IR 05000302/1993022
| ML20057E565 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 09/30/1993 |
| From: | Butcher R, Holmesray P, Landis K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20057E551 | List: |
| References | |
| 50-302-93-22, NUDOCS 9310120296 | |
| Download: ML20057E565 (8) | |
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[/pnech UNITED STATES
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NUCLEAR REGULATORY COMMISSION
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101 MARIETTA STREET, N.W., SUITE 2900
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Report No.:
50-302/93-22 Licensee:
Florida Power Corporation 3201 34th Street, South l'
St. Petersburg, FL 33733
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Docket No.:
50-302 License No.: DPR-72
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Facility Name:
Crystal River 3 Inspection Conducted:
August 15 - September 11, 1993
Inspector:
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t 3D N3 P. Holmds-Ray',' Senior sident Inspector Dat'e Si' ned
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g Inspector:
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e R. Butcher.,8etiior Residept Inspector Dath Sidned
Approved by:
K. Lindis, Section Chief Date Signed Division of Reactor Projects SUMMARY
Scope:
I This routine inspection was conducted by the resident inspectors in the areas of plant operations, security, radiological controls, maintenance and surveillance activities, Licensee Event Reports, facility modifications, and licensee action on previous inspection items. Numerous facility tours were conducted and facility operations observed.
Backshift inspections were conducted on 8/21, 26, 28, 29 and 30.
Results:
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In the area of plant operations, no violations were identified. The operating
. instructions for Decay Cooling valves were posted by the licensee and verified
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to be correct by the inspector (Paragraph 3.a.2).
In the area of maintenance / surveillance, two examples of good work practices
were observed during this reporting period (Paragraph 4.b and 4.c)
In the area of self assessment, aggressive self assessment was again observed
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by the inspector. This continued aggressive self assessment by the Plant Review Committee is considered a strength. (Paragraph 3 b)
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REPORT DETAILS 1.
Persons Contacted Licensee Employees
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J. Alberdi, Manager, Nuclear Plant Operations
- G. Becker, Manager, Site Nuclear Engineering Services
- G. Boldt, Vice President Nuclear Production
- W. Brewer, Supervisor, Site Nuclear Engineering Services
- W. Conklin, Director, Nuclear Operations Materials and Control
- R. Davis, Manager, Nuclear Plant Maintenance
- E. Froats, Manager, Nuclear Compliance
- F. Fusick, Manager, Design and Modifications G. Halnon, Manager, Nuclear Plant Systems Engineering
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B. Hickle, Director, Nuclear Plant Operations
- T. Lehmann, Nuclear Chemistry Manager
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- G. Longhouser, Nuclear Security Superintendent j
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- W. Marshall, Manager, Nuclear Plant Operations
- P. McKee, Director, Quality Programs
- R. McLaughlin, Nuclear Regulatory Specialist
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- A. Miller, Senior Nuclear Scheduling Coordinator
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- B. Moore, Manager, Nuclear Integrated Scheduling R. Widell, Director, Nuclear Operations Site Support
- K. Wilson, Manager, Nuclear Licensing
- R. Yost, Supervisor, Quality Audits Other licensee employees contacted included office, operations, engineering, maintenance, chemistry / radiation, and corporate personnel.
NRC Resident Inspectors
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- P. Holmes-Ray, Senior Resident Inspector R. Butcher, Senior Resident Inspector
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- Attended exit interview i
F Acronyms and initialisms used throughout this report are listed in '.he last paragraph.
2.
Plant Status and Activities
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The plant continued in power operation (Mode 1) for the duration of this inspection period.
On August 23 and 24 the Chief, Projects Section, Branch 2B, DRP was on site for a site visit.
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Plant Operations (71707, 93702, & 40500)
Throughout the inspection period, facility tours were conducted to observe operations and maintenance activities in progress.
The tours included entries into the protected areas and the radiologically
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controlled areas of the plant. During these inspections, discussions L
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were held with operators, health physics and instrument and controls technicians, mechanics, security personnel, engineers, supervisors, and plant management.
Some operations and maintenance activity observations were conducted during backshifts.
Licensee meetings were attended by the inspector to observe planning and management activities. The i
inspections confirmed FPC's compliance with 10 CFR, Technical
Specifications, License Conditions, and Administrative Procedures.
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a.
Operational Events 1)
On September 1, 1993, the operators reduced power to approximately 80 percent to isolate the "D" condenser waterbox and the "B" SCHE for work. The power reduction was performed with no problems encountered. The scheduled reduced power window was 32 hours3.703704e-4 days <br />0.00889 hours <br />5.291005e-5 weeks <br />1.2176e-5 months <br /> but the work was completed in 23 hours2.662037e-4 days <br />0.00639 hours <br />3.80291e-5 weeks <br />8.7515e-6 months <br />.
The plant was returned to full power on September 3, 1993.
The planing for and the work to complete
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these jobs was very well done.
2)
The instructions for operating DCV-177, 178, 17, and 18 were
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revised and posted in the decay heat pits to reflect the new manual operators installed by MAR 93-08-10-01.
The inspector reviewed the instructions and found that, if followed, the valves would be properly operated.
b.
Self assessment Several PRC meetings were held during this reporting period and attended by the resident inspector. The plant modifications to MVV-491 and to the DC control valves were on the agenda. The post maintenance testing for each of the modifications was also discussed. The PRC members, through their questions and discussion of the MARS, exhibited full understanding of the scope of the modifications. The MARS and the functional testing were approved by the PRC. The inspector observed that the discussion
and questions raised in PRC meetings were safety oriented and
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probing, resulting in a more thorough safety review than in the past.
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Radiological Protection Program Radiation protection control activities were observed to verify that these activities were in conformance with the facility policies and procedures, and in compliance with regulatory
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requirements. These observations included:
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Entry to and exit from contaminated areas, including step-l off pad conditions and disposal of contaminated clothing; t
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Area postings and controls;
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Work activity within radiation, high radiation, and contaminated areas;
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RCA exiting practices; and i
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Proper wearing of personnel monitoring equipment, protective i
clothing, and respiratory equipment.
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The implementation of radiological controls observed during this inspection period were proper and conservative.
The decay heat pits, with the exception of the areas in close proximity to the BSPs and the DHPs, were maintained in an
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uncontaminated condition during this report period. As a result, i
the work to replace the manual actuators on four DC valves was easier and therefore less dose intensive and more quickly accomplished since no protective clothing was required, d.
Security Control
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In the course of the monthly activities, the inspector included a
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review of the licensee's physical security program. 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; patrols; and compensatory posts.
In addition, the inspector observed the operational status of protected area lighting, protected and vital areas barrier integrity, and the security organization interface with operations and maintenance.
No performance discrepancies were identified by the inspectors.
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Fire Protection Fire protection activities, staffing, and equipment were observed to verify that fire brigade staffing was appropriate and that fire alarms, extinguishing equipment, actuating controls, fire fighting equipment, emergency equipment, and fire barriers were operable.
Violations or deviations were not identified.
4.
Maintenance and Surveillance Activities (62703 & 61726)
Surveillance tests were observed to verify that approved procedures were
being used; qualified personnel were conducting the tests; tests were
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adequate to verify equipment operability; calibrated equipment was utilized; and TS requirements appropriately implemented.
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The following tests were observed and/or data reviewed:
- SP-150, Operability and Functional Check of the Loose Parts Monitoring Subsystem;
- SP-190A, Functional and Operability Test of the Auxiliary Building Fire Detection Instrumentation;
- SP-210, ASME Class 3 Hydrostatic Testing;
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SP-317, RC System Water Inventory Balance; and
- SP-325, Turbine Generator Checks.
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In addition, the inspector observed 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 performed inspection activities as required; and TS requirements were being followed.
Maintenance was observed and work packages were reviewed for the following maintenance activities:
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WR312849, Replace SFV-27;
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WR313516, Replace manual operators on DCV-177,17,178 and 18;
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WR312972, Alignment of BSP-1B;
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UR312914, Repair computer points on plant computer;
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WR313196, Repair temperature element on MS-17-TE;
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WR310689, Hydrostatic test of SF system;
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WR311506, Clean and shoot DCHE-1B;
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WR312614, Removal of AHFL-10A filters, retaining clips and fasteners; and
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WR312618, Removal of AHFL-10B filters, retaining clips and fasteners.
The following items were considered noteworthy.
a.
NRC Bulletin 93-02, Debris Plugging of Emergency Core Cooling Suction Strainers On August 25, 1993, the licensee removed the filters from Air Handling Fan 2A and 2B (AHFL-10A/B) to complete the actions required in response to Bulletin 93-02. This work was accomplished by WR312624 and 312618.
The inspector attended the planning meetings and reviewed the completed work packages for the filter removal.
This completes actions to comply with NRC Bulletin 93-02, Action Item 1.
The licensee has also completed Action Item 2 by submitting a report to the NRC confirming the completion of Action Item 1.
This report was submitted on September 9, 1993.Bulletin 93-02 actions are completed.
b.
The issue of manual control of DCV-177, 178, 17 and 18 was resolved by WR313516 which implemented MAR 93-08-10-01.
The old manual operators which required engaging of the handwheel then removal of a shaft pin to gain manual control of the valve was replaced with a direct acting handwheel. The new manual control acts directly on the top of the shaft to move the valve from its normal position an backing off of the handwheel allows spring force to return the valve to its normal position. Two of the valves are normally open and two are normally closed. The
inspector observed portions of the modification in progress and portions of the functional testing. The expertise of the technician setting up the air operators for these DC valves was impressive.
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During trouble shooting of the plant computer to determine the c.
cause of rod 7-2 indicating greater than 100 percent withdrawn, the specialist noticed that other rods were indicat'ing greater than 100 percent. A printout disclosed that a total of eight rods were involved. The specialist recognized that the computer chips each contained eight data points and looked to see if all eight improperly indicating rods were from the same chip.
They were.
The chip was replaced and all rod height indications were indicating properly. The questioning attitude by this specialist i
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was observed by the inspector and was considered outstanding.
Overall, surveillance and maintenance activities observed and discussed above were performed in a satisfactory manner in accordance with procedural requirements and met the requirements of the TS.
Violations or deviations were not identified.
5.
Review of Licensee Event Reports (92700)
LERs were reviewed for potential generic impact, to detect trends, and to determine whether corrective actions appeared appropriate.
Events that were reported immediately were reviewed as they occurred to determine if the TS were satisfied.
LERs were also reviewed in accordance with the current NRC Enforcement Policy.
(Closed) LER 93-07:
Raised Setpoint on Pressure Regulator Leads to Operation Outside Design Basis. The corrective action for this LER was tracked by violation 93-17-01.
Violations or deviations were not identified.
6.
Design, Design Changes and Modifications (37828)
Installation of new or modified systems were reviewed to verify that the
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changes were reviewed and approved in accordance with 10 CFR 50.59, that the changes were performed in accordance with technically adequate and approved procedures, that subsequent testing and test results met acceptance criteria or deviations were resolved in an acceptable manner, and that appropriate drawings and facility procedures were revised as necessary. This review included selected observations of modifications and/or testing in progress.
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The following MARS were reviewed and/or associated testing observed:
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MAR 93-07-12-01, replace SFV-27; and
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MAR 93-08-10-01, replace manual operators on DCV-177,17,178, and 18.
Both MARS were installed and tested properly and the functional testing proved that both were installed correctly. The inspector observed portions of the installation and testing of both MARS.
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Licensee Action on Previ-ously Identified Inspection Findings (92702 &
92701)
(Closed) Violation 302/93-17-01 - Failure to Perform a Safety Evaluation Prior to Making a Plant Change That Affects Safety.
The immediate corrective action was to reduce the MUT hydrogen regulator setpoint to 10 psig and to increase operators' awareness with an Operations Study Book entry that proper documentation is required prior to making a plant change.
PRC reviewed a safety evaluation based on an engineering analysis that allowed increasing the MUT pressure to 19.5 psig and this evaluation was accepted by the PRC. The inspector observed the actions of the PRC and concluded that the review was indepth and the acceptance of the revised setpoint was based on solid evidence. This item is closed.
Violations or deviations were not identified.
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Exit Interview
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The inspection scope and findings were summarized on September 14, 1993,
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with those persons indicated in paragraph 1.
Proprietary information is not contained in this report.
Dissenting comments were not received
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from the licensee.
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Item Number Status Description and Reference I
VIO 50-302/93-17-01 Closed Failure to Perform a Safety
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Evaluation Prior to Making a Plant
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Change That Affects Safety.
(Paragraph 7)
LER 93-07 Closed Raised Setpoint on Pressure
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Regulator Leads to Operation Outside Design Basis. (Paragraph 5)
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Acronyms and Abbreviations
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AHFL - Air Handling Filters
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ASME - American Society of Mechanical Engineers
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BSP
- Building Spray Pump
i CFR
- Code of Federal Regulations
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- Decay Heat Cooling DCHE - Decay Heat Cooling Heat Exchanger DCV
- Decay Heat Cooling Valve DHP
- Decay Heat Pump DRP
- Division of Reactor Projects FPC
- Florida Power Corporation LER
- Licensee Event Report
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- Modification Approval Record i
MUT
- Make-up Tank i
MUV
- Make-up Valve
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NRC
- Nuclear Regulatory Commission PRC
- Plant Review Committee psig - pounds per square inch gauge
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- Radiation Control Area SCHE - Secondary Cooling Heat Exchanger SF
- Spent Fuel Cooling SFV
- Spent Fuel Valve SP
- Surveillance Procedure TS
- Technical Specification VIO
- Violation WR
- Work Request i