View source for PLA-2771, Cycle 2 Startup Test Summary

{{Adams
| number = ML20213A357
| issue date = 01/28/1987
| title = Cycle 2 Startup Test Summary
| author name = Boesch R, Forgie J, Keiser H
| author affiliation = PENNSYLVANIA POWER &amp; LIGHT CO.
| addressee name = Murley T
| addressee affiliation = NRC OFFICE OF INSPECTION &amp; ENFORCEMENT (IE REGION I)
| docket = 05000388
| license number = 
| contact person = 
| document report number = PLA-2771, NUDOCS 8702030235
| document type = TECHNICAL SPECIFICATIONS &amp; TEST REPORTS, TEST REPORT
| page count = 14
}}

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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
PDR

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.

LJW412 LJW530 LJW518 LJW554 LJW385 LJW519 LJW529 60 LJW461 LJW513 X21001 LJW754 X21002 LJW725 X21003 LJW569 58 LJWO99 LJW512 LJW348 X21007 LJW762 X21008 LJW585 X21009 LJW763 X21010 56 LJW505 LJW733 X21015 LJW741 X21016 LJW675 X21017 LJW601 121018 LJW481 54 LJW492 LJW338 X21023 LJW705 X21024 LJW479 X21025 LJW704 X21026 LJW691 X210 LJW147 LJW542 LJW503 X21033 LJW746 X21034 LJW617 X21035 LJW643 X21036 LJW659 52 LJW451 LJW747 X21043 LJW739 X21044 LJW600 X21045 LJW677 X21046 LJW598 X2104 50 LJW413 LJW349 X21055 LJW584 X21056 LJW692 X21057 LJW358 X21058 LJW630 X21059 48 LJW450 LJW493 X21067 LJW732 X21068 LJW631 X21069 LJW359 X21070 LJW388 X21071 L 46 LJW384 X21081 LJW716 X21082 LJW555 X21083 LJW633 X21084 LJW632 X21085 LJW363 44 LJW462 LJW724 X21095 LJW615 X21096 LJW647 X21097 LJW648 X21098 LJW660 X21099 42 LJW504 X21109 LJW706 X21110 LJW583 X21111 LJW690 X21112 LJW434 X21113 LJW392 40 LJW541 LJW755 X21123 LJW693 X21124 LJW661 X21125 LJW676 X".ll26 LJW373 X21127 L 38 LJW528 X21137 LJW717 X21138 LJW599 X21139 LJW644 X21140 LJW491 X21141 LJW428 36 LJW478 LJW570 X21151 LJW557 X21152 LJW556 X21153 LJW460 X21154 LJW435 X21155 34 LJW552 LJW565 X21163 LJW475 X21164 LJW474 X21165 LJW459 X21166 LJW427 X21167 32 LJW502 X21175 LJW760 X21176 LJW689 X21177 LJW642 X21178 LJW539 X21179 LJW43 30 LJW488 LJW722 X21189 LJW595 X21190 LJW627 X21191 LJW610 X21192 LJW361 X2119 28 LJW525 X21203 LJW581 X21204 LJW703 X21205 LJW596 X21206 LJW426 X21207 LJW366 26 LJW458 LJW753 X21217 LJW673 X21218 LJW641 X21219 LJW638 X21220 LJW626 X2122 24 LJW378 X21231 LJW761 X21232 LJW477 X21233 LJW655 X21234 LJW654 X21235 LJW343 22 LJW410 LJW538 X21245 LJW745 X21246 LJW657 X21247 LJW346 X21248 LJW370 X2124 20 LJW449 LJW337 X21259 LJW701 X21260 LJW594 X21261 LJW347 X21262 LJW656 X212 18 LJW411 LJW730 X21271 LJW738 X21272 LJW686 X21273 LJW611 X21274 LJW688 X2 16 LJW135 LJW489 LJW527 X21283 LJW731 X21284 LJW671 X21285 LJW645 X21286 LJW 14 LJW537 LJW335 X21293 LJW580 X21294 LJW553 X21295 LJW582 X212% LJW597 X 12 10 LJW526 LJW744 X21303 LJW736 X21304 LJW613 X21305 LJW687 X21306 LJW55 8
LJWO94 LJW516 LJW336 X21311 LJW715 X21312 LJW702 X21313 LJW714 X21 6
LJW457 LJW517 X21319 LJW723 X21320 LJW752 X21321 LJW566 4
LJW448 LJW501 LJW510 LJW476 LJW379 LJW511 LJW500 2
1 3
5 7
9 11 13 15 17 19 21 23 25 27 29 SUSOTRANNA UNIT 2 CYCT 2 QRE M

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14 1,
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6 LJW563 X21322 LJW721 X21323 LJW750 X21324 LJW509 LJW455 4
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31 33 35 37 39 41 43 45 47 49 51 53 55 57 59 SUSQUDUWNA LWrr 2 CYN 2 m m s

,~
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.
l I
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.
l l
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
l l

9 Equation 5.1 g,100 (%1 - h2) h1 + h2.
I 2
~
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
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