PLA-2771, Cycle 2 Startup Test Summary
| ML20213A357 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 01/28/1987 |
| From: | Boesch R, Forgie J, Keiser H PENNSYLVANIA POWER & LIGHT CO. |
| To: | Murley T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| PLA-2771, NUDOCS 8702030235 | |
| Download: ML20213A357 (14) | |
Text
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SUSQUEHANNA SES UNIT 2 CYCLE 2 STARIUP TEST S119IARY Prepared by:
R.R. Bocsch J.B. Fo le Approved By:
Approved By:
((/
Te6hhiEhl Section Supervisor j
8702030235 870128 8li PDR ADOCK 05000388 P
Susquehanna Unit 2 Cycle 2 Startup Test Sunmary Susquehanna Unit 2 resuned carnercial operation for Cycle 2 on October 28, 1986 following a refueling and maintenance outage. The S2C2 reload introduced 324 Exxon Nuclear Capany 9x9 fuel assemblies. Since the current reload includes a new fuel design, a cmprehensive startup testing program was performed. % e following startup tests are presented in the report:
1.0 Core Ioading Verification and Audit 2.0 Control Rod Operability and Subcritical Check 3.0 Subcritical Shutdown Margin Demonstration 4.0 In-Sequence Critical and Shutdown Margin Detemination 5.0 TIP Asynnetry Check In addition to the above tests, the startup program included a moderator tanperature coefficient determination, LPRM calibrations, core flow calibration, scram time testing, a neutron noise baseline data acquisition test, core stability data acquisition, and a baseline recirculation flow data acquisition test. Also, a pre-operational program was successfully ccanpleted which verified the operation of We Exxon Powerplex Core Monitoring Systen, which is now being used to monitor the Unit 2 core. The additional test results are available at the site upon request.
Susquehanna Unit 2 Cycle 2 Startup Test No. 1 Core Verification and Audit Purpose The purpose of this test is to visually verify that the core is loaded per the analyzed designs.
Criteria Upon empletion of core alterations during the refueling outage, the core must be verified to conform with the reference core design used in the various licensing analyses. The verifications to be performed include fuel bundle location, fuel bundle orientation, and proper seating of the fuel bundles within the core. The above verification will be performed by the Reactor Engineering Group utilizing an underwater television camera.
The verification will be videotaped so that an independent verification may be performed. Any discrepancies discovered in the loading will be prmptly corrected and the affected bundles shall be reverified prior to unit startup.
Results The Cycle 2 core verification consisted of tuo videotaped passes over the core. During the first pass, the fuel bundle serial numbers were audibly and visibly recorded on the video tape to verify proper location. The second pass was performed to verify proper fuel assmbly coating (assably height check) and proper orientation. One discrepancy was found (one bundle was misoriented) and was prmptly corrected and videotaped. The core verification tapes were then independently verified to be correct by the Reactor Engineering Supervisor and Quality Control on Sept mber 22 1986. Therefore, the as-loaded core configuration is consistent with the design Docon Nuclear used in the evaluation of Susquehanna Unit 2 Cycle 2 Reload Licensing analysis. The Cycle 2 Core Map is included in this report.
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9 11 13 15 17 19 21 23 25 27 29 SUSOTRANNA UNIT 2 CYCT 2 QRE M
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Susquehanna Unit 2 Cycle 2 Startup Test No. 2 Control Rod Functional (Insert and Withdrawl Checks)
M h purpose of this startup test is to assure proper control rod function, ensure that no gross local reactivity discrepancies exist, and demonstrate that criticality will not occur due to the withdrawal of a single rod.
Critaria Following core loading, a control rod tunctional taat, which includes mobility, overtravel and suberitically checks, will be parforned on each control rod.
Each control rod will be cycled individually to ensure mobility. As each rod is fully withdrawn, it will be checked for overtravel by mntinually applying a withdrawal signal. Suberiticality will also be verified with the rod withdra w.
assults A change was made in the above criteria prior to performing the control rod operability and suberitical checks in that the tests were perfortmx! as the core was loaded rather than after fuel load capletion. 'Ihis revision has been evaluated per 10CFR50.59 and found to be acceptable. No control rods overtravelled and suberiticality was maintained as each rtx1 was individually fully withdrawn and reinsertad.
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i
3 Susquehanna Unit 2 Cycle 2 Startup Test No. 3 Subcritical Shutdown Margin Desnonstration Purpose h purpose of this startup test is to assure at least the nuninun required shutdown margin exists with the strongest worth control rod fully withdrawn.
Criteria h mininun required shutdown margin at BOC for Susquehanna Unit 2 Cycle 2 is 0.3964 K/K. mis test will verify at least this amount by performance of a subcritical shutdcun margin demonstration. S e highest (strongest) wrth control rod is fully withdrawn, then diagonally adjacent rod (s) are slowly notcN d out verifying subcriticality at each step until the analytically determined reactivity worth of the control rod (s) at its (their) respective notch position (a) equals or slightly exceeds the required amount of SDN, Results the reactor remained suberitical with the highest worth control rod fully withdrawn and an additional diagonally adjacent rod pulled to a notch position with a calculated worth of 1.25% AK/K. % e required shutdown margin to be demonstrated was calculated to be.5952% AFJK. h is is 0.24%
AK/K plus a correcticn factor for the recirculation loop temperature (122 degrees F) at the time of the test. Using data supplied by Exxon, it was determined that the following rods pulled to the indicated position would demonstrate a shutdown martJ n of at least 1.045n 4K/K, after correction i
l I
for moderator tarperature.
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HOD POSITION TUTAL WOR 1H & aK/K l
~
50-15*
48 0.00 46-19 12 1.252 analytically determined strongest rod, Rods were pulled and suberiticality was verified after each notch.
i Suberiticality was also verified with the rods at the above indicated positions, thus satisfying the purpose of this startup test.
l
Susquehanna Unit 2 Cycle 2 Startup Test No. 4 In-Sequence Critical and SDM Detenrdnation Purpose The purpose of this startup test is to calculate the actual shutdown margin of the Cycle 2 core and to dmonstrate that no reactivity anmaly exists.
Criteria 1)
Shutdown Margin Technical specification 3.1.1 requires an adequate shutdown margin to ensure the reactor can be made suberitical from all operating conditions. This value,.38%aK/K has been determined to be the minim e required SDM to bring a reactor suberitical under the worst case conditions - a cold, xenon-free core at the most reactive point in the cycle with the highest worth control rod unavailable for reactivity control. At beginning of cycle, the required SIM value must be increased by a factor, R, if it is determined that core shutdown margin is less at another point in the cycle than the initial shutdown margin. The required beginning-of-cycle SDM for Susquehanna Unit 2 Cycle 2 is 0.39%aK/K; the actual SIM will be calculated fr a data obtained during the initial startup criticality.
2)
Reactivity Anmaly Core reactivity is monitored to prevent excessive reactivity additions due to unforeseen reactivity changes or reactivity anmalies. At BOC, a 1%AK/K difference between predicted and actual critical control rod positions might indicate improper core loading or a c mputer code that is unreliable. Data gathered during the in-sequence critical, cpecifically the Keff at notch position of the control rod at which criticality occurs is empared to predicted critical rod position Keff and a % reactivity difference is calculated.
Results The calculated SDM was 2.794%AK/K and the difference between actual Keff and predicted Keff at criticality was.065% #/K.
l Control rods were withdrawn in the A sequence until the reactor was on a stable, positive period. The notch position at which criticality occurred was rod 30-35, notch 04, step 67. A special log was initiated to record SRM count rates and recirculation loop tmperatures. The average period was 73.4 seconds and the average loop tmperature 134.8 degrees F which a
yield period and tmperature corrections of.743 x 10-3aK/K and 2.54 x 10-3 AK/K respectively.
1)
Shutdown Margin The equation used to calculate S m SDM = Kerit - KSHO op (period) - op (tsp)
Kcrit
- KSRO Kcrit is Keff at the actual critical control rod position (1.00395) and Ksro is Keff predicted with the strongest rod out (.97344).
The minimum required SDM for Unit 2 Cycle 2 at beginning of cycle is 0.39% ^K/K; the calculated shutdown margin based on this test is 2.794% AK/K, thus satisfying the acceptance criteria.
2)
Reactivity Ancmaly
'Ihe reactor went critical at step 67 with Kcrit of 1.00395. 'Ihe equation used to calculate reactivity difference was reactivity difference = Kcrit op (period) -a p (tmp)
Kcrit
'Ihc calculated reactivity difference was.065% AK/K.
'Ihis satisfies i 1% AK/K acceptance criteria.
Susquehanna Unit 2 Cycle 2 i
Startup Test No. 5 Tip Asymetry Purpose
'Ihe purpose of this test is to check core symetry by performing a statistical uncertainty analysis on the Traversing Incore Probe (TIP)
Systen. Also, by the performance of this test, the proper operation of the TIP systen will be assured.
Criteria 2
hX test of significance will be performed with the significance level fixed at 1%. h test will be performed utilizing an octant symetric rod pattern at a power level greater than 75% of rated power The startup test criteria for symetric TIP d4fference is that the X value calculated shallbelessthanthecriticalX'va}ue. Since Susquehanna has 19 spinetric TIP pairs, the calculated X value must be less than a, critical X~ value of 36.19 (as determined by Exxon). If the calculated X~ value exceeds.the critical value, the instrumentation and data processing-systan should be reviewed for any problems whichgy contribute to abnormal TIP asymetries. A second ptermination of X should then be made. If the new measured value of X exceeds the critical value, the fuel vendor shall be consulted and appropriate action taken to assure that a larger than anticipated TIP asymetry does not adversely affect the safe operation of the reactor.
Results A ocuplete set of TIP data was obtained at the ocupletion of Susquehanna Unit 2 BOC 2 Startup Testing Program at rated thermal power. The nodal TIP values (nodes 3 through 22) were stamed up for each symetric TIP pair using oquation 5.1 with the results sumagized in Table 5.2.
Using Equations 5.2 and 5.3, th9 variance and X~ were calculated to be 3.37 and 1.78 respectively. N X~ value of 1.78 is well within the 36.19 limit established by Exxon.
l 4
i
Table 5.1 Symnetric TIP Incation Symnetrical TIP Pairs TIP Pair No.
Upper left Lower Right 1
08-17 16-09 2
08-25 24-09 3
08-33 32-09 4
08-41 40-09 5
08-49 48-09 6
16-25 24-17 7
16-33 32-17 1
8 24-33 32-25 9
16-41 40-17 10 16-49 48-17 11 24-41 40-25 12 16-57 56-17 13 24-49 48-25 14 32-41 40-33 15 24-57 56-25 16 32-49 48-33 17 32-57 56-33 18 40-49 48-41 19 40-57 56-41 l
I L
Table 5.2 Absolute Relative Difference Symnetric TIP Pair Absolute Relative Difference ch 1
6.10 2
0.47 3
2.82 4
1.33 5
1.62 6
3.12 7
2.56 8
0.15 9
0.10 l
10 2.50 i
11 3.54 12 0.80 l
13 0.48 14 5.56 15 2.10 l
16-1.63 17 1.57 18 0.05 19 1.31 i
f l
l l
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9 Equation 5.1 g,100 (%1 - h2) h1 + h2.
I 2
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22 22 Notas %1 = f T(k) for TIP1 ami h2 = f T(k) for TIP2 K=3 K=3 where TIP1 ami TIP2 are synestric TIP pairs aquatica 5.2' (variance) 19 8 da l
3.37 S 78Pgj =
=
38 Equation 5.3 2
19 S TIPii = 1.78 X
=
36 w s-
,y
~
f~
V.
PP&L Pennsylvania Power & Light Company Two North Ninth Street
- Allentown, PA 18101
- 215 1 770'5151 Harold W. Keiser Vice President-Nuclear Operations 215/770-7502 JAN 281987 Dr. Thomas E. Murley Regional Administrator-Region 1 U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406 SUSQUEHANNA STEAM ELECTRIC STATION UNIT 2 STARTUP REPORT PLA-2771 FILE R41-2A Docket No. 50-388
Dear Dr. Murley:
Attached is a copy of the Susquehanna SES Unit 2 Startup Report for the Unit 2 Cycle 2 startup. This report is submitted in accordance with Technical Specifications Section 6.9.1.1 through 6.9.1.3.
The report addresses those startup tests described in our application for reload dated June 19, 1986 (PLA-2661).
Very truly yours, M
H. W. Keiser Vice President-Nuclear Operations Attachment cc: Document Control Desk w/ original Mr. M. C. Thadani - NRC Mr. L. R. Plisco - NRC IEu
'It