IR 05000302/1978026
| ML19270F021 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 11/13/1978 |
| From: | Ford E, Kellogg P, Ouzts J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19270F009 | List: |
| References | |
| 50-302-78-26, NUDOCS 7901110172 | |
| Download: ML19270F021 (9) | |
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UNITED STATES g>* REGoq[o NUCLEAR REGULATORY COMMISSION
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Report No. 50-302/78-26 Docket No.
50-302 License No.
DPR-72 Licensee: Florida Power Corporation
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3201 34th Street South
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St. Petersburg, Florida 33733 Facility Name:
Crystal River Unit No. 3 Inspection at:
Crystal River, Florida Inspection conducted: October 23-27, 1978 Inspectors:
J. E. Ouzts B. R. Messitt E. J. Ford Accompanying Personarwip pe.
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>f Approved by:
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P. J.
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Nuclear ~ pport Section No. 2 Reactor Operations and Nuclear Support Branch Inspection Summary Inspection on October 23-27, 1978 (Report No. 50-302/78-26)
Areas Inspected:
Routine, unannounced inspection of calibration, surveil-lance and maintenance for Unit No. 3.
The inspection involved 84 inspector-hours on site by three NRC inspectors.
Results: Of the three areas inspected, no items of noncompliance or deviations were found in two areas; one apparent item of noncompliance was found in one area (deficiency - failure to take corrective action on data that was out of tolerance paragraph 5.).
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RII Report No. 50-302/76-26 I-I h, h z<
// - 27W Prepared by:[ dord, Reactor Inspector DETAILS I E.J.
Date Nuclea-Support Section No. 2 Reactor Operations and Nuclear Su ort Br nch b
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' Messitt, Reactor Ittspector Date Nuclear Support Section No. 2 Reactor Operations and Nuclear Suppogt anch l
'W O-2 9 -TT Date J. If.pm _tmac tf r Irppec t o r Nucleat Support Sectioh No. 2 Reactor Operations and Nuclear Support Branch Dates of Inspectionn 0 obar 23.7,1978
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Reviewed by:
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P. K Dhte
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Nuclear Support Section No. 2 Reactor Operations and Nuclear Support Branch 1.
Persons Contacted
- G. P. Beatty, Plant Manager
- J. Cooper, NRC Coordinator R. Cunningham, I&C Supervisor J. Harrison, Assistant Chemistry /RADCON Engineer
- K. L. Lancaster, Compliance Auditor J. Parrish, Plant Engineer F. W. Pluebell, Electrical Supervisor P. D. Breedlove, Office Manager
- J. R. Wright, Chem / Rad Protection Engineer
- P. F. McKee, Assistant Plant Manager
- J. E. Mack, Plant Engineer
- W. R. Nichols, Operations Supervisor
- G. R. Westaf er, Maintenance Superintendent The inspectors interviewed three nuclear technical support technicians and members of the engineering staf f were also contacted, as well as other mechanics and technicians in the shops.
- Denotes those attending exit intervie.
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RII Report No. 50-302/78-26 I-2 2.
Licensee Action on Previous Inspection Findings Not inspected.
3.
Unresolved Items Unresolved items are matters about which more in, formation is required in order to ascertain whether they are acceptable items, items of noncompliance or deviations. Three unresolved items disclosed during the inspection are discussed in paragraphs 5, 6, and 7.
4.
Exit Interview The inspectors met with licensee representatives (denoted in paragraph 1)
at the conclusion of the inspection on October 27, 1978, and summarized their findings as discussed in paragraphs 5, 6, and 7.
The licensee acknowledged these findings and committed to corrective actions as discussed in these details.
5.
Instrument Calibration Program Verification The inspectors conducted a review of the following calibration proce-dures and associated test results:
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Containment Sump Level and Flow Montioring System Calibration Plant Instrumentation Calibration SP-169
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Calibration of the Reactor Protection System SP-112
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Functional Testing and Calibration of the Triaxial Time-History Accelographs and Triaxial Seismic Switch SP-162
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Post Accident Monitoring Instrumentation Calibration SP-132
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Engineered Safeguards Channel Calibration Pressurizer Level Instrumentation Calibration SP-170
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Core Flood Tank 3A, Proc. CF 1-2 CF-001-P11
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Borated Water Storage Tank Level, SP-162 DH-007-L1
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LP Injection Crossover Flow, Proc DH38 DH-038-FIl
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RII Report No. 50-302/78-26 1-3 Borated Water to Reactor Vessel, SP-161 DH-039-TI
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DW-010-FIT
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Demin Water to Nuclear P.' ant, 5,000 gals.
DW-10 Main Feedwater 3A Discharge - Proc. FW38 FW-038-PI
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RC Pump Seals 3A-1 Pump Proc. MU7-1 MU-007-DP71
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KUV-031-AC7
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RC Makeup Flow Proc. SP-170 SC Surge Tank Proc. T505 SC-067-LI
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The procedures and calibration results were reviewed to verify:
reviews and approvals were being conducted and data were recorded
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and evaluated;
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test instruments were listed and identified in test results; adherence to technical specifications requirements and limiting
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conditions for operations were observed; technical contents were correct and verification of return of
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equipment to service and removal of test equipment was being done;
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acceptance criteria were given and had been met, documented and signed of f by performing persons that a second person had reviewed test results.
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The inspector conducted an inspection of measuring and test equipment laboratory facilities and reviewed records as follows:
Primary and secondary standards laboratory
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Measuring and test tool storage and issuing room
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These facilities were inspected to verify:
that standard test instruments were labeled and included in the
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Q equipment calibration program; instruments were calibrated on schedule and labeled with calibra-
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tion status; storage facilities were proper for protecting the equipment;
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RII Report No. 50-302/78-26 I-4 nonconforming equipment was being tagged and provided with
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segregated storage; certification and calibration records were available and being
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maintained for measuring and test equipment.
The inspector used one or more of the following acceptance criteria for evaluating the above items in the calibration program:
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Quality Programs Administrative Procedure No. 22, Surveillance Activities AI-700, Administrative Instructions for Conduct of Technical Services
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Technical Specifications
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Compliance Procedure CP-107: Test Instruments, Standards and Calibration Control
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ANSI N18.7 (1972/76)
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ANSI N45.2 (1971)
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Inspector Judgement The inspector witnessed calibration test SP-433, In-Core Neutron Detectors Channel Check, and interviewed technicians to insure:
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that the correct procedure was being used; prerequisites for the test had been established;
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calibrated test instruments were being used;
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stations were manned and communications established;
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data was properly collected and evaluated;
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the technicians understood the instrume,nts and procedures.
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Within the areas inspected, one apparent item of noncompliance was identified.
In accordance with ANSI 18.7 of November 1972, Paragranh 6.4 as implemented by document AI-700, Paragraph 3.2.1.1, acceo-tance criteria is required to be evaluated and approved and out-of-specification test results require correction.
Contrary to the above, Data Sheet IV of SP-132, Engineered Safeguards Channel Calibration, indicated that RC-3B-PT3 failed to meet specified tolerances and no apparent corrective action was taken. This is desig-nated as an item of noncompliance, a deficiency (50-302/78-26-01).
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RII Report No. 50-302/78-26 I-5 An unresolved item was also identified during the inspection; the emergency safety features bus under voltage relay (s) lacked calibra-tion procedures (50-302/78-26-04).
6.
Surveillance (Periodic) Test Procedure and Results Verification The inspectors conducted a review of test proce,dures and results as follows:
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Moderator Temperature Coefficient SP-103
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Reactor Protective System Functional Testing SP-110
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Containment Leak Tests - Type B&C SP-179
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Containment Airlock Test (Semi-Annual)
Heat Balance Calculations SP-132
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RC System Water Inventory Balance SP-317
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BWST Operability Test SP-320
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ECCS Pump Operability Test ECCS & Boration Flow Path SP-347
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Emergency Diesel Fuel Oil Quality and Diesel SP-354
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Generator Monthly Tests Reactivity Balance Calculation SP-421
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RC Support System Chemistry Surveillance Program SP-713
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The inspectors also monitored the performance of Section 6.3 - 6.7 and Section 6.9 of SP-110 Reactor Protective System Functional Testing that was performed on 10-25-78.
The inspectors used one or more of the following acceptance criteria for the above items:
FSAR Section 1.7, 12, and 13
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ANSI N18.7 (1976)
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ANSI N18.1 (1972)
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RII Report No. 50-302/78-26 1-6
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P0QAM Technical Specifications
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ANSI N45.2 (1971)
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Inspector Judgement The test procedures and test results were reviewe'd to verify:
that test prerequisites and plant conditions were specified and
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reviewed, and approvals had been performed; that contents of the procedures were correct and the tests were
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performed on schedule;
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that test instruments were listed in the procedures and instruments used were identified in the results; that test results were recorded and compared with acceptance
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criteria and the return of the system / equipment to service and removal of test equipment was verified upon completion of the test.
Within the areas inspected there were no items of noncompliance identi-fied. However, two areas of concern were noted as indicated below:
a.
A lack of documentation of prompt supervisory review exists in regard to the chemistry surveillance procedures.
The licensee has acknowledged that the problem exists and has agreed to take steps to correct it.
This item will remain unresolved pending future reviews of chemistry data sheets by NRC (50-302/78-26-02).
b.
A procedural deficiency in SP-110 with regard to specifying an acceptable range in the acceptance criteria exists. The licensee has acknowledged this finding and has. agreed to take steps to rectify the situation.
This item will remain unresolved pending f urther NRC review of licensee surveillance records (50302-78-26-03).
7.
Maintenance Program Verification The inspec.or conducted a review of maintenance documentation as follows:
WR No. T 01373 - Installation of Grating Around Reactor Coolant
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Pump "A" Seal
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RII Report No. 50-302/78-26 I-7 WR No. 0024 - Install Lower Manway on OTSG 1B
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WR No. C00614 - Repair Vent Valve for CRD 61
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WR No. M01905 - Replace Control Rod Drive Motor Tube - H2
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WR No. C00575 - Replace Valves HVJF7 and HVJF8 for FW Turbine
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Lube Oil System
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WR No. 00305 - FWV-3B-FW - Booster Pump Isolation Valve Leak Repair WR No. 01208 - Auxiliary Building Personnel Hatch RMDJ-2J -
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Replaced Broken Roller Bearing WR No. MC0189 - Valve CFV-1 Repair - Core Flood
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WR No. M01335 - Repair Valve CFV-5 Packing Leak
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WR No. M0125 - Repair Valve CFV-12 Motor Operator - Core Flood System
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WR No. M01307 - Repair Packing Leak for Decay Heat DC Pump WR No. M00316 - Repair Valve DCV-8 Seat Leak - Decay Heat Closed
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Cycle Cooling WR No. T00723 - Repair Valve DCV-29 Manual Operator - Decay Heat
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Closed Cycle Cooling WR No. 002074 - Repair Leaking Injector For Diesel Generator "A"
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WR No. 006059 - Repair Valve DFV-48 Bonnet Leak For Diesel Generator The inspector also reviewed the training qualification records of eight maintenance mechanics.
The inspector used one or more of the follo0ing acceptance (riteria for inspecting the above items:
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Administrative Instruction Al-600 - Conduct of Maintenance Administrative Instruction Al-901 - Maintenance of Plant
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Instrumentation Quality Assurance Manual Policy No. 5.51 - Plant Maintenance
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Control
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RII Report No. 50-302/78-26 I-8 Quality Assurance Manual Policy No. 10.50 - Maintenance Inspection
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ANSI N18.7 (1972)
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ANSI N45.2.9 (1971)
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Inspector Judgement
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The above documentation results were reviewed to verify:
administrative Approval was.ibtained prior to initiating work;
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where required maintenance wis performed using an approved
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procedure; where required functional testing was performed prior to return
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to service; Quality Assurance review was per f o rmed;
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maintenance was performed by qualified personnel;
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where required a reportable occurrence report was submitted in connection with the maintenance.
Within the areas inspected no items of noncompliance or deviations were identified.