IR 05000400/1992023
| ML18010A900 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 11/05/1992 |
| From: | Christensen H, Shannon M, Tedrow J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML18010A899 | List: |
| References | |
| 50-400-92-23, NUDOCS 9211180096 | |
| Download: ML18010A900 (13) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTASTREET, N.W.
ATLANTA,GEORGIA 30323 Report No.:
50-400/92-23 Licensee:
Carolina Power and Light Company P. 0.
Box 1551 Raleigh, NC 27602 Docket No.:
50-400 Facility Name:
Harris
Inspection Conducted:
Se tember 26 - October 23, 1992 Inspectors:
J.
Ted ow, enior Resident Inspector M.
nnon, Resident nspector Approved by:
H. Christensen, Section Chief Division of Reactor Projects Licensee No.:
NPF-63 D
Date Signed Da e Si ned II S Da e
igned SUMMARY Scope:
This routine inspection was conducted by two resident inspectors in the areas of plant operations, radiological controls, security, fire protection, surveillance observation, maintenance observation, audit of safety reviews, and refueling activities.
Numerous facility tours were conducted and facility operations observed.
Some of these tours and observations were conducted on backshifts.
Results:
No violations or deviations were identified.
The licensee's safety review of plant modifications was considered to be strong, paragraph 6.
The licensee's response to an industry concern regarding feedwater pipe erosion was considered to be proactive, paragraph 8.
92iii80096 'V2ii05 PDR ADOCK 05000400
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REPORT DETAILS 1.
Persons Contacted Licensee Employees
- J. Collins, Manager, Operations
- J. Cribb, Manager, guality Control
- C. Gibson, Manager, Programs and Procedures
- C. Hinnant, General Manager, Harris Plant
- D. Knepper, Project Engineer, Nuclear Engineering Dept.
- B. Meyer, Manager, Environmental and Radiation'onitoring
- T. Morton, Manager, Maintenance J.
Moyer, Manager, Project Assessment
- J. Nevill, Manager, Technical Support C. Olexik, Manager, Regulatory Compliance A. Powell, Manager, Harris Training Unit
- W. Seyler, Manager, Outages and Modifications H. Smith, Manager, Radwaste Operation
- G. Vaughn, Vice President, Harris Nuclear Project W. Wilson, Manager, Spent Nuclear Fuel Other licensee employees contacted included office, operations, engineering, maintenance, chemistry/radiation and corporate personnel.
- Attended exit interview 2.
Acronyms and initialisms used throughout this report are listed in the last paragraph.
Review of Plant Operations (71707)
The plant began this inspection period in the cold shutdown (Mode 5)
condition.
On September 27, 1992, refueling operations (Mode 6) were commenced and the plant was defueled at 5:35 a.m.
on October 4.
The plant remained in the defueled condition for the duration of this inspection period.
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Shift Logs and Facility Records The inspector reviewed records and discussed various entries with operations personnel to verify compliance with the Technical Specifications (TS)
and the licensee's administrative procedures.
The following records were reviewed:
Shift Supervisor's Log; Outage Shift Manager'
Log; Control Operator's Log; Night Order Book; Equipment Inoperable Record; Active Clearance Log; Grounding Device Log; Temporary Modification Log; Chemistry Daily Reports; Shift Turnover Checklist; and selected Radwaste Logs.
In addition, the inspector independently verified clearance order tagout The inspectors found the logs to be readable, well organized, and provided sufficient information on plant status and events.
Clearance tagouts were found to be properly implemented.
No violations or deviations were identified.
Facility Tours and Observations Throughout the inspection period, facility tours were conducted to observe operations, surveillance, and maintenance activities in progress.
Some of these observations were conducted during backshifts.
Also, during this inspection period, licensee meet ngs were attended by the inspectors to observe planning a d management activities.
The facility tours and bservation's encompassed the following areas:
security perimeter fence; control room; emergency diesel generator building; reactor auxiliary building; reactor containment buildihg; waste processing building; turbine building; fuel handling building; emergency service water building; battery rooms; electrical switchgear rooms; and the technical support center.
During these tours, the following observations were made:
(I)
Honitoring Instrumentation
- Equipment operating status, area atmospheric and liquid radiation monitors, electrical system lineup, reactor operating parameters, and auxiliary equipment operating parameters were observed to verify that indicated parameters were in accordance with the TS for the current operational mode.
(2)
Shift Staffing - The inspectors verified that operating shift staffing was in accordance with TS requirements and that control room operations were being conducted in an orderly and professional manner.
In addition, the inspector observed shift turnovers on various occasions to verify the continuity of plant status, operational problems, and other pertinent plant information during these turnovers.
(3)
Plant Housekeeping Conditions - Storage of material and components, and cleanliness conditions of various
~ areas -throughout the facility were observed to determine whether safety and/or fire hazards existed.
(4)
Radiological Protection Program - Radiation protection control activities were observed routinely to verify that these activities were in conformance with the facility's policies and procedures, and in compliance with regulatory requirements.
The inspectors also
reviewed selected radiation work permits to verify that controls were adequate.
(5)
Security Control
- The performance of various shifts of the security force was observed in the conduct of daily activities which included:
protected and vital area access controls; searching of personnel, packages, and vehicles; badge issuance and retrieval; escorting of visitors; patrols; and compensatory posts.
In addition, the inspector observed the operational status of closed circuit television monitors, the intrusion detection system in the central and secondary alarm stations, protected area lighting, protected and vital area barrier integrity, and the security organization interface with operations and maintenance.
(6)
Fire Protection
- Fire protection activities, staffing and equipment were observed to verify that fire brigade staffing was appropriate and that fire alarms, actuating controls, fire fighting equipment, emergency equipment, and fire barriers were operable.
The inspectors found plant housekeeping and material condition of safety related components to be good.
The licensee's adherence to radiological controls, security controls, fire protection requirements, and TS requirements in these areas was satisfactory.
c.
Review of Nonconformance Reports Adverse Condition Reports were reviewed to verify the following:
TS were complied with, corrective actions and generic items were identified and items were reported as required by 10 CFR 50.73.
Surveillance Observation (61726)
Surveillance tests were observed to verify that approved procedures were being used; qualified personnel were conducting the tests; tests were adequate to verify equipment operability; calibrated equipment was utilized; and TS requirements were followed.
.The following tests were observed and/or data reviewed:
~ MST-1182 Containment Spray Additive Tank Level Loop (L-7150)
Calibration
~ PIC-E007 Differential Voltage Relay PVD21 Calibration
~ OST-1813 Remote Shutdown System Operability 18 Month Interval
~ OST-1825 Safety Injection:
ESF Response Time, Train A 18 Month Interval on a Staggered Test Basis The performance of these procedures was found to be satisfactory with
'roper use of calibrated test equipment, necessary communications established, notification/authorization of control room personnel, and knowledgeable personnel having performed the tasks.
No violations or deviations were observed.
Maintenance Observation (62703)
The inspector observed/reviewed maintenance activities to verify that correct equipment clearances were in effect; work requests and fire prevention work permits, as required, were issued and being followed; quality control personnel were available for inspection activities as required; and TS requirements were being followed.
Maintenance was observed and work packages were reviewed for the following maintenance activities:
~
Replacement of the camshaft for the "B" EDG in accordance with procedure CH-H0153, Emergency Diesel Generator Camshaft Disassembly and Reassembly.
~
Replacement of a reactor vessel level detector in accordance with modification PCR-5322, Replacement of PT-OIRC-0402IW.
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Replacement and realignment of the rotating element for the turbine driven auxiliary feedwater pump in accordance with procedure CH-H0071, Ingersoll
- Rand Turbine Driven Auxiliary Feedwater Pump Size
X 9 NH-7 Disassembly and Maintenance.
~
Disassembly and Reassembly of the lube oil keep warm pump for the
"B" EDG in accordance with procedure CH-M0163, Emergency Diesel Generator Lube Oil Keep Warm Pump.
~
Preventive Maintenance on electrical switchgear in accordance with procedures PM-E003, 6.9 KV Bus and Cubicle, and PM-E005, 6.9 KV 1200/2000 Amp Air Circuit Breaker PH.
During the performance of the five-year inspection of the "B" EDG, licensee personnel, in conjunction with a manufacturer representative, noticed some spalling and wear on several camshaft lobes.
One tappet assembly was also observed to be cracked.
These conditions were unexpected since the diesel had only 622 accumulated hours of operation or an equivalent 372 full load operating hours.
The licensee decided to conservatively replace both camshafts on the diesel engine and has added a camshaft inspection of the "A" EDG to the current outage schedule.
The performance of work was satisfactory with proper documentation of removed components and independent verification of the reinstallation.
No violations or deviations were identifie Review of Plant Nuclear Safety Committee Activity (40500)
The inspectors attended selected PNSC meetings to observe committee activities and verify TS requirements with respect to committee composition, duties, and responsibilities.
Minutes from these meetings were also reviewed to verify accurate documentation.
During the September 30, 1992 PNSC meeting, a modification to replace the charging system alternate mini-flow relief valves with a flow orifice was discussed.
The inspector considered the conduct and documentation of these meetings to be satisfactory.
No violations or deviations were identified.
CFR 50.59 Safety Re'view Audit During the week of April 20, 1992, the NRR Project Manager performed an audit of safety reviews to verify conformance with the provisions of 10 CFR 50.59.
The audit was commenced from the Harris 1991 annual summary report of the
CFR 50.59 activity submitted by letter dated February 25, 1992.
This summary listed 47 Plant Change, Requests (PCR) which received a
50.59 review during 1991.
The list was reviewed with respect to safety significance.
Based on their safety significance, four PCR reviews were selected for detailed review.
The controlling plant procedure, AP-011, Safety Reviews, was reviewed in detail against NSAC-125, "Guidelines for 10 CFR 50.59 Safety Evaluation."
The most current version of AP-011 (Revision 5) was reviewed for any intervening changes.
The 50.59 reviews of the PCRs were then evaluated for conformance to plant procedure, AP-011, Safety Reviews.
The PCR evaluations selected for audit were:
~ PCR-3418, Main Feed Pump Recirculation Valve Replacement
~ PCR-5236, Reactor Coolant Pump Motor Oil Reservoir Level Indication
~ PCR-5748, Component Cooling Water Thermal Relief Valve Deletion
~ PCR-4489, Residual Heat Removal Midloop Modifications In summary, the 50.59 review process at Harris is considered a strength because it is consistent with NSAC-125.
Trained, tested and experienced reviewers are maintained by technical discipline to perform 50.59 evaluations.
In addition, two independent reviewers perform the evaluation to confirm the conclusion.
Refueling Activities (60710)
The inspectors witnessed several shifts of fuel handling operations and verified that the refueling was being performed in accordance with TS requirements and approved procedures.
Areas inspected included containment integrity, housekeeping in the refueling area, shift
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staffing during refueling, surveillance testing, and periodic monitoring of plant status during refueling operations.
In addition, the following procedures were reviewed:
~ GP-009 Refueling Cavity Fill, Refueling, and Draindown of the Refueling Cavity
~ FHP-010 Core Mapping Following Fuel Loading
~ FHP-014 Fuel and Insert Shuffle Sequence
~ FHP-020 Fuel Handling Operations
~ FHP-22T Temporary Procedure for Fuel Ultrasonic Inspection and Reconstitution Operations Procedure FHP-22T was planned and implemented due to the elevated RCS activity levels noticed during the operating cycle as discussed in NRC Inspection Report 50-400/91-23.
The licensee found that two fuel rods had failed.
These rods were replaced with dummy stainless steel inserts.
The defueling operation and fuel reconstitution were performed satisfactory.
No violations or deviations were identified.
Licensee Action in Response to NRC Information Notices (92701)
The licensee's action in response to NRC Information Notice 92-07, Rapid
,
Flow-Induced Erosion/Corrosion of Feedwater Piping, was reviewed.
During this refueling outage the licensee decided to conservatively check the six inch diameter pre-heater bypass piping and associated auxiliary feedwater piping in the steam tunnel and containment building even though computer calculations indicated that no problem should exist.
During ultrasonic testing, licensee personnel found significant erosion in the carbon steel pre-heater bypass piping and on several auxiliary feedwater elbows and other piping inside containment which indicated that piping thickness was below the minimum design thickness required.
Approximately 30 percent of the subject piping is in need of repair.
IFI (400/92-23-01):
Review the license's activities to repair pre-heater bypass and auxiliary feedwater piping due to erosion.
The licensee's proactive measures to check this piping, even though the erosion/corrosion computer program indicated satisfactory conditions, was beneficial and avoided a potentially serious pipe rupture and plant transient.
Exit Interview (30703)
The inspectors met with licensee representatives (denoted in paragraph 1) at the conclusion of the inspection on October 23, 1992.
During this meeting, the inspectors summarized the scope and findings of the inspection as they are detailed in this report, with particular emphasis
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on the Inspector Follow-up Item addressed below.
The licensee representatives acknowledged the inspector's comments and did not identify as proprietary any of the materials provided to or reviewed by the inspectors during this inspection.
No dissenting comments from the licensee were received.
Item Number Descri tion and Reference 400/92-23-01 IFI:
Review the license's activities to repair pre-heater bypass and auxiliary feedwater piping due to erosion, paragraph 8.
II.
Acronyms and Initialisms CFR EDG ESF FSAR IFI KV NRC NRR PCR PNSC RCS/RC-TS Code of Federal Regulations Emergency Diesel Generator Engineered Safety Feature Final Safety Analysis Report Inspector Follow-up Item Kilovolt Nuclear Regulatory Commission Nuclear Reactor Regulation Plant Change Request Plant Nuclear Safety Committee Reactor Coolant System Technical Specification
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