IR 05000458/1988017
| ML20151X386 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 08/12/1988 |
| From: | Constable G, Ford E, William Jones, Michaud P NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20151X378 | List: |
| References | |
| 50-458-88-17, IEB-88-005, IEB-88-5, NUDOCS 8808250337 | |
| Download: ML20151X386 (8) | |
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E APPENDIX
U. S. NUCLEAR REGULATORY COMMISSION
REGION IV
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_ NRC Inspection Report: 50 458/88-17 Docket: 50-458 Licensee Gulf States Utilities Company (GSU)
P. 0. Box 220 St. Francisville, Louisiana 70775 Facility Name River Bend Station (RBS)
Inspection Att' River Bend Station, St. Francisville, Louisiana
Inspection Conducted: July 1 through 31, 1988 i
Inspectors f
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E. J. Ford, S or Resident Inspector
/ Dale Project Se ion C, Division of Reactor Projects
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W. B. Jones, ResiKryl Inspector D
Project Section Y, Division of Reactor Projects
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(f Tka.fW y-P. W. Michaud, Resident Inspector.
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Project Section B, Division of Reactor Projects f'
..-3 Approved:
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'G. LT Constable. Chief, Project Section C Date i
Division of Reactor Projects g
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t 8008250337 8000$$
PDR ADOCK 05000450
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-2-Inspection Summary Inspection Conducted July 1 through 31, 1988 (Report 50-458/88-17)
Areas Inspected: Routine, unannounced inspection of licensee action on NRC Bulletin 88-05, surveillance test observation, maintenance observation, operational safety verification, radiological protection observation and security.
Results: Within the areas inspected, no violations or deviations were identifie __
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-3-DETAILS
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Persons Contacted i
D. L. Andrews, Director, Nuclear Training..
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- R. J. Backen, Supervisor, Operations Quality Assurance (QA)
R. Barnes, Field Engineering
- J. E. Booker, Manager, Oversight
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E. M. Cargill, Supervisor, Radiation Programs
- J. W. Cook, Lead Environmental Analyst,. Nuclear Licensing
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- T. C. Crouse, Manager, Quality Assurance (QA)
- W. L. Curran, Site Representative, Cajun
- J. C. Deddens, Senior Vice President, River Bend Nuclear Group D. R. Derbonne, Assistant Plant Manager, Maintenance R. G. Easlick, Supervisor, Radwaste
- L. A. England, Director, Nuclear Licensing A. O. Fredieu, Supervisor,-Operations P. D. Graham, Assistant Plant Manager, Operations
- K. J. Gladrosich, Acting Supervisor, Quality Engineering
- J. R. Hamilton, Director, Design Engineering
- R. J. King, Supervisor, Nuclear Licensing
- J. H. McQuirter, Licensing Engineer
- V. J. Normand, Supervisor, Administrative. Services
- W. H. Odell, Manager, Administration
- T. F. Plunkett, Plant Manager
- K. E. Suhrke, Manager, Project Management N,R,Q
- G. L. Constable, Chief, Reactor Projects Section C
- E. J. Ford, Senior Resident Inspector, Reactor Projects Section C In addition, the NRC inspectors held discussions with various operations, engineering, technical support, maintenance, and administrative members of the licensee's staff.
- Denotes those persons that attended the exit interview conducted on August 5, 1988.
2.
Plant Status River Bend Station operated at essentially full reactor power during this inspection period.
No outages are presently scheduled until the second refueling outage in March 1989.
3.
Licensee Action on NRC Bulletin 88-05 (92701)
This bulletin and its supplement concerns nonconforming material supplied by Piping Supplies, Incorporated (PSI) and West Jersey Manufacturing
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-4-Company (WJM).
In accordance with the bulletin, the licensee determined that 656 total flanges supplied by WJM were installed in the plant. Of
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percent))were tested within the Brinell Hardness range of l
i these 419 (63.9 percent were above the range and 88 (13.4 percent) were 137-187, 31 (4.7 below the range.
The remaining 118 (18 percent) flanges were considered
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to be inaccessible due to locations such as the discharge of the safety relief valves, underwater in the suppression pool, and cooling tower and in the drywell.
As directed by the bulletin, the licensee performed an analysis justifying continued operation. Thisjustificationforcontinuedoperation(JCO)was given to the NRC on August 2, 1988.
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No violations or deviations were identified in this area of the inspection.
4.
Surveillance Test Observation (61726C)
The NRC inspectors observed the performance of Surveillance Test Procedure STP-203-4208, "ECCS/HPCS - Suppression Pool Water Level - High Monthly CHFUNCT, 18 Month CHCAL, 18 Month LSFT (E22-N055G, E22-N655G)," and STP-000-0001, "Daily Operating Log."
o STP-203-4208 - This surveillance procedure was performed on July 28, 1988, with the reactor in 0,erational Condition 1.
This surveillance n
test satisfies the nonthly channel functional test of the Emergency Core Cooling System /High Pressure Core Spray - Suppression Pool Water Level-High instrumentation (E22-N055G, E22-N655G) as required by River Bend Station Technical Specification 4.3.3.1 Table 4.3.3.1-1.C.1.e.
The NRC inspector verified that the instrumentation and control technicians performing the surveillance had obtained permission from the control operating foreman (C0F) to conduct the test and that the test was being conducted in accordance with the approved procedure. The required lifted leads were properly documented in accordance with General Maintenance Procedure GMP-0042,
"Circuit Testing and Lifted Leads and Jumpers." The lifted leads were subsequently verified to be properly landed and independently verified. The test results were found tn be within the limits established by the River Bend Station Technical Specification and were subsequently reviewed and approved by the C0F.
o STP-000-0001 - The resident inspectors observed selected performances of this surveillance test throughout this inspection period. This STP contains River Bend Station Technical Specification surveillance requirements which have a frequency of less than or equal to every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. This STP must be performed when the reactor is in Operational Conditions 1, 2, and 3.
This surveillance was performed within the required frequency and any abnormal readings were circled in red ink as required and reported to the shift supervisor / control operating foreman (SS/C0F). Conditions which indicated
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-5-malfunctioning equipment were identified in a maintenance work request. - The daily logs were reviewed by the applicable C0F prior to shift turnover.
No violations-or deviations were identified in this area of the
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Maintenance Observation (62703C)
During this inspection period, the resident inspectors observed a
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corrective maintenance activtty on the containment air lock personnel door and a diagnostic maintenance activity to evaluate the extent of pitting
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and corrosion that has occurred in the auxiliary building unit coolers.
The following maintenance activities were observed and the maintenance work packages reviewed, o
MWO R116821 - This maintenance work order (MW0) was released for work on July 23, 1988, to replace the outer containment air lock door seals which had been degraded because of a cut and delaminating of the rubber seals.
Prior to initiating work, the licensee locked closed the applicable inner containment air lock door and entered the limiting conditions for operation as specified in River Bend Station Technical Specification 3.6.1.4 with the reactor in Operational Condition 1.
The air lock seals were replaced in accordance with the licensee's Corrective Maintenance Procedure CMP-9249, "Personnel Air Lock Door Seal Replacement IJRB*DRA1, DRA2, and DRA3." The door was tested in accordance with Surveillance Test subsequently functionall{ Containment Personnel Air Lock Door Seal Air Procedure STP-057-5203, System 18 Month Leak Rate Test," prior to being returned to service.
The quality control inspectors observed selected portions of the work performed and verified the work to be satisfactory. The inspection l
results are documented in Quality Control Inspection Reports (QCIR) 88-21563, 21569, 21577, 21593 and 21598. The containment air lock was returned to service on July 27, 1988.
o MWO R113150 - This MWO was initiated to implement Modification Request (MR) 88-0201 to determine the extent of pitting and corrosion that has occurred in the unit coolers serviced by the normal service water system. The MWO authorized the removal of two samples of copper tubing from the Auxiliary Building Unit Cooler HVR*UC4.
River Bend Station Clearance RBI-88-0710 was verified to be properly implemented which isolated the service water system from the unit cooler and deenergized the associated fan. The MWO was released for work by the control operating foreman on July 30, 1988.
The maintenance activities were observed to be performed in accordance with the approved maintenance instructions. Following removal of the two tubes from the unit cooler, the affected tubes were sealed in accordance with the approved brazing procedure. The subsequent work to be performed on the unit coolers during the second refueling outage, based on the analysis of the removed unit cooler tubes, will
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be reviewed as part of NRC Inspection Report 50-458/88-03,Open Item 458/8803-09.
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No violations or deviations were identified in this area of the inspection.
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Operational Safety Verification (71707C)
The NRC inspectors observed operational activities throughout the inspection period and closely monitored operational events. Control room activities and conduct were generally observed to be well controlled.
Proper control room staffing was maintained and access to the control room operational areas was controlled. Sele:ted shift turnover meetings were observed and it was found that information concerning plant status was being covered in each of these meetings. Several control board walkdowns were conducted by the NRC inspectors.
In all cases, the responsible reactor operators were cognizant.as to why an alarm was lit and the reason for each plant configuration. Operational conditions and events, identified through discussions with the reactor operators and through review of the shift turnover logs, were identified in the main control room log, Inoperable equipment identified during the main control board walkdowns were identified by the applicable limiting condition for operation.
The NRC inspectors conducted several tours of the facility during this inspection period. General housekeeping practices were found to be good.
Several walkdowns of the low
)ressure core spray (LPCS),) low pressurecoolant injection (LPCI), higi pres isolationcooling(RCIC)systemswereconducted.
Major flow paths were verified to be in the required standby position.
The associated power supply for each major flow path valve and pump was observed to be available. No conditions were noted which would indicate the associated system would not perform its intended safety function.
The re.sident inspectors also reviewed licensee actions on operational events and potential problems. The results of reviews of selected items are described below:
Inadvertent Activation of Emer On July 13, 1988, at approximately 8:30 a.m. (CDT) gency Siren:
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an emergency siren in Point Coupee Parish inadvertently actuated.
A message was subsequently broadcast over the emergency broadcast station stating that no actual emergency existed at River Bend Station. The licensee has conducted interviews in the Point Coupee Parish area and have positively verified that the siren t.hich actuated was part of the River Bend Station emergency notification system. At the time of the actuation, no electrical storms were in the area and the licen;ee did not receive any indication that the siren had activated. To date, the licensee has not detemined why the siren actuated. The resident inspectors, along with NRC Region IV personnel, are reviewing the licensee's actions to eliminate the inadvertent siren activations. The licensee
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actions to eliminate inadvertant siren activations is identified in NRC Inspection Report 50-458/88-12 as Open Item 458/8812-01, b.
Annulus Mixing Particulate Radiation Monitor: On July 12, 1988, at 5:26 p.m. (CDT) the annulus mixing particulate radiation monitor (RMS*REllB), went into alam immediately after having secured from a source check. The annulus pressure control system isolated and the
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Division II annulus mixing fans and standby gas treatment system automatically started as expected. A review of the plant effluent indicated no increase in radiation level. The licensee has initiated Maintenance Work Order 116408 to evaluate and repair the cause of the spurious signal. This event will be further reviewed by an NRC inspector during the review of the licensee event report (LER).
The LER associated with this event is due by August 11, 1988.
Fuel Building Radiation Monitor:
On Jul 13, 1988, at 8:40 a.m.
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(CDT) an engineered safety feature (ESF)yactuation occurred when the fuel building radiation monitor (1RMS*RE5B) was inadvertently deenergized while securing from a preventive maintenance (PM)
activity. Deeneraizing the monitor caused the system to "fail-safe" and automatically initiated both trains of the fuel building ).
emergency ventilation.
Lineup was restored at 8:45 a.m. (CDT The instrumentation and control (I&C) technician had completed changing the sample filter paper when the individual deenergized the radon monitor instead of the controller / data display acnitor (RM-23P). The licensee has revised their FM procedures for changing filter paper / cartridges for ESF radiation monitors to prohibit use of the RM-23P. The PMs now reflect the method used in the surveillance test procedures to temporarily disable the monitor's ESF function and provide further guidance on how to perform the PM.
This event will be further reviewed by an NRC inspector during the review of LERs.
The LER describing this event is required to be submitted to the NRC by August 12, 1988.
No violations or deviations were identified in this area of the inspection, 7.
Radiological Protection Observations (71709)
The NRC inspectors verified that selected activities of the licensee's radiological protection program were implemented in conformance with the River Bend Station Technical Specifications and licensee approved procedures.
Radiation work permits (RWP) contained appropriate information to ensure that work could be performed in a safe and controlled nenner. Radiation and contaminated areas were properly posted and controlled.
Personnel performing work authorized by 6 specific RWP were questioned concerning the requirements and limitations given in the i
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No violations or deviations were identified in this area of the inspec. tion.
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Security (71881)
g The resident inspectors. observed-security activities during this inspection period. The activities observed included a physical search of a vehicle, licensee personnel and packages prior to allowing access into
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the protected area.' Compensatory posts were observed to be in place and attentive when intrusion detection equipment was degraded. Security L
officer response to vital area door alarms was prompt. The licensee has modified the access corridor for-personnel entering into the protected area to further ensure,that prohibited materials are deleted prior to being
brought into the protected area.
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No violations or deviations were identified in this area of the inspection.
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Exit Interview An exit interview was conducted on August 5, 1988, with licensee representatives (identified in paragraph 1). During this review the RI
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