IR 05000400/1987012
| ML18004B752 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 03/18/1987 |
| From: | Jape E, Mathis J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML18004B751 | List: |
| References | |
| 50-400-87-12, NUDOCS 8704130194 | |
| Download: ML18004B752 (5) | |
Text
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0 y*y4 UNITED STATES NUCLEAR REGULATORY COMMISSION
REGION II
101 MARIETTASTREET, N.W., SUITE 2900 ATLANTA,GEORGIA 30323 Inspector:
L.
at 1s Approved by:
F. Jape, Section ChTe
,
S Engineering Branch Division of Reactor Safety Report No.:
50-400/87-12 Licensee:
Carolina Power and Light Company P. 0.
Box 1551 Raleigh, NC 27602 Docket No.:
50-400 Facility Name:
S. Harris Inspection onducted:
February 23-27, 1987 License No.:
NPF-63 9/i~lg7 g
8/iz/i'7 Date Signe SUMMARY Scope:
This routine, unannounced inspection was in the areas of start-up test result evaluation and follow-up to inspector identified item.
Results:
No violations or deviations were identified.
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REPORT DETAILS 1.
Persons Contacted Licensee Employees
- J.
L. Harness, Assistant Plant General Manager
"D. Tibbitts, Director Regulatory Compliance
"R, B.
Van Metra, Manager Technical Support W.
R. Wilson, Principal Engineer, Technical Service W. Harris, Principal Engineer, Technical Service Other licensee employees contacted included engineers,'echnicians, operators, and office personnel.
NRC Resident Inspectors
Exit Interview The inspection scope and findings were summarized on February 27, 1987, with those persons indicated in paragraph 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 material provided to or reviewed by the inspector during this inspection.
3.
Licensee Action on Previous Enforcement Matters This subject was not addressed in the inspection.
4.
Unresolved Items Unresolved items were not identified during this inspection..
5.
Start-up Test Result Evaluation (72301)
The following completed test procedures were reviewed to assure that acceptance criteria were satisfied and all test deficiencies resolved:
a.
9105-S-14, Reactor Coolant System Flow Measurement at 50K Power, was performed on February 22, 1987.
The purpose of this test was to determine the reactor coolant system flow rate utilizing a precision primary to steam generator heat balance analysis.
The acceptance criteria is that RCS total flow is greater than or equal to 298,948 gpm.
The calculated RCS flow, by the licensee, from data sheet 10.3 was 309,420 gp b.
9104-S-14, Load Swing at 30% Power, was performed on February 18, 1987.
Three (3) test exceptions were written against this procedure.
During the performance of this test the following acceptance criteria were not met:
a) primary pressure change during the load decrease transient exceeded 50psi, (actual value was 56psi);
and b) steam pressure during the load decrease transient overshot the final value by more than 25psi (actual 65psi).
The licensee forwarded test data to Westinghouse for evaluation.
Westinghouse response (C(L-850),
dated February 18, 1987, stated that plant parameters that did not fall within the acceptance criteria defined in the start-up tests were within acceptable deviations.
No retesting was required.
c.
9105-S-13, Turbine Generator Statepoint Data-50%,
was performed February 23, 1987, at 1450.
There were one (1) test exception, five (5) advance changes and two (2) temporary changes made against this procedure.
The purpose of this test was to gather baseline statepoint data for the turbine generator at 50% rated load.
The reactor power level was approximately 49.6% based on NI's detectors.
Turbine load was 365 mwe.
Acceptance criteria 7.2. 13 was not met in that the differential temperature between Hz side and air side seal oil temperature exceeded 2'F.
A test exception was written to average the three temperature reading.
The average hT reading was 2'F.
However, bT maximum was 3 F.
No retesting was required since 6T was within the acceptance criteria.
d.
e.
9105-S-16, Operational Alignment of Process Temperature Instrumen-tation at 50/o Power Plateau.
The purpose of this test was to verify that loop A, B and C,
BT and Tavg (Protection 8 Control Channel of Instrumentation)
were tracking correctly at approximately 50% power.
Also to obtain data for extrapolating Tavg and percent hT to 100%
power.
There were no test exception, advance change or temporary change made to the procedure.
9105-S-18, Preliminary Incore/Excore Calibration.
The purpose of this test was to determine the normalized, full power, zero percent axial offset currents.
All acceptance criteria were satisfactorily met.
The incore axial offset at 30% and 50% were -2.688% and -6.685%
respectively.
No test exception were written against this test.
9104-S-19, Remote Shutdown Test, was performed on January 25, 1987.
Four test exceptions were written against this procedure.
There was one temporary change (TC) and one advance change (AC) written against this procedure.
Both were implemented before the test was begun.
During this test 13 items were identified on data sheet 10.2 as equip-ment or procedural problems at the Auxiliary Control Panel (ACP).
The two procedural problems were referred to the p'rocedures group for incorporation into AOP-004.
None of these problems prevented successful completion of the remote shutdown test.
The, inspector
g.
verified that the acceptance criteria were met.
Hot standby was maintained by six operators from outside the control room for at least 30 minutes after all controls had been assumed at the ACP.
The RCS was cooled from Hot Shutdown condition sufficiently to allow RHR System operation.
The inspector verified that personnel charged with responsibility for review and acceptance of test results documented their review and acceptance of the data package.
All test exceptions appeared reasonable and did not invalidate the test.
9104-S-15, Station Electrical Blackout, was performed on January 29, 1987.
There were four (4) test exceptions, three (3) temporary changes (TC)
and two (2) advance changes written during the perform-ance of this test.
After an automatic start, during the performance of this test, the turbine driven feedwater pump (TDFWP) tripped on an apparent overspeed signal.
Refer to inspection report 87-02 for more details.
However, Inspector Follow-up Item 400/87-02-01 was identified at the exit meeting on January 29, 1987.
The licensee committed to resolve this item prior to exceeding 30X power plateau.
(Refer to paragraph 6 for closeout of this item.)
Hot standby condition per Technical Specification Table 1.2 was achieved and maintained for at least
minutes using only emergency on-site power sources.
Both emergency diesel generators started and sequenced loads when off-site power was not available.
All test exception appeared reasonable and did not invalidate the test.
Follow-up to Inspector Identified Item (92701)
(Closed)
50-400/87-02-01 (IFI), Resolution of Turbine Driven Auxiliary Feedwater Pump Overspeed Trips.
The licensee found the trip of the TDAFW pump 1X-SAB on overspeed was attributed to a loose speed pickup switch which provides the overspeed trip signal via the tactometer.
WR5A 87-ADLU1 was written to tighten the loose speed pickup switch.
The licensee re'ported that no overspeed trips have occurred since the tightening of the pickup switch, during which time pump 1X-SAB has successfully completed several verification starts, 48 hours5.555556e-4 days <br />0.0133 hours <br />7.936508e-5 weeks <br />1.8264e-5 months <br /> endurance run, EPT-05lt on February
and 12, 1987.
Operation surveillance test (OST) -
1411 was ran on pump 1X-SAB to declare the pump operable per Technical Specification Surveillance requirement.
This item is considered closed by the inspector.