressure Due to Improper Reassembly of Main Turbine Governor Valve i
Hydraulics," The NRC inspector found that Procedures MM-3-017, -027, and-028 had all been ch3nged to require marking the hydraulic lines with i
identification prior to disassembly. This item is closed.
(Closed) LER 382/87-009, " Containment Pressure Monitoring Instrument Not Sufficiently Accurate." The NRC inspector found that the licensee had
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implemented revised methods to determining containment internal pressure.
In addition, the licersee has requested a change to the Technical Specifications in a letter dated July 19, 1987. This item is considered closed.
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(Closed)LER 382/87-013, " Fire Wrap Not Installed Due to Inadequate Modification Implementation." The NRC inspector verified that Station Modification 1901, which rerouted the affected cable and wrapped conduit and junction boxes as required, had been completed.
(Closed)LER 382/87-017, " Diesel Fuel Oil Analysis Results Not Received Within Required Time Due to Personnel Error." The NRC inspector verified thet Procedure CE-2-030, " Maintaining Diesel Fuel Oil," had been revised to require additional administrative controls for fuel oil analysis from vendor laboratories.
No violations or deviations were identified.
4.
Allegation Followup (4-87-A-0062)
An allegation was received regarding propriety of licensee hiring practices in regard to an individual. The individual was not clearly identified; however, the NRC-inspector found a person who appeared to be the subject of the allegation. That person was assigned duties that were i
generally clerical. The person was not involved in safety-related activities. The NRC inspector also reviewed personnel and recruiting records. The individual had been given standardized clerical pre-employment screening tests, and no impropriety was found. The NRC inspector was unable to substantiate the allegation of improper hiring practices.
No violations or deviations were identified.
5.
Plant Status i
The inspection period began with the plant at 100 percent power. On August 29, 1987, power was reduced to 60 percent to repair a ruptured tube
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on the turbine component cooling water (TCCW) heat exchanger. After l
returning the TCCW heat exchanger to service later the same day, the plant was returned to 100 percent power.
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On September 3, 1987, the plant was manually shut down because of increasing temperatures on the Reactor Coolant Pump (RCP) 2B i> earings.
After cleaning the pump lubrication oil strainer, restoring the reactor power cutback system to service (see NRC Inspection Report 50-382/87-17 and LER 382/87-20), and completing several primary and secondary leak repairs, the reactor was taken critical on September 5 and reached 100 percent power on September 6, 1987.
No violations or deviations were identified.
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Monthly Maintenance i
Station maintenance activities affecting safety-related systems and
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I components were observed and reviewed to ascertain that the activities were conducted in accordance with approved procedures, regulatory guides,
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industry codes or standards, and in conformance with TS.
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Procedure ME-4-155, " Maintenance Procedure Reactor Trip Switchgear
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Breakers," as performed on Reactor Trip Breaker TCB3.
Work Authorization 01000663 and Station Modification (SM) 1357,
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" Replace B-8 bolts on Low Pressure Safety Injection Pump 'B' Suction Line Check Valve (SI-108B) with Higher Strengch Bolts to Achieve More Casket Com]ression and Reduce System Leakage." The NRC inspector observed tlat the work documents present at the site were no longer controlled because the procedure and diagram update verifications had expired on August 24, 1987, 3 days before to the work performance.
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These were up@ted prior to torquing the bolts. During replacement,
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several studs here found to be installed at less than the expected torque value of 327 foot / pounds.
Six of the studs were found installed " hand tight." The licensee performed an evaluation and determined that the B-8 bolt torque reduction has no effect on system structural integrity. The licensee has initiated a program to identify and correct this torque reduction problem. This program consists of verifying and monitoring torque valves on flanges installed with B-8 bolts and Flexitallic gaskets. Also, in order to determine the cause of the torque reduction, studs will be replaced on some flanges and various measurements will be taken including stud I
length, gasket crush, and flange depth.
The licensee is continuing stud replacement per SM 1357.
Followup on the licensee identification and correction of torque reduction for B-8 bolts used with Flexitallic gaskets is considered an open item (382/8720-01).
During replacement, several studs could not be removed because of pipe support interferences. After a decision was made to delay the replacement of the remaining studs, all studs were torqued or verified torqued to 327 foot / pounds.
No violations or deviations were identified.
7.
Monthly Surveillance The NRC inspectors observed and reviewed TS required testing and verified that testing was performed in accordance with adequate procedures, that test instrumentation was calibrated, that limiting conditions for operation were met, and that any deficiencies identified were properly reviewed and resolved.
On August 21, 1987, the NRC inspector observed the performance of
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Procedures OP-903-035, Revision 6, " Containment Spray Pump Operability Check," and OP-903-063, Revision 6, " Chilled Water Pump Operability Verification," on the "A" containment spray and the "A" essential services chilled water pumps.
Performance of Procedure OP-903-035 meets, in part, the requirements of TS 4.6.2.1.c and 4.0.5.
Procedure OP-903-063 performance satisfies, in part, the requirements of TS 4.0.5.
No violations or deviations were identified.
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8.
Routine Operational Safety Inspection By observation during the inspection period, the NRC inspectors verified that the control room manning requirements were being met.
In addition, the NRC inspectors observed shift turnover to verify that continuity of system status was maintained. The NRC inspectors periodically questioned shift personnel relative to their awareness of the plant conditions.
l Through log review and plant tours, the NRC inspectors verified compliance with selected TS and limiting conditions for operations.
l During the course of the inspection, observations relative to protected and vital area security were made including access controls, boundary integrity, search, escort, and badging, r
On a regular basis, radiation work permits (RWPs) were reviewed and the specific work activity was monitored to assure the activities were being conducted per the RWPs.
Selected radiation protection instruments were periodically checked and equipment operability and calibration frequency were verified.
The NRC inspectors kept themselves informed on a daily basis of overall status of plant and of any significant safety matter related to plant operations.
Discussions were held with plant management and various members of the operations staff on a regular basis. Selected portions of operating logs and data sheets were reviewed daily.
The NRC inspectors conducted various plant tours and made frequent visits of the control room.
Observations included: witnessing work activities in progress; verifying the status of operating and standby safety systems and equipment; confirming valve positions, instrument and recorder readings, annunciator alarms; and housekeeping.
No violations or deviations were identified.
9.
Exit Interview The inspection scope and findings were summarized on September 16, 1987, with those persons indicated in paragraph 1 above. The licensee acknowledged the NRC inspectors findings.
The licensee did not identify as proprietary any of the material provided to or reviewed by the NRC inspectors during this inspection.
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