ML19254F727
| ML19254F727 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 11/08/1979 |
| From: | Furr B CAROLINA POWER & LIGHT CO. |
| To: | |
| References | |
| GD-79-2820, NUDOCS 7911160497 | |
| Download: ML19254F727 (3) | |
Text
,m g,s q t 'l s.L w re r
w'c, November 8, 1979 FILE: NG-3513 (B)
SERIAL: GD-79-2820 flr. James P. O'Reilly, Director U.S. Nuclear Regulatory Commission Region II 101 t!arietta Street, Suite 3100 Atlanta, GA 30103 IIRUNSWICK STEAtl ELECTRIC PLANT, UNIT NO. 2 LICENSE NO. DpH-62 DOCKET NO. 50-324 CYCLE 3 SUMt1ARY START-UP TEST REPORT
=
Dear Fir. O Reilly:
This report is submitted in accordance with Technical Specifications, Section 6.9, to provide the Start-up Test Report for Unit No. 2 Cycle 3 as appropriate for insertion of S x 8R iuel.
Due
- o a n' sinterpretation 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 of completion of start-up testing and represent s completion of start-up test reporting required by Tee hnical Specification 6.9.1.3.
The following physics testing was performed on Brunswick Unit No 2 during the beginning of cycle start-up and power ascension:
1.
Shutdown flargin Demonstration The beginning of cycle, co.4, xenon-1ree shutdown margin test was performed to demonstrate that the reactor remained shut down by the prescribed margin with the strongest rod fully withdrawn. With the strongest rod f ally withdrawn, a diagonally adjacent control rod was withdrawn to a calculated position corresponding to 181 +
R, and the reactor was observed to remain shut down (R = 0.0 for this cycle).
2.
React:vity Anomaly At 3 95% power and core flow, the predicted control rod dennity was compared to the actual cont rol rod density with the iollowing results:
~
134/
918 k
Y 7 911160 N 7
?!r. James P. O'Reilly I;ovember 8, 19/9 Cont rol Rod De ns_ity Required Control Rod Density ?!easured Predicted 1.5%
?!i n i anim Ma x i mtun 0.0 6.8%
The hot, full power reactivity measurement was found to be within th" required band (+1% reactivity) and as predicted.
3.
C r i t i ca 1 1;i;,enva l ue The cold, critical, xenon-free eigenvilue was measured on t ht initial start-up of Cycle 2.
The results are as f.,I l os s eti-.
fleasured K
% Deviation From Predicted Predicted K e f f-1.006 1.0091 31%
The cold, critical eigenvalne was found to b e' ( l o s e to the predicted value and within the acceptance criteria of + 1"/.
4.
l il' Uncert ainty Total TIP uncertainty was determined above and below 75%
power while at steady state.
Resul ta a re.is f ollow<
flaximum Allowed Uncertainty
!!easurul Uncertainty 9.004 4.85% at < 75%
5.317,at > 7 5*/,
The TIP uncertainty war determined to be welI below the rerpii red 1 imi t.
5.
Core Power Distribution anil Svmmetry a.
At medium and high power l eve l ;., bundle power comparisons were made between symmetr;c bundles with the following results:
Maximum Expected Bundle flaximau fleasured Bundle Power Asymmetry Powei Asymmetrv 15%
4.66%
b.
!!casured and predicted values of cere thermal limits (flCPR, MAPCilGR, LilGR) were compared at > 957, and the measered values were found to be within i 10% of the predicted values 1347 019
Ftr. James P 0'Heiliy aCVU
"'I o.
The core power distribution aint symmet ry test indicated a symmetric power distribution a :, well as clone agreement between predicted and measured values of core thermal limits.
As discus &d in our to Mr T. A.
Ippolito o; larch 16, 1979, on the subject of Physics Start-up Test Program, the following tests were satisf actorily concluded:
a.
Core !.oading \\'eri f ication - A core loading veri fication was perf ormed per BSEP Fuel llandling Procedure (Fil
'1,.
It was ver i fied that. the core was loaded as speci f ied by the design reference toading pattern.
This I s recently been reverified from video tapes.
h.
Core Power Svmmetry - See Response No. 4,TI_Pljncertainty, c.
Cont roI Rod Mobilitv - Control rod mobi1ity war verified prior to start-up by control rod functional / friction testink Each control rod was veri fied t o more full travel eithout hinding or excessive friction.
In addition, the reat tor w.i s observed to remain subcritical during the wit hdrawal of each cont rol rod.
d.
Heat tivity Testing - Refer to Item 1, Shutdown Margin, arni Item 3, Cri t ica l Ei genva lue Core physics testing performed during t he Uni t No. I beginning of Cycle 2 start-up and power ascension indicates t lja t the reactor is performicg sa f ety and as predicted.
Yours very t ruly,
, A,?
s
,y'- "}L' j
U. J. Furr
\\' i c e P re:; i den t - Nuclear Operationn MAJ/CSB/jnhc 1347 J20