IR 05000250/1982006
| ML20050N854 | |
| Person / Time | |
|---|---|
| Site: | Turkey Point  |
| Issue date: | 03/19/1982 |
| From: | Dance H, Vogtlowell R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20050N844 | List: |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.B.1, TASK-2.B.3, TASK-2.E.4.2, TASK-2.F.1, TASK-2.F.2, TASK-TM 50-250-82-06, 50-250-82-6, 50-251-82-06, 50-251-82-6, NUDOCS 8204140440 | |
| Download: ML20050N854 (8) | |
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Itty UNITED STATES
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NUCLEAR REGULATORY COMMISSION
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E REGION 11 O[
101 MARlETTA ST., N.W., SUITE 3100 o,
ATLANTA, GEORGIA 30303
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Report flos. 50-250/82-06 and 50-251/82-06 Licensee: Florida Power & Light Company 9250 West Flagler Street Miami, FL 33152 Facility flame: Turkey Point Occket flos. 50-250 and 50-251 License flos. CPR-31 and CPR-41 Inspection at Turkey Paint site near llomestead, Florida inspector:
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ifate Signed
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Approved by: -
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11. C. Dance, Section Chief, Division of D4te Signed Project and Resident Programs SUMf1ARY
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inspection on January 18 - February 25, 1982 Areas Inspected This routine, unannounced inspection involved 212 resident inspector-hours on site in the areas of followup on licensee action on previous inspection findings; Post Tit! Implementation followup (llVREG-0737); plant operations; surveillance test observations; and plant tours.
Resul ts Of the five areas inspected, no violations or deviations were identified.
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DETAILS 1.
Persons Contacted Licensee Employees H. E. Yaeger, Site Ibnager
- J. K. Hays, Plant Ibnager Nuclear J. P. Mendieta, Maintanence Superintendent Nuclear D. W. Haase, Operations Superintendent - Nuclear J. P. Lowman, Assistant Superintendent liechanical ibintenance - Nuclear L. L. Thomas, Assistant Superintendent ibchanical liaintenance J. Kenney, Primary ibintenance Supervisor P. Banister, Secondary Maintenance Supervisor W. R. Williams, Assistant Superintendent Electrical liaintenance - Nuclear J. W. Kappes, Instrumentation and Control Supervisor V. B. Wager, Operations Supervisor A. E. Byrnes, Auxiliary Building Supervisor J. S. Wade, Chemistry Supervisor P. W. Hughes, Health Physics Supervisor
- D. W. Jones, Quality Control Supervisor K. N. York, Document Control Supervisor J. A. Labarraque, Technical Department Supervisor D. E. Sands, Construction Document Control Supervisor J. C. Balaguero, Licensing Engineer 11. J. Crisler, Quality Assurance Supervisor - Construction J. F. O'Brien, Project QC Suparvisor Other licensee employees contacted included technicians, operators, mechanics, security force members, and office personnel.
Other Organizations J. Quinn, Westinghouse Electric Co.
- Attended exic interview 2.
Exit Interview The inspection scope and findings were summarized on February 26, 1982, with those persons indicated in paragraph 1 above.
The inspector maintained frequent unprogranned discussions and communications with the Plant Ibnager during the inspection report period.
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3.
Licensee Action on Previous Inspection Findings
a.
(Closed) 250, 251/81-25-01 - Failure to implement existing procedure
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during maintenance of "A" Auxiliary Feedwater Pump". The inspector
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reviewed the licensee's corrective action and held several discussions with the Assistant Superintendent of liechanical liaintenance - Nuclear.
Reviews of the training records in the area of quality assurance and quality control for various personnel in the mechanical maintenance department were performed by the inspector. The inspector has no further question on the corrective action related to this specific violation but will continue to focus attention on the adequacy of performance of mechanical maintenance, b.
(Closed) 250, 251/81-20-01 - Inadequate review of Technical Specifi-cations related to equipment out of service. The inspector reviewed the licensee's corrective action and had no further questions.
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c.
(Closed) 251/81-20-02 - Failure to Monitor Blowdown Effluent. The inspector reviewed the licensee's response and had no further questions. Additionally, the inspector noted the existence of change request numbers one on PC/1178-101B and number 2 on PC/!178-102B, both of which will result in the interlocking of the sample line and the blowdown isolation valves on both unit 3 and unit 4 thereby precluding an unmonitored release from the blowdown system.
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(Closed) 250, 251/81-13-01 - Failure to implement housekeeping proce-dure. The inspector reviewed the licensee's corrective action and had no further questions.
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(Closed) 250, 251/81-16-02 - Failure to properly fill out QC tags. The inspector reviewed the licensee's corrective action and had no further
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questions.
4.
Unresolved Items Unresolved items are matters about which more information is required to determine whether they are acceptable or may involve violations or devia-tions. New unresolved items identified during this inspection are discussed in paragraph 8.
5.
Post TMI Implementation Followup (NUREG-0737)
l (Closed) Item II.E.4.2.1 through.4 Containment Isolation Dependability.
11odifications were completed on both Unit 3 and Unit 4 for the following penetrations:
P5 - Pressurizer Relief Tank Gas Analyzer line P25 - Excess Letdown RCP Seal Water Return P29 - Instrument Air Supply P6 - Pressurizer Relief Tank Nitrogen Supply P42 - Nitrogen Supply to Accumulators
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The addition of five new valve control switches to enhance separation over control of more than one containment isolation valve has been implemented for both Unit 3 and Unit 4.
Each unit now has ten switches controlling the following eleven valves:
CV-2826, CV-2819, CV-2822, CV-2821, CV-2911, CV-2912, CV-2913, CV-2600 CV-2601, CV-2602, CV-2603 These switches were installed under PC/M 80-51 for Unit 3 and PC/ft 80-52 for Unit 4.
(Closed) Item II.E.4.2. 5B Containment Isolation Dependability Containment Isolation Pressure Setpoint.
Based on an August 31, 1981 NRC to FPL (Varga to Uhrig) letter, this item is closed for both Units.
Enclosure 6 to this letter contains the Safety Evaluation Report on the minumum containment pressure setpoint and it concludes that the current 4.0 psig setpoint meets the NUREG-0737 require-ments and "is within the additional limiting guidelines provided by the NRC s ta f f".
Consequently, no modifications are necessary.
(Closed) Item II.E.4.2. 7 Closure of Containment Purge and Vent Isolation Valves on a High Radiation Signal.
No modifications are necessary for either unit for, as indicated in Table 6.6-1 of the FSAR, the Containment Purge Vent In Valves POV-2600 and POV-2601 in addition to the Vent Out Valves POV-2602 and POV-2603 are currently set up to receive a close signal from containment high radiation originating from either of two containment radiation monitors (R-11:
Particulate; R-12: gaseous).
(0 pen) Item 11.8.1.3 Reactor Coolant System Vents In a January 7, 1982 letter FPL to NRC (Uhrig to EisenhJt) the licensee stated that it intends to submit a set of operating procedures by flarch 1, 1982. The current plans according to the licensee are to complete the system installations in Unit 3 prior to the startup from the steam generator (SG) repair outage, and on Unit 4 during its SG repair outage.
(0 pen) Item II.B.3.2B Post Accident Sampling System.
The system was not installed by January 1,1982 as required by NUREG-0737.
The licensee intends to complete the installation and have the system operational on Unit 3 prior to the startup from the SG repair outage.
The licensee further indicated that proposed technical specifications will be submitted following installation of the system.
(0 pen) Items II.F.1.1 and II.F.1.2 Accident fionitoring - Noble Gas flonitoring/ Iodine and Particulate Samplin.
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In December 1981 the licensee was informed by an instrument manufacturer that a design defect on the microcomputer printed circuit board of the
"Special Particulate, Iodine, Noble gas" (SPIf4G) flonitors, installed to satisfy the post accident effluent sampling requirements, would result in improper operation of the monitors under certain conditions and must be replaced.
Based on discussions with licensee representatives, the inspector
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determined that the circuit boards have been replaced on all units.
However, a licensee representative stated that problems with both printers and other hardware problems with two of the four SPIf4G units onsite continue to delay complete system operability. By liarch 1, 1982, the licensee intends to have these inadequacies, corrected, the system calibrated, operating procedures written, and the necessary training conducted.
(0 pen - Unit 3) (Closed - Unit 4) Item II.F.1.3 Containment High Range Radiation Monitors.
Unit 4:
The inspector reviewed the channel calibration sheets for radiation monitors RAD-4-6311A and RAD-4-6311B installed under PC/t180-26 and cali-brated under plant work order PWO-7683.
Unit 3:
The installation and calibration of the radiation monitors for Unit 3 are expected to be completed prior to startup from the current SG repair ou tage.
The licensee stated that proposed technical specifications would be submitted to the f4RC prior to fiarch 1,1982.
(0 pen) Item II.F.1.4 Containment Pressure Monitors.
Unit 4: The inspector reviewed the post installation calibration sheets for the 0 '80 psig containment pressure monitors channels P-6306A and P-6306B completed under plant work order PWO-3998.
Unit 3: The licensee stated that installation and calibration will be completed on the 0-180 psig monitors prior to startup from the SG repair ou tage.
The licensee has indicated in their January 7,1982 and February 18, 1982 letters to the f4RC that delivery of the transmitters for the vacuum portion (0 to-5 psig) of the system is scheduled for 11ay 22,1982, and that since installation of the transmitters is not outage related, it will be done promptly following receipt of the equipment.
The licensee intends to submit proposed technical specifications for the monitors once the system is fully installed.
(0 pen)
Item II.F.1.5 Containment Wall Level lionitor This system consists of level monitoring and indications from the bottom of the containment sump to the containment floor (14 foot elevation up to a 90 inch elevation by level transmitters LT-6309 A and B).
At this time the
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monitors have been installed and are operational on Unit 4.
The licensee indicated that they would be operational on Unit 3 prior to the startup from
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the SG repair outage.
NUREG-0737 requires monitoring of level in the containment up to an elevation equivalent to a 600,000 gallon capacity. Also, clarification 2 in
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attachment 5 to item II.F.1 in NUREG 0737 stated that "For older plants with smaller water capacities, licensees may propose deviations from this requirement based on the available water supply capability at their plants."
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i The inspector's review of this item revealed that although the installed system is designed to monitor a 500,000 gallon level equivalent; a proposed deviation from NUREG-0737 was never submitted by licensee.
The licensee's representative indicated that an evaluation in support of this deviation would be prepared and submitted by April 1, 1982.
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(0 pen)
Item II.F.1.6 Containment Hydrogen Monitors The containment post-LOCA hydrogen monitoring system has been partially
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installed in both Unit 3 and Unit 4.
Two sample cabinets are in place at
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the 4 foot elevation (Each unit will have a two channel monitoring system.
The two cabinets at the 4 foot elevation comprise one of the two channels for each of the two units).
Although the sampling lines to these cabinets have been installed, at the conclusion of the inspection report period, the installation of electrical connections and the system calibration for these channels was yet to be completed.
The licensee indicated his intentions
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were to have the full system installed and operational by March 1,1982.
(0 pen) Item II.F.2.3B Inadequate Core Cooling - Installation of Level j
Meters.
The licensee has indicated that it intends to have the system installed and
i operational following the first refueling outage for each unit after January 1, 1983. At this time, purchase orders for the system have been
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issued to the appropriate vendors.
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6.
Plant Operations
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The inspector kept informed on a daily basis of the overall plant status and any signficant safety matters related to plant operations.
Discussions were held with plant management and various members of the operations staff on a regular basis.
Selected portions of daily operating logs and operating data
sheets were reviewed during the report period.
The inspector conducted
various plant tours and made frequent visits to the control room.
Obser-l vations included witnessing work activities in progress, status of operating an standby safety systems, confirming valve positions, instrument readings
and recording, annunciator alarms, housekeeping, radiation area controls,
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and vital area controls.
Informal discussions were held with operators and other personnel on work activities in progress and the status of safety-l related equipment or systems.
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On February 16, 1982, the inspectors observed maintenance activities in progress on the "A" Auxiliary Feedwater Pump. The inspectors verified that the PWO was properly prepared and that an authorized maintenance procedure was being used. The work observed was being perfonaed in accordance with
maintenance procedure 11.P. 7307.2, Auxiliary Feedwater Pump Disassembly,
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j Inspection, Repair and Assembly, dated September 18, 1980. The liaintenance
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j activity was governed by PWO-2866.
On February 23, 1982 the inspector witnessed the calibration of channel 6308-B of the Containment Water Level lionitoring Systen for Unit 4.
A calibration of the pressure transmitter, indicator and recorder was per-
formed under the control of PWO-8663.
This level monitoring system was installed as a result of item II.F.1.5 of NUREG-0737.
No violations or deviations were identified within the areas inspected.
7.
Surveillance Test Observation
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The inspector witnessed the performance of the monthly periodic test of the Intake Cooling Water System for Unit 4.
This test was performed in
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accordance with Operating Procedure 0.P. 3404.2, Intake Cooling Water System
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- Periodic Test of Pumps, dated December 31, 1981. The test was performed on February 17, 1982.
The inspector verified the following aspects of this surveillance test:
the procedure conformed to technical specification requirements; proper licensee review; test instrumentation was calibrated; removal of the systen fran service; conduct of the surveillance test; restoration of the system to service; review of the test data for accuracy
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and completeness; independent calculation of selected test results data to I
verify its accuracy; confirmation that surveillance test documentation was reviewed and test discrepancies were rectified; test results satisfied technical specification requirements; testing was done by qualified personnel; and the surveillance schedule for this test was met.
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On February 18, 1982, the inspector observed portions of the performance of l
0.P. 0209.3, Inservice Pump Testing Program Implementation Procedure for Auxilairy Feedwater Pump, in conjunction with the performance of 0.P.
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7304.1, " Auxiliary Feedwater System - Periodic Test".
The inspector ascertained that the following objectives were being met:
testing was I
scheduled in accordance with technical specification requirements,
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procedures were being followed, testing was perfonned by qualified
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personnel, LCOs were being met, and system restoration was correctly
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accomplished following testing.
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No violations or deviations were identified within the areas inspected.
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8.
Plant Tours The inspector conducted various plant tours during the inspection report period.
A walk through of operating procedure 4303.1, " Emergency Diesel Generator Normal Standby Conditions" was performed by the inspector on February 11, 1982. Minor discrepancies encountered during the walk through (such as burned out light bulbs) were promptly corrected when brought to the attention of the Operations Superintendent.
On another occasion, the inspector made note of a developing practice of using the entrance area to the Unit 4 Boron Injection Tank (BIT) room as a storage area for miscellaneous material. The inspector then proceeded to request a written evaluation from the licensee that would show that such a practice did not conflict with or impair the ability of carrying out the design function of the required equipment in the room. The licensee responded with the following communication:
reasonable use of the access corridor to the subject room for staging materials and tool storage associated with the extensive modifications in progress would be acceptable provided no hazards were introduced and accessability was not impaired.
However, rather than develop a specific evaluation for this purpose, the root cause has been treated by removal of the offending material / tools".
The inspector confirmed that such action had been carried out.
During a tour of the Auxiliary Building, the inspector focused attention on the four heat tracing recorders, noting that several of the 24 toggle switches on each of the four recorders were in the " blocked" position.
Inasmuch as operating procedure 0.P. 2500.1, " Heat Tracing System - Normal Operation" does not provide a listing of the required position of these switches nor of the particular component or system whose temperature the individual 24 heat tracing circuit switches on each recorder are monitoring, the inspector requested that the licensee review this matter and advise on the findings. The acceptability of all the switches found in the blocked position could not be ascertained at the conclusion of the inspection report period. This item is unresolved pending further review.
(50-250, 251/82-06-01).
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