B12019, Summary Rept,Cycle 11 Startup Physical Testing

Summary Rept,Cycle 11 Startup Physical Testing

ML20154R841
Person / Time
Site:	Millstone
Issue date:	03/31/1986
From:	Mroczka E, Opeka J NORTHEAST NUCLEAR ENERGY CO., NORTHEAST UTILITIES
To:	Murley T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
B12019, NUDOCS 8603310213
Download: ML20154R841 (4)

Text

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Docket No. 50-245 d

Millstone Nuclear Power Station, Unit No. I Summary Report Cycle 11 Startup Physics Testing 1

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i March,1986

' 8603310213 860331 PDR ADOCK 05000245 P PDR g

7 Millstone Unit 1 Cycle 11 Startup Physics Testing Reactor Core Verification At the completion of fuel loading, the reactor core was videotaped and verified. Fuel assembly location, seating and rotation were found to be correct.

Cold Control Rod Drive Testing At the completion of core verification, each control rod underwent functional, subcritical and friction testing. No abnormalities were noted.

Hot Control Rod Drive Scram Time Testing With the reactor at hot operating conditions, each control rod was individually scrammed and timed. The following results were obtained:

Average

% Inserted Tech. Spec. Titae (Sec.) Actual Ylme (Sec.)

5 0.375 0.320 20 0.900 0.710 50 2.000 1.415 90 3.500 2.548 The average 5%, 20%, 50% and 90% scram times for the three fastest control rods in a two-by-two array were also compared to Technical Specification limits. No discrepancies were noted.

Shutdown Margin Test Shutdown margin demonstration was performed using the in-sequence critical data method. The results indicated that the reactor core at BOC 11 had a shutdown margin of 1.64% Ak/k. The required shutdown margin at BOC 11 was 0.79%, based on the Technical Specification limit of 0.33% and an analyzed decrease in shutdown margin of 0.46% between BOC 11 and the most reactive point in the fuel cycle.

Non-Voided Critical Eigenvalue Comparison for a Fixed Control Rod Pattern The expected critical control rod pattern was compared to the actual critical control rod pattern. The actual control rod pattern required 12 additional notches of control rod withdrawal to achieve core criti-cality. The reactivity associated with these additional notches is not considered to be an anomaly.

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! Critical Rod Configuration Comparison at Rated Reactor Conditions i At 100% power and core equilibrium conditions, the actual control rod pattern was compared to the predicted ccStrol rod pattern for BOC 11

operation. The actual number of control rod notches inserted in the core was 518 notches, as compared to 500 notches predicted to be inserted. The reactivity associated with the 18 additional notches is t well within the acceptance criteria of 1% Ak/k and is not considered -to be an anomaly (for Cycle 11 operation at rated conditions, 339 notches is equivalent to 1% Ak/k).

Jet Pump Performance Jet pump baseline data was acquired at reactor power levels of 60%, 70%,

80%, 90% and 100%. Based on data reduction, jet pump and recirculation

! system performance was found to be acceptable. Recirculation System MG Set mechanical stop positions were verified to be adequate to maintain flows below 102.5% in the event of controller failure to maximum demand.

Power Distribution and Core Performance Comparison at Rated Power l

At 100% power and equilibrium conditions, the following parameters were i compared to the predicted values and found to be acceptable:

{ Relative Axial Power Shape Node Predicted Actual 1 0.60 0.56 4

2 1.25 1.17  !

! 3 1.34 1.30 i 4 1.32 1.29 5 1.33 1.25 6 1.27 1.25 7 1.17 1.13 1

8 1.11 1.07 '

9 1.01 1.02 10 0.85 0.93 1 11 0.67 0.72 i 12 0.20 0.31 i ,

Core Performance i

I Parameter Predicted Actual Notches in core 500 518 MLHGR 9.89 9.99 MAPLHCR 0.78 0.75 MCPR 1.70 1.59 1

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H ARTFORD. CONNECTICUT 06141-0270 L L J 7$[,37.,*,7,C , *" (203) 665-5000 March 14,1986 Docket No. 50-245 B12019 Dr. Thomas E. Murley Regional Administrator Region i U. S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406 Gentlemen:

Millstone Nuclear Power Station, Unit No. I Startup Physics Testing Program for Cycle 11 Pursuant to the Millstone Nuclear Power Station Unit No. 1 Technical Specifications, Section 6.9, enclosed please find a summary report of the Cycle 11 Startup Physics Test results. In keeping with established practice, this report has the same basic format and content as submitted for the last several fuel cycles.

Should you have any questions on the attached summary report, please feel free to contact us.

Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY IE Coe w J. F. Opeka '

Senior Vice President

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By: E. J./NJroczka (/

Vice PreMdent cc: C. I. Grimes i\

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