IR 05000416/1987002
| ML20207T810 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf |
| Issue date: | 02/25/1987 |
| From: | Bernhard R, Jape F NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20207T804 | List: |
| References | |
| 50-416-87-02, 50-416-87-2, TAC-61930, NUDOCS 8703240365 | |
| Download: ML20207T810 (3) | |
Text
_ _ _ - _ _ _ _ _ _._____ - _
..
,
/pnpr;o UNITED STATES
*o NUCLEAR REGULATORY COMMISSION
[
REGION 11
,
g j
101 MARIETTA STREET,N.W.
ATLANTA, GEORGI A 30323
\\...../
Report No.:
50-416/87-02 Licensee: -System Energy Resources, Inc.
Jackson, MS 39205 Docket No.:
50-416 License No.: NPF-29 Facility Name: Grand Gulf Inspection Conducted: Jan ary 30 -
1, 1987 Inspector M
j M
-
.'H. Bernhard
(/ /
Date Signed M27 Approved by:
cd,t e'
Date Signed F. Jape, Section Chief p/
Test Programs Section
.
Division of-Reactor Safety
.
.
SUMMARY'
Scope: This routine, announced inspection was coriducted in the areas of test witnessing and the reviewing of the procedure for performance ;of core stability test.
~
.
a
,
,
Results: No violations or deviations were identified.
"
s
'
,
,
'
.
Y 8703240365 870227 PDR ADOCK 05000416 G
PDR j
-
_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
..
4-REPORT DETAILS 1.
Persons Contacted Licensee Employees
- A. S. McCurdy, Manager of Plant Operations
- Y. Balas, Reload Licensing Manager
- C. W. Angle, Principal Engineer, NPE-0AS
- W. R. Patterson, Reactor Engineering Supervisor R. Kelley, Nuclear Safety Analysis Supervisor
- R. Martin, Nuclear Fuels
- R. T. Errington, Reactor Engineer G. Zinke, Technical Engineering Supervisor Other Organizations
'
- D. N. Fry, Group Leader, Oak Ridge National Laboratory (ORNL)
- J. March-Leuba, Development Engineer, ORNL
- I. Nir, Lead Nuclear Engineer System Services, Inc.
- R. Grummer, Team Leader, Advanced Nuclear Fuels Corp. (ANFC)
- L. Nielsen, Engineer, ANFC
- K. Jenks, Test Coordinator, ENERCON
- J. A. Thie, Consultant, AMS NRC Personnel R. Butcher, Senior Resident Inspector (Operations)
W. Smith, Resident Inspector L. Phillips, NRR
- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on January 31, 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 not identify as proprietary any of the materials 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 inspectio..
2 5.
Review of Test Results and Witnessing of Core Stability Testing The inspector performed a review of Technical Special Test Instruction IJ11-86-002-0-S.
The test setup was reviewed and the methodology of stability testing was discussed with ORNL and ANFC representatives.
A meeting was held to discuss the sequence of testing. A determination was made that two test points out of the original five suggested would not be tested due to core limitations.
The test placed the reactor in conditions corresponding to regions of the power-flow map with estimated decay ratios of 0.6 to 0.9.
The test measured actual core stability and compared it to the predicted values. Data was taken on GETARs for later analysis and with ORNL equipment for real time analysis of core stability.
The test did not have acceotance criteria, as it was for data gathering only. The results of the test are to be the basis for determination of possible future operating restrictions for the reactor.
L. Phillips, Section Leader, RSB/ DBL /NRR, was also present to witness testing.
Stability measurements taken during the testing at the selected test points ranged from decay ratios 0/0.090.03 at 100% power and 100% flow to 0.280.15 at 52% power and 39% flow.
In order to obtain one flow / power point, the reactor had to be taken temporarily into Region IV of the power flow map.
Stability in this region based upor measurements taken while moving through Region IV showed actual decay ratios of 0.310.10. The decay ratios measured at the time of testing were well below the estimated decay ratios of 0.6 to 0.9.
Within the areas inspected no violations or deviation were identified.