ML20059H610

Cycle 7 Startup Physics Test Summary Rept for Physics Testing Completed on 931220

ML20059H610
Person / Time
Site:	Grand Gulf
Issue date:	01/14/1994
From:	Hutchinson C ENTERGY OPERATIONS, INC.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
GNRO-94-00002, GNRO-94-2, NUDOCS 9401310035
Download: ML20059H610 (7)

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• e " Entsrgy operatnons,inc.

_ ENTERGY

-om Ibrt Gbwru MS 39150 T.! 001437 2GYJ C. R. Hutchinson January 14, 1994 $%7" orya n.e unam n n U.S. Nuclear Regulatory Commission Mail Station P1-137 Washington, D.C. 20555 Attention: Document Control Desk

SUBJECT:

Grand Gulf Nuclear Station Unit 1 Docket No. 50-416 License No. NPF-29 Post RFO6 Startup Test Report GNRO-94/00002 Gentlemen:

Entergy Operation, Inc. is transmitting, with this letter, the Grand Gulf Nuclear Station (GGNS)

Unit 1 Post Refueling Outage-6 (RFO6) Startup Test Report. This report is sent in compliance with the requirements of Grand Gulf Technical Specifications 6.9.1.1,6.9.1.2, and 6.9.1.3.

The startup physics testing was completed on December 20,1993. The attached report provides a summary of each test and the results where applicable.

If further information is required, please contact this office.

Yours truly,

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l l_ CRH/TMC attachments: 1. Startup Physics Test Summary

2. Core Loading Verification

3. Control Rod Functional Testing

4. Shutdown Margin Determir,ation c 5. TIP Asymmetry Check cc: (See Next Page) t 0 i i 9401310035 940114 7 -hI k PDR ADOCK 05000416 '! /

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' January 14, 1994 GNRO-94/00002 Page 2 of 3 l

cc: Mr. R. H. Bernhard (w/a)

Mr. D. C. Hintz (w/a) i Mr. R. B. McGehee (w/a)

Mr. N. S. Reynolds (w/a) 1 Mr. H. L Thomas (w/o) -l Mr. Stewart D. Ebneter (w/a)

Regional Administrator 1 U.S. Nuclear Regulatory Commission  !

Region 11 l 101 Marietta St., N.W., Suite 2900 l Atlanta, Georgia 30323 1 l

Mr. P. W. O'Connor, Project Manager Office of Nuclear Reactor Regulation i U.S. Nuclear Regulatory Commission Mail Stop 13H3 Washington, D.C. 20555 I

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I Attachment I .

• 1 GNRO-94/00002 Grand Gulf Nuclear Station Unit I Cycle 7 Startup Physics Test Summary Grand Gulf Nuclear Station (GGNS) resumed commercial operation in Cycle 7 on December 4,1993 following a Refueling / Maintenance Outage. The Cycle 7 reload consisted of replacing 240 Siemens -

Power Corporation (SPC) 8X8 fuel assemblics,32 SPC 9X9 fuel assemblies and 4 SPC 9X9 lead test fuel ~ '

assemblics with 276 SPC 9X9 fuel assemblics. These startup tests were performed during RFO6 and w hile attaining full power after RFO6 and are summarized in this report:

1) Core Loading Verification

2) Control Rod Functional Testing

3) Shutdown Margin Determination

4) TIP Asymmetry In addition to the above startup physics tests, the startup test program included: Core Monitoring System Verification, Neutron Monitoring System Response, Recirculation System Calibration, plant modification testing for continuous reactor water level reference leg keep fill, and digital feedwater control system tuning as well as other surveillance testing required by GGNS Technical Specifications. The additional >

test results are available at the site on request.

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Attachment II CNRo-94/00002 Startuo Physics Test #1 Core Loading Verification Purpose Ensure each reactor fuel assembly is:

• in its correct core location, e oriented properly, e and seated properly in its support piece.

Cnteria The reactor core is visually checked to verify conformance to the vendor supplied core loading pattern.

Fuel assembly serial numbers, orientations, and core locations are recorded. A height check is performed to verify all assemblies are properly seated.

1 BLS11.11 The as-loaded core was verified for proper fuel assembly serial numbers, locations, orientation, and seating in accordance with the SPC Cycle 7 core loading pattern. The core verification procedure was successfully completed on October 30,1993.

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• . Attachment III CNRO-94/00002 Startuo Physics Test #2 Control Rod Functional Testing E91P2K Verify operability of each control rod by:

e normal withdrawals and insertions.

• ensuring it is latched to its control rod drive, e and moves at design speeds without excessive friction.

Cntena Functional testing of each control rod is performed to ensure proper operability. This testing includes withdrawal and insertion timing, coupling verification, friction testing where required and scram time testing.

Results A control rod coupling check was performed in accordance with GGNS Technical Specification surveillance requirement 4.1.3.4 cach time a control rod was fully withdrawn.

Each individual control rod was timed during a normal withdrawal and insertion sequence. Control rods with stroke times outside the tolerance of normal stroke time 20% were readjusted to within normal .

stroke time i 10% This was in accordance with GE recommendations.

No control rod drives were replaced and no fuel cells were disassembled during RFO6. Friction testing was not required.

Each control rod was scram time tested during the Operational Hydro Test or reactor startup in accordance with GGNS Technical Specification surveillance requirement 4.1.3.2. A number of control rods were slow to start of motion. These control rod's hydratic control units were reworked and retested.  :

All of the control rod scram times were within the allowable limits. '

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Attachment IV GNRO-94/00002 Startun Physics Test #3 Shutdown Marrin Determination Purpose To ensure:

the reactor can be made suberitical from all operating conditions.

the reactivity transients associated with postulated accident conditions are controllable within acceptable limits, e

the reactor will be maintained sufficiently subcritical to preclude inadvertent criticality in the shutdown condition.

Cntena The subcritical demonstration verifies the reactor remains suberitical with the analytically determined strongest worth control rod withdrawn.

The in-sequence rod withdrawal shutdown margin calculation begins by withdrawing control rods in their standard sequence until criticality is achieved. The shutdown margin of the core is determined from calculations based on the critical rod pattern, the reactor period, and the moderator temperature. To ensure no reactivity anomaly exists, the actual critical control rod positions will be verified to be within 1% delta M of the predicted critical control rod position.

Results The suberitical demonstration was performed on November 3,1993.

The in-sequence critical shutdown margin surveillance procedure was completed on November 26,1993.

The shutdown margin (SDM) at the beginning of-cycle (BOC) was calculated to be 0.9785% delta M.

The Cycle 7 "R" value is equal to 0.14% delta k/k, therefore, the Cycle 7 minimum shutdown margin is i 0.8385% delta M which is well within GGNS Technical Specification 3.1.1 requirement of 0.38% delta  :

M.

The calculated reactivity difference between the actual and predicted SDM was 0.3115% delta M which l

was well within GGNS Technical Specification 3.1.2 requirement of 1% delta M. j i

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~ Attachment V

. GNRO-94/00002 Startuo Physics Test 11 TIP AsymmStry Check blIPQTs Verification that the observed variance in integral MICP > BURN calculated TIP responses at GGNS is statistically consistent with the variance of the integral TIP measurements used in SNP's Neutronics Methods for Design and Analysis.

CIl!Etia A gross asymmetry check is performed as part of a detailed statistical uncertainty evaluation of the TIP System. A complete set of TIP data is obtained at steady state conditions while greater than 85% rated power. A total average deviation or uncertainty is determined for all symmetric TIP pairs as well as the maximum absolute deviation. The results will be evaluated to assure proper operation of the TIP System and symmetry of the core loading.

83191tj The TIP Reproducibility and Symmetry Uncertainty calculations were performed on December 20,1993 at 100% core thermal power. A_ total of four Chi-squared tests were performed. The first consistency test examined the variance in the combined measured and calculated integral TIP data. The second consistency test evaluated variance in the measured integral TIP responses for symmetric locations. The third and fourth test repeated the first two tests on a planar basis by renormalizing the nodal TIP distribution to unity within each plane separately for both the measured and calculated TIP distributions.

The results of the four tests are as follows:

T_Ist Chi-Sauared Value Critical Value 1 8.13 60.48 2 2.20 30.14 3 169.04 950.I3 4 43.06 426.46 All of the Chi-squared vahx:s were much less than the Critical values indicating no TIP Asymmetry exists.  ;

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