IR 05000400/1986007
| ML18019A690 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 03/13/1986 |
| From: | Burris S, Fredrickson P, Humphery P, Maxwell G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML18019A688 | List: |
| References | |
| 50-400-86-07, 50-400-86-7, IEB-83-05, IEB-83-5, NUDOCS 8603240446 | |
| Download: ML18019A690 (9) | |
Text
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UNITED STATES NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTASTREET, N.W.
ATLANTA,GEORGIA 30323 RePOrt NOeI 50-400/86-07 Licensee:
Carolina Power and Light Company P. 0.
Box 1551 Raleigh, NC 27602 Docket No.:
50-400 Facility Name:
Harris Unit
License No.:
CPPR-158 Inspection Conducted:
Inspectors:
.
F.
Maxwel Bur ri anuary
February 20, 1986 elis(rs Date Signed 3lG lFi Date Signed 3(isis>
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G umphr y Approved by:
P.
E. Fredrickson, Section Chief Division of Reactor Projects Date Signed 3 /3 D te Signed SUMMARY Scope:
This routine, announced inspection involved 250 inspector-hours on site in the areas of Preoperational Testing, Testing of Pipe Support and Restraint Systems, Integrated Hot Functional Test Witnessing, Licensee Activities and IE Bulletin Follow-up.,
Results:
No violations or deviations were identified.
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REPORT DETAILS Persons Contacted Licensee Employees N. J. Chiangi, Manager, QA/QC Harris Plant J.
M> Collins, Manager, Operations G.
L. Forehand, Director, QA/QC J.
L. Harness, Assistant Plant General Manager, Operations C.
S. Hinnant, Manager, Start-up L. I. Loflin, Manager, Harris Plant Engineering Support C.
L. McKenzie, Acting Director, Operations QA/QC G. A. Myer, General Manager, Milestone Completion M. Thompson, Jr.,
Manager, Engineering Management D.
L. Tibbitts, Director, Regulatory Compliance B.
Van Metre, Manager, Harris Plant Maintenance E. J.
Wagner, Manager, Engineering C.
C. Wagoner, Project General Manager, Construction R. A. Watson, Vice President, Harris Nuclear Project J.
L. Willis, Plant General Manager, Operations Other licensee employees contacted included technicians, operators, and engineering personnel.
Exit Interview The inspection scope and findings were summarized on February 21, 1986, with the Plant General Manager, Operations.
One Inspector Follow-up Item was identified,
"Independent Verification", Paragraph 5.
No written material was provided to the licensee by the resident inspectors during this reporting period.
The licensee did not identify as proprietary any of the materials provided to or reviewed by the resident inspectors during thi s inspection.
Preoperational Test Program Implementation Verification (71302)
The inspectors conducted routine tours of the facility to make an independent assessment of equipment conditions, plant conditions, security, and adherence to regulatory requirements.
The tours included a
general observation of plant areas to determine if fire hazards existed; observation of activities in progress (e.g.,
maintenance, preoperational testing, etc.)
to determine if they were being conducted in accordance with approved procedures; and observation of activities which could damage installed equipment or instrumentation.
The tours also included evaluation of system cleanness controls and a
review of logs maintained by test groups to identify problems that may be appropriate for additional follow-up.
No violations or deviations were identified in the areas inspecte Testing of Pipe Support and Restraint Systems (70370C)
The inspectors toured areas of the reactor auxiliary building and the containment building.
Three struts, two spring can supports and fifteen mechanical snubbers were observed.
Visual examinations were conducted to check for deterioration and physical damage of the mechanical snubbers.
,Visual examinations were also conducted to check proper installation of base support plates, fasteners, locknuts, brackets and clamps for fixed pipe supports.
No violations or deviations were identified.
Integrated Hot Functional Test Witnessing (70314)
The integrated hot functional preoperational testing for Harris commenced on December 22, 1985.
The inspectors had previously observed portions of the tests and documented the results, in Region II report 50-400/85-52.
During this reporting period the Hot Functional Test (HFT) continued with the plant at Normal Operating Temperature (NOT)
and Normal Operating Pressure (NOP).
The inspectors witnessed Operations personnel using proper procedures consistent with the HFT instructions, as the various plant systems and controls were being manipulated.
The inspectors also witnessed Start-up and Test personnel performing portions of the in-process tests at NOT and NOP and observed that the tests were conducted in accordance with procedural requirements.
Test exceptions were documented and tracked by Start-up and Test personnel to assure that satisfactory resolution was achieved.
At the NOT and NOP plateau, pressurizer pressure and level controls were tested.
Pressurizer power relief valves and initial turbine roll were completed.
The reactor coolant loop low flow and steam generator level were tested.
The auxiliary and main steam systems tests were performed.
The Resistance Temperature Detector (RTD) thermocouples cross calibration tests were conducted and the final system test required the licensee to demonstrate operability of the remote shutdown capabilities for the auxiliary control panel.
The pressurizer pressure power-operated relief valves (PORV) and pressurizer pressure and level control tests were performed in accordance with test procedure 2005-P-04, as required in the HFT procedure 2005-P-01, step 6.2.3.
The licensee encountered problems with the pressurizer controls while conducting these tests.
On initial operation, the PORV block valve (445-A)
failed to fully open.
Investigation revealed that the valve operator was binding during its operation.
The valve operator was replaced and testing was resumed and satisfactorily completed.
The pressurizer pressure indicators were not within the required tolerances; this was identified previously by the resident inspectors as an Inspector Follow'-up Item (400/85-52-04),
which remains open.
The licensee evaluated this concern and found the pressurizer pressure transmitter tubing had been designed and manufactured incorrectly.
The design error caused the pressure transmitter
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to be manufactured with the reference and high pressure legs reversed.
The licensee made a
temporary modification to the pressurizer transmitter tubing.
The modification was conducted under the control of a Construction Work Request Authorization (CWRA) and the Start-up Manual, Section 14.
The licensee plans to initiate later a Field Change Request (FCR) to correct the design deficiency.
While shifting controls from the main control panel to the auxiliary control panel, the 1-B pressurizer heaters energized and would not cycle off as designed.
The licensee found the control wiring had not been completed in accordance with the control wiring diagram.
The licensee initiated a
CWRA requiring Operations maintenance to correct this deficiency.
The resolution of these problems allowed the licensee to complete test procedure 2005-P-04 and step 6.2.3 of 2005-P-01.
The main steam dump system was tested in accordance with 2005-P-Ol and 3035-P-03.
The inspectors witnessed portions of these tests ( steps 2.0 through 2.7).
During the performance of the test the licensee identified that the main steam dump valves failed to open within the prescribed 'ime limits.
The licensee evaluated this condition and found that the instrumentation air line which connects to the valve diaphragm was oversized.
FCR-I-3049 was initiated, and the instrumentation tube size was reduced and the test was satisfactorily completed.
The auxiliary feedwater system was tested as required by 2005-P-Ol and 3065-P-02.
The inspectors witnessed the cold starts of the turbine-driven auxiliary feedwater pump.
During the initial start, problems were found with the turbine governor.
The governor was causing the turbine speed to oscillate.
The licensee found that the gain on the turbine speed control circuit was improperly adjusted.
The requirement adjustments were made and the remaining cold starts were performed.
The main steam turbine generator was brought up to speed and synchronized with the off-site electrical grid in accordance with Start-up Procedures 2005-P-Ol, 5005-P-Ol, and Operating Procedures OP-153.01 and OP-137.
The inspectors observed the initial turbine warm-up to 1800 rpm.
The licensee did not identify any major di screpancies during turbine testing.
The reactor coolant pump flow balancing tests were conducted in accordance with 2005-P-Ol, step 6.2.
The inspectors observed technical personnel conducting the final reactor coolant pump balancing.
The site simulated loss of station AC power as required by 2005-P-01, steps 6.2. 11.9 through 6.2. 11.9.9, and Operating Procedure OP-155.
The test was conducted to demonstrate manual control capabilities under adverse lighting and communication conditions.
The inspectors witnessed this test and observed that natural recirculation could be achieved during loss of station AC power.
During the test the
"B" emergency service water pump failed to start upon demand.
The licensee investigated and found that the secondary contacts for the pump motor were dirty.
This condition was cleared and the pump was placed back into operatio v h
I
The resident inspectors participated with Region II personnel during the performance of the plant remote shutdown capability testing, as required by Start-up Procedures 2005-P-01, step 6.3.2, and 6013-P-03; and Abnormal Operating Procedure AP-004.
The test was conducted to demonstrate cold shutdown capability of the plant from hot standby using controls and instrumentation located outside of the control room.
The inspectors witnessed steps 6. 1 through 6. 17, which performed the transfer of power to the auxiliary control panel.
While attempting to shift the electrical controls from the main control panel to the auxiliary control panel, the test was interrupted.
When the inspectors inquired as to why the test was secured, the licensee stated that control power could not be totally transferred.
The licensee conducted an investigation and found that a
control circuit would not respond to the shift signal.
The circuit would not perform due to an electrical lead being lifted.
The inspectors requested that the licensee perform an evaluation to determine why this lead was lifted without the knowledge of the responsible start-up engineer.
This item will be identified as an Inspector Follow-up Item,
"Independent Verification", 50-400/86-07-01.
Following completion of the remote shutdown capabilities test the plant was cooled down in accordance with 2005-P-01 and required data was obtained and recorded.
No violations or deviations were identified.
Licensee Activities (40301B)
During the week of January 27, 1986 personnel from the Instrumentation and Control Systems and the Power System Branch of NRR conducted a si.te audit.
The audit team reviewed as-constructed instrumentation systems and controls, electrical separation and cable routing, operating and test procedures, and conducted walkthroughs of select procedures.
Subsequent to this review, an audit report will be issued by NRR.
IE Bulletin Follow-up (92703)
The inspectors reviewed the licensee's actions taken in response to IE Bulletin 83-05,
"ASME Nuclear Code Pumps and Spare Parts Manufactured by the Hayward Tyler Pump Company".
The inspectors observed in-process testing of the emergency service water pumps, which were being tested in various system configurations to comply with the Start-up Test Procedure 4065-M-01.
Procedure 4065-M-Ol incorporated the test requirements of IE Bulletin 83-05, which verified pump performance and the ability to meet their intended safety function.
The pump test results are being evaluated by Harris Plant Engineering.
This Bulletin was also identified as an Unresolved Item 400/85-37-02,
"Resolution of Concerns Associated with IE Bulletin 83-05".
The inspectors will continue to review this item in subsequent inspection reports.
This item remains open.
No violations or deviations were identifie (i 4'