IR 05000416/1986038
| ML20210C727 | |
| Person / Time | |
|---|---|
| Site: | Grand Gulf  |
| Issue date: | 01/09/1987 |
| From: | Jape F, Mathis J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20210C694 | List: |
| References | |
| 50-416-86-38, NUDOCS 8702090448 | |
| Download: ML20210C727 (4) | |
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NUCLEAR REGULATORY COMMISSION o
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Report No.: ;50-416/86-38.
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Licensee: Mississippi Power and Light Company Jackson, MS i39205 a
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Docket'No.:
50-4I6 License No.:
NPF-29 Facility Name: ' Grand Gulf Inspection Conducted: Novem er 27. ' December 1, 1986 Inspecto -
A A L. Mathis (/-
Date Signed
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Approved by:
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F. Jape, Section Chief
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Dhte Signed
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Eiigineering Branch Division of Reactor Safety SUMMARY Scope:
This routine, unannounced inspection was in the areas of post refueling startup.
-Results: No violations or deviations were identified.
8702090448 8701 N PDR ADOCK 05000416 PDR G
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REPORT DETAILS i-
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Persons Contacted
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Licensee EmpJoyees
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- C. R. Hutchinson, General Manager
- L. F. Daughtery,' Compliance Supervisor
- A. S. McEundy,rManager Plant OPS
- J. D. Bailey,< Compliance Coordinator R. Patterson', Reactor Engineer Supervisor D. Cupstid,, Start-up Superintendent G. Staples, Reactor. Engineer T. Errington, Reactor Engineer Other licensee employees contacted included construction craftsmen,
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engineers, technicians, operators, mechanics, security force members, and office personnel.
Other Organization R. Grummer, Exxon Fuel Representative NRC Resident Inspectors
- R. Butcher, SRI
- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on December 1, 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 inspector during this inspection.
3.
Licensee Action on Previous Enforcement Matters This subject was not addressed in the inspection.
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Unresolved Items Unresolved items were not identified during the inspection.
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Post-Refueling Startup Tests (72700, 61707)
Grand Gulf Unit I was returned to criticality at 0448, November 30, 1986, following its first refueling outage. Cycle 2 loading consists of 264 fresh Exxon Nuclear Company (ENC) 8 x 8 x N-1.1 reload assemblies and 536 General Electric 8 x 8 initial core assemblies. The average assembly enrichment of fresh ENC fuel, including the six inch natural uranium blanket at the top and bottom of the assembly, is 2.81 W/0 U-235.
The inspector witnessed portions of initial operations over the first four days of the cycle, Activities observed included withdrawal of control rods, source range monitor (SRM) response to rod movement, shutdown margin determination and control room surveillance.
The inspector reviewed the following completed startup tests to verify that the acceptance criteria were met and all deficiencies were resolved in a timely manner:
a.
Control Rod Scram Testing The inspector reviewed the completed procedure 06-RE-SC-11-V-402 (Rev. 25) titled " Control Rod Scram Testing," which was performed on November 11, 1986, at 1008 in operational condition 4.
Control rod scram timing successfully met acceptance criteria of Technical Specification 4.1.3.2.
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Source Range Monitor Response to Rod Movement This test was performed in accordance with procedure 09-S-02-20 titled " Neutron Monitoring System performance."
The test result was found to be acceptabla.
c.
Shutdown Margin Determination The inspector reviewed completed procedure 06-RE-SB13-V-401 entitled
" Shutdown Margin (SDM) Demonstration - In Sequence Critical Shutdown Margin Determination."
SDM was performed on November 30, 1986, at 0537.
The calculated SDM determined by the licensee was 4.06 %Ak/k.
The beginning of cycle (BOC) calculated SDM equalled 4.09 %Ak/k.
The percent difference of calculated SDM and B0C calculated SDM is 0.03
%Ak/k. Test results were found acceptable.
Other document reviewed included the reactor operator's log book, test engineer's log book, control rod withdrawal sequence data sheets, and OD-7 print out.
No violations or deviations were identified.
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Followup On Previously Identified Items (Closed) IFI (416/84-50-01), Revise Calculations of Average Vessel Water Level by December 31, 1984.
The inspector reviewed the revised procedure 1-B21-50-16-1 (Rev. 2) entitled, " Selected Process Temperature and Water Level Measurement." -The procedure was changed in the manner the data is to be taken in order to minimize the effects of indicator accuracies. Also, the new data sheet 2 allows correct comparison of the level indicating switches and transmitter on each condensing pot. The inspector is satisfied with the licensee's corrective action, therefore, this item is considered closed.
(0 pen) UNR 416/86-06-02, The allowed use of rod position bypass switches is not defined.
This item will remain open until NRR has evaluated the proposed Technical Specification amendment submitted by MP&L on allcwed use of rod position bypass switch.
(Closed) Vio 416/86-06-01, Failure to follow Operating Procedure requirement to establish RPCS Sequence Before Dropping Below LPAP.
Procedure I0I 03-1-01-2 was revised to require verification that the rod pattern conforms to RPCS constraints prior to down shifting the recirculation pumps..This item will be closed out in this report.
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