IR 05000261/2003005
| ML032820002 | |
| Person / Time | |
|---|---|
| Site: | Robinson  |
| Issue date: | 10/09/2003 |
| From: | Fredrickson P NRC/RGN-II/DRP/RPB4 |
| To: | Moyer J Carolina Power & Light Co |
| References | |
| IR-03-005 | |
| Download: ML032820002 (21) | |
Text
October 9, 2003
SUBJECT:
H.B. ROBINSON STEAM ELECTRIC PLANT - NRC INTEGRATED INSPECTION REPORT 05000261/2003005
Dear Mr. Moyer:
On September 13, 2003, the US Nuclear Regulatory Commission (NRC) completed an inspection at your Robinson facility. The enclosed integrated inspection report documents the inspection findings, which were discussed on September 12, 2003, with Mr. Tim Cleary and other members of your staff.
The inspection examined activities conducted under your license as they relate to safety and compliance with the Commissions rules and regulations and with the conditions of your license.
The inspectors reviewed selected procedures and records, observed activities, and interviewed personnel. Based on the results of this inspection, no findings of significance were identified.
In accordance with 10 CFR 2.790 of the NRC's "Rules of Practice," a copy of this letter and its enclosure will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records (PARS) component of NRCs document system (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Sincerely,
/RA/
Paul E. Fredrickson, Chief Reactor Projects Branch 4 Division of Reactor Projects Docket No.:
50-261 License No.:
Enclosure:
Inspection Report 05000261/2003005 w/Attachment: Supplemental Information
REGION II==
Docket No:
50-261 License No:
DPR-23 Report No:
05000261/2003005 Licensee:
Carolina Power and Light Company Facility:
H. B. Robinson Steam Electric Plant, Unit 2 Location:
3581 West Entrance Road Hartsville, SC 29550 Dates:
June 15 - September 13, 2003 Inspectors:
R. Hagar, Senior Resident Inspector D. Jones, Resident Inspector M. Shannon, Senior Resident Inspector, Oconee Approved by:
P. Fredrickson, Chief Reactor Projects Branch 4 Division of Reactor Projects
SUMMARY OF FINDINGS
IR 05000261/2003-005; 06/15/2003-09/13/2003; H.B. Robinson Steam Electric Plant, Unit 2; routine integrated inspection report.
The report covered a three-month period of inspection by resident inspectors. The NRCs program for overseeing the safe operation of commercial nuclear power reactors is described in NUREG-1649, Reactor Oversight Process, Revision 3, dated July 2000.
NRC-Identified and Self-Revealing Findings
No findings of significance were identified.
Licensee-Identified Violations
None
REPORT DETAILS
Summary of Plant Status: The unit began the inspection period at full rated thermal power, and operated at full power for the entire inspection period.
REACTOR SAFETY
Cornerstones: Initiating Events, Mitigating Systems, Barrier Integrity
==1R01 Adverse Weather Protection
a. Inspection Scope
==
During a tornado watch that was issued for the Darlington County area on July 1, and prior to the onset of severe weather, the inspectors reviewed actions taken by the licensee in accordance with Procedure OMM-021, Operation During Adverse Weather Conditions, to verify that the anticipated weather conditions would neither initiate a plant event nor prevent any system, structure, or component (SSC) from performing its design function. Documents reviewed are listed in the Attachment.
b. Findings
No findings of significance were identified.
==1R04 Equipment Alignment
a. Inspection Scope
Partial System Walkdowns==
During this inspection period, the inspectors performed the following four partial system walkdowns, to verify the operability of redundant systems with both trains in service or while the SSCs were out of service for maintenance and testing:
- Auxiliary feed water (AFW) system with the steam-driven AFW pump out of service on July 15.
- Component cooling water system on August 21.
- Service water system on August 19 and 20.
- Dedicated shutdown diesel generator during scheduled maintenance activities on August 28.
To evaluate the operability of the selected trains or systems under these conditions, the inspectors verified correct valve and power alignments by comparing observed positions of valves, switches, and electrical power breakers to the procedures and drawings listed in the Attachment.
b. Findings
No findings of significance were identified.
==1R05 Fire Protection
a. Inspection Scope
==
For the six areas identified below, the inspectors reviewed the licensees control of transient combustible material and ignition sources, fire detection and suppression capabilities, fire barriers, and any related compensatory measures, to verify that those items were consistent with Final Safety Analysis Report (FSAR) Section 9.5.1, Fire Protection System, and FSAR Appendix 9.5.1A, Fire Hazards
Analysis.
The inspectors walked down accessible portions of each area and reviewed results from related surveillance tests, to verify that conditions in these areas were consistent with descriptions of the areas in the FSAR. Documents reviewed are listed in the
.
The following areas were inspected:
Fire Zone Description Safety injection pump room Component cooling room Auxiliary building hallway (ground floor)
Diesel fuel oil storage tank Control room Service water pump area
b. Findings
No findings of significance were identified.
==1R11 Licensed Operator Requalification
a. Inspection Scope
==
On August 5, the inspectors observed licensed-operator performance during continuing simulator training for crew 2, to verify that operator performance was consistent with expected operator performance, as described in Operations Training Procedure, FSS-SEG-30. This training tested the operators ability to correctly diagnose abnormal conditions, use appropriate emergency operating procedures when necessary, and declare the appropriate emergency action level in a timely manner. The inspectors focused on clarity and formality of communication, the use of procedures, alarm response, control board manipulations, group dynamics and supervisory oversight.
The inspectors also observed the post-exercise critique, to verify that the licensee identified deficiencies and discrepancies that occurred during the simulator training.
Documents reviewed are listed in the Attachment.
b. Findings
No findings of significance were identified.
==1R12 Maintenance Effectiveness
a. Inspection Scope
==
The inspectors reviewed overheating of the engine-driven fire pump, as described in action request (AR) 100310, to verify the licensees appropriate handling of this condition in accordance with 10CFR50, Appendix B, Criterion XVI, Corrective Action, and 10CFR50.65, Maintenance Rule. Documents reviewed are listed in the Attachment.
During this review, the inspectors focused on the following:
- Appropriate work practices,
- Identifying and addressing common cause failures,
- Scoping in accordance with 10 CFR 50.65(b),
- Characterizing reliability issues (performance),
- Charging unavailability (performance),
- Trending key parameters (condition monitoring),
- 10 CFR 50.65(a)(1) or (a)(2) classification and reclassification, and
- Appropriateness of performance criteria for SSCs/functions classified (a)(2) and/or appropriateness and adequacy of goals and corrective actions for SSCs/functions classified (a)(1).
b. Findings
No findings of significance were identified.
==1R13 Maintenance Risk Assessments and Emergent Work Evaluation
a. Inspection Scope
==
For the time periods listed below, the inspectors reviewed the licensees risk assessments and the risk management actions used by the licensee to manage risk.
The inspectors verified that the licensee performed adequate risk assessments, and implemented appropriate risk management actions when required by 10CFR50.65(a)(4).
- The work week of August 31, which included an outage of the A emergency diesel generator.
- The work week of September 7, which included maintenance on the A residual heat removal system and emergent work associated with a level-control valve.
b. Findings
No findings of significance were identified.
==1R14 Personnel Performance During Non-Routine Plant Evolutions
a. Inspection Scope
==
On August 14, during a 12-MW load reduction that occurred as a result of electrical grid disturbances, the inspectors observed plant instruments and operator performance, to verify that the operators performed in accordance with the associated procedures and training. Documents reviewed are listed in the Attachment.
b. Findings
No findings of significance were identified.
==1R15 Operability Evaluations
a. Inspection Scope
==
The inspectors reviewed the operability determination described in AR 99903, available net positive suction head for emergency core cooling system pumps. The inspectors assessed the accuracy of the evaluations, the use and control of any necessary compensatory measures, and compliance with the Technical Specifications (TS). The inspectors verified that the operability determination was made as specified by procedure PLP-102, Operability Determinations. The inspectors compared the justifications made in the determination to the requirements from the TS, the FSAR, and associated design-basis documents, to verify that operability was properly justified, and that the subject component or system remained available, such that no unrecognized increase in risk occurred. Documents reviewed are listed in the Attachment.
b. Findings
No findings of significance were identified.
==1R16 Operator Work-Arounds
a. Inspection Scope
==
The inspectors reviewed the cumulative effects of the operator workarounds in effect on July 18, to verify that those effects could not increase an initiating event frequency, affect multiple mitigating systems, or affect the ability of operators to respond in a correct and timely manner to plant transients and accidents.
b. Findings
No findings of significance were identified.
==1R19 Post Maintenance Testing
a. Inspection Scope
==
For the seven post-maintenance tests listed below, the inspectors witnessed the test and/or reviewed the test data, to verify that test results adequately demonstrated restoration of the affected safety function(s) described in the FSAR and TS. Documents reviewed are listed in the Attachment. The tests included the following:
- OST-910, Dedicated Shutdown Diesel Generator (Monthly), on July 11
- OP-306, Component Cooling Water, on July 9
- OST-206, Comprehensive Flow Test for the Steam Driven Auxiliary Feedwater Pump, on July 15
- OST-202, Steam Driven Auxiliary Feed Water System Component Test, on July 15
- OST-401-1, Emergency Diesel Generator A Slow Speed Start, on July 14
- OST-152-1, SI Valve Position and ERFIS Indication Test - Train A, on July 16
- OST-401-1, Emergency Diesel Generator A Slow Speed Start, on September 3
b. Findings
No findings of significance were identified.
==1R22 Surveillance Testing
a. Inspection Scope
==
For the five surveillance tests identified below, the inspectors witnessed testing and/or reviewed the test data, to verify that the SSCs involved in these tests satisfied the requirements described in the TS, the FSAR, and applicable licensee procedures, and that the tests demonstrated that the SSCs were capable of performing their intended safety functions. Documents reviewed are listed in the Attachment.
- OST-051, Reactor Coolant System Leakage Evaluation, on August 13
- OST-750-1, Control Room Emergency Ventilation System - Train A (Monthly), on July 10
- OST-642, Main Transformer Deluge System Flow Test (Annually), on July 3
- SFS-001, IF-300 Shipping Cask Operations, on July 1
- OST-252-1*, [Residual Heat Removal] System Valve Test - Train A, on September
- This procedure included inservice testing requirements.
b. Findings
No findings of significance were identified.
==1R23 Temporary Plant Modifications
a. Inspection Scope
==
The inspectors reviewed the temporary modifications described in the Engineering Changes (ECs) listed below, to verify that the modifications did not affect the safety functions of important safety systems, and to verify that the modifications satisfied the requirements of 10CFR50, Appendix B, Criterion III, Design Control. Documents reviewed are listed in the Attachment.
- EC 53127, Heating Ventilation Exhaust - 6A
- EC 53007, Belzona Repair to A Main Feed Pump Casing
b. Findings
No findings of significance were identified.
OTHER ACTIVITIES
4OA1 Performance Indicator Verification
a. Inspection Scope
Barrier Integrity Cornerstone For the Reactor Coolant System Specific Activity Performance Indicator (PI), the inspectors reviewed licensee submittals for the period from September, 2002, through August, 2003. To verify the accuracy of the PI data reported during that period, the inspectors compared the licensees reported data to the PI definitions and guidance contained in NEI 99-02, Regulatory Assessment Performance Indicator Guideline, Rev.
2. The inspectors also observed licensee sampling and analysis of reactor coolant
system samples, and compared the licensee-reported performance indicator data with records developed by the licensee while analyzing previous samples.
b. Findings
No findings of significance were identified.
4OA6 Meetings, Including Exit
On September 12, 2003, the resident inspectors presented the inspection results to Mr.
Tim Cleary and other members of his staff. The inspectors confirmed that proprietary information was not provided or examined during the inspection.
SUPPLEMENTAL INFORMATION
KEY POINTS OF CONTACT
Licensee personnel
- C. Burton, Director of Site Operations
- E. Caba, Design Engineering Superintendent
- B. Clark, Manager Training
- A. Cheatham, Radiation Protection Superintendent
- C. Church, Engineering Manager
- T. Cleary, Plant General Manager
- W. Farmer, Technical Services Superintendent
- R. Howell, Regulatory Support Supervisor
- R. Ivey, Operations Manager
- E. Kapopoulos, Outage & Scheduling Manager
- J. Lucas, Nuclear Support Services Manager
- G. Ludlum, Operations Training Superintendent
- J. Moyer, Vice President, Robinson Nuclear Plant
- E. Rothe, Nuclear Assurance Section Manager
- D. Stoddard, Maintenance Manager
NRC personnel
- P. Fredrickson, Chief, Reactor Projects Branch 4
LIST OF ITEMS OPENED, CLOSED, AND DISCUSSED
None