IR 05000416/1985031

Insp Rept 50-416/85-31 on 850807-12.No Violation or Deviation Noted.Major Areas Inspected:Startup Testing Results & Procedure Review

ML20134N114
Person / Time
Site:	Grand Gulf
Issue date:	08/22/1985
From:	Jape F, Vandyne K NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20134N112	List: IR 05000416/1985031 ML20134N110
References
50-416-85-31, NUDOCS 8509050010
Download: ML20134N114 (4)

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UNITED STATES

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Report No.: 50-416/85-31 Licensee: Mississippi Power and Light Company Jackson, MS 39205 Docket No.: 50-416 License No.: NPF-29 Facility Name: Grand Gulf

' Inspection Conducted: August 7-12, 1985 Inspector:

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Ddte.91gned Approved by:

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F. JapF, Section C119ff f

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Date Signed Test Programs SectioV, Engneering Branch Division of Reactor Safety SUMMARY Scope:

This routine, unannounced inspection involved 40 inspector-hours on site in the areas of startup testing results review and startup testing procedure review.

Results: No violations or deviations were identified.

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8509050010 85082

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REPORT DETAILS 1.

Persons Contacted Licensee Employees J. D. Bailey, Compliance Coordinator J. E. Cross, General Manager

• D. G. Cupstid Start-up Test Supervisor Other licensee employees contacted included engineers, technicians, operators, and office personnel.

Other Organization T. R. Enright, General Electric, Engineer, Startup Testing NRC Resident Inspectors R. C. Butcher, Senior Resident Inspector J. L. Caldwell, Resident Inspector

• Attended exit interview 2.

Exit Interview The inspection scope and findings were summarized on August 12, 1985, 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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4.

Unresolved Items Unresolved items were not identified during the inspection.

5.

IndependentInspectionEffort(72302)

Unit I resumed operation on August 9,1985, following a reactor scram due to a turbine generator rotor low cooling flow transmitter failure.

The inspector witnessed portions of the startup preparations on August 8 and the startup on August 9.

Activities observed included withdrawal of control

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rods and adjustment of cooling water flow to the turbine generator rotor.

Documentation reviewed included the reactor operator's log, shift technical advisor's log and plant computer output.

In addition, the inspector conducted a general inspection of adherence to proper housekeeping and formal behavior in the control room during startup and subscquent operation.

All personnel appeared to be attentive to their respective duties and responsibilities.

Within the areas examined, no violations or deviations were identified.

6.

StartupTestProgramInspection(72300,72301,72512)

a.

The following test procedures were reviewed to ensure t_ hat prepar,ation, review, approval, and revision were accomplished in accordance with applicable administrative requirements.

In addition, the Final Safety Analysis Report (FSAR) was reviewed to ensure testing commitments were included in the test procedures. All test procedures reviewed appeared to be adequate. The procedures and the purpose of each are as follows:

(1)

1-833-5U-30-6, Recirculation System, Recirculation Puc Trip section only to obtain Recirculation System performance data durinf the

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pump trip, flow coastdown and pump restart

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to verify that the Feedwater Control System can_ satkfac-

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torily control water level without a turbine trip I

' to obtain baseline data for analysis of flow related neutron

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s flux oscillations and core plate delta-P fluctbe.io.ns u

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to record and verify acceptable perfornance of thet Recir-

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culation System two-pump trip (RPT) circuit

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to obtain baseline data for analysis of flow related neutron

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flux oscillations and core plate delta-P fluctuations.

(2)

1-000-SU-23-6, Feedwater System, Feedwater Pump Trip,section only to demonstrate that the feedwater system has been adjusted to

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provide acceptable reactor water level control by 1.iducing level and flow transients

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to demonstrate the capability of the autostic core flow

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runback feature to prevent a low. level f Scram following a feedwater pump trip via perfonnance of that event

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to determine the feedwater flow runout capability via data

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collection and analysis

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b.

1-B33-50-30-6, Recirculation System Pump Trip Testing is partially complete. Recirculation Pump 'A' was tripped per section 6 of the test procedure on August 7,1985.

The inspector reviewed and evaluated the data obtained against FSAR acceptance criteria and expected test results as outlined on the licensee's test assessment form.

Included in the review were the following plant parameters:

(1) Recirculation Pump 'A'

(a) High speed breaker (open/close)

(b) Speed'

(c) Drive flow 2) Recirculation Loop 'A' flow 3) Recirculation Loop 'B' flow 4) ' Core flow (5) feedwater flow (6) APRM Simulated heat flux (7) Reactorvessellevel(narrowrange)

(8)

Flow-biased scram (9) Flow-biased rod block Within the areas inspected, no violations or deviations were identified.

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