IR 05000280/1991004
| ML18153C593 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 03/21/1991 |
| From: | Fredrickson P, Holland W, Tingen S, York J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML18153C592 | List: |
| References | |
| 50-280-91-04, 50-280-91-4, 50-281-91-04, 50-281-91-4, NUDOCS 9104110250 | |
| Download: ML18153C593 (10) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTA STREET, ATLANTA, GEORGIA 30323
. Report Nos.:
50-280/91-04 and 50-281/91-04 Licensee:
Virginia Electric and Power Company 5000 Dominion Boulevard Glen Allen, VA 23060 Docket Nos.:
50-280 and 50-281 License Nos.:
DPR-32 and DPR-37 Facility Name:
Surry 1 and 2 Inspection Conducted: January 27 through February 23, 1991 Inspectors:
c::;::,~ ~
W. E. Hol~ior Resident Inspector
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.
Date Signed 3;%~/
J. W. Yo~ent Inspector SUMMARY Scope:
This routine resident inspection was conducted on site in the areas of plant-operations, plant maintenance, plant surveillance, licensee event report closeout, action on previous inspection findings, and plant procedure During the performance of this inspection, the resident inspectors conducted review of the licensee's backshift or weekend operations on February 7, 15, 17, 22, and 23, 199 Results:
In the area of safety assessment/quality verification, a weakness was identified that involved a lack of sensitivity to the potential degradation of a safety-related component (paragraph 3.d).
- Failure.to test the hydrogen analyzers as required by Technical Specification
.Table 4.1-2A, Item 20, is identified as a non-cited violation (paragraph 6).
Failure to perform Technical Specification required surveillances within the allowed time interval is identified as a non-cited violation (paragraph 7.b).
- 9104110250 910321 eoR ADOCK 05000280 W
- Persons Contacted Licensee Employees REPORT DETAILS R. Allen, Supervisor, Shift Operations
- W. Benthall, Supervisor, Licensing
- R. Bilyeu, Licensing Engineer D. Christian, Assistant Station Manager J. Downs, Superintendent of Outage and Planning
- D. Erickson, Superintendent of Health Physics R. Gwaltney, Superintendent of Maintenance M. Kansler, Station Manager T. Kendzia, Supervisor, Safety Engineering
- J. McCarthy, Superintendent of Operations
- A. Price, Assistant Station Manager
- E. Smith, Site Quality Assurance Manager
- T. Sowers, Superintendent of Engineering NRC Personnel
- W. Holland, Senior Resident Inspector
- S. Tingen, Resident Inspector
- J. York, Resident Inspector
- Attended exit intervie Other licensee employees contacted included control room operators, shift technical advisors, shift supervisors and other plant personne Acronyms and initialisms used throughout this report are listed in the last paragrap.
Plant Status Unit 1 began the reporting period in power operatio The unit operated at power for the duration of the inspection perio Unit 2 began the reporting period in power operatio The unit operated at power for the duration of the inspection perio The unit was limited to 90% power because control rod M12 was stuck. This issue was discussed in Inspection Report 50-280,281/90-3.
Operational Safety Verification (71707 & 42700) Daily Inspections The inspectors conducted daily inspections in the following areas:
control room staffing, access, and operator behavior; operator
-adherence to approved procedures, TS, and LCOs; examination of panels containing instrumentation and other reactor protection system elements to determine that required channels are operable; and review of c.ontrol room operator logs, operating orders, plant deviation reports, ta gout logs, temporary modification logs, and tags on components to verify compliance with approved procedure The inspectors also routinely accompanied station management on plant tours and observed the effectiveness of their influence on activities
. being performed by plant personne * Weekly Inspections The inspectors conducted weekly inspections in the following areas:
operability verification of selected ESF systems by valve alignment, breaker positions, condition of equipment or component, and operability of instrumentation and support items essential to system actuation or performanc Plant tours were conducted which included observation of general plant/equipment conditions, fire protection and preventative measures, control of activities in progress, radiation prptection controls, physical security controls, missile hazards, and plant housekeeping conditions/cleanlines The inspectors routinely noted the -temperature of the AFW pump discharge piping to ensure increases in temperature were being properly monitored and evaluated by the license Biweekly IQspections The inspectors conducted biweekly inspections in the fol)owing *reas:
verification review and walkdown of safety-related tagouts in effect; review of sampling program (e.g., primary and secondary coolant samples, boric acid tank samples, plant liquid and gaseous samples);
observation of control room shift turnover; review of implementation of the plant problem identification system; verification of selected portions of containment isolation lineups; and verification that
- notices to workers are posted as required by' 10CFR1 Other Inspection Activities Inspections included areas in the Units 1 and 2 cable vaults, vital battery rooms, steam safeguards areas, emergency switchgear rooms, diesel generator rooms, control room, auxiliary building, cable penetration areas, independent spent fuel storage facility, low level intake structure, and the safeguards valve pit and pump pit area RCS leak rates were reviewed to ensure that detected or suspected leakage from the system was recorded, investigated, and evaluated; and that appropriate actions were taken, if require The inspettors routinely independently calculated RCS leak rates using the NRC Independent Measurements Leak Rate Program (RCSLK9)._
On a regular -
basis, RWPs were reviewed, and specific work activ,ities were monitored to assure they were being conducted per the RWP Selected
radiation protection instruments were periodically checked, and equipment operability and calibration frequency were verifie On January 31, diesel driven ESW pump 1-SW-P-lC was tested following maintenanc On the first and second attempts to start the pump, the diesel failed to star On the third attempt, the diesel started satisfactoril The diesel was secured and on a fourth attempt, it also started satisfactorily. After the first and second unsuccessful start attempts, operators reverified initial conditions for starting the diesel and verified that the battery connections were tigh No abnorma 1 conditions that would have prevented the diesel from starting were note The Shift Supervisor suspected that possible dirty contacts in the diesel start circuit had prevented the diesel from starting on the first two attempts, and since the diesel started on the third and fourth attempts it was considered operabl The Shift* Supervisor contacted the off-site Operations Manager on call, who i~ turn contacted the Assistant Station Manage The off-site Operations Manager and Assistant Station Manager concurred that the*
diesel was operabl DR S-91-0143 was submitted to document the two unsuccessful start attempts and a work request was initiated to troubleshoot the diesel start circui On February 5, DR S-91-0143 was reviewed by SNSO The corrective action required by the DR was to submit a work request to investigate/repair.and perform an analysis in accordance with the CFA progra No time constraints for performing this corrective action were specifie SNSOC concurred with the corrective actio Troubleshooting of the pump's diesel conducted on February 12 revealed a short in the starter solenoid coi This maintenance activity is discussed in paragraph It cannot be concluded that the short in the solenoid coil was the reason that the ESW pump 1-SW-P-lC diesel failed to start during the first two attempts on January 3 Because testing on the shorted solenoid coil performed during the February 12 maintenance window indicated that it still operated satisfactorily, the inspectors agree with the licensee that ESW pump 1-SW-P-lC was operabl However, the inspectors consider it would have been prudent to intnediately troubleshoot the start circuit or take some compensatory action after the diesel fai 1 ed to start in 1 i eu of troubleshooting the circuit twelve days late The lack of sensitivity to the potential degradation of a safety-related component is identified as a weaknes Physical Security Program Inspections In the course of monthly activities, the inspectors included a review of the 1 i censee' s physical security progra The performance of various shifts of the security force was observed in the conduct of daily activities to include: protected and* vital areas access*
controls; searching of personnel, packages and vehicles; badge
issuance and retrieval; escorting of visitors; and patrols and compensatory post No discrepancies were note Within the areas inspected, no violations were identifie.
Maintenance Inspections (62703 & 42700)
During the reporting period, the inspectors reviewed maintenance activities to assure compliance with the appropriate procedure The following maintenance activity was reviewed:
WO 38000107484 Troubleshoot ESW pump 1-SW-P-lC Starting Relays On February 12, ES~ pump 1-SW-P-lC was removed from service in order to perform several maintenance item One of the maintenance items was to troubleshoot the pU1np 1s diesel start circuit due to several start failures on January 3 The inspectors monitored portions of the troubleshooting which revealed that.the starter solenoid coil contained a short and was defectiv Prior to replacing the coil, the starter solenoid was tested and operated satisfactorily with the shor During the troubleshooting, no other deficiencies wefe foun The diesel starter motor and solenoid were replaced and the diesel subsequently started* *satisfactor El ectri;..
cal checks were again-performed arid no deficiencies were note A CFA will be performed on the starter motor and solenoid that were replace Within the areas inspected, no violations were identifie.
Surveillance Inspections (61726 & 42700)
During the reporting period, the inspectors reviewed various survei 11 ance activities to assure compliance with the appropriate procedures as follows:
Test prerequisites were me Tests were performed in accordance with approved procedure Test procedures appeared to perform their intended functio Adequate coordination existed among personnel involved in the tes Test data was properly collected and recorde The following surveillances were either reviewed or observed:
1-PT-25.3C 1-NSP-VS-001 Emergency Service Water.Pump Test (1-SW-P-lC)
Performance Test of Control Room Chiller l-VS-E-4A
- Within the areas inspected, no violations were identifie.
Licensee Event Report Review (92700)
The inspector reviewed the LER's listed below to ascertain whether NRC reporting requirements were being met and to evaluate initial adequacy of the corrective action The inspector's review also included followup on implementation of corrective action and review of licensee documentation that all required corrective actions were complet (Closed) LER 280/90-12, Co111Tion Mode Failure Mechanism Due to Marine Growth Identified for ESW Pump The issue involved the inoperability of ESW pumps 1-SW-:P-lA and 1-SW-P~lc due to low flow rates obtained during routine testin The cause of the low flow rates was determined to be excessive marine growth on the impellers and pump endbell Immediate corrective actions were discussed in Inspection Report 50-280,281/90-2 Long tenn corrective action involved increasing the ESW pumps' test frequency from quarterly to monthly in order to monitor for pump flow rate degradatio Also, the licensee plans to conduct an engineering evaluation to find a long term solution to the marine growth problem on the ESW pump This engineering study is currently scheduled to be completed by June 15, 199 The inspectors consider that the completed and ongoing action taken by the licensee are adequate-to close this LE (Closed) LER 280/90-14, Unit 1 and Unit 2 Recirculation Spray Heat Exchangers Declared Inoperable Due to Potentially Inadequate Service Water Flow Caused.by Macrofoulin The issue involved the inoperability of the Units 1 and 2 RSHXs due to low SW flow rate The cause of the low SW fl ow rates and corrective actions were discussed in Inspection Reports 50-280,281/90-30, and 50-280,281/90-3 Escalated enforcement action was taken as a result of the inoperable RSHX Long tenn corrective action in response to the inoperable RSHXs ~ill be reviewed during the closeout 6f this enforcement actio (Closed) LER 280/90-15, Hydrogen Analyzer Surveillance Testing in Violation of Technical Specifications Due to Misinterpretation of Technical Specification Requirement The issue involved a failure to test the hydrogen analyzers trouble alann as required by T After identification of the problem, the proper TS action statement was entered and a temporary procedure was written and perfonned to test the trouble alarm After satisfactory testing, the TS action statement was exite The issue was identified by the licensee during a procedure review which is a part of the procedure upgrade progra This program continues to review surveillance test procedures for compliance with TS requirements and appea~s effective. Failure to test the hydrogen analyzers as required by TS Table 4.1-2A, Item 20 is identified as an NCV (280,281/91-04-0l).
This licensee identified violation is not being cited because the criteria specified in section V.G.1 of the NRC Enforcement Policy were satisfi.ed.
6 '
(Closed) LER 280/90-17, Personnel Errors During Preparatio~s for Eme~gency Bus Undervoltage Testing Results in Loss of 4160V Transfer Bus and Start of Emergency Diesel Generator The issue involved an inadvertent ESF actuation which was caused by a short circuit when taking a continuity reading across undervoltage relay contacts during preparation for testing of the Unit lH emergency bu The actuation resulted in a loss of preferred power to the lH and 2J emergency busses. The emergency diesels auto-started and loaded onto the busses as designed, and operators took additional actions as* necessary to stabi 1 ize the unit This event was discussed in Inspection Report 280,281/90-3 A violation was identified in that report for failure to follow procedure during testing preparatio Additional corrective actions for this event will be reviewed during closeout 6f the violatio (Closed) LER 280/90-18, Unplanned Engineered. Safety Features Actuation Due to Inadequate Procedure The issue involved an unplanned ESF actuation during testing * of the consequence 1 imi ting safeguards 1 ogi c.. The actuation resulted in an inadvertent safety injection signal and was caused by an inadequate test procedur Several B train SI components actuated as designed; however, the consequences were minimal due to Unit 1 being in cold shutdown and much of the system being aligned for testin This event was discussed in Inspection Report 280,281/90-3 A violation was identified in that report for inadequate procedure during testin Additional corrective actiqns for this event will be reviewed during closeout of the violjtion. *
(Closed) LER-280/90-19, All Six~Main Feedwater Flow Transmitt~rs Rendered In6perable as a Resu*lt of Failure to Follow Procedures During Performance
- of a Hydrostatic Tes The issue involved* identification by technicians that the main feedwater fl ow transmitters were equal i.zed and isolated after Unit 1 startup. *immediate corrective action was to enter TS 3. action statement which reqtiired the condition to be correcte4 within the next six hours or the unit to be placed in hot shutdown conditio The transmitters *were returned to operation within the ne~t two hours ana the unit exited the action statemen The cause of the event was personnel error on the part of a test engineer perfonning unauthorized valve operation The licensee.also conducted a*root cause evaluatio.n of this event and several additional.* reco11111endations were identified to management *
for consideratio This event was discussed in Inspection Report 280,281/90-3 A licensee identified violation.was noted in that feport for failure to maintain the instrumentation operable as required by T (Closed) LER 281/90-05, Special Report Due to Exceeding 2 percent Quadrant Power Tilt for Greater Than 24 Hours. The issue involved exceeding the TS 3.12.B.7 limit for greater than 24. hour The limit was exceeded for approximately 32 hours3.703704e-4 days <br />0.00889 hours <br />5.291005e-5 weeks <br />1.2176e-5 months <br /> until excore detectors were recalibrate The condition was fully understood and was due to the inoperabil ity of rod (M-12) which is stuck and almost fully *inserted in the cor This co.ndition of operation is allowed by the TS.* This* event was discussed in Inspection Report 280~281/90-3 Within the areas inspected, one non-cited violation was identifie.
Action on Previous Inspection Findings (92701, 92702) (Closed) URI 280,281/88-04-02, Licensee Evaluation of Steam Flow Indication at Low Power Levels From a Design, Safety Analysis, and Operator Action Point of Vie The issue involved an inspector observation during a Unit 1 startup that steam flow indication was not available for operator infonnation until the indicated power level reached approximately 18 percent. Licensee review of the issue concluded that waiting until about 25 percent power level to verify operability of instrumentation with channel checks would have no impact on the existing safety analyse The issue was referred to NRC (NRR) offices for technical revie Based on these initial reviews, the issue is being considered for multiplant implications and any concerns that may be identified will be addressed after these reviews are complete. This unresolved item is close (Closed) URI 280,281/90-14-03, NRC Review of Required Surveillance Test Frequenc The issue involved a performance of TS required surveillances outside of the plus 25 percent grace period which was specified by TS 4. During these inspections, the licensee's position was that they were in compliance with TS and their program had been in effect since the units were license They also stated that the issue has been reviewed in the past by the NRC; however, no documentation was provided to support NRC acceptance of the current progra The NRC (NRR and Region II) reviewed the issue and concluded that the licensee's program was not in compliance with TS 4. The NRC reviewers stated that surveillance requirement time intervals should be determined from actual performance of surveillances, and that TS 4.0.2 specified time interval adjustments are to be based on actual performance of survei 11 ance After further discuss ions, the licensee implemented changes to their program to assure that TS required test intervals are me Failure to perform TS required surveillances within the allowed time interval is identified as an NCV (280,281/91-04-02).
This violation is not being cited because criteria specified in Section V.G.1 of the NRC Enforcement Policy were satisfie (Closed) Violation 281/90-20-01, Failure to Take Adequate Corrective Action for Pump 2-RS-P-2A Motor Bearing Drain Plug Oil Leakag The issue involved the failure to take timely corrective action for oil leakage from the motor lower bearing oil reservoir drain plug on outside recirculation spray pump 2-RS-P-2 The licensee responded to this violation in a letter dated July 26, 199 In that letter, the licensee stated that corrective*action was taken to replace the leaking oil plug with an oil drain assembly, and that, in the future, the drain plugs on the remaining Unit 1 and 2 outside recirculation spray pump motors would be replaced with oil drain assemblie The
- inspectors walked down the Units* 1 and 2 outside recirculation spray pumps and verified that the oil drain plugs were replaced with oil drain assemblie The inspectors consider that the corrective actions in response to the violation were properly implemente Within the areas inspected, one non-cited violation was identifie.
Plant Procedures (42700)
During this inspection period, a review was conducted of the status of th licensee's progress in implementation of their Procedure Upgrade Program for technical procedure The program was initially conceived in early 1989, and was redefined in scope in February, 199 Since that time, approximately 1100 procedures have been upgrade Current authorized staffing level for the station procedures group is 45 personne Eight vacancies are currently identified in the site technical procedures upgrade program sec ti o The technical upgrade program is projected to take approximately five more years to complete the initial procedure upgrade This area will receive additional review in the next inspection perio Within the areas inspected, no violations or deviations were identifie.
Exit Interview The inspection scope and results were surrmarized on February 25, 1991 with those individuals identified by an asterisk in paragraph The following summary of inspection activity was discussed by the inspectors during this exi Item Number NCV 280,281/91-04-01 NCV 280,281/91-04-02 Description and Reference Failure to test the hydrogen analyzers as required by TS Table 4.1-2A, Item 20
{paragraph 6).
Failure to perform TS required surveillances within the allowed time interval (paragraph 7.b).
Licensee management was informed of the weakness identified in paragraph 3.d and of the items closed in paragraphs 6 and The licensee acknowledged the inspection conclusions with no dissenting comment The 1 i censee did. not i den ti fy as proprietary any of the materials provided to or reviewed by the inspectors during this inspectio ~-------------------
1 Index of Acronyms amd Initialisms AFW AUXILIARY FEEDWATER CFA COMPONENT FAILURE ANALYSIS CFR CODE OF FEDERAL REGULATIONS DR DISCREPANCY. REPORT ESF ENGINEERED SAFETY FEATURE ESW
. EMERGENCY SERVICE WATER LCO LIMITING CONDITIONS OF OPERATION LER LICENSEE EVENT REPORT NCV NON-CITED VIOLATION NRC NUCLEAR REGULATORY COMMISSION NRR NUCLEAR REACTOR REGULATION RCS REACTOR COOLANT SYSTEM RSHX RECIRCULATION SPRAY HEAT EXCHANGER RWP RADIATION WORK PERMIT SNSOC STATION NUCLEAR SAFETY AND OPERATING COMMITTEE SW SERVICE WATER
_
TS TECHNICAL SPECIFICATION*
URI UNRESOLVED ITEM