IR 05000250/1990001
| ML17347B582 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 02/01/1990 |
| From: | Conlon T, Hunt M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML17347B581 | List: |
| References | |
| RTR-REGGD-01.097, RTR-REGGD-1.097 50-250-90-01, 50-250-90-1, 50-251-90-01, 50-251-90-1, NUDOCS 9002260280 | |
| Download: ML17347B582 (14) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTASTREET, N.W.
ATLANTA,GEORGIA 30323 Report Nos.:
50-250/90-01 and 50-251/90-01 Licensee:
Florida Power and Light Company 9250 Mest Flagler Street Niami, FL 33102 Docket Nos.:
50-250 and 50-251 Facility Name:
Turkey Point 3 and
License Nos.:
DPR-31 and DPR-41 Inspection Conducted:
January 8 - 12, 1990 Inspector:
A Qy l0
.
fl 9/.J n. p
. Hunt, am ea er Team Members:
A. B. Ruff N. Herriweather Approved by:~ W~~~
.
E.
Con on, Chief Plant Systems Section Engineering Branch Division of Reactor Safety
/
2 r/6 Date Signe at Signed SUMMARY Scope:
This routine announced inspection was in the areas of the licensee's conformance to Regulatory Guide (RG) 1.97, Instrumentation for Light - Mater Cooled Nuclear Power Plant to Assess Plant and Environs Conditions during and following an Accident.
Information on an Inspector Followup Item ( IFI) in the Environmental gualification of Electrical Equipment area was also examined and considered to be satisfactory.
Results:
In the areas inspected, violations or deviations weI e not identified.
The licensee has performed the installation and modification of instruments to comply with Regulatory Guide 1.97, Revisions 3.
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Strength:
An attribute in the engineering and management areas was identified in that these organizations acted prudently and effectively in the implementation of RG 1.97 criteria and in the preparation for the NRC inspection of the same.
Instrument loop diagrams, a
new revised RG 1.97 instrument list, which will be included in the FSAR by a
1990 amendment, and individual instrument packages that contained all the pertinent data to support RG 1.97 commitments were provided to the NRC inspectors to aid in the inspection.
The RG 1.97 Types A, B,
and C, Categories
and 2 instruments were environmentally qualified and uniquely identified in the Control Room and Simulator so that the operators can easily discern that these instruments are intended for mitigation of accident conditions.
The instruments in the field were tagged for easy identification including tagging for EQ qualification.
The above referenced documentation for record and audit purposes, plus field work performed by the licensee indicated that they recognized what was needed and committed resources to complete the=
actions necessary to enact the RG 1.97 program at Turkey Poin REPORT DETAILS Persons Contacted Licensee Employees K. N. Harris, Vice President
- J. Cross, Plant Manager
- J. Arias, Jr., Technical Assistant to Plant Manager
- T. V. Abbatiello, gA Supervisor
- D. L. Smith, Manager Electrical/18C Engineering
- G. E. Regal, Manager Engineering Procurement
- J. Kovarik, I8C Maintenance Support Superintendent G. Heisterman, Assistant Superintendent Electrical Maintenance W. Busch, Electrical Engineer C. Bible, Electrical Engineer
- M."Musrock, Associate Engineer ISC
- J. Osborne, I&C Lead Engineer M. 'Pearce, Electrical Engineer R.'Rajan, Senior Plant Engineer Maintenance
- D. Herrin, Regulation and Compliance Head Engineer Other licensee employees contacted during this inspection included craftsmen, engineers, operators, security force members, technicians, and administrative personnel.
Other Organizations NRC Resident Inspectors
- R. Butcher, Senior Resident Inspector G. Schnebli, Resident Inspector T. McElhinney, Resident Inspector
- Attended exit interview Acronyms and initialisms used throughout this report are listed in the last paragraph.
Inspection of Licensee's Implementation of Multiplant Action A-17:
Instrumentation for Nuclear Power Plants to Assess Plant and Environs Conditions During and Following an Accident (Regulatory Guide 1.97)
(25587).
~Criterion 13, "Instrumentation and Control," of Appendix A to 10 CFR Part 50 includes a requirement that instrumentation be provided to monitor variables and systems over their anticipated ranges for accident conditions as appropriate to ensure adequate safety.
Regulatory Guide 1.97 (RG 1.97)
describes a
method acceptable to the NRC staff for
complying with th'e Commission's regulations to provide instrumentation to monitor plant variables and systems during and following an accident.
The purpose of this inspection was to verify that the licensee has an instrumentation system for assessing variables and systems during and following an accident, as discussed in Regulatory Guide (RG) 1.97.
Under accident conditions it is necessary that the operating personnel have; (I) information that permits the operator to take preplanned actions to accomplish a safe plant shutdown, (2) determine whether the reactor triped, Engineered Safety-Feature Systems actuation (ESFS),
and that other manually initiated safety systems important to safety are performing their intended functions, and (3) provide information to operators that will enable them to determine the potential for causing a gross breach of the barriers to radiation release and to determine if a gross breach of barrier has occurred.
For this reason multiple instruments with overlapping ranges may be necessary.
The required instrumentation must be capable of surviving the accident environment for the length of time its operability is required.
It is desirable that components continue to function following seismic events.
As a result, five types of variables have been specified that serve as guides in defining criteria and the selection of accident-monitoring instrumentation.
The types are:
Type A - Those variables that provide, information needed to permit the control room operating personnel to take specified manual actions for which no automatic control is provided and that are required for safety systems to accomplish their functions for design basis accident events; Type B - Those variables that provide information to indicate whether plant safety functions are being accomplished; Type C -
Those variables that provide information to indicate the potential for barriers being breached or the actual breach of barriers to fission product release; Type D - Those variables that provided information to indicate operation of individual safety systems and other systems important to safety; Type E - Those variable to be monitored in determining the magnitude of the release of radioactive materials and for continuously assessing such release.
The design and qualification criteria are separated into the separate categories that provide a graded approach to requirements depending on the importance to safety of the measurement of a specific variable,,Category
provides the most stringent requirements and is intended for key variables.
Category 2 provides less stringent requirements and generally applies to instrumentation designated for indicating systems operating status.
Category 3 is intended to provide requirements that will ensure that high-quality off-the-shelf instrumentation is obtained and applies to backup and diagnostic instrumentation.
A key variable is that single accomplishment of a safety function (Types B and C), or the operation of a safety system (Type D), or radioactive material release (Type E).
Type A
variables are plant specific and depends on the operations that the designer chooses for planned manual actions.
Inspection of Categories I
and 2 equipment was performed as described belo Category I and 2 Instrument for Units 3 and
The instrumentation listed in the Table, was examined to verify that the design and qualification criteria of RG 1.97 had been satisfied.
The instrumentation was inspected by reviewing drawings, procedures, data sheets, other documentation and performing walkdowns for visual observation of selected installed equipment including CR indicators and recorders.
The following areas were inspected:
Equipment Qualification - The EQ Master Equipment List and the Q-List were reviewed for confirmation that the licensee had addressed environmental qualification requirements for Class lE equipment.
(2)
(3)
(4)
Redundancy
-
Walkdowns were performed to verify by visual observation that selected instruments were installed as specified and that separation requirements were met.
In addition, loop drawings for all listed category I
instrumentation were reviewed to verify redundancy and channel separation.
Power Sources
-
Loop drawings were reviewed to verify the instrumentation is energized from a safety-related power source.
Display and Recording - Walkdowns were performed to verify by visual observation that the specified display and recording instruments were installed.
Loop drawings were reviewed to verify there was at least one recorder in a redundant channel and two indicators, one per division (channel) for each measured variable.
Range - Walkdowns were performed to verify the actual range of the indicator/recorders was as specified in RG 1.97 or the SER.
Review of calibration procedures verified sensitivity and overlapping requirements of RG 1.97 for instruments measuring the same variable.
'(7)
Interfaces
- The loop drawings arid Q - List were reviewed to verify that safety-related isolation devices were used when required to isolate the circuits from non safety systems.
Director Measurement
- Loop drawings were reviewed to verify that the parameters are directly measured by the senors.
Service, Testing, and Calibration - The maintenance program for performing calibrations and surveillances was reviewed and discussed with the licensee.
Calibration and surveillance procedures and the latest data sheets for each instrument were reviewed to verify the instruments have a valid calibratio CATEGORY
INSTRUMENTS Units 3 and 4 unless otherwise indicated Variable RCS Pressure Instrument Number l
Channel or Train PT-404 A
QSPDS A
PT-406 B
QSPDS B
RCS Hot Leg Temperature TE-410 A TE-410
TE-420 A
TE-420 B
TE-430 A
TE-430 B
TR-413 records loops, A,B.C for Train A QSPDS A Display A QSPDS B Display B
RCS Cold Leg Temperature TE-413 A
TE-413 B
TE-423 A
TE-423 B
TE-433 A
TE-433 B
TR-413 records loops A, B, C for Train A QSPDS A Display A QSPDS 8 Display B
Reactor Building Level Reactor Building (Containment)
Pressure'Normal Range LT-6309 A
LI-6309 A LR-6308 A LT-'6309 B
LI-6309 8 LR-6308 B
PT-6425 A
PI-6425 A
PR-6306 A
PT-6425 B
PT-6425 B
PR-6306 B
Variable CATEGORY
INSTRUflENTS (cont'd)
Instrument Number Channel or Train Reactor Building (Containment)
Pressure Extended Range Reactor Building (Containment)
Hydrogen Concentration PT-6306 A
PI-6306 A
PR-6306 A
PT-6306 B
PI-6306 B
PR-6306 B
AE-6307 A
AI-6307 A RAR-6311 A (Hydrogen recorder)
AE-6307 B
AI-6307 B
RAR-6311 B (Hydrogen Recorder)
Steam Generator Level Narrow; Range (Unit 4 only)
LT-474 LI-474 LT-475 RI-475 LT-476 LI-476 FR-478 LT-484 LI-484 LT-485 LI-485 LT-486 LI 486 FR-488 LT-494 LI-494 LT-495 LI-'495 LT-496 LI-496 FR-498 S/G A Ch I S/G A Ch I S/G A Ch II S/G A Ch II S/G A Ch III S/G A Ch III S/G B Ch I S/G B Ch I S/G B Ch II S/G B Ch II S/G B Ch III S/G B Ch III S/G C
Ch I S/G C Ch I S/G C Ch II S/G C Ch II S/G C
Ch III S/G C Ch III.
Refueling Water Storage Tank Level Neutron Flux LT-6583 A LI-6583 A LT-6583 B
LI-6583 B
ERDADS Recording capabilities ND-6649 A NI-6649 A-2 ND-6649 B
NI-6649 B-2 ERDADS Recording capabilities
Reactor Building (Containment)
Sump Level CATEGORY 2 INSTRUMENTS Units 3 and
LT-6308 A LI-6308 A LR-6308 A LT-6308 B
LT-6308 B
LR-6308 B
SIS Fl ow in HPI System RHR Flow RHR Ht Xchr Outlet Temperature PT-495 S/G C
PI-495 S/G C
PT-496 S/G C
PI-496 S/G C
FT-940 FI-940 FT-605 FI-605 TE-606 TR-604 Steam Generator Pressure PT-474 S/G A
PI-474 S/G A
PT-475 S/G A
PI-475 S/G A PT-476 S/G A PI-476 S/G A
PT-484 S/G B
PI-484 S/G B
PT-485 S/G B
PI-485 S/G B
PT-486 S/G B
PI-486 S/G B
PT-494 S/G C
PI-494 S/G C
Ch II Ch II Ch III Ch III Ch IV Ch IV Ch II Ch II Ch III Ch III Ch 1V Ch IV Ch II Ch II Ch III Ch III Ch IV Ch IV Pressurizer Heater Status 3811 Control Group 3812 Back-up Group 3A 3813 Back-up Group 3B Monitoring and Display of of electric current to determine operating status is by the ERDADS
b.
Discussion and Conclusion The licensee was well prepared and expended considerable effort to assist the inspectors in performing the RG 1.97 inspection.
All previously requested documentation including the g-List, the Eg-List, electrical drawings, instrument loop diagrams, and calibration data sheets were pulled and available in an organized manner.
This information was also included or referenced in individual RG 1.97 instrument packages.
The Licensee had an up-dated RG 1.97 instrument list, which was a
considerable aid in the inspection.
This new revised list is to be incorporated in the FSAR by an amendment in 1990.
The instrument loop diagrams, which were specifically developed f'r this NRC inspection, were very helpful in the inspection and were considered to be a quality product.
The instrument loop diagrams contain the
'ecessary information, including electrical cables numbers, wiring, termination and test points for a technician to trouble shoot and understand how the loop operates.
Instrument Loop'rawings are considered to be one of the important tools at an operating facility.
The licensee states that the plant's file of controlled drawings will be enhanced to include the information from these loop instrument diagrams.
All RG 1.97 Types A, B, and C, Categories 1 and 2, instruments were uniquely marked with magenta tape in the Control Room and the
.
Simulator to clearly identify the instruments intended for use during postulated accidents.
In addition, the tags on the instruments in the field were color-coded and properly inscribed for easy identification.
Tagging to designate Eg qualification was also on field instruments to alert maintenance personnel to special requirements.
The results of the inspection were that the licensee satisfactorily met the requirements and intent'f RG 1.97 Guidelines.
3.
Actions on Previous Inspection Findings (92701)
a 0 (Closed)
IFI 250, 251/87-08-16, Brand Rex Coax Jacket Integrity.
During the March 1987, NRC Eg Audit, concerns were raised with respect to the use of this cable with the General Atomic High Range Radiation Monitor (HRRM).
The concerns were:
(1) the file contained a record of a telephone conversation with regard to qualification procedure for'he HRRM but there was no confirming letter in the file; and (2) the test report indicated that numerous jacket cracks had been observed in the tested sample and these were not discussed or addressed with regard to Eg.
A 1988 inspection showed the licensee addressed these concerns by including appropriate formal correspondence in the DOC PAC and the cable jacket integrity was addressed and discussed in the summary DOC PAC 5.0.
The testing of the Branch Rex Cable referenced in the DOC PAC was at a much more
severe environment and environmental transient condition than that which would be anticipated at Turkey Point and the report did not consider the protective characteristics utilized in the Turkey Point installed configuration (cable run in conduit).
As a result of this correspondence, concerns were raised in that it appeared that the HRRM may not meet RG 1.97 accuracy guidelines (Table 3 Note of the RG states that accuracy is to be within a factor of two over the entire range).
At abnormally high containment temperatures (peak accident temperature)
and low radiation levels the HRRM indication could be slightly over the factor of two requirement; The licensee, however, considered that the HRRM was environmentally qualified and met the intent of RG 1.97.
FPSL subsequently provided the Turkey Point resistive values (cable, penetration, etc.)
and other pertinent data with regard to the Turkey Point HRRN installation to their consultant and General Atomic Company.
Calculations were performed to show that the accuracy the Turkey Point HRRM installation meets the accuracy requirement of the R.G.
The applicable EQ DCO PAC's (Number 11.0 and 5.0)
have been up-dated to reflect the additional analysis and calculations.
Discussions with FPSL engineers and review of the data in the DOC Pac's resolved this IFI concern.
4.
Exit Interview The inspect)on scope and results were summarized on January 12, 1990, with those persons indicated in Paragraph 1.
The inspector described the area inspected and discussed in detail the inspection results indicated above.
Proprietary information is not contained in this report.
5.
Acronyms and Initialisms EQ EQ DOC PAC ERDADS FSAR HRRM HT IFI FI FR FT HPI LI LR LT ND NI PAM PI Environmental Qualification Environmental Qualification Documentation Package Emergency Response Data Acquisition Display System Final Safety Analysis Report High Range Radiation Monitor Heat Inspector Follow-up Item Flow Indicator Flow Recorder Flow Transmitter High Pressure Injection Level Indicator Level Recorder Level Transmitter Neutron Detector Neutron Indicator Post Accident Monitoring Pressure Indicator
PR PT gSPDS RAR RHR RC RCS R.G.
RWST SER SIS S/G TE TI TR XCHR Pressure Recorder Pressure Transmitter equality Safety Parameter Display System Recorder Area Radiation Residual Heat Removal Reactor Coolant Reactor Coolant System Regulatory Guide Refueling Water Storage Tank Safety Evaluation Report Safety Injection System Steam Generator Temperature Element Temperature Indicator Temperature Recorder Exchanger