IR 05000395/1987015
| ML20235Y024 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 07/15/1987 |
| From: | Jape F, Mathis J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20235Y002 | List: |
| References | |
| 50-395-87-15, NUDOCS 8707250033 | |
| Download: ML20235Y024 (4) | |
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tka MGoq UNITED STATES
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NUCLEAR REGULATORY COMMISSION
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101 MARIETTA STREET, N.W., SUITE 2900
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I Report No.:
50-395/87-15 Licensee:
South Carolina Electric and Gas Company Columbia, SC 29218 Docket No.:
50-395 License No.:
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Facility Name:
V. C. Summer
I Inspection Conducted: May 7-9 & 26-29, 1987
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/Ly Inspector:
Jp.Mathis"
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Date Signed Approved by:
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F. Jape, Section Chief V
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Date SignLd Test Programs Section Division of Reactor Safety SUMMARY Scope:
This routine, unannounced inspection was in the areas of witnessing performance of the integrated safeguard test, review of the procedure for start-up from a refueling outage and followup of previously identified items.
Results: No violations were identified.
l 8707250033 B70721 PDR ADOCK 05000395 G
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REPORT DETAILS 1.
Persons Contacted Licensee Employees 0. S. Brandham, Director Nuclear Plant Operation J. L. Skolds, Deputy Director, Operation and Maintenance
- A. R. Koon, Manager, Technical Support B. William, Supervisor, Operation
- G. Soult, Manager, Operation G. A. Loignon, Associate Manager, Performance and Result
- D. Malkmus, Technical Support
- R. Steffy, Performance Engineer Other licensee employees contacted included engineers, technicians, operators, security force members, and office personnel.
NRC Resident Inspectors
- R. L. Prevatte, Senior Resident Inspector
- P. C. Hopkins, Resident Inspector
- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on May 9 and 29, 1987, 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 identify some material as proprietary during this inspection, but this material is not included in this inspection report.
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.
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I 5.
Witnessing of the Integrated Safeguards Test (61701)
Train "B" of the. Integrated Safeguard Test was performed on May 9, 1987, under the guidance of Surveillance Test Procedure (STP) 125.011
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(Revision 2).
The portion of the test witnessed by the inspector consisted of a simulated loss of offsite power in conjuction with an Engineered Safety Feature Actuation (ESF) test signal. There appeared to be adequate coordination among personnel involved in the test, however, there were a few problems that are discussed below.
Test #2 of the Integrated safeguard test demonstrated that on an ESF activation, diesel generator "B" starts on standby by manually initiating an SI signal from the control board.
Test #3 demonstrated that by manually initiating an SI signal, the. diesel generator returns to standby and emergency loads sequence on offsite power.
Except for the items discussed below, the plant response to the test
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appeared to be satisfactory.
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During Test #1, the strip chart recorded did not show starts times on
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service water, component cooling water and chiller water pumps.
This item was written es e deficiency and retested during Test #2.
The retest was satisfactory.
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Feedwater regulating valves and bypass valves were not verified closed during Test #1. Because water was injected water into the reactor vessel the licensee reset train B safety injection switch much sooner than had they not inject 6d into the reactor vessel. Therefore, the personnel
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l, that were assigned to verify ' SF position of equipment listed in
E Attachment 1 of the procedure did not do a thorough verification prior I
to resetting of the SI signals. A test deficiency was written and a verification of the feedwater regulating valves and bypass valves were performed during Test #2 of the integrated safeguard test.
Reactor building spray flow data was not recorded because the pumps were aligned for the recirculation mode. This deficiency was retested under STP 125.010 satisfactory.
Overall, the test STP 125.011, met acceptance criteria and the V. C. Summer-Technical Specification.
No violations or deviations were identified in the areas inspected.
5.
Post-refueling Startup Tests (72700, 61708, 61710)
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The following procedures were reviewed prior to performance:
I REP-107.001 (Revision 2), Controlling Procedure for Refueling and Refueling Startup Testing,
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REP-107.003 (Revison 0), Beginning of Cycle Dilution To Criticality, REP-107.008 (Revision 1), Boron Endpoint Measurement, REP-107.010, (Revision 2), Shutdown and Control Rod Drop Test,
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l STP-134.001, (Revision 6), Shutdown Margin Verification, STP-210.002, (Revision 1), Isothermal Temperature Coefficient Measurement, STP-202.001, (Revision 2), Target Axial Flux Difference Meas:;,cinent, and REP-103.001, (Revision 2), Control Rod Worth Measurements.
A 10-CFR 50.59 evaluation for the cycle 4 design was reviewed in concert with the aforementioned procedures.
At the end of the review, it was concluded that the proposed test program was technically sound.
6.
Previous Outstanding Items (92701)
(Closed) IFI 395/85-45-01:
Verification of procedure revisions during two year procedure review cycle.
The licensee added signoff steps for the following procedures REP's 107.001, 107.003, 107.008, 107.009 103.001, STP's 210.002 and 208.001.
These procedures were observed to work well during this inspection.
(Closed) IFI 395/85-45-02:
Verify implementation of test log during startup.
The inspector verified that the licensee maintains a startup test log. This item is closed.
i (Closed) IFI 395/85-45-03:
Verify inclusion of additional guidance in rod-worth and temperature measurement procedures to assure scaling and l
spanning of chart traces provide the largest practical trace for graphical analysis.
The inspector verified that procedures STP-210.002 and REP 103.001 were revised to change the X-Y chart recorder scaling to 2 PCM/ inch for reactivity and 1 F/ inch for RCS Tavg.
The changes were made, therefore, this item is closed.
(Closed) IFI 395/86-14-01:
Review corrective action to assure adequate 50.59 reviews.
The licensee failed to perform an adequate safety review of the implementation of SCALS, as required by 10 CFR 50.59.
The inspector reviewed the licensee corrective action which was a revision to procedure TPS-106, unreviewed safety question evaluation "that include more guidance on 50.59 review". This item is closed, i
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