ML14184A114

Forwards Cycle 7 Startup Physics Test Results.

ML14184A114
Person / Time
Site:	Robinson
Issue date:	10/26/1979
From:	Furr B Carolina Power & Light Co
To:	O'Reilly J NRC Office of Inspection & Enforcement (IE Region II)
Shared Package
ML14184A115	List: ML14184A114 ML19254E240
References
GD-79-2678, NUDOCS 7910310355
Download: ML14184A114 (5)

Text

,2 G LA0 , FORMATION DISTRIBUTION SYSTEM (RIDS)

ACCESSION N8R:7910300292 DOCDATE: 79/10/26 NOTARIZED: NO DOCKET #

FACIL:50261 H. B, Robinson Plant, Unit 2, Carolna Power and Ligh 05000261 AUTH.NAME AUTHOR AFFILIATION FURR,8,J. Carolina Power & Light Co, RECIP.NAME RECIPIENT AFFILIATION O'REILLYJP, Region 2, Atlanta, Office of the Director

SUBJECT:

Forwards Cycle 7 Startup physics test rept.

DISTRIBUTION CODE: A0278 COPIES RECEIVED:LTR ENCL j SIZE:_

TITLE: Reactor Startup Test Report, NOTES:-----------------------------------

RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL ACTION: 05 BCO&8 # 2 2 LA 0Z84 1 1 0 INTERNAL: 0 FILE 1 1 02 NRC PDR I I 0 2 2 09 MPA 1 1 10 TECH AST EDO 1 1 11 PLANT SYS BR 1 1 12 EEB 1 1 13 REAC SFTY BR 2 2 15 CORE PERF BR 1 1 16 QAB 1 1 EXTERNAL: 03 LPDR 1 1 04 NSIC 1 1 17 ACRS 1 1 TOTAL NUMBER OF COPIES REQUIRED: LTTR 18 ENCL 17

Carolina Power & Light Company October 26, 1979 FILE: NG-3513 (R) SERIAL: GD-79-2678 Mr. James P. O'Reilly, Director U.S. Nuclear Regulatory Commission Region II 101 Marietta Street, Suite 3100 Atlanta, GA 30303 H. B. ROBINSON STEAM ELECTRIC PLANT, UNIT NO. 2 DOCKET NO. 50-261 LICENSE NO. DPR-23 START-UP PHYSICS TEST REPORT

Dear Mr. O'Reilly:

In accordance with Section 6.9.1.a of the Technical Specifications for the H. B. Robinson Steam Electric Plant, Unit No. 2, the attached Cycle 7 Start-up Physics Test Report is submitted. This report fulfills the requirement for a summary report within ninety (90) days of the completion of the start-up test program following reactor power uprating.

The H. B. Robinson Unit No. 2 reactor power level was uprated from 2200 MWt to 2300 MWt during the Cycle 7 refueling outage. As outlined in our letter from Mr. E. E. Utley to Mr. A. Schwencer on March 17, 1978, additional core power distribution measurements were taken at 95.7% power (2200 MWt) and 100% power (2300 MWt). Also, NSSS parameters were closely monitored to ensure temperatures and pressures followed their expected trends during the last 100 MWt escalations in power, which they did.

You s very truly, B. J. Furr Vice President - Generation GD/CSB/jnh*

Attachment

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Enclosure To Serial: GDAA 2678 CAROLINA POWER & LIGHT COMPANY H. B. ROBINSON UNIT NO..2 CYCLE 7 STARTUP PHYSICS TEST RESULTS Cycle 7 Initial Criticality: July 16, 1979.

Startup Physics Test Completion Date: July 30, 1979.

I. All Rods Out Critical Boron Concentration Measurements:

A. Acceptance Criteria: Prediction and measurement shall agree within + 50 PPM.

B. Results: Prediction: 1216 PPM Measurement: 1227 PPM Difference: 11 PPM II. Control Rod Worth Measurements:

A. Acceptance Criteria:

1. Control Bank "C" integral reactivity worth prediction and measurement shall agree within + 15%.

2. Control Bank "D" integral reactivity worth prediction and measurement shall agree within + 15%.

3. Control Banks "C" & "D" combined integral reactivity worth prediction and measurement shall agree within + 10%.

B. Results:

Bank Prediction Measurement  % Difference C 745 723 -3.0 D 1279 1270 .7 D&C 2024 1993 -1.5 pb Enclosure to Serial:- GD-79-2673 III. Moderator Temperature Coefficient Measurements:

A. Acceptance Criteria:

Sufficient data shall be collected to implement administrative controls to ensure that the moderator temperature coefficient during power escalation is non-positive.

B. Results:

Moderator Temperature Bank "D" Position Bank "C" Position Boron Concentration Coefficient (PCM/OF) 211 228 1215 PPM +2.82 0 209 1165 PPM .+0.26 42 (Overlap) 170 1145 PPM -0.01 0 120 1119 PPM -1.16 Administrative controls were implemented to ensure a non-positive moderator temperature coefficient during power escalation.

These controls were based on the control rod positions and boron con centrations which were observed during the moderator temperature coefficient measurements.

IV. Power Distribution Measurements:

Flux maps were taken at approximately 0, 30, 70, 90, 95.7, and 100% power.

A. Acceptance Criteria:

1. Hot zero power map:

a. Assembly wise FAH <(1.08 X predicted) if (FAH predicted) > 1.0.

b. Assembly wise FAH < (1.15 X predicted) if (FAH predicted) < 1.0.

c. Quadrant tilts < 1.02.

pb Enclosure to Serial: GD-79-2678.

IV. Continued

2. Power maps:

a. FQ(Z) < 2.2/P P = Fraction of full power P 50%

4.4 P 507%

b. FKH < L.55 (1 + .211-P))

1.04

c. Quadrant tilts < 1.02 B. Results:

1. Hot zero power map:

All assemblies satisfied the FAH acceptance criteria. The most limiting comparisons were:

a. For FAH predicted > 1.0, quarter core location G-8.

Prediction = 1.071 1.08 X Prediction = 1.157 Measurement = 1.151

b. For FAR predicted < 1.0 quarter core location G-9.

Prediction = .943 1.15 X Prediction = 1.084 Measurement = 1.022 The HZP quadran.t tilts satisfied the acceptance criteria.

The largest quadrant .tilt measured was 1.004 (.4%) in the Northeast quadrant.

2. Power maps.

All maps satisfied each acceptance criteria. The following is a summary of the results:

% Power Fg Limit FQ(Z) 1.55 (1 + .2(1-P)) FAH Maximum Quadrant Tilt 1.04 31 4.400 2.124+ 1.696 1.425 1.000 ( <.1%)

69 3.188 2.390 1.583 1.390 1.009 (.9%)

90 2.444 1.974 1.520 1.393 1.008 (.8%)

95 2.316 1.974 1.505 1.401 1.008 (.8%)

100 2.200 1.880 1.490 1.399 1.005 (.5%)

pb