IR 05000416/1986030

Insp Rept 50-416/86-30 on 860915-19.No Violations or Deviations Noted.Major Areas Inspected:Refueling Activities, Spent Fuel Pool Activity,Followup to Previously Identified Items & Meeting on Stability Testing

ML20215N155
Person / Time
Site:	Grand Gulf
Issue date:	10/21/1986
From:	Burnett P, Jape F, Mathis J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20215N151	List: IR 05000416/1986030 ML20215N150
References
50-416-86-30, NUDOCS 8611040374
Download: ML20215N155 (5)

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UNITED STATES

/p2 Rtet, 'o NUCLEAR REGULATORY COMMISSION g #

n REGION 11 g ,j 101 MARIETTA STREET, I

• I c ATLANTA, GEORGI A 30323 s,

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Report No.: 50-416/86-30 Licensee: Mississippi Power and Light Company Jackson, MS 39205 Docket No.: 50-416 License No.: NPF-29 Facility Name: Grand Gulf Inspection Conducted: September 15-19, 1986 Inspectors: k.I. M M \ok 24k8(o J. Mathis Date Signed AW /0 ~ 2/-N P. T' Bu ett' ~ Date Signed Approved by: mok FTJape,'Section~ Chief,TBy

/# ol2/- M Date Signed Engineering 3 ranch Division of Reactor Safety SUMMARY Scope: This routine, unannounced inspection was in the areas of refueling activities, spent fuel pool activity, followup to previously identified items and

, meeting on stability testing Results: No violations or deviations were identifie l l

8611040374 861024 PDR ADOCK 05000416 1 0 PDR l

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REPORT DETAILS

.i A Persons Contacted Licensee Employees

• C. R. Hutchinson, General Manager

• J. E. Cross, Site Director

• R. F. Rogers, Unit 1 Project Manager

• L. L. Daughtery, Compliance Supervisor

• D. G. Cupstid, Technical Support Superintendent

• J. D. Bailey, Compliance Coordinator G. H.-Lee, SR0 Refueling 1 Y. Balas, Reload Project Engineer M. Harrigill, Technical Support Engineer R. Kelley, Nuclear Plant Engineering J. Lee, Nuclear Fuels Engineer R. Patterson, Technical Support Nuclear Engineer Other licensee employees contacted included engineers, operators, security force members, and office personne Other Organizations L. Nielson, Engineer -Exxon Nuclear Corporation H. Williamson, Engineer -Exxon Nuclear Corporation

I. Nir, Nuclear Engineer - Middle South Services

S-J. Penj, Nuclear Engineer - Middle South Services L. Phillips, Engineer - USNRC

RSB/ DBL D. Fry, I&C Division - Oak Ridge National Laboratory NRC Resident Inspectors R. C. Butcher, NRC Senior Resident Inspector W. F. Smith, NRC Resident Inspector

• Attended exit interview Exit Interview i

The inspection scope and findings were summarized on September 19,1986, with those persons indicated in paragraph 1 above. The. inspector described the areas inspected and discussed in detail the inspection finding No dissenting comments were received from the licensee.

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The licensee did not identify as proprietary any of the materials provided i

to or reviewed by the inspectors during this inspectio !

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2 Licensee Action on Previous Enforcement Matters This subject was not addressed in the inspectio . Unresolved Items Unresolved items were not identified during the inspectio . Refueling Activity (60705, 70710)

Grand Gulf Nuclear Station Unit 1 commenced its first refueling outage on September 6,1986, at 12:01 a.m. During this first refueling outage at GGNS-1, MP&L will be replacing approximately 264 irradiated GE assemblies with Exxon Nuclear Company (ENC) SN-1.18x8 fuel assemblies. These ENC XN-1.18x8 fuel assemblies were designed and built by ENC for the_ GGNS cycle 2 reload core. Changes to GGNS Unit 1 Technical Specifications to support power in cycle 2 were submitted to the NRC on July 15, 198 Approval of the proposed TS changes is expected around October 24, 198 a. . Preparation for Refueling The inspector reviewed the Unit 1, Integrated Operating Instruction

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(10I) 03-1-01-5, Refueling which provided instructions for plant shutdown for 101-3 to Mode 5 (Refuel). The inspector reviewed the following procedures to ascertain the licensee's preparation for refueling including, adequacy of procedures, and administrative controls for both refueling and maintenance activities performed during the outage:

AP 01-S-06-10 (Rev. 2), Control of Refueling Operations S0I 04-1-01-F11-1 (Rev. 15), Refueling Platform 501 04-1-01-F11-2 (Rev.14), Horizontal Fuel Transfer Mechanism SP 06-0P-1C51-V-0001, SRM Channel Functional Test SP 06-0P-1C71-V-0002, Refueling Interlock Check 10I 03-1-01-5 (Rev.19), Refueling The test procedures above were examined for embodiment of the necessary test prerequisites, preparation, acceptance criteria and sufficiency of technical conten Refueling Activities The inspector witnessed refueling activities from the control room, refueling platform and spent fuel pool areas to verify the following:

(1) Core monitoring during refueling operations is in accordance with T (2) Vessel and spent fuel storage pool water levels are as required by T _ _ - _ _ _ _

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(3) Reactor mode switch position is as required by T ~

(4) Operability of refueling interlock (5) Checks of decay heat removal system flowrate are being conducted l as required by T l l

(6) Staffing requirements were in accordance with T (7) Radiological controls were maintained in accordance with approved I procedure (8) Direct communication was established between the control room and reactor buildin (9) Appropriate steps and QA hold points were signed of Spent Fuel Pool Activities The inspector observed fuel handling operations during fuel movement in the spent fuel pool area and reviewed procedures related to fuel handling to verify that the following were included in the procedures:

(1) A limitation on the number of fuel assemblies that can be out of safe geometry locations at the same tim (2) Provision for verifying prior to fuel handling that the spent fuel pool area crane interlocks or physical steps prevent the crane from passing over fuel storage location (3) Provision for verifying prior to fuel handling that the spent fuel pool ventilation system'is operabl (4) Provision for verifying that minimum water level for the spent fuel pool is monitored during fuel handling operation (5) Provision for verifying that the spent fuel pool storage area radiation and airborne radioactivity monitors are operabl (6) Provision for verifying that the spent fuel pool cleaning and cooling system are operabl Fuel handling operations in the spent fuel pool were observed by the inspector. Spent fuel pool water level was equal to or higher than the level established by Technical Specificatio No violation or deviations were identified in the areas inspected.

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, Meeting on Stability Testing (92705)

A meeting was held among representatives of the licensee, Exxon Nuclear Corporation (ENC), Oak Ridge National Laboratory (0RNL), and the NRC (RSB/ DBL and RII) to discuss forthcoming tests of reactor stability to be performed early in cycle 2. The tests will not require deliberate pertur-bation of the reactor. Instead, neutron noise analysis will be performed at steady-state conditions with the reactor operating in a power- flow region of predicted low stability. Much of the meeting addressed providing signals to allow ORNL to make direct, real-time measurements of stability, and hence perform an audit function for the NRC. Any data to be used in support of future changes in Technical Specifications will be obtained and analyzed by the licensee and ENC. . A new Technical Specification to be implemented starting with cycle 2 will require additional surveillance when the reactor is operated in a power-flow region in which the predicted stability decay ratio is> = 0.6. The goal of these tests is to better define that regio The inspector made arrangements to receive advance notification of the tests so they may be witnessed by Region II personne . Followup on previously identified items (Closed) Inspection Followup Item (IFI) 416/84-29-01: Verify resolution of vibration displacement values for small bore piping prior to exceeding test condition 2. MP&L contracted Wyle Laboratories to provide trained personnel and equipment for data collection, reduction and analysis. The changes made in data collection, reduction and analysis for small bore piping vibrations I fall within the description of special testing found in chapter 14 of FSA The changes made satisfies MP&L ' commitment for providing an alternate program for small bore pipe analysis prior to leaving test condition Inspection Followup Item 416/84-29 01 is close (Closed) IFI 416/85-11-01: Resolution of Data for level 1 Criteria in Startup Test 1-B33-SU-30-3 subsection 4.7, figure 4. MP&L submitted pump coastdown results to GE Engineering for evaluation of pump coastdown data and agrees that the result was adequate to proceed to 100 percent powe This item is close (0 pen) Unresolved item 416/86-06-01: Define the allowable applications of the rod position bypass switches. The licensee has proposed changes to Technical Specifications 3.1.4.2 and 4.1.4.2 and the associated base This item will remain open until there is a final decision on the proposed change .-. .

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