IR 05000395/1982023
| ML20052C274 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 04/02/1982 |
| From: | Hunt M, Jape F, Matt Thomas NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20052C270 | List: |
| References | |
| 50-395-82-23, NUDOCS 8205040560 | |
| Download: ML20052C274 (4) | |
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UNITED STATES
NOCLEAR REGULATORY COMMISSION o
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101 MARIETTA ST., N.W., SUITE 3100 f*j
4 ATLANTA, GEORGIA 30303 Report No. 50-395/82-23 Licensee:
South Carolina Electric and Gas Company Columbia, SC 29218 Facility Name:
V. C. Summer Docket No. 50-395 License No. CPPR-94 Inspection at V. C. Summer site near Winnsboro, SC
Inspectors:
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Date Signed
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Af W da te' S i gned M. T
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b Approved by:
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Yate Signed En/)apef'Section Chief
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gineering Inspectio ranch Division of Engineering and Technical Programs SUMMARY Inspection on March 16-19, 1982 Areas Inspected This routine, unannounced inspection involved 52 inspector-hours on site in the areas of preoperational test results review and inspector follow items.
Results Of the areas inspected, no violations or deviations were identified.
8205040560 820406 PDR ADOCK 05000395 C
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REPORT DETAILS j
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1.
. Persons Contacted
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l Licensee Employees
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- 0. S. Bradham, Station Manager.
- J. G. Connelly, Deputy Plant Manager i
- H. C. Fields, Technical Services Enrineer I
- D. A. Lavigne, Director, Surveillance Systems
- K. W. Nettles, Engineering
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- P. V. Fant, Director, Station QC l
- S. S. Howze, Nuclear Licensing Engineer i
- H. I. Donnelly, ISEG Engineer
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Other Organizations t
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- H. A. Bamberger, Gilbert Associates, Inc. (GAI), Resident Engineer.
l D.-Cunningham, GAI, Field Engineer
- L. M. Klingman, GAI, Resident Engineer i
- D. A. Yoder, GAI, Design Group Supervisor
'c. W. Bowman, Westinghouse Electric Corporation (W), Startup Engineer NRC Resident Inspector r
- J. L. Skolds
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- Attended exit interview
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2.
Exit Interview
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The -inspection scope and findings were summarized on March 19, 1982, with
those persons indicated in paragraph 1 above. The licensee committed to the i
retest of~the containment spray pumps as discussed in paragraph 7.d.
Other l
inspection findings were acknowledged without significant comments by the licensee.
.3.
Licensee Action on Previous Inspection Findings Not inspected.
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Unresolved Items Unresolved items were not identified during this inspection.
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5.
Integrated Hot Functional Test (HFT) Results. Evaluation The _ inspectors reviewed the evaluation of the thermal expansion measurements taken during the HFT. 'The data were collected in accordance with TE 001, Rev. 2, System Thermal Expansion During HFT. The results had been evaluated
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and in a few cases, additional clarification was required to justify the readings.
In other instances, additional measurements will be required during the next system heatup. Additionally, piping systems such as feed-water pressurizer spray, emergency feedwater did not attain full operating
temperature due to the operating conditions. The supports for these systems will be monitored during the next system heatup. All the areas requiring additional rework or monitoring have been identified in the discrepancy list for this procedure and identified as TCR #9. The inspectors will continue to follow the completion of the system thermal expansion tests. The comple-tion of.the items identified under TCR #9 will be identified as an inspector followup item 50-395/82-23-01, Complete ' Discrepancy Items noted in TE-1, Rev. 2.
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Inspector Followup Items (IFI)
(Closed) IFI 395/80-26-01, Review final test results and AE evaluation of TE data. See paragraph 5 for discussion.
(Closed) I F_I 395/80-22-02, Reinspect supports and restraints that are adjusted during or after HFT on next system heatup.
The licensee has performed two system HFT, the latter being to reevaluate hangers.
This evaluation is discussed in paragraph 5.
(Closed) IFI 395/80-22-03, Compare RCS thermal growth with predicted values - reanalyze as necessary. See the discussion in paragraph 5.
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7.
Preoperational Test Results Review - Engineered Safety Features
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The following preoperational tests were reviewed to verify that the tests adequately address NRC requirements and licensee commitments relating to Engineered Safety Features (ESF).
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CS-002 Charging Pump Flow Test b.
RH-001 RHR Flow Test c.
SI-003 Accumulator Blowdown Test d.
SP-002 Reactor Building Spray Pump Flow Test
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The inspectors reviewed results of the above tests to verify the following:
a.
Individual test steps and data sheets were properly initialed and dated.
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Data sheets were completed.
c.
Changes to the procedure were made in accordance with pertinent requirements.
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d.
Test changes did not change the basic objective of the test.
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During review of the test 'results for the reactor building spray pump' flow
test,.the inspector found that it was not clear what the pump flow rates i
were-(full flow condition), nor was it clear under what conditions the flows were ob.tained. The inspectors discussed this with the licensee representa-
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tive who acknowledged that the results were not very clear. The licensee
representative stated that in order to verify the flow rates for the reactor building spray pumps and to clarify the test results, the pumps would be retested. Preoperational test procedure SP-007 is being written to accomp-
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lish this. Followup during conduct of SP-007 and review of the test results
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will be done by the Senior Resident Inspector.
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