ML19249D887
| ML19249D887 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 09/30/1979 |
| From: | NORTHEAST UTILITIES |
| To: | |
| Shared Package | |
| ML19249D883 | List: |
| References | |
| NUDOCS 7909250508 | |
| Download: ML19249D887 (5) | |
Text
DOCKET No. 50-245 MILLSTONE NUCLEAR POWER STATION, UNIT NO.1
SUMMARY
REPORT STARTUP PHYSICS TESTING PROGRAM FOR CYCLE 7 9
1018 110 7909250CoE SEPTEMBER, 1979
SUMMARY
REPORT Cycle 7 Physics Startup Testing Millstone Unit 1 1.
Cola Control Rod Drive Testing At the completion af the fuel shuffle and the reactor core verifica-tion, each control rod was friction and function tested and timed with a stopwatch.
No abnormalities were noted.
2.
Hot Control Rod Drive and Scram Time Test After the reactor achieved hot operating conditions, each control rod was scrammed and timed using the Brush recorder.
The following results were obtained:
Table 1
% Scram Insertion Tech. Spec. Time (sec.)
Actual Time (sec.)
5 0.375
~
0.317 20 0.900 0.694 50 2.00 1.408 90 3.50 2.528 The average scram insertion time for 5%, 20%, 50%, and 90% for the three fastest control rods in a two-by-two array were also compared to the. technical specification limits.
Initially, all but one two-by-two array. were within the technical specification limits for all insertion times.
The two-by-two array which failed the 5%
insertion time was retested when control rod was rescrammed, which resulted in satisfactory times for the three fastest control rods in a two-by-two array for all insertion times.
i All control rods scrammed to 90% insertion in less than 7.00 seconds and are considered operable.
3.
Shutdown Margin Test The Shutdown Margin Test was performed using the In-Sequence Critical Data Method. The results indicated that the reactor core had a shutdown margin at BOC 7 of 1.79% AK/K with the strongest rod withdrawn.
The technical specification limit is 0.47% AK/K.
4.
Non-Voided Critical Eigenvalue Comparison for a Fixed-Control Rod Pattern The expected critical control rod pattern was compared to the actual control rod pattern.
The actual control rod pattern required to bring the reactor critical required 44 additional notches be withdrawn from the core as compared to the predicted critical control rod pattern. These additional notches are not considered an abnormality.
5.
Power Distribution Comparison at a Given Control Rod Pattern and Power Level at 100% Rated Power At 100% power, the following parameters were compared to the predicted values:
Relative Axial Power Shape As found Predicted node 1
0.59 0.36 2
1.01 0.64 3
1.17 0.85 0 l ljf
4 1.21 1.14 5
1.20 1.18 6
1.20 1.20 7
1.14 1.21 8
1.14 1.20 9
1.09 1.19 10 1.02 1.15 11 0.82 0.96 12 0.40 0.55 Notches in the Core 682 550 Maximum Linear Heat 9.49 9.36 Generation Rate, KW/FT Maximum Average Planar 0.792 0.78 Linear Heat Generation Rate Ratio Minimum Critical Power 1.5661 1.59 Ratio The actual number of notches in the core was well within the +1% a K anomaly curve.
6.
TIP Reproducibility and TIP Symmetry Test at 100% Rated Power The TIP uncertainty test was performed at 100% power when xenon had stabilized. The results indicated the following uncertainties:
Total TIP Uncertainty - 3.95%
TIP Random Noise Uncertainty - 1.48%
TIP Geometric Uncertainty - 4.22%
Symmetric pairs of LPRM's were observed for symetry.
No abnormal conditions exist in the reactor core with the present 100% power control rod pattern.
7.
Reactor Core Verification At the completion of the fuel shuffle, the reactor core was verified.
The verification was recorded on video tape and Core 7 was recon-structed by QC by viewing these recordings.
Throughout the verifica-tion, no loading errors were found.
1018 114