IR 05000413/1986001
| ML20151R614 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 01/30/1986 |
| From: | Jape F, Mcelhinney T, Vandyne K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20151R612 | List: |
| References | |
| 50-413-86-01, 50-413-86-1, 50-414-86-04, 50-414-86-4, NUDOCS 8602060163 | |
| Download: ML20151R614 (5) | |
Text
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MQE UNITED STATES NUCLEAR REGULATORY COMMISSION O"
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REGION li
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101 MARIE 1TA STREET.N.W.
2-ATI.ANTA, G EORGI A 30323
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Report Nos.:
50-413/86-01 and 50-414/86-04 Licensee: Duke Power Company 422 South Church Street Charlotte, NC 28242 Docket Nos.:
50-413 and 50-414 License Nos.:
NPF-35 and CPPR-117 Facility Name:
Catawba 1 and 2 Inspection Cond cted: Janu ry 7-10, 1986
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[3 N Inspectors:
K. W. VanDyne l
D(tejigned W l' ?cLl n1ntJM '
l 30 $b
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T. F. MciElhinney g Date Signed Approved by:
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/gF. Jape,SectionChief Date Signed Test Programt Section, Engireering Branch Division of Reactur Safety SUMMARY-Scope: This routine, unannounced inspection entailed 52 inspector-ho'urs on site-in the areas of preoperational test witnessing, preeperational test result review, and followup of previously identified items.
Results: No violations or deviations were identified.
8602060163 % h:3 PDR ADOCK PDR O
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REPORT DETAILS 1.
Persons Contacted Licensee Employees T. Deese, Test Coordinator, I&E
- R. A. Jones, Performance Test Engineer J. A.
Kammer, Test Coordinator, Performance
- D. Rogers, Supervisor, I&E
- F.
P. Schiffley, II, Licensing Engineer
- J. A. Stackley, Supervisor, I&E Other licensee employees contacted included engineers, technicians, operators, mechanics, and office personnel.
NRC Resident Inspectors P. K. Van Doorn P. H. Skinner
- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on January 10, 1986, with those persons indicated in paragraph 1 above.
The inspector described the areas inspected and discussed in detail the inspection findings.
No dissenting comments were received from the~ licensee.
The licensee did not identify as proprietary any of the materials provided to or reviewed by the insrectors during this inspection.
3.
Licensee Action on Previous Enforcement Matters This subject was not addressed in the inspection.
l 4.
Unresolved Items Unresolved items were not identified during the inspection.
5.
Diesel Generator Governor Controls Calibration Test (70312)
The inspector witnessed portions of the Diesel Generator Governor Controls Calibration Test to verify that:
l a.
Appropriate revis'on of the procedure IP/0/A/3680/02 was available and
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in use by test personnel.
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b.
The test was performed in accordance with requirements.
c.
Test data were collected and recorded in the proper manner.
d.
Coordination among personnel involved in the test was adequate.
e.
Problems encountered during testing were properly identified and documented.
No violations or deviations were identified in the areas inspected.
6.
Preoperational Test Result Evaluation (70537, 70329)
The inspector reviewed the test results for the following tests:
TP/2/A/1250/06, Main Steam Isolation Valve Closure Timing Functional Test.
This test verified the ability of the MSIVs to close fully within their allowed time under full pressure and temperature conditions during hot functional testing.
TP/2/A/1200/19, Lower Containment Personnel Air Lock Leak Rate Test.
This test determined the leakage rate of the containment personnel air lock and verified seal integrity and door interlocks.
These test results packages were reviewed to verify the following:
a.
Test results were adequately evaluated.
b.
Proper review, evaluation, and acceptance of test results were accomplished.
c.
Test' data were within acceptance criteria as specified in Technical Specifications.
l No violations or deviations were identified in the areas inspected.
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7.
Preoperational Test Witnessing (70317)
The inspector witnessed portions of IP/2/A/3200/03, Reactor Protection System (RPS) Response Time Testing.
The objective of this test was to accurately determine:
a.
Response time from the initiating device to the reactor trip switchgear for the RPS.
b.
Response time from the initiating device to the output of the demultiplexer cabinet for the Engineered Safety Features Actuation System (ESF).
c.
Response time for the RPS and/or ESF system from the initiating device to the bistable trip in the process control syste.
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Licensee activities were observed to verify the following:
a.
Testing was conducted in accordance with approved procedures and the latest revision of the test procedure was available and in use by personnel conducting the test.
b.
Test procedure prerequisites were met.
c.
System check sheets were completed as required.
d.
Test equipment was calibrated and installed as required by the procedure, e.
Data required were collected by the proper personnel.
f.
Adequate coordination existed among the responsible organizations to conduct the test properly.
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No violations or deviations were identified in the areas inspected.
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8.
Followup on Inspector Identified Problems (92701)
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a.
(0 pen) IFI 413/85-51-01, 414/85-59-01 Daily Check of the Emergency Diesel Generator Governor Oil Level The inspector interviewed responsible licensee personnel concerning the status of this item.
This item involves checking the governor oil level daily as recommended by the Transamerica Delaval Incorporated
(TDI) owners manual.
The licensee informed the inspector that this daily check has not yet been incorpo' rated into the Nuclear Equipment
Operat'or's (NED) rounds list. The inspector informed the licensee that
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this item will remain open and will be followed up on subsequent inspections.
I b.
(0 pen) IFI 413/85-51-02, 414/85-59-02, When Can A Valid Governor Oil Level Be Obtained o
l Resolve Question of When a Valid Governor Oil Level can be obtained for i
the Emergency Diesel Generators (EDG). This item involves checking the governor oil level while the engine is running in order to verify that
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the governor has adequate oil for proper operation.
The inspector
reviewed procedures, OP/2/A/6350/02 Diesel Generator Operation and l
PT/1/A/4350/10 Diesel Generator Operating Parameters. Review of these
procedures revealed that there is no step included to check the
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governor oil level while the engine is running. The inspector informed responsible licensee personnel that this item will remain open and will
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l be followed up on future inspections.
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c.
(0 pen) IFI 414/85-42-01, Low 011 Level Prgblem - EDG 2A Governor Resolve Question of Low 011 Level Problem in Diesel Generator 2A Governor.
The inspector questioned responsible licensee personnel concerning the status of this item.
The licensee informed the inspector that the governor was still leaking oil after replacing the internal seal. The licensee decided to replace the entire hydraulic actuator with a new one to try to stop the leak.
The licensee has run the enoine with the new actuator installed, but there is insufficient run time on the engine to ascertain whether the governor is still leaking oil.
The inspector informed the. licensee that follow up on this item will be performed during future inspections.
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