ML19322A564
| ML19322A564 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 11/08/1979 |
| From: | Furr B CAROLINA POWER & LIGHT CO. |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| NUDOCS 7911150296 | |
| Download: ML19322A564 (3) | |
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November 8, 1979 h
FILE: NG-3513 (B)
SERIAL: GD-79-2820 (QN
?!r. James P. O'Reilly, Director DOCU
'{ i ig QD U.S. Nuclear Regulatory Ccnanission 3
Region II 101 !!arietta Street, Suite 3100 Atlanta, CA 30,03 BaCNSWICK STEA:! ELECTRIC PLE T, C:llT NO. 2 LICENSE NO. DPH-62 00CKET NO. 50-324 TiCLE 3 SU:!:!AR'i START-CP TEST REPORT
Dear ?!r. O'Peill:
This repo rt is
- mmitted in acc c rdance with Technical Specifications, Section 6.9, to provide the Start-up Test Report for Unit No. 2 Cycle 3 is appropriate for insertion of 3
- < 3R fuel. Due to a misinterpretation of the start-up test reporting requirements, this report is not submitted within 90 days of resumption of commercial operation; however, it is within 90 days cf completion ::
start-up testing and represents completion of start-ap test ruporting required by Te nnical Specification 6.9.1.3.
The folicwing physics testing was performed on Brunswick Unit No. 2 during the beginning of cycle start-up and power ascensica:
1.
Shutdown B!argin Demonstration The beginning of cycle, cold, :<e no n-f re e shutdown margin test was performed to demonstrate that the reactor crmained shut down by the prescribed margin with the strongest rod fully withdrawn. With the strongest rod fully withdcawn, a diagonally adjacent control rod was withdrawn to a calculated position cccresponding to. W',
+ R, and the reactor was observed to remain shut down (R = 0.0 for this cycle).
2.
Reactivity Anomaly At > 95% power and core flow, the predicted control rod density was compared to the actual control rod density with the following results:
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!11r.?J:me f P. O'R: illy Nov mber 8, 1979 I
Control Rod Density Required-Control Rod Density ?leasured Predicted 3.5%
. flinimum '
flaximum 0.0 6.8%
The :io+., full power reactivity measurement was found to be within the requi red band (+1'l, reactivity) and as predicte J.
~
3.
Cr;tical Eiuenvalue The cold,-critical, xenon-free eigenvalue was measured on the initial start-up of Cycle 2.
The results are as f c t l e. 3 :
Preficted K
- leasured K.
% Deviation From Predicted ct ett 1.-000 1.0091
. 31't The cold, critical eigenvalue was found to lo close to the
. predicted value and within the acceptance criteria of t I ?..
4.
T P Uncertainty l
Total TIP uncertainty was determined above and belos 75%
power while at steady state. Results are as follows:
- !aximum Allowed Uncertainty
- leasured Uncertainty 9.004 4.85% at < 75%
5.31% 2t > 75%
The. TIP uncerta t aty was determined to be well below the required limit.
L 5.
Core Power Distribution an i Symr
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-a.
At medium and high power levels, bundle power comparisons were made between symmetric bundles with the following results:
tiaximum Expected Bundle
!!aximum !!easuri_d Bundle Power Asymmetry Powet Asymmetry 15%
4.66%
.b.
!!easured and predicted values of core thermal limits (flCPR, flAPCHGR, LHGR) were compared at > 95%, and the l
measured values were-found to be within + 10% of the predicted values.
50 10 Mr. James P.'0'Retily 3v ber o, 2.
The core power distributior. and symmetry test indicated a symmetric power distribution as well as
.close agreement between predicted and measured values of core thermal limits.
As discuss d in our letter to !!r. T. A. Ippotito o f Bla rch 16, 1979, on the subject of Physics Start-up fest P ro g ram, the following tests were natis f actorily concluded:
a.
Core Loading Verification - A coce loading verification was performed per BSEP Fuel Handling Procedure (Fil-11). It was veri fied th at the core cas loaded as specif teif by LLe design reierence loading pattern.
This has recently been reverified f rom video tapes, b'.
Core l' owe r Svamet rv - See Response No. 4, TIP Uncertainty.
c.
Cont rol Rod !!obility - Control rod mobility was verified prior to start-up by control rod tunctional/ friction testing. Each control rod was verified to more full travel without binding c e:<cessive friction.
In additien, the reactor cas observed to remain subtritical du r.i s.g the withdraval of each control rod.
d.
Renetivity Testing - Refer to item I, Suutdown ?!arnin, and Item 3, Critical Eigenvalue.
Core physics testing performed during the Uni t No. I beginning of Cycle 2 start-up and power ascension indicates that the reactor is performing safety and as predicted.
Yours very truly, A
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{ # 1'b B. J. Furr Vice Presi, lent - Nuclear Operations MAJ/CSB/jnh*
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