ML20064B211
| ML20064B211 | |
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|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 11/09/1989 |
| From: | GENERAL ATOMICS (FORMERLY GA TECHNOLOGIES, INC./GENER |
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| 910049, NUDOCS 9010150245 | |
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Text
Attachment to P-90301 GENERAL ATOMICS October 2,1990 3.......,
ISSUE
SUMMARY
TITLE FSV Cycle 4 RT-500L Test Report gv& 0 APPROVAL LEVEL 2
g O DESIGN DISCIPLINE SYSTEM 000. TYPE PROJECT DOCUMENT NO.
ISSUE NO./LTR.
N 18 RTE 1900 910049 N/C QUALITY ASSURANCE LEVEL SAFETY CLASSIFICATION SEISMIC CATEGORY ELECTRICAL CLAS$lFICATION p'
QAL-1 FSV-I FSV-I N/A APPROVAL PREPARED ISSUE
}SSUE DATE u
FUNDING APPLICABLE DESCRIPTION /
BY ENGINEERING 7
PROJECT PROJECT CWBS NO.
'N/C gyy i s 339 S. Munoz D. Alberst ei -
D. Alberstein Initial Release
$. A WO 1920116 g_
i CONTINUE ON GA FORM 14851 NEXT INDENTURED DOCUMENTS
- See List of Effective Pages N-6759 9010150245 901002 PDR ADOCK 05000267 P
j ppt; GA PROPRIETARY INFORMATION THIS 00CUMENT IS THE PROPERTY OF GENERAL ATOMICS. ANY TRANSMITTAL OF THIS DOCUMENT OUTSIDE GA WILL BE IN CONFl0ENCE. EXCEPT WITH THE WRITTEN CONSENT OF GA, (1) THIS DOCUMENT MAY NOT BE COPIED IN WHOLE OR IN PART AND WILL BE RETURNED UPON REQUEST OR WHEN NO LONGER NEEDED BY RECIPIENT AND (2) INFORMATION CONTAINED HEREIN MAY NOT BE COMMUNICATED TO OTHERS AND MAY BE USED BY RECIPIENT ONLY FOR THE PURPOSE FOR WHICH IT WAS TRANSMITTED.
[ NO GA PROPRIETARYINFORMATION PAGE 0F y
l 910049 N/C LIST OF ETTECTIVE PAGES
,Page Number Pete Count Revision Issue Sununary 1
N/C i through 111 3
N/C 1-1 through 1-3 3
N/C 2-1 through 2-2 2
N/C 3-1 through 3-25 25 N/C 4-1 through 4-22 22 N/C 5-1 through 5-2 2
N/C 6-1 1
N/C 7-1 1
N/C A-1 through A-23
,2,3, N/C Total Pages 83 i
910049 N/C i
CONTENTS 1.
INTRODUCTION.........................
1-1 2.
SUMMARY
AND CONCLUSIONS 2-1 3.
TESTING 3-1 3.1.
Objectives.
3-l' 3.2.
Test Plan 3-1 3.3.
Test Limits 3-4 3.4.
Deviations from Test Plan and Procedures.
3-7 3.5.
July 1987 Testing 3-9 3.6.
March 1988 Testing.
3-11 1
3.7.
August 1989 Testing 3 l l l 4.
TEST DATA 4-1 j
4.1.
Instrumentation and Data Recording...........
4 4.2.. Data Packages 4-2 4.3.
Results of July 1987 Testing i
4-3 l
4.4.
Results of March 1988 Testing 4-3 4.5.
Results of August 1988 Testing.
4-4 1
4.6.
Shim Motor Tamperatures 4-15 4.7.
Conclusions 4-15 5.
SAFETY CONSIDERATIONS 5-1 5.1.
Introduction.
5-1 5.2.
Conclusions 5-1 6.
LONG-TERM' OPERATION 6-1 6.1.
Review of Previous Conclusions.
l6-1 6.2.
Termination of Operations 1-7.
REFERENCES.
'7-1 APPENDIX A.
A-1 11 t
910049 N/C
-FIGURES 3-1.
RT-500L test strategy 3-2 3-2.
Cycle 4 RT-500L testing 3-16 4-1.
March 12, 1988 60 - 66% power rise region outlet temperature changes 4-5 4-2.
August 2, 1989 66 - 66% power rise region outlet temperature changes 4-6 4-3.
August 2, 1989 66 - 69% power rise core power and flow.
4-7 4-4.
August 2, 1989 66 - 69% power rise reactor parameters 4-8 4-5.
August,2, 1989 66 - 69% power rise core pressure drop and resistance.
4-9 4-6.
August 2, 1989 66 - 69% power rise module B-2-6 helium temperatures.
4-10 1
4-7.
August 2, 1989 66 - 69% power -ise linear power Channels III, IV, V deviations.
4-11 4-8.
August 2, 1989 66 - 69% power rise linear power Channels VI, VII,_VIII deviations 4-12 4-9. August 2, 1989 66 - 69% power rise string E2 gap temperatures 4-13 4-10. Gap thermocouple locations.
................. 4-14 4-11. August 2, 1989 69 - 72% power rise core power and flow 4-16 4-12. August 2, 1989 69 - 72% power rise reactor parameters 4-17 4-13. August 2, 1989 69 - 72% power rise core pressure drop and resistance.
4-18 4-14. August 2, 1989 69 - 72% power rise Module B-2-6 helium temperatures.
4-19 4-15. August 2, 1989 69 - 72% power rise string E2 gap temperatures.
4-20 4-16. Region 12 shim motor temperatures 4-21 TABLES 3-1.
July 1987 RT-500L testing.
3-17 3-2.
March 1988 RT-500L testing.
3-21 3-3.
August 1989 RT-500L testing 3-24 111
t 910049 N/C i
l 1.
INTRODUCTION During the initial rise-to-power program of the Fort St. Vrain (FSV) reactor in October 1977, while approaching 60% power, temperature fluctuations were observed in the primary coolant circuit at the outlets of individual core regions and the inlets to steam generator modules.
'A comprehensive program of investigation into the nature and cause of the temperature fluctuations was initiated immediately.
The fluctuation investigations led to the design and fabrication of region constraint devices (RCDs) as a solution to the problem. _These mechanical links l
were installed on the top of the core in November 1979.
They were installed at locations where three regions intersect and are designed to provide interregion linking to stabilize the gaps between regions at the top of the core to near nominal values.
Steady-state testing performed during initial operation following installation of the RCDs verified that the overall core performance was unaffected by the presence of the RCDs. Testing to evaluate the success of RCDs as a solution to the temperature fluctuations was first performed in November and December of 1980.
These tests confirmed that j
the RCDs were successful at preventing fluctuations up to 701 power and a core pressure drop of 4.2 paid.
However, once in November and again in December, at a transient peak core pressure drop of 3.8 psid, follow-ing an increase in reactor power, a region outlet temperature redistri-bution was observed. These redistributions resulted in several bound-ary region outlet temperatures, particularly in the NW section of the core, decreasing while inner core region outlet temperatures generally increased somewhat more than would be expected from the power increase.
In March 1981, Nuclear Regulatory Commission (NRC) approved testing of FSV above 70% power.
Testing to confirm the success of the RCDs as a 1-1
_.=
910049 N/C L
solution to the temperature fluctuations and to investigate the region outlet temperature redistribution above 70% power was conducted in Cycle 2 during March, April, and May of 1981, and in Cycle 3 during October and November of 1981.
Again, no fluctuations occurred, but redistributions similar to those experienced in November and December of 1980 were observed.
On November 6, 1981 100% power was reached.
Following three days at 100% power, the reactor was shutdown for scheduled plant modifica-
-tions.
Based on the success of the Cycles 2 and 3 testing, the NRC authorized full-power operation of FSV in October 1982.
During 1986 and 1987 a substantive review was conducted by the NRC of the design basis accident analysis presented in.the Final Safety Analysis Report (FSAR).
Some of this analysis was reevaluated by General Atomics (GA).
It was determined that the backup safety-related feed water pumps (fire water pumps) would have insufficient head to pre-vent boiling and consequent steam binding in the steam generators during the shutdown cooling sequence for highly improbable accidents in which all other sources of feed water are lost.
Therefore, the NRC placed a limit on FSV operation at 82% power in July 1987.
Testing was performed for Cycle 4 during July 1987, March 1988, and August 1989 to verify that the RCDs will prevent fluctuations over the 1
range of core pressure drop expected for Cycle 4 and that the character-istics of the region outlet temperature redistributions are bounded by those observed during previous testing.
No fluctuations or redistribu-tions were observed during any of the Cycle 4 testing.
On August 18, 1989, FSV was shutdown to replace a control rod which had become stuck during a routine surveillance test on the previous day.
The stuck control rod and the subsequent discovery of cracks in the steam generator ring headers led to the decision on August 29, 1989 to j
not restart FSV.
1-2 j
i
D 910049 N/C-
)
i This report gives the results from Cycle 4 testing and compares j
these results with those from previous cycles.
The previously reported safety analyses which were based on Cycle 2 and 3 testing are reviewed
'I with' regard to Cycle 4 test results. While there will be no future operation of FSV, the previously reported evaluation of long-term
~
operation is also reviewed.
e i
1-3
910049 N/C i
'I 1
l 2.
StAttARY AND CONCLUSIONS l
Testing in which attempts were made to induce fluctuations, after installation of region constraint devices, was conducted during Cycle-2 i
in November and December of 1980 and in March, April, and May of 1981.
During Cycle 3, testing was conducted in October and November of 1981.
During Cycle 4, testing was conducted during July 1987, March 1988, and August 1989.
Reactor power levels from 40% to 100% of rated thermal power were surveyed with a maximum steady-state core pressure drop of 5.0 paid reached during cycle 3.
With the FSV reactor limited to 82% of-rated thermal power, Cycle 4 testing covered operation from 60% to 80%
power with a maximum core pressure drop of 4.73 paid.
No fluctuations have been observed, even in operating regimes where fluctuations occurred prior to installation of the region constraint' devices.
Unlike Cycle 2 and Cycle 3 testing, no region outle't tempera-ture redistributions were observed during Cycle 4 testing.
In Cycles 2 and 3 redistributions were generally observed at core pressure drops
'between ~3.5 psid and ~4.0 psid.
They resulted in several boundary region outlet temperatures, particularly in the NW sector of the core, decreasing while inner core region outlet temperatures generally increased somewhat more than would be expected from the power change.
While they were not observed during Cycle 4 testing, it cannot be concluded that region outlet temperature redistributions.could not have occurred under different operating conditions.
The region outlet temperature redistributions observed in previous cycles were the result of small incore displacements.
These displace-ments were similar in nature to the initial motion which' occurred dur-ing fluctuations. However, these displacements did not display cyclic behavior.
These small (on the order of 0.10 in. or less) displacements 2-1
910049 N/C
+
(
a i
caused changes in gap distribution,' changes in crossflow, and (for the j
seven NW boundary regions, Regions 20 and 32 through 37) changes in the amount of cool transverse helium flow (Type II flow) along the sleeve (s) surrounding the region outlet temperature thermocouples.
These observa-tions were consistent with a general (although asymmetric) tightening of the inner regions of the core, wherein the gaps'around the outer regions generally were increased and gaps between inner regions were generally.
decreased.
Previous evaluations of the region outlet temperature redistribu-tions indicated that these events involve no unreviewed safety ques-tions. A method for operating the reactor which accounts for region outlet temperature measurement discrepancies both before and after a redistribution has been developed'and implemented.
Under this operating method, the seven NW boundary regions, which are susceptible to outlet-temperature measurement errors, are operated by comparison regions in a manner similar to that which was employed in test procedure RT-500K.
In support of this operating method, appropriate revisions to the Technical Specifications were submitted to the NRC for review and approved.
i l:
1:
Testing during Cycle 4 has demonstrated that the reactor core L
behavior up to the maximum expected core pressure drop for Cycle 4 is within the bounds of that observed during previous cycles. Conse-L quently, the results of previous testing and analyses, and the conclu-l sion that the core can be operated in a stable manner at its licensed l
power remain valid.
2-2
-l 910049 N/C I
a; il 1
3.
TESTING 3.1.
OBJECTIVES Testing during Cycle 4 was conducted per the procedures of RT-500L, which was released as part of PSC test T-359 (Ref. 1).
A copy of this=
procedure is included as Appendix A of this report.
The main objectives of this test were (1) to confirm that the RCDs had eliminated fluctuations for operation up to the maximum expected pressure drop for
=
Cycle 4, and (2) to obtain data and operating experience during and
[
following the region outlet temperature redistributions to verify that the characteristics are within the bounds of those seen during Cycle 2' and 3 testing.
3.2.
TEST PLAN p
During this test, attempts were made to initiate fluctuations, thereby demonstrating the effectiveness of RCDs at preventing fluctua-tions.
The attempts to initiate fluctuations consisted of stepwise l
reactor power increases of approximately 3% at about 3% per minute.
Such stepwise power increases were an effective means for initiating i
L fluctuations in the absence of RCDs.
Further, the character of region outlet temperature redistributions initiated in this manner is well known as a result of similar-testing during Cycles 2 and 3 (Refs. 2, 3).-
Thus, comparisons of redistributions experienced during Cycle 4 testing with those of Cycles 2 and 3, would be most meaningful.
t.
The initial recommended strategy for RT-500L is shown schematically-in Fig. 3-1.
Since testing should start below the previously determined core pressure drop threshold of redistributions (i.e., approximately 3.2 psid), testing was planned to commence at a core pressure drop of about 2.5 psid with the core orifice positions in a normal configura-tion, i.e., with the most open orifice position corresponding to about i
3-1
~
>ns-
?
Figure:3-1
~
RT-500L Test Strategy 7
f Core Resistance l
Maxinium hessbre Drop :
End Test '
O R = 50
- - " "-"- ~ " " " " p""" : -- " - - - " " - " " " " - ~ ~ " "- - %: - ~
Ex ected During Cycle 4-6-
- - A R = 69 j
i i
j 73 Maxinh. um Presd.ure Drop i i
f:
o Tested to During Cycle 3 :
- - - -- + - - - - - - - - - -- - -- -
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40 45 50 55 60 65 70
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u 910049 N/C-j t-90% region flow.
For Cycle 4 this was projected to correspond to a core flow resistance of approximately 50 and a reactor thermal power level of approximately 50% to 60%.
The following describes the initial test plan shown in Fig. 3-1.
Deviations from this plan are described in Section j
3.4.
I At the beginning of this test, the plant should be in a normal-operating configuration with a core pressure drop of about 2.5 psid and I
in thermal equilibrium with equilibrium xenon.
The reactor power level is then to be increased in steps of approximately 3% at about 3% per minute until fluctuations are encountered, a test limit is reached, or 82% thermal power is reached. After each approximately 3% increase in thermal power, data should be recorded for approximately 1 h prior to the next increase.
When 82% thermal power is reached the first time during this test, the core pressure drop will not be the maximum which will occur during'
{
Cycle 4, because the region peaking factors (RPFs) are not as large as they will be later in the cycle.
Thus the next step is to reduce power (and flow) so as to reduce the core pressure drop to about 2.0 paid.
The power reduction should be done in a stepwise fashion (steps of approximately 5% to 10% thermal power) to allow recording data during the relaxation of the redistribution (s) that occurred during the power ascension to 82%.
At a core pressure drop of about 2.0 paid, the core should be reorificed to a higher core flow resistance.
Based upon the operating data from the first power ascension to 82%, it will be possible to determine the core flow resistance required to yield a core pressure j
drop of 6.0 psid at 82% thermal power operating conditions. Assuming l
the core is orificed for equal outlet temperatures, a power to flow ratio of 0.92, and core inlet temperature and pressure the same as during RT-500K, the required resistance is about 69.
The projected 3-3 1
910049 N/C maximum core pressure drop during Cycle 4 with this operating config-uration is approximately 6 psid; thus, that is the target value for 82%
power operation at the end of this test.
When the core is reorificed to achieve the core flow resistance that will lead to core pressure drop of approximately 6.0 psid at 82%
power, the core pressure drop should not exceed approximately 2.5 psid.
This is, again, because the testing should start at a core pressure drop below the threshold of redistributions (see Fig. 3-1).
There is a second reason for the second series of stepwise power increase of approximately 3% at 3% per minute.
It is important to demonstrate repeatability of redistributions during this cycles hence the testing along the second core flow resistance line.
(Also, it'is important to test under normal operating conditions, i.e.,
the first core-resistance line.
The operating data obtained from testing along this first core flow resistance line will enable the test team to deter-mine what core flow resistance will yield a core pressure drop of 6 paid at 82% power and, therefore, how much to reorifice.)
i L
l 3.3.
TEST LIMITS In addition to the normal plant operating procedures and technical
. specifications, the following guidelines were observed during perfor-mance of RT-500L:
1.
The MS temperature imbalance between any steam generator module and the average for the loop should not exceed *35'F in steady-state.
In addition, the maximum individual module MS steady-state temperature should be limited to 1020'F.
p l
2.
The HRH temperature imbalance between any steam generator module and the average for the loop should not exceed the i
l 3-4
h 910049 N/C range specified in Fig. A of Appendix A during steady-state operation.
3.
The helium inlet temperature imbalance between any steam generator module and the average of the 12 modules should not
.I exceed the range specified in Fig. B of Appendix A during steady-state operation.
4.
The helium purification system will'be in service during all testing.
5.
CRD shim motor temperatures should not exceed 245'F prior to any power increase.
This is to provide margin on the 250'F-limit.
The following test limits apply to reactor operation in a nonflue-tuation mode.- Appendix ~A gives additional limits to those below for operation during a fluctuation. The plant was defined to be in a flue-tuation operating mode when individual nuclear channels exhibit cyclic deviations from the average power equal to or greater than 0.5% peak-to-peak of full power not exceeding a 30-min period:
1.
Testing will be conducted within the letter and intent of both the technical specifications and the interim technical specifications.
[
2.
A unidirectional module main steam temperature change of 60*F (excluding the average component of intentional steam tempera-ture changes) is cause to take-immediate corrective action by reducing power.
3.
A steady-state individual module main steam temperature exceeding 1025'F but less than 1050'F is cause to take cor-
~
l rective action within 12 h to reduce this temperature.
i 3-5
910049 N/C 4.
An individual module main steam temperature of 1050'T is cause
-to take corrective action within 1 h by reducing power.
5.
A primary coolant activity increase greater than 25% but less than a factor of five over the prior equilibrium _value for that power level is cause to take immediate corrective action by reducing power. An increase in primary coolant activity levels greater than a factor of five over prior equilibrium values for that power level during any fluctuation test will be cause for terminating the testing and proceeding with an orderly plant shutdown.
Figure C of Appendix A shows the expected primary coolant activity.
6.
In the event of a region exit temperature redistribution or fluctuations at (70% power, a limit of 10% of the full power range on any nuclear channel deviation will be maintained.
During testing at >70% power, a limit of 15% of full power range on any nuclear channel deviation will be maintained.
Any changes greater than these limits is cause to take immediate corrective action by reducing power.
7.
A CRD shkn motor temperature >245'F must be lowered to (245'T by opening that region's orifice prior to the next power rise.
8.
If any of the following conditions are exceeded, immediate action will be taken to terminate the test, and further test-ing will be suspended until authorization to proceed is obtained from the NRC:
a.
Technical specification limits are exceeded as a result of this test program.
b.
An increase in primary coolant activity levels greater chan a factor of five over prior equilibrium values for 3-6
i 910049 N/C that power level.
Figure C of Appendix A shows-the.
expected primary coolant activity.
c.
A temperature change of module main steam temperature of 150'T relative to the initial steady-state temperature and exclusive of temperature change due to load changes.
d.
~ A module main steam temperature which exceeds 1075'F.
i 3.4.
DEVIATIONS FROM TEST PLAN AND PROCEDURES This section describes the deviations from the test plan outlined in Section 3.2.
Additionally, the deviations from test procedure RT-500L, which is included as Appendix A of this report, are discussed.
For all of the testing conducted under RT-500L, the maximum core thermal power was limited to 78% by an operations order.
This differs from the 82% limit in FSV's license. This lower power level ^ limit was implemented to ensure that the core power remained below the license limit in the event of a plant transient.
The 5% to 10% power decreases shown.in Fig. 3-1 were neve.* per-formed during the test program.- They were omitted as a result of the interruptions of the test and to minimize the amount of time spent oper-i ating the plant at lower power levels. Also the power rises were per-formed a slower rate than originally planned.
The decision to use 1%
per minute power rises rather than 3% per minute was'made to minimize the transient overshoot.
During the initial July 1987 testing, the primary coolant oxi-1 dant level exceeded 10 ppm. Also during the July 1987 testing, it was observed that the circulating activity was increasing more rapidly with increased power than was shown in the expected activity versus power figure in the RT-500L test procedure.
The expected activity curve 3-7 l
910049 N/C in RT-500L was based on Cycle 3 data.
It was concluded that this condi-tion was acceptable since the test data indicated that the circulating activity was increasing smoothly, but more rapidly than previous cycles, and that the activity decreased following a power decrease to the previ-ously observed equilibrium value for Cycle 4.
A new figure was gener-ated to replace the original circulating activity guideline figure in RT-500L.
During the March 1988 testing, the circulating activity monitor was out of service. A procedure deviation wcs written to allow testing with the monitor out of service. Radiochemistry snalysis of grab samples was l
provided every 24 h to determine circulating activity.
Radiochemistry personnel were available on call to perform additional analysis as required.
l Testing in March 1988 was performed on a core resistance line mid-way between the two resistance lines shown in Fig. 3-1.
The core resis-tance was increased for this test run to try to reach, at 78% power, a core pressure drop equal to that which would have been reached on the lower resistance at 82% power.
l Testing in August 1989 was initiated at approximately 66% power L
on the high core resistance line of Fig. 3-1.
The test plan called for beginning the high resistance line at a core power less than 50% so that the core pressure drop would be below the previously observed r3distri-L bution threshold. However, to minimize the risk of a plant upset while the reheat steam attemperation flow is turned off during the power l
L reduction to establish test conditions, and while the attemperation is reestablished during the power increase, it was decided to begin the test at 66% power.
It was planned to continue the test to about 76% to 78% power, at which time the core pressure drop would be greater than the maximum expected cycle 4 core pressure drop.
u l
1 l'
l 3-8
910049 N/C 3.5.
JULY 1987 TESTING Table 3-1 summarises the RT-500L testing during July 1987.
The testing is described in more detail below.
On July 2, 1989, PSC received the release from the NRC to operate FSV at over 35% power. Setup of the core for testing began on July 4, but due to the primary coolant oxidant level and problems with the attemperation, the start of RT-500L was delayed.
Cycle 4 testing under RT-500L was initiated on' July 7, 1987.
The initial conditions for the test were 54.8% core power, with a core pressure drop of 2.39 paid, a core resistance of 47, and a core temperature rise of 670'F.
Testing was initiated with the primary coolant oxidants over 10 ppe and without the reheat attemperation flow.
The first power rise began at 1445 MDT on July 7.
Power was increased to 58.0%.
The core pressure drop increased to 2.61 psid, while the core temperature rise increased to 675'F.
Reactor conditions remained stable throughout the power rise and the 1 h data collection /
observation period.
The second power rise began at 1750 MDT. Power was increased to 59.9%.
The core pressure drop increased to 2.74 paid, while the tem-perature rise was essentially unchanged.
The reheat steam temperature for module B-2-6 increased to 1035'F on the PPS following the power rise.
Core conditions remained stable.
RT-500L testing was suspended following the second power rise on July 7.
The reheat steam attemperation flow had still not been estab-lished and the oxidants remained above 10 ppm.
RT-500L testing was resumed on July 18 with attemperation flow l
the primary coolant oxidants below 10 ppm.
The core was reorificed to establish test conditions. Additionally, rod bump tests were performed 3-9
_~
1 I
910049~N/C f
prior to the RT-500L power rises.
Initial conditions were 58.2% power, with a core pressure drop of 2.30 paid, and a core temperature rise of 744'F.
The core resistance was 49.
i The next power rise began at 0605 MDT on July 19.
The core power-
-t increased to 61.1%.
The core pressure drop increased to 2.41 psid, while'the core temperature rise increased to 760'F.
Reactor condi-tions remained stable throughout the power rise and I h data collection /
observation period.
The core was reorificed following the completion of
[
the data collection to establish margins on LCO 4.1.7 prior to the next power rise.
L The next power rise began at 1107 MDT.
The core power was increased to 63.5%.
The core pressure drop increased to 2.61 psid, with a core temperature rise of 771'F.
Again reactor conditions remained stable.
Following completion of the data collection, the PCRV was pumped up.
s To obtain a higher core flow rate, and a corresponding drop in core temperature rise, on July 20.the attemperation flow was put in msnual control and dropped by 4 kib/h from the preprogrammed attemperation schedule.
This was done in four equal steps.
The result of the change in attemperation was an increase in core pressure drop from 2.72 to-2.90 paid, and a drop in core temperature rise from 739' to 711'F.
The next power rise began at 0125 MDT on July 21.
Core power was' increased from 62.9% to 65.6%.
The core pressure drop increased from 2.92 to 3.03 psid, and the core temperature rise increased from 718* to a
742'F.
Reactor conditions remained stable.
The next power rise began at 0345 MDT.
Core power was increased to 68.3%.
The core pressure drop increased to 3.22 psid.
The core 3-10
a.
--a.-
..a...
..n.a.
.-a-..
a u,.
n.
910049 N/C temperature rise increase to 750'F.
Again reactor conditions remained q
stable.
Following completion of the data collection, the linear power
)
. channels were recalibrated.
The next power rise' began at 0624 MDT. A RWP on one of'the-linear power channels occurred at 74.0% power during the power rise. Maximum' overshoot for that channel during the power rise transient was 74.9%.
The sr.eady-state power rise after the transient was 70.5%.
The core pressure drop increased to 3.37 paid, the core temperature rise I
increased to 759'F.
Reactor conditions were stable following the L
power rise.
The next power rise began at 2015 MDT from 69.9% power.
Again there was a RWP at 74.0% during the power rise transient. This occurred because the scram and RWP setpoints had not been reset. The power rise
.was aborted, an the reactor power stabilized at 69.9%.
The linear power channels were recalibrated, and the scram and RWP setpoints were reset i
in preparation for the next power rise.
At 0008 MDT on July 22, while waiting to take a power rise, "C"
. circulator tripped.
The circulator trip was followed by a turbine and rod runback to 50% power.. Power was then reduced to 30% to recover "C"
circulator.
RT-500L testing was suspended.
j l
The control rod drive shim motor temperatures were monitored throughout the test.
The shim motor temperatures are limited to 250'F.
The maximum shim motor temperature recorded during the July 1987 testing was 230'F, well below the maximum allowable temperature.
3.6.
MARCH 1988 TESTING Table 3-2 summarizes the testing performed during March 1988.- The following text discusses the testing in more detail.
1 3-11
b 910049 N/C RT-500L testing was resumed on March 12, 1988 following an extended-outage in which "C" circulator was replaced.
The initial conditions established for the test run were 60.9% power, core pressure drop 3.07 psid, with a core temperature rise.of 747'F.
The core resistance was increased to 57.6 for this test run in order to achieve a higher pressure drop.
The first power rise began at 1450 MST and was larger than planned.
During the power rise one of the linear channels peaked at 74.5%.
This resulted in a RWP.
Core pressure ~ drop peaked at 3.95 paid and the core temperature rise reached 786'F.
The core power settled out at 66.5%.
The core pressure drop after the power rise transient was 3.55 paid.
The core temperature rise was 766'F.
In addition to the regulating rod.
coming out during the power rise the reactor operator pulled the shim bank out from 60 to 68 in.
Reactor conditions were stable following the power rise.
The core was reorificed to establish margins for LCO 4.1.7 follow-ing the completion of the data collection period.
Several regions had gone into the limited acceptable condition of LCO 4.1.7-following the previous power rise.- Adjustments were also made to the feedwater-flow.
The core pressure drop decreased from 3.55 to 3.49 paid as a result of the feedwater flow adjustment.
The next power rise began at 1840 MST.
The power increased to.
69.0%.
The core pressure drop increased to 3.70 psid.
The core temper-ature rise increased from 757' to 769'F.
Reactor conditions remained stable. After the data gollection period was completed, the linear powerchannelswererecaiibrated,andthescramandRWPsetpointswere reset.
The next power rise began at 2220 MST. The core power increased to 71.9%.
The steady state core pressure drop increased to 3.97 psid, while the core temperature rise increased to 781'F.
Reactor conditions l
3-12
910049 N/C remained stable throughout the power rise and the 1 h period after.
Following' completion of the data collection, the core was reorificed in preparation for the next power rise.
1 At 0233 MST on tiarch 13, the next power rise began.
The core power increased to 75.4%, while the core pressure drop increased to 4.15 psid.
The core temperature rise increased to 789'F.
Reactor conditions remained stable.
Following the completion of the data collection period, the linear power channels were recalibrated.
The final power rise for the March 1989 testing began at 0530 MST on. March 13.
During the power rise a RWP occurred when one of-the lin-i ear power channels exceeded 81%.
The steady-state core power after the power rise transient was 78.8%.
The core pressure drop increased to 4.35 psid, while the core temperature rise increased to 800'F.
This is-l the maximum core temperature rise for which the region outlet tempera-ture mismatch can be as much as 50'F.
Reactor conditions remained stable throughout the power rise and the 1 h data collection / observation L
period.
L The control rod drive shim motor temperatures were monitored'
(-
throughout RT-500L.
The maximum shim motor temperature recorded during the March 1988 testing was 247'F.
This value is below the maximum allowable shim motor temperature.
3.7.
AUGUST 1989 TESTING Table 3-3 summarizes the August 1989 RT-500L testing.
The following text describes the testing in more detail.
Testing under RT-500L was resumed on August 1, 1989.
The strategy for this test run was to set up the core for the higher resistance line at about 66% power and take power rises up to 76%.
Key to the choice of 66% power as the starting point was that the pressure drop would be i
3-13 l
l l
i 910049 N/C j'
i slightly below what.had been reached in previous testing and that by L
starting this high going through bringing the attemperation flow on could be avoided.1 y
The power reduction to 66% was initiated at 2100 MDT.
Core f
reorificing for RT-500L began at 2300 MDT, and was completed at 0422 on August 2.
The entire core was reorificed in seven steps.
During the reorificing, the core pressure drop increased from 3.19.to 4.10 psid.
The initial conditions established for the test were core power 66.1%,
core pressure drop of 4.10 poid, core temperature rise of 738'F, and a core resistance of 60.
-The first power rise was taken at 0455.
The core power increased to 69.4%.
The core pressure drop increased to 4.32 paid, while the core L
temperature rise increased to 755'F.
Reactor conditions remained stable throughout the power rise and the 1 h data collection / observation period following the power rise.
q Following the first power rise, the scram and RWP setpoints were reset,~and the reactor was pumped up.
The core was reorificed to estab -
lish'the required region outlet temperature mismatch margins'for the i
next power rise. As a result of pumping up and reorificing, the core temperature rise dropped to 729'F.
The second power rise began at 1136.
This power rise was taken veryuslowly to minimize the-risk of overshoot on the linear power chan-nels, and was accomplished in two steps.
The power rise was completed at.1158 with a steady-state core power of 73.7%.
At 1221 "D" circulator tripped during a concurrent surveillance test. 'This trip resulted in a turbine and rod runback to 50% power.
Power was then reduced to 30% to recover "D" circulator.
During the power rise and the data collection period prior to the circulator trip, the reactor behaved in a stable and predictable manner.
3-14
-~
910049 N/C l
The steady-state core pressure drop prior to the trip was 4.73 psid with a core resistance of 58.6.
The core temperature rise was'744'F.
As was done during previous testing the control rod drive shim motor temperatures were monitored throughout the test.
The maximum con-trol rod drive shim motor temperature measured during the August testing i
was 238'F.
This is well below the maximum allowable temperature of 250'F.
Figure 3-2 summarises the testing performed under RT-500L during
.. i Cycle 4.
L i-1 l
3-15
-910049 N/C
.i i
Figure 3-2 Cycle 4 RT-500L Testing 5
Cycle 4 i
u July 1987 i
A :-
a O July 1987 i
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45-9 Ju.ly 1987 O March 1988 l
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i 6 A_u_9_ust 1989 i
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i 50 55 60 65 70 75 80 Core Power, %
3-16
TABLE 3-1 JULY'1987 RT-500L TESTING Mt r Reg Orifice Adjustments /
Temperature Comments
' Core Power Core AP Core AT Core Rod Date Time
(%)
(psid)
(*F)
Resistance (in.)
Region 12 Region 26 Region Initial Final 7/7/87 1444 54.8 2.39 670 46.9 102.4 216 218 7/7/87 Maximum 60.1 2.64 677 47.1 118.5 7/7/87 1633 58.0 2.61 675 46.6 113.3 218 220 7/7/87 1710 8
21.0 22.0 12 20.3 21.4 16.
11.7 12.1 7/7/87 1748 57.0 2.64 674 46.6 100.2 218 220 u
7/7/87 Maximum 61.8 2.80 678 46.7 110.5 h
7/7/87 1858 59.9 2.74 676 45.9 104.9 219 220 L
7/7/87 1900 19 11.0 11.9 36 34.2 35.4 37 25.1 27.5 7/19/87 0605 58.2 2.30 744 48.8 102.2 215 216.
7/19/87 Maximum 67.7 2.72 761 49.6 124.5 7/19/87 0712 61.1 2.41-760 49.2 114.8 N/A N/A 7/19/87 0837 8
27.6 29.7 12 18.8 19.8 13 20.7 21,. 7 -
14 27.0 25.4 15 16.6.
17.1 16 15.4 16.2 23 13.1 12.1 3
25 20.5 21.6 8
0 Ea
TABLE 3-1 (Continued)
S"*'"*"'8 Reg Temperature Comments Core Power Core AP Core AT Core Rod Date Time (1)
(psid)
(*F)
Resistance- (in.)
Region 12 Region 26 Region Initial ' Final 27 13.6 14.2 28 33.3 31.6 30 14.1 13.4 7/19/87 1030 4
33.9 36.0 11 14.9 14.5 21 22.6 23.6 23 12.1 11.0 25 21.6 22.3 u,
28
'31.6 29.2 I
[
29' 28.1 25.5 33 48.2 50.5 35 24.0 23.0 36 33.0 34.5 7/19/87 1107 60.9 2.39 771 49.1 106.7 216 215 7/19/87 Maximum 67.0 2.68 780 49.3 119.6' 7/19/87 1214 63.5 2.61 771 48.5.
112.6 N/A N/A 7/19/87 1240 Pumped up.PCRV.
7/20/87 2150 62.8 2.72.
739 48.2 111.9 Attemperation in manual.
7/20/87 2235 62.8 2.90 711 48.2
'111.0 Dropped attemperation flow 4.klb/h/ loop.
7/21/87 0125 62.9 2.92 718 47.7.
101.2
'224'
,217 f
7/21/87 Maximum 68.2-3.16 751 48.6 125.1 c)E E,
c
ca.
TABLE 3-1 (Continued)
D Motor.
Reg Orifice Adjustments /-
Core Power Core AP ' Core AT Core Rod
- Perature Comments Date Time' (I)
(psid)
(*F)
Resistance (in.)
Region 12 Region 26 Region Initial Final
[
7/21/87 0234 65.6 3.03 742 47.9 115.5 224 214 7/21/87 0310 8
30.5 34.1-12 20.5 21.4 16 16.2 17.0 i
7/21/87 0345 65.8 3.02 740 47.9 100.5 225 212 7/21/87 Maximum 69.5 3.25 753-48.4 109.9 7/21/87 0450 68.3 3.22 750 47.7 107.2 226 210 Y
Q*
7/21/87 0500 Recalibrated linear channels.
7/21/87 0624 68.4 3.18 754 48.0.
100.8 227 208 7/21/87 Maximum 74.9 3.57 772 48.4 115.9 RWP at 74% power.
7/21/87 0733
'70.5 3.37 759 47.8 105.7 228 208 l
i 7/21/87 1145 33 50.5 60.6 7/21/87 1800 16 17.0 18.0 31 9.7 10.9 7/21/87 1900 l
8 34.1 36.1 21 23.6 25.6 22 58.1 69.8 37 22.0 24.0 7/21/87 1935 16 18.0 19.5 33 60.6-70.6 e
o e
o
.. ~
~
TABLE 3-1 (Continued)
Reg.
r1Hce Adjustments /
t r Core Power Core AP Core AT Core Rod
- mPerature h nts Date Time (I)
(psid)
(*F)
' Resistance (in.)
Region 12 Region 26 Region Initial Final 7/21/87 2015 69.9 3.20
-752 47.3' 100.0 230 216 7/21/87 -Maximum 72.7 3.36 759 47.4 109.6 RWP at 741 power.
7/21/87 2057 69.9 3.21 752 46.9 101.3 N/A N/A Power rise aborted.
7/21/87 2100 Recalibrated linear channels.
7/21/87 2250 Reset scram and REP setpoints.
Y 7/22/87 0008 69.5 3.21 755 47.2 106.4 "C" circulator trip.
o Turbine and rod run-back to 50% power.
Dropped power to 30%
to recover circulator.
3 8
Eo
TABLE 3-2 MARCH 1988 RT-500L TESTING M or ri ce Adjustments /
Reg N#* "**
Core Fouer Core AP Core AT Core Rod Date Time (Z)
(psid)
(*F)
Resistance (in.)
Region 12 Region 30 Region Initial Final 3/12/88 0821 60.8 2.29 714 42.9 120.3 209 200 Reorificed entire code 3/12/88 1415 in 4 steps.
3/12/88 1450 60.9 3.07 747 57.6 109.5 227 211 3/12/88 1505 RWP at 74% power.
3/12/88 Maximum 74.5 3.95 786 58.4 127.0 shim bank pulled from 3/12/88 1607 66.5 3.55 766 57.4 82.4 232 220 60 to 68 in.
3/12/88 1650 2
11.7 12.5 6
11.0 12.1 s'
9 13.8 14.9 10 29.5 27.1 13 20.4 22.1 14 14.7 16.6 16 13.6 14.6 17 15.6 17.0 19 9.0 9.6 24 11.6 13.0 25 15.7 14.4 28 22.6 21.6 33 50.7 47.0 34 17.0 16.0 3/12/88 1730 36 18.0 16.9 3/12/88 1755 66.8 3.55 760 56.8 70.5 237 224 3/12/88 1808 Feedwater flow e
adjusted.
o E
a
='
'- 1 TA8LE 3-2 (Continued)
Reg Orifice Adjustments /
r Core Power Core AP Core AT Core Rod N '**"'*
"E" Date Time (1)
(psid)
(*F)
Resistance (in.)
Region 12 Region 30 Region Initial Final 3/12/88 1830 66.6 3.53 757 57.6 64.2 3/12/88 Maximum 73.0 3.72 772 57.9 81.1 3/12/88 1943 69.0 3.70 769 57.7 69.6 239 226 3/12/88 2000 Reset RWF and screm setpoints.
3/12/88 2130 Recalibrated linear channels.
3/12/88 2140 4
25.9 28.3 u.
5 13.7 19.8 3/12/88 2212 69.2 3.74 769 57.2 99.1 240 228 3/12/88 Maximum 75.8 3.99 785 57.7 114.5 3/12/88 2332 71.9 3.97 781 57.3 107.6 242 231 3/13/88 0030 2
12.4 13.4 3
31.9 35.3 4
26.0 30.1 5
18.7 20.8 6
12.1 12.5 7
10.4 10.8 8
27.5 28.8 12 16.7 17.3 16 14.6 15.4 21 17.8 18.6 25 14.4 15.0 3/13/88 0150 36 16.9 18.2 3
8; E
o
TABLE 3-2 (Continued)
Reg Ori Hce Adjustments /
t r Core Power Core AP Core AT Core Rod Date Time (I)
(psid)
(*F)
Resistance- (In.)
Region 12 Region 30 Region Initial Final 3/13/88 0220 72.9 3.90 786 56.8 106.9 242 231 3/13/88 Maximum 76.8 4.23 799 56.9 122.9 3/13/88 0348 75.4 4.15 789 56.1 114.9 244 233 3/13/88 0355 Reca11brated linear channels.
3/13/88 0420 5
20.8 21.3 25 15.0 15.4 Y
3/13/88 0522 75.6 4.11 788 56.1 108.6 245 235 U
3/13/88 0536 RWP at 812 power.
3/13/88 Maximum 81.2 4.39 806 56.8 120.6 3/13/88 0633 78.8 4.35 800 56.1 114.5 247 236 3/13/88 0920 Reorificed entire core 3/13/88 1037 in two steps.
I 8
0 5o
TABLE 3-3 AUGUST 1989 - RT-500L TESTIIeG CRD Motor Orifice Adjustments /
Temperature h nts Core Power Core AP Core AT Core Date Time (1)
(psid)
(*F)
Resistance (in.)
Region 12 Region 30 Region Initial Final 8/1/89 2300 65.9 3.19 704 45.0 109.6 217.5 218.7 Reorificed entire core 8/2/89 0422 66.1 4.10 738 60.0 99.6 in 7 steps.
8/2/89 0455 66.0 4.10 738 60.0 99.6 228.4 226.3 8/2/89 0604 69.4 4.32 755 59.2 104.1 231.3 230.4 8/2/89 0610 14 13.2 13.9 21 11.9 13.3
[
8/2/89 0632 Resetting scrom/RWP e-setpoints.
8/2/89 0714 4
22.7 23.2 8/02/89 072B Adjusted bypass pres-sure ratio.
8/2/89 0752 Scram and RWP reset complete.
8/2/89 1015 Pumping up reactor.
8/2/89 1022 2
10.6 11.4 3
30.3 34.0 4
23.2 24.6 5
17.0 18.3 6
10.7 11.2 7
9.8 10.5 8
18.7 19.1 9
18.6 19.7 12 13.9 14.9
=
16 12.8 13.2 g
e.
a
. - ~.
TABLE 3-3 (Continued)
Reg Orifice Adjustments /
t r Core Power Core AP Core AT Core Rod
- Perature h nts Date Time (1)
(psid)
(*F)
Resistance (in.)
Region 12 Region 30 Region Initial Final 17 24.6 25.0 18 29.8 31.3 22 36.0 31.6 26 6.5 5.2 28 21.8 19.8 29 11.3 12.5 8/2/89 1106 30 14.4 12.9 8/2/89 1136 69.3 4.37 729 58.4 89.9 233.0 235.0 Begsn slow power rise.
Y 8/2/89 1158 73.9 4.72 749 107.9 237.0 Completed power rise.
D 8/2/39 1221 73.7 4.73 744 58.6 98.7 236.0 238.0 "D" circulator trip.
Turbine and rod run-back to 50% power.
Dropped power to 302 to recover circulator.
3 8
O E
o
910049 N/C 4.
TEST DATA 4.1.
INSTRUMENTATION AND DATA RECORDING The following data systems used during RT-500L:
j 1.
Both wide range (700' to 1200'F) real-time trending recorders (or equivslent, such as Data Logger tables) and either narrow range (100'F, sero suppressed) real-time time trending record-ers (or equivalent) or digital display to monitor the system generator module main steam outlet temperatures.
2.
Data logger and associated trend recorders.
i 3.
The primary coolant activity monitor.
4.
The post-refueling fluctuation rise-to-power data acquisition system (RTPDAS).
The linear power channels and traversing TC's were connected to the RTPDAS per PSC CN 1748.
i l
5.
CRD shim motor temperature trend recorders.
The above systems were required during each load increase.
The only exception to these requirements was during March 1988 testing when the circulating activity monitor was out of service.
Radiochemical L
analysis of primary coolant grab samples was performed by site personnel to cover the requirement to monitor circulating activity.
l 4-1 l
910049 N/C During power increases and for a period of 1 h following the power increase, the following data systems and data recording frequencies were used.
1.
Data logger on a fast sample rate (15 s ).
2.
Post-refueling fluctuation RTPDAS (300 ms).
3.
Real-time trending recorders (or equivalent).
At periods during the test when the initial conditions are being established prior to a load increase (orifice adjustments, flow / power changes, but not during the initial protest core orificing), the following data systems and data recording frequencies were desired r
1.
Data logger on a sample rate of 2 min.
2.
Post-refueling fluctuation RTPDAS.
Sample rate of 300 ms.
3.
Rea?-time trending recorders (or equivalent).
The traversable thermocouples were positioned (per RT-524) in as close to the same locations as possible as they were for RT-500K testing e.g., the locations of November 1981.
i 4.2 DATA PACKAGES 9
Data packages were generated for each of the power rises initiated during RT-500L. The data packages include plots of Data Logger and RTPDAS' recorded data, esiculated data, CRD shim motor temperatures, and copies of the data sheets generated during the test.
Data recorded during pretset core reorificing was also inchpded in the data packages for reference. The data packages were issued as G internal memos (Refs. 5 - 11).
4-2 w
e w
- W W
N -
i 910049 N/C r
f 4.3 RESULTS OF JULY 1987 TESTING Testing during July 1987 was performed during three periods. A summary of this testing was given in Table 3-1.
The July 1987 testing was uneventful l
from a core performance point of view. However, there were numerous reactor problems unrelated to the core performance which interruptad the test.
The circulator trip on July 22 resulted in an extended outage to replace the "C" circulator.
i No fluctuations or redistributions were observed during any of the July 1988 RT-500L power rises.
The core response during each was smooth, predictable, and very similar to that observed during thc Cycle 2 and 3 power rises at core pressure drops below the " redistribution threshold." The l
maximum steady. state core pressure drop reached during July 1987 testing was 3.37 paid.
i.
4.4 RESULTS OF MARCH 1988 TESTING l
The testing during March 1988 was the most successful of the Cycle 4 RT-500L test periods. This testing was summarized in Table 3-2.
The March l
1988 testing extended Cycle 4 operation to a maximum steady-state core L
pressure drop of 4.35 paid.
Testing was initiated at a pressure drop of 3.07 paid to provide overlap with the July 1987 testing. As was the case in July 1987, no fluctuations or redistributions were observed during any of the March 1988 testing. The core response was smooth and predictable even at pressure drops well over the Cycle 2 and 3 " redistribution threshold." The first power rise was unusual, however, in that the power increase was approximately 6% of rated posar, L
instead of the 3% power increase specified in the test procedure.
t The first power rise was also unusual in that the shim bank was withdrawn from 60 to 68 in, during the power rise, while the flux controller inserte'd the regulating rod automatically to compensate.
The test procedure called for 4-3
910049 N/C the power rise to occur by withdrawal of the regulating rod so the that the resulting changes in the core power distribution would be as uniform as possible.
The shim bank rods were to remain at a fixed position.
The effect of the regulating rod insertion shows clearly in Fig. 4-1, which shows the changes in the measured region outlet temperatures resulting from the 60 - 66%
power rise.
Region l's outlet temperature decreased 26'T after the power rise, and the ring 2 regions (2 through 7) increased less than average.
In a more typical power rise, these seven inner regions would have increased more than average, with Region I showing the largest increase. The changes in measured region outlet temperatures (with the exception of the seven northwest boundary regions which are known to be susceptible to temperature measurement error) are consistent with the control rod motion which occurred during the power rise.
r 4.5 RESULTS OF AUGUST 1989 TESTING The testing performed in August 1989 covered operation up to a core pressure drop of 4.73 paid. Table 3-3 summarized the August 1989 testing. As with previous Cycle 4 RT-500L testing, no fluctuations or redistributions were obse.rved. As with the July 1987 testing, the August 1989 testing was terminated as the resalt of a circulator trip.
t The August 1989 testing was initiated at a core pressure drop of 4.1 psid to provide overlap with the previous testing. The changes in the measured region outlet temperatures following the power rise from 66 to 69% power are shown in Fig 4-2.
These changes are typical for RT-500L and similar to those seen during. Cycles 2 and 3 testing. As expected the largest changes occurred for the seven inner regions. Note that the thermocouple for Region 33 was broken prior to the August 1989 testing and not replaced.
Figs. 4-3 through 4-6 show representative core data for the 66 to 69% power rise.
The linear power channel deviations shown in Figs. 4-7 and 4-9 show how stable the core was during the test.
Fig. 4-9 shows representative gap thermocouple temperature for this power rise.
Fig. 4-10 shows the location of the gap thermocouples.
4-4 1
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August 2, 1989 66 - 69% power rise core power and flow t
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August 2, 1989 66 - 69*. power rise reactor parameters 4-8
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August 2, 1989 66 - 69% power rise core pressure drop and resistance p
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August 2, 1989 66 - 69% power rise linear power Channels III, IV, V deviations 4-11
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The second power rise was interrupted by a circulator trip. As the core power decreased following the trip, several regions exhibited " retrograde" behavior.
This behavior is the initial increase in a measured temperature I
which should be decreasing. It was previously determined that the " retrograde" behavior is caused by sudden decrease in the amount of cold bypass flow entering the region outlet temperature thermocouple sleeve.
The " retrograde" behavior was also seen for some of the gap thermocouples.
Figs. 4-11 through i
4-15 show representative data recorded during the power rise and circulator I
- rip transient.
4.6 SHIM HOTOR TEMPERATURES While RT-500L is concerned primarily with the reactor core performance as the core pressure drop increases, the control rod drive motor temperatures
(
were monitored throughout the test.
The highest shim motor temperature recorded during RT-500L was 247'T for Region 12 during the March 1988 testing.
The temperature limit for shim motors is 250'F.
Fig. 4-16 shows the Region 12 shim motor temperature data collected during Cycle 4 RT-500L testing.
4.7 CONCLUSION
S t
The testing performed under RT-500L during Cycle 4 demonstrated the stable operation of the FSV reactor core up to a steady-state core pressure l
drop of 4.73 paid.
No fluctuations were observed during any portion of the test program.
Unlike Cycles 2 and 3, no redistributions were observed.
The behavior of the reactor core during each of the 31 power rises was very similar to that observed for the Cycle 2 and 3 power rises which did not result in redistributions.
It should, however, be kept in mind that the Cycle 4 testing did not demonstrate that redistributions could not have occurred under the full range of Cycle 4 operating conditions.
It is possible that a redistribution could have occurred had the testing continued to higher pressure drops, or that a redistribution had occurred prior the start of test l.
preparations.
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August 2, 1989 69 72% power rise reactor parameters 4 17
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Region 12 shim motor temperatures 4-21
)
i 910049 N/C I
One opera',ional concern which became appe, rent during the Cycle 4 RT-500L testing was P.he high core temperature rise during operation at high pressure drops.
The only effective action taken to lower the core temperature rise while mainteinina core p:ver was to increase the primary coolant helium J
inventory. This action was only partially effective.
It is somewhat surprising that this problem 5as encountered, since the core temperature rise was maintained below 700'T d ring Cycle 3 testing.
Had FSV operations not terminated, this operational issue would have become increasingly important.
i t
4 f
4-22
l 910049 N/C i
5.
SAFETY CONSIDERATIONS 5.1.
INTRODUCTION In Ref. 2 a safety evaluation of the region outlet temperature redistribution was submitted to the Nuclear Regulatory Commission.
In this report it was noted that, because the outlet temperature redistribution is caused by a mechanism similar to that which previously produced fluctuations, the safety evaluation for a fluctuation event (Ref. 4) remains valid for the outlet temperature redistribution event.
It was concluded that the reactor could be operated following a redistribution, up to 100% power, without increasing the risk to public health and safety.
The redistribution safety evaluation in Ref. 2 was based upon data obtained during testing below 70% power in November and December 1980. A subsequent safety evaluation in light of data obtained above 70% power was performed in Ref. 3.
It was again concluded that the reactor may be operated following region outlet temperature redistributions, up to 100% power, without increasing the risk to public health and safety.
The reactor power limit was subsequently reduced to 82% for reasons not related to the core behavior in a redistribution.
While FSV operations terminated on August 18, 1989, the Cycle 4 RT-500L test results were reviewed with respect to safety considerations.
5.2 CONCLUSION
S No fluctuations or redistributions were observed during any of the Cycle 4 RT-500L testing.
Accordingly, the data recorded during Cycles 2 and 3 bounds the magnitude of redistributions.
The previous safety 5-1
L 910049 N/C.
evaluations therefore remain valid, as does the conclusion that the reactor-can be safely operated up to its licensed limit without increasing the risk
- to public health and safety.
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5-2
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910049 N/C i
l 6.
LONG-TERM OPERATION-6.1 REVIEW OF PREVIOUS CONCLUSIONS The operating experience gained during Cycle 2 and 3 RT-500 testing (Refs. 2 and 3), led to the method of operation by comparison-regions:for l
the seven northwest boundary regions. With this method it was possible to account for the temperature measurement errors in these regions during i
normal operation and after redistributions through the use of a Ring 4 i
comparison region.
The temperature-changes seen in other regions following a redistribution were real and adjustment of the region orifice valves was
[
sufficient to. maintain compliance with Technical Specification LCO 4.1.7.-
l l
The operating experience during Cycle 4 RT-500L testing confirmed that the comparison region method of operation is successful during normal operation.
Because no redistributions occurred during Cycle 4 RT-500L testing, the success of the camparison region method following a redistribution is not evaluated.
-lo 6.2 TERMINATION OF OPERATIONS t"
2 FSV was shutdown on August 18, 1989 to replace a control rod which had become stuck during a routine surveillance test, buring the shutdown, cracks were found in the ring headers of 11 of the 12 steam generator modules. On August 29, 1989 PSC decided not to continue with their restart efforts, thus bringing to an end FSV operation.
M l(c
/
O 6-1
910049 N/C 1
7.
REFERENCES 1.
PSC Test T-359, Authorized for use, June 16, 1987.
2.
Asmussen,-K.
E.,
et al., " Testing at Fort St. Vrain After Instal.
lation of Region Constraint Devices, GA-C16277, February 1981.-=PSC Submittal to NRC P-81312, December 10, 1981.
3.
Asmussen, K.
E., M. R. Hackney,.and J. C. Saeger, " Testing and Oper-ation of Fort St. Vrain up to 100% Power," GA-C16701, June 1982.
- 4.
" Safety Evaluation - Reactor outlet Temperature Fluctuations," PSC Submittal to.NRC P-78137, August 11, 1978.
5.
GA Internal Memo "FSV Rise To Power Data Acquisition System (RTPDAS)
~
Data.For July 1987 - RT-500L," CED:517:WLL:87, September 1, 1987.
6.
GA Internal Memo "RT-500L Data Package -- July 1987," US:1659:SPM:87, September 30, 1987.
7.
GA-Internal Memo "RT-500L Data Sheets -- July 1987," ISC 1690 SPM:88, April 29, 1988.
t 8.
GA Internal Memo "FSV Rise To Power Data Acquisition System (RTPDAS)
Data For. March 1988 - RT-500L,".CED:225:WLL 88, April 21,'1987.
9.
GA Internal Memo "RT-500L Data Package -- March 1988,"
ISC:1688 SPM 88, April 22, 1988.
10.
GA Internal Memo "FSV Rise To Power Data Acquisition System (RTPDAS)
. Data For August 1989 - RT-500L," ISC:1710:SPM:89, August' 29, 1989.
11.
GA Internal Memo "RT-500L Data Package -- August 1989,"
ISC 1709:SPM 89, August 29, 1989.
7-1
=
IE 910049 N/C APPEND!X A RT-500 Revision L/ Final Sheet 1 of-23 RT-500L RT - 500 Revision L POT REF NA I
REE REF NA DATE ISSUED-REQUEST FOR TEST i
l REQUESTOR-SYSTEM 12 PURPOSE /0BJECTIVE - There are two main objectives of this test:
1.
To demonstrate that the region constraint devices have elimd-nated fluctuations at all core pressure drops up to the maxi.
mum expected,' under normal 82% power conditions, during the' fourth' cycle of= reactor operation.
l
'2.
To obtain, under normally~ expected operating conditions, auf-i ficient data to evaluate core parameters and any effects of.
region exit temperature redistributions.
.a DESCRIPTION OF TEST - With the plant in normal operation and with the-orifice positions in a normal configuration for Cycle 4, power will be increased in_ approximately 31 steps to obcata data at power levels ranging from a beginning power level corresponding to a pressure drop across the core of.approximately 2.5 paid' to a power level of 82%.
Power will.then be reduced, orifice positions adjusted to increase core flow resistance, and power again increased in stepwise fashion to about 82%. The increased flow desistance will be such as to result in a core pressure drop,-at 82% power conditions, equalling the maximum expected i
under normal operating conditions during Cycle 4.
Revision L represents a change of the procedures based upon the experience gained while testing under RT-500K and the results of A-1
910049 N/C RT-500 Revision L/ Final Sheet 2 of 23 analyses of-the data obtained.
Revision L reflects the fact that the Technical Specifications (i.e., LCO 4.1.7 and SR 5.1.7) have been revised to incorporate special operating procedures to govern reactor operation with region outlet temperature measurement discrepancies, including region exit temperature redistributions. The magnitude of region exit temperature redistributions will be monitored, and the procedures and test limits will ensure compliance with both the letter.
and intent of the Technical Specifications. The region outlet temper-t ature mismatch limits recommended in Fig. C of RT-500K have been incor-j porated in the current LCO 4.1.7 (i.e., Fig. 4.1.7-1 of LCO 4.1.7).
Monitoring for regions which require operation per a comparison region is no longer required. Revision L also reflects the 250*F limit on CRD shim motor temperatures and the anticipated restriction to 82% of rated reactor thermal power.
In essence, the procedures and test limits pro-s vide for obtaining data up to 82% power in a well-defined and carefully-controlled manner.
ANTICIPATED RESULTS/ ACCEPTANCE CRITERIA
.The test will provide' data to demonstrate the effectiveness of the region constraint devices at elimi-nating fluctuations and to evaluate core parameters and any effects of region exit temperature redistributions.
There are no specific antici--
paced results or acceptance criteria.
i A-2
910049 N/C, RT-500 Revision L/ Final-i Sheet 3 of 23 t
SAFETY EVALUATION RT-500 Revision L is a combination of RT-500 Revision K, which has been reviewed and accepted by NRC upon issuance of Operating License Amendment No. 23, and the procedures and' limits reviewed and accepted by NRC upon issuance of Operating License Amendment No. 28.
Operation _will comply with_the letter and intent of the plant technical' specifications-and with the letter and intent of the interim technical specifications t
-(submitted under P-85242, July 10, 1985, and approved for operation via G-85294, July 23, 1985).
Therefore,-this test will not adversely affect the integrity of the core or steam generators-or the control rod drive shim motors, will not affect public health and safety, and will raise no.
unreviewed safety questions as defined in 10CFR50.59.
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910049 N/C RT-500 Revision L/ Final
[
Sheet 4 of:23 c
INTRODUCTION' The purpose of this test is twofold.. First, this test is to demonstrate during the post-refueling rise-to-power the effectiveness of the region constraint devices at eliminating core temperature fluctua-tions at all core pressure drops 'up to the naximam expected under normal operating conditions during the refueling cycle.
(It is assumed that reactor power will be limited to 82% of rated power throughout the refueling cycle.)
Second, this test is to obtain data during region outlet temperature redistribution events so as to ascertain whether their character (e.g., magnitude) remains unchanged from those observed during previous cycles and thus whether the bases for Technical i
Specifications LCO 4.1.7 and/or SR 5.1.7 remain appropriate.
'i Reactor data will be obtained as power is increased in stepwise fashion in approximately 3% steps at about 3% per minute.
Data collection shall connance at a power level where the core pressure drop is 2.5 psi,-which is below the threshold for redistributions (i.e.,
below 3.2 paid) and continue up to a core pressure drop of approximately 6 psid (the maximum pressure drop expected at 82% power conditions
'during Cycle 4).
Testing will be conducted by the coordinated efforts of a test team lt consisting of, but not limited to, the following members L
1.
PSC Shift Supervisor
(=
2.
PSC Reactor Operator (s) l:
3.
Test Coordinators 4.
Core Performance Engineer L
In the event of a fluctuation, a Data Sheet 1 will be provided to the NRC within-2 weeks.
i l
A-4
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=-
i; 1e j
010049 N/C RT-500 Revision L/ Final Sheet 5 of 23 4
OPERATING CONSIDERATIONS In addition to the normal plant operating procedures and limita-tions, the>following should be observed during performance of this tests i
1.
The MS temperature imbalance between any steam generator j
module and the average for the loop should not exceed *35'F in j
steady state._ In addition, the maximum individual module MS steady-state temperature should be limited to 1020'P.
'i 2.
The HRH temperature imbalance between any steam generator module and the average for the loop should not exceed the5 M
range specified in Fig. A during steady-state operation.
(Same as.in S0P 12-04.)
s 3
3.
The helium inlet temperature imbalance between any steam ~
generator module and the average of the 12 modules should not
[
exceed the-range specified in Fig. B during steady-state t
it operation. -(Same as in SOP 12-04. )
4.
The Helium Purification System will be in service during all testing.
F 5.
' CRD shim motor temperatures should not exceed 245'F prior to
't any power increase.
l:
Limits During Testing I
L Section A provides test limits which apply to operation in a nonfluctuatian mode.
Section B provides additional limits to those in L
Section A for a fluctuation.
The plant is defined to be in a fluctuation operating mode when I
individual nuclear channels exhibit cyclic deviations from the average l
A-5 l.
e, l
L 1
2r y
910049 N/C 1
RT-500 Revision L/ Final.
I 7
Sheet 6 of 23 1
1 pewer equal to or greater than.0.5% peak-to-peak of full power not exceeding a 30-min period.
Section A --Operatina Limits Prior to' Fluctuations.
1.
Testing will be conducted within the letter and intent of both the technical specifications and the interim technical speci-fications.
2.
A unidirectional module main steam temperature change of 60'F =
(excluding the average component of intentional steam tempera -
ture changes) is cause to take immediate corrective action by.
reducing power.
3.
A steady-state individual module main steam temperature g
exceeding 1025'F but less than 1050'F is cause to take corrective action within 12 h to reduce this temperature. -
' i; 4.
An individual module main steam temperature of 1050*F is cause to take corrective action within 1 h by reducing power.
S.
A primary coolant activity increase greater than 25% but less than a factor of five (5) over the prior equilibrium value for 1
that power level is cause to take-immediate corrective action by reducing power.
An increase in primary coolant activity m
levels greater than a factor of 'five -($) over prior equilib-rium values for that power level during any fluctuation test will be cause for terminating the testing and proceeding with an orderly plant: shutdown.
Figure C shows the expected pr4.-
mary coolant activity..
' 6.
In the event of a region exit temperature redistribution or fluctuations at (70% power, a limit of 10% of the full power range on any nuclear channel deviation udll be maintained.
1 A-6
j
.1 010049LN/C
-I i
RT-500 Revision L/ Final Sheet 7 of 23 r
During testing at >70% power, a limit of 15% of~ full power range on any nuclear channel deviation will be maintained.
Any changes greater than these limits is cause to take immediate corrective action by reducing power.
7.
A CRD shim motor temperature >245'F must be lowered to (245'T by opening that region's orifice prior to the next power rise.
i 8.
If any of the following conditions are exceeded, immediate action will be taken to terminate the test, and further testing will be suspended until authorization to proceed is obtained from the Nuclear Regulatory Commission l
1
.i t
a.
Technical Specification limits are exceeded as a result a
u of this test program.
l l
b.-
An increase in primary coolant activity. levels' greater
.than a factor of five (5) over prior equilibrium values for that power level.
Figure C shows the expected pri-mary coolanc activity.
i L
A temperature change of module main steam temperature of c.
150'T relative to the initial steady-state temperature and exclusive of temperature change due to load changes.
d.
A module main ateam temperature which exceeds 1075'F. -
L Section B - Operation During a Fluctuation i
Operation during fluctuations may be continued for a limited period of time (<2 h per event) provided the following limits are met:
1.
All the limits given in Section A continue to be in force.
If any of these lindts are exceeded, immediate corrective action A-7
l 910049 N/C i
RT-500 Revision L/ Final Sheet 8 of 23 shall be taken, and the power will be reduced to stop the j
fluctuations.
2.
A temperature fluctuation of module main steam temperature about its mean of *10'F (20'T total amplitude) is acceptable I
with no specific time considerations.
3.
A temperature fluctuation of module main steam temperature about its mean greater than *10'F (20'F total amplitude) but less than *30'T (60*F total amplitude) should not exceed I h in duration per event.
4.
A temperature fluctuation of module main-steam temperature.
about its mean of *30'F (60'F total amplitude) is cause to take.immediate corrective action by reducing power to stop the fluctuations.
5.
CRD shim motor temperatures remain (250'F for each region.
{orrective Action 1.
If any of the established linden or conditions are exceeded during this test, the test will be terminated and further plant testing will be suspended until specifically authorized by PSC management.
1 2.
If fluctuations are observed (see "Liedes During Testing" for 1
l the definition of a fluctuation), corrective action will be taken to terminate the fluctuation per the instructions given in Section B of "Liedts During Testing." PSC management authorization will be required prior to returning to a power level that would approach that level at which the fluctuations were observed.
e l'
A-8 m.
i ;i;'.
910049 N/C RT-500 Revision L/ Final Sheet 9 of 23 INSTRUMENTATION / DATA SYSTEMS I
The-following data systems shall be operating, and personnel will l
be present for power changes and data collection periods for monitoring:
)
1.
Both wide range (700'F to 1100'F) real-time trending recorders (or equivalent, such as Data Logger tables) and either narrow' range (100'F, zero suppressed) real-time tium trending recorders (or equivalent) or digital display will be available to monitor the steam generator module main steam outlet temperatures.
.2.
Data logger and associated trend recorders.
m 3.
The primary coolant activity monitor.
1
.4.
The Post-Refueling Fluctuation Rise-to-Power Data Acquisition System (RTPDAS). The linear power channels and traversing TC's will be connected to the RTPDAS per CN 1748.
5.
CRD shim motor temperature trend recorders.
-If any of the above systems becomes inoperable, further load increases shall be halted until the system is reinstated.
If fluctuations are encountered when any of these systems is inoperable,
'l core power should.be reduced'until the fluctuations cease.
f L
A-9 I-
910049 N/C RT-500 Revision L/ Final l
Sheet 10 of 23 During power increases and for a period of 1 h following the power increase, the following data system and data taking f requencies are s
desired:
1.
Data logger on a fast sample rate (15 s or less).
2.
Post-Refueling Fluctuation Rise-to-Power Data Acquisition h
a System.
(300 ms).
3.
Real-tian trending recorders (or equivalent).-
l' At periods during the test when the initial conditions are being established prior to a load increase (orifice adjustments, flow / power changes), the following data systems and data taking frequencies are desired.
i l
l-1.
Data logger on a sample rate of 2 min or faster.
e 2.
Post-Refueling Fluctuation. Rise-to-Power Data Acquisition System.
Sample rate of 300 mm.
c 3.
Real-time trending recorders (or equivalent).
The traversable thermocouples are to be positioned (per RT-524) in l
the same locations as they were for previous RT-500K testing; e.g.,
locations of November 1981.
i A-10
e.
910049 N/C 3
RT-500 Revision L/ Final Sheet 11 of 23 TESTING i
Initial Conditions 1.
Plant operating in a normal configuration at a power level less than or equal to 70% corresponding to a core pressure i
drop of not greater than 2.5 psid.
2.
The orifices are to be adjusted to achieve orifice valve i
positions such that the region exit temperatures and steam generator inlet temperatures are balanced per normal procedures and per the Operation Considerations section of
,this RT.
r 3.
Comparison regions should be initially selected from the following recommended regions:
26 through 31.
_(The region exit temperatures of Regions 26 through 31 were_never observed to decrease during Cycles 2 and 3 redistributions.)
1',
Procedure 1..
NOTES:
Prior to each incremental load' increase, adjust orifices a.
as necessary to balance region outlet gas temperatures and module inlet gas temperaturez, maintain margin on g
mismatch limits during power rise, and to maintain CRD shim motor,' temperatures (245'F.
In addition, adjust the reg rod positio'n to 100 in.-115 in.
l' b.
The most effective means of halting fluctuations is by power reduction. Experience has shown that to halt a fluctuation, the power may have to be reduced by 5% to 10% below the power level which produced the fluctuation, l.
A-11 j :-
I c
I 910049 N/C-I RT-500 Revision >L/ Final j
Sheet 12 of 23 c.-
Wait at least 0.5 h to reach thermal equilibrium prior to commencing tests wait 1 h after a load increase before continuing.
d.
Surveillance Requirement SR 5.1.7 states that " percent
'RPF discrepancy" evaluations must be performed prior'to
" exceeding 40% of rated thermal power for the first time-i after refueling, but at a power-level above 30%.
e.
For purposes of this test, comparison regions should be selected from boundary regions 21 through 31, and these regions'are referred to as " candidate comparison regions."
l f.
The initial core pressure drop should be about 2.5 psid.
.i 2.
Verify that the region outlet gas temperatures and the steam generator module temperatures are within.the Operating Limits section of this RT, that the CRD shim motor temperatures are (245'F, and that the initial conditions specified for this RT"-
are met before proceeding.
3.
Increase core power by approximately 3% by increasing turbine load by about 3% (approximately 9 MW(e)] at about'3% per minute.
If fluctuations are encountered, proceed to step 10.
If a redistribution is observed wherein a candidata comparison region's exit temperature decreases by more than 20*F, complete a data sheet 2.
Further, if a redistribution is observed wherein a candidate comparison region's exit V
temperature decreases by more than 65'F, go to step 9 before continuing.-
L 4.
Repeat step 3 starting at the new power level (approximately 3% above the preceding power level). Continue incrementally A-12
910049 W/C:
RT-500 Revision L/ Final Sheet 13 of-23 increasing the power level until fluctuations develop, a test a-limit is reached, or until about 82% power is achieved.
5.
.After reaching approximately 82% power and recording data for j
at least 1 h, reduce power by 5% to 10%.
Record Data Logger
~ data during the power decrease and for at least 30 min following the power reduction.
t 6.
Continue to reduce power in a stepwise fashion in 5% to 10%:
steps,.until the core pressure drop is approximately 2 psid.
Record Data Logger data during and at least 30 min following each power decreaseg wait at least 30 min after a load decrease before continuing.
7.
While maintaining core power at or below the level of step 6, adjust the core flow control orifice positions to increase the core flow resistance. The resistance should be increased to the. extent necessary such that when 82% power and flow conditions are subsequently attained, a core pressure drop of
(
about 6.0 paid
- will result.
The required value for core flow resistance can be determined, based upon the known resistance and pressure drop experienced when about 82% power conditions were first achieved (in step 4).
p NOTE:
The core pressure drop resulting from step 7 should not.
exceed approximately 2.5 psid.
If necessary, the core.
L power level can be-reduced so as to allow achieving the L.
required value for resistance while limiting the core pressure drop to about 2.5 psid.
l-u ll
- The maximum expected under normal operating conditions during Cycle 4 A-13 lr
N 910049 ft/C o
RT-500' Revision L/ Final-
- 1 Sheet 14 of 23 8.
Repeat' steps 3 and 4, then go to step 11.
9.
Any candidate comparison regions whose exit temperature is observed to decrease by more than 65'F as a result of a redistribution is unacceptable for, and may not be'used'as, a-l comparison region unless and untill a.
The inferred coolant temperature rise (or the margin from-the LCO 4.1.7 mismatch limit) in the region (20 or 32.
through 37) being controlled by the comparison region is increased by the amount by which the comparison region's exit temperature decreased plus 10'F-(to account' J
s b.
A " Percent RPF Discrepancy" evaluation is performed (as is done routinely in support of SR 5.1.7) and the.in-ferred coolant temperature rise (or the margin from the LCO 4.1.7 mismatch limit) in the region (20 or 32 through 37) being controlled by the comparison region is increased by a percent amount equal to or greater than i
the absolute magnitude of the comparison region's RPF discrepancy.
c.
If a region exit temperature redistribution 'is observed wherein a comparison region's exit temperature. decreased, by more than 65'F, there is to be no further power increases until a.new acceptable comparison region is, employed or step 9(a) or step 9(b) has been completed.
Continue with step 3 above.
10.
If fluctuations develop, it is desirable to obtain data-for about I h during the fluctuations, then reduce. power to stop fluctuations. Further, Data Sheet 1 must be completed. The operating limits stated in this RT must be adhered to during the 1-h period.
If these limits cannot be met, reduce power to stop fluctuations.
Go to step 11.
A-14
910049 N/C.
. RT-500 Revision L/Tinal l'
Sheet-15 of 23-s 11.
Based on the results of the test, a determination will be'ma'de as to the necessity to repeat any portions of the test or to~
perform any additional tests utilizing different orifice patterns or core flow resistance values.
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A-15
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910049 N/C
-1
- RT-500 Revision ~ L/ Final:
Sheet 16,of 2'3 a
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ACCEPTABLE
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P 0
10 20 30 40 50 60 70' 80 90 100
?. RATED THERMAL POWER Fig. A.
Range of steady-state steam generator module reheat steam' temperature mismatches (imbalance between individual module and average for the loop)
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A-16
010049-N/C RT-500 Revision L/ Final Sheet 17'of 23 CORRECTIVE ACTION REQUIRED
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Range of steady-state steam generator module lj '
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(imbalance between individual module and i
average of the 12 modules) l A-17
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l t-910049 N/C-RT.500 Revision :./Fina:.
t Sheet 18 of 13 Primary Coolant Activity RT-500L Guideline 16
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" !.O Exp.eted + 25% : ~t" t" 1 ~ ~ t "" "1""! "
1" ~t " < " t" ~ t " t ? " !
?. " ' ~!"".
..o.................~.
1 12,
..g.
..).
..{..
i. g.....;..
. 6.. t..... n.
..)..
..p.
......4...
ogo. p.
- t..
.t,.ot.
o..
4 up o.
g..
..t o oq..
y<.p....;..
m h
l s
O 3
y==
...)
.(..')...<..
i..).
.p...).
..(.-
)...<....(....).
...i..
.6
..(..o)....
.. f... 3..
s,.
X s.
10
.........u
.o
...i,..a....i........(.....
....).
..i..4....
...a.........'
..b..
..o
,n
- o K
o.oc.ot.on)..co.p.opo o t. o...
..p
...to
.p.oto t.o..
3 o.c o....}
o c t.o o).
. o t.., q o.
l.
O l
.e.-
o t...
8-
... ;...;.. o p....
.. i.. 4..
.. &.. 6... p... n.. s
...:.... {........
. i...
.(....o 1
...p.
.p.o.
.p...p......
..e
.....9..#
.e=
........eo..
s
...p.
C Q-
.o j
o
,....;....p...p..
.. g.... p.. o... p... p.
..p..q...,
.(.o.}.
....{.... +..(....)..
O-
..p
.p..,;..
.t..
b 6.,
.....p..
y....
r.
p...p.
p.
W
.. ;.. e.. :..;..
...:.... (.... ;,..:... ;..
Q E
.. &.. 4.... i..... ;...,;... ;
..l..
.:_ ~ 4...
..... i..:.,
3
..t......
..g.,
.t.....
...p...y..
p
)......t...q..
.p..q.
..t..
...p....3..
q,..
4y
..n......4...
.... n....:... t.... 1..... ;.... s. o
.t
..).
.p...)..
.. i.... a..
s
- 4.. o. ).
..i.....>.4..
.t..
..p.
/
4,.
.p...).
.p...).. c... p... p.
..p...>..
.po..).
..p..q..
.p...).
.p....p
..p...p 2,
4
.4
...f.
4...
.p..
.t...q.
..p.
...p...}.
. t.... p....3
.q.
..p.o).
.p...}.
.p.
q..
9 0
40 50 60 70 80 90 10 0 Reactor Power, Percent Fig. C.
Primary coolant activity guideline A-18
i 910049 N/C j
RT-500 Revision L/ Final Sheet 19 of 23 1
t DATA SHEET 1-s Complete this data sheet if fluctuations were encountered. This data sheet is to certify that test limits were not exceeded.
A.
If any of the following limits are exceeded, testing must be stopped until further authorization by PSC Management.
r Limit
.i
.c i
1.
Were OPERATING CONSIDERATIONS 1, 2, and 3 met:
N/A Yes No c
2.
Time /date fluctuation started N/A 3.
Power level.at start of fluctuation N/A 4
Time /date' power reduced.
I hour 5.
Time /date fluctuation stopped N/A 6.
Power-level when fluctuation stopped N/A I
7.
Maximum fluctuation on Nuclear Channel f N/A Peak Magnitude
- 10%'(<70%)
.I
- 15% (>70%)
i 8.
Maximum fluctuation of Loop I MS' j
Temp Module #
N/A
'{
Fluctuation Magnitude 60'F P-P q
Hottent Module #
'F 1050'F
=j 9.
Maximum fluctuation of Loop II MS f
Temp Module f N/A a
Fluctuation Magnitude 60'F P-P l
Hottest Module f
'F 1050*F
'10.
Equilibrium value of primaryocoolant activity-for power level of test N/A 11.
Maximum value of primary coolant activity during-(
l test 25% increase 12.
Were data systems in service?
Required for i
~Yes__
No testing 13.
Was a purification train in service?
Required.for Yes__
No testing r
B.
For any of the following, testing must be stopped and reported to the NRC -.i l
1.
Any technical specification exceeded?
=Yes No L
(as a result of this test) l 2.
Any MS-temperature fluctuation >150'F?
Yes No
{
.3.
Primary coolant activity )5 times normal?
Yes No 4.
Any module main steam temperature exceed 1075'F7 Yes No l
PSC SHIFT SUPERVISOR Signature /Date TEST COORDINATOR Signature /Date I
A-19
- -_~-.
s 910049 N/C' RT-500 Revision L/ Final Sheet 20 of 23 DATA SHEET 2 i
Before Temperature After Temperature r
Redistribution Redistribution
.7 3 ate:
Times Date:
Time
-TIN TIN 4
TOUT' TOUT Orif.
Region Orif. Region Adjusted (l)
TATTER -
-)
REGION Pos..
Temp.
Pos.
Temp.
Region Temp.
TBEFORE-i 1
i 3
4
^
5 6
g 7
8 9
h'.
10 P
1g E
.12 13-14 15 16 17 18 19 Lm 20 l.
21
!.1 22 23 24 p
^
K A-20 l
Ie
.$e
=-
4
--w-
910049 N/C RT-500 Revision L/ Final Sheet 21 of 23 DATA SHEET 2'(Continued)
Before Temperature After Temperature Redistribution Redistribution Date:
Times
-Date Times TIN TIN TOUT TOUT f
Orif.
Region Orif. Region Adjusted (l)-
TAFTER -
REGION
.Pos.
Temp.
Pos.
Teup.
Region Temp.
TBEFORE 1
26 27 (l,
28 29
-30 31 32 33 34 35 36 o
-(l)If an orifice has been adjusted during the' temperature redistribution, calculate its region exit temperature accounting
[~
for the effect of this adjustment.- The attached flow fraction j
tables may be used to do this. Look op the flow fractions (FF) for the orifice positions (8) from before and after the redistribution, then compute the adjusted region exit temperature by:
FF' 8(after))
h TOUT-ADJ. = TIN (after)+(Tog 7(after)--TIN (after))FF'
'8(before)'
i L[
}
l ji
- l I
A-21
/;U r
.o
~
Flow Frection Tables for 7 Column Regions POS = Orifice Position FLOW = Flow Fraction POS FLOW POS FLOW POS " FLOW POS FLOW POS FLOW POS FLOW POS FLOW POS FLOW POS FLOW POS tIow I
1880 1.SSS 999
.993 SSS
.906' 788
.973 688
.964 ESS
.917 488
.361 388
.779 299
.635 ISO 14 3e '
(
998 1.SSS 898
.993 798
.986 698
.972 590
.963 498
.916 398
.988 298'.776 198
.631 98 426 i
996 1.999 096
.993 796
.906.
696
.972-596
.962 496
.916 396
.868 296
.773 196
.629 96 423 i
994 1.900 894
.993 794
.906 694
.972 594
.961 494
.914 394
.967 294
.771 194
.625 94 417' I
992 1.SSS 992
.993 792
.905 692
.971 592
.961 492
.913 392
.866 292
.768 192
.622 92
.412 999 1.SSS 998
.993 798
.985 699
.971 699
.968 498
.912 398
.964 298
.766 198
.619 95 488 908
.999 SSS
.992 798
.984 883
.971 588
.949 488
.911 398
.863 298
.763 ISS
.616 SS
.de3 J
906
.999 996
.992 796
.904 SOS
.979 EOS
.948 496
.915 386 852 296
.768 106
.613 06
.M9 964
.999 884
.992 784
.984 684
.979 584
.948 494 999 384
.868 284
.768 194
.611 94
.193 982
.999 382
.992 782.See 682
.978 582
.947 482
.900 382
.949 282 765 182
.600 82
.389 908
.999 988
.992 799
.903 SOS
.999 EOS
.946 400
.997 300
.848 208
.753 ISS
.685 38-.384 978
.999 878
.992 778
.903 878
.989 -
578
.946 478
.996 370
.347 278
.758 179
.691 78
.376 976
.999 876
.992 776
.903 878
.989 576
.946 476
.986 376 846 276
.748 176
.596 76
.368 l
974
.999 874
.992 774
.983 674
.988 674
.944 4T4
.984 374
.344 274
.745 174
.592 74
.361 972
.999 072
.992 772
.902 672
.999 572
.943 472
.993 372 043 272
.743 172
.598 72
.354 975
.999 879
.992 778
.982 879
.987 578
.943 478
.992 376..041 278
.748 179
.594
- 78..347 i
968
.998 368
.991 788
.982 SSS
.987 568
.942 468
.982 368
.349 268
.738 ISS
.588 68
.339 8
l 966
.999 868
.991 766
.981 OS6
.987 586
.941 466
.981 366
.839 266
.736 166
.576 66
.311 o
y a
964
.998 864
.991 764
.901 064
.986 564
.948 464
.988 364
.338 264
.733 164
.673 64
.324 N
962
.998 962
.991 762
.981 682
.906 562
.948 462
.899 362
.336 262
.731 162
.569 62
.317 i
968
.998 SSS
.991 768
.981 SSS
.986 EOS
.939 468 898 368
.835 268
.729 188
.565 OS
.311 2
.i 960.-
SES
.nl 768
.9 9 658
.985 558
.m 46
.e97 369
.834 268
.726 168
.661 58
.386 3
966
.996 866
.991 756
.908 856
.985 556
.938 466
.896 356
.933 266
.724 156
.566 66
.382 964
.998 854
.991 754
.909 854
.985 554
.937 464
.995 364
.831 254
.722 164
.652 64
.298
}
962
.998 852
.991 762
.999 652
.984 552
.936 462
.994 362
.330 252
.729 152
.548 62
.294 i
968
.998 868
.991 758
.979 458
.984 558
.936 468
.993 368
.929 268
.718 158
.544 ES
.299 I
948
.997 848
.999 748 -.979 648
.9s4 548
.936 448
.892 348
.927 249
.714 148
.548 48.2ss 946
.997 846
.998 746
.979 646
.963 646
.934 446
.891 346
.826 246
.718 146
.636 46
.288 944
.997 844
.999 744
.979 844
.988 644
.933 444
.889 344
.322 244
.796 144
.532 44
.216 942
.997 942 999 742
.978 642
.982 542
.932 447
.SSS 342
.829 242
.782 142
.629 42
.2F1 r
945
.997 S48
.999 748
.978 848
.982 548
.932 446
.887 348
.318 248..698 148
.625 49
.267
{
938
.997 838
.998 738
.978 SSS'.962-638
.931 438
.SS6 330
.316 238
.696 138
.629 38
.266 t
936
.996 836 989 736
.977 838
.981 ESS
.938 436
.904 336
.814 236
.691 136
.515 36
.265 I
934
.996 834
.999 734
.977 834
.961 634
.929 434
.883 334
.312 234
.688 134. Ele 34
.263 932
.996 832
.999 732
.977 632
.900 532
.929 432
.881 332
.818 232
.684 132
.586 32
.262 f
938
.996 839
.999 739
.977 638
.908 638
.928 438.See 338
.SSS 238
.681 139
.581 38
.26e a e l
m.-
Sn.-
in
.m 828. m En
.927 4n
.m 3a. 06 2n
.677 in 497
.n
.2s -
g 926
.995 926
.988 726
.976 626
.959 526
.926 426
.977 326
.894 226
.674 126
.492 26
.256 o
924
.995 024
.908 724
.976 624
.959 524
.925 424
.876 324
.992 224
.671 124
.400 24
.254 N
f 922
.995 822
.988 722
.978 822
.958 522
.925 422
.375 322
.SSS 222
.667 122
.494 22
.252
" *[
.)
929
.995 028
.908 728
.975 629
.958 529
.924 429
.874 329
.790 229
.664 129
.400 29
.25e o<
918
.995 818
.988 718
.976 SIS..957 518
.923 418
.372 318
.796 218
.861 119
.475 19
.25e
"* 7 j 916
.994 816
.988 716
.975 616
.957 516
.922 416
.371 316
.794 216
.669 116 4f9 16 2Se -
oo 914
.994 814
.997 714
.975 814
.956 514
.922 414
.878 314 792 214
.665 114 464 14 25e uo 912
.994 812
.907 712
.974 612
.956 512
.921 412
.968 312
.798 212
.662.
112
.468
~12
.25e 918
.994 818
.987 719
.974 819
.958 Ele
.929 die
.967 319
.789 218
.649 lie
.453 le
.2be e*
998
.994 888
.987
-798
.974 888
.955 ESS
.919 498
.866 3ee 786 288
.646-ISS
.448 8
.250 Q
[
996
.994 SS6
.967 796
.973 OSS
.955 ESS
.919 496
.965 398. 784 296
.643 186
.444 6
.25e r
l 964
.993 884
.996 784
.973 664
.954 ES4
.918 404
.863 364
.792 294
.648 194
.439 4
.250 982
.993 892
.986 782
.973.
692
.954 682
.917 462
.962 382
.781 292
.637 192
.435 2
.758 f,
.(
I
.a
~
n_
t ~
Flow Fraction Tables for 6 Column Regione i
i POS = Orifice Position FLOW = Flow Fraction POS FLOW POS FLOW POS FLOW POS FLOW POS FLOW POS FLOW POS FLOW POS FLOW POS FLOW POS 'It_Os l
1988 1.SSS 988
.996 SSS
.992 799
.996 SSS
.974 688
.961-488
.916 389-.868 299
.742 189 -.541-998 1.889 898
.996 790
.992 698
.984 598
.973 498
.961 398
.916 298
.866 198
-739 90
.536 996 1.889 096
.996 796
.992 696
.984' 596
.973 496
.968 396
.914 296
.364 196
.737 96
.531 994 1.999 994
.996 794
.992 694
.984 594
.972 494
.949 394
.913 294
.862 194
.734 94
.526
-i 992 1.999 892
.996 792
.992 692
.904 592
.972 492
.949 392
.912 292
.868 192
.731 92 -.521 998 1.988 890
.996 798
.991 699
.984 699
.971 499
.948 399-.911 299
.849 199
.729 99
.516 988 1.999 SSS
.996 708
.991 SOS
.983 sos
.971 488
.94n 388
.919 288
.946 ISS
.726 SS
.5:1 906 1.SSS 996
.996 796
.991 688
.983 ESS
.979 406
.947 396
.918 206
.944 106
.724 06
.505 984 1.999 884
.996 784
.991 SS4
.983 584
.979 404
.947 384
.999 294
.843 184
.721
' S4
.5ee i
902 1.SSS SS2
.996 782.9e1 eS2
.983 sS2
.979 482
.946 382
.998 282
.041 192
.718 82
.495 j
988
.999 SSS
.996 799
.991 SSG
.903 EOS
.969 498
.946 300
.987 289
.939 108
.716 SS
.498 r
979
.999 076
.996 778
.991 878
.902 578
.969 478
.946 370
.986 278
.937 178
.712 78
.480 p
976
.999 876
.996 776
.999 676
.902 576
.968 476
.944 376
.996 276
.836 176
.788 76
.4F1
)
974
.999 874
.996 774
.998 674
.982 E74
.968 474
.944 374
.994 274
.333 174
.794 74 462' Le-(
972
.999 872
.996 772
.999 672
.982 672
.967 472
.943 372
.983 272
.331 172
.789 72
.454
- ~
978
.999 879
.996 178
.999 678
.982 s79
.967 478
.943 378
.983 279
.829 17e
.697 18
.448 8
968
.999 068
.996 768
.998 SSS. Set Sc6
.967 468
.942 369
.982 268
.028 168
.693 69 437 o
966
.999 966
.996 766
.998 666
.901 EOS -.966 466
.941 366
.991 266
.826 166
.689 66
.428 f
964
.999 864
.995 764
.999 664
.991 564
.966 464
.941 364
.988 264
.824 164 696 64
.419
- =
962
.999 862
.996 762
.989 662.9et sS2
.966 462
.949 362
.899 262 822 162
.682 62
.411
~
~!
96e
.999 869
.996 769
.989 SSS
.981 sSS
.966 468
.946 368
.898 268
.829 168
.679 6e
,4e3
- t 0
960
.999 SES
.996 768
.999 Ss3.SeS sst.9e4 468
.939 368
.890 268
.819 158
.676 60
.398 o
966
.999 966
.996 766
.999 666
.908 556
.964 466
.939 366
.897 266
.017 166
.671 68
.392 W
964
.999 964
.996 754
.989 664
.ffSS 554
.964 464
.930 364
.896 264
.916 154
.666.
64
.387 962
.999 862
.996 762
.989 062
.908 -
552
.963 462
.937 362
.896 262
.813 152
.662 52
.382 968
.999 868
.996 758
.988 SES. 908..
558
.983 468
.937 360
.894 268
.812 1ES
.668 68
.378 949
.999 848
.996 748
.999 648
.979 548
.962 448
.936 348
.993 248
.SSS 148
.666 48
.372 946
.998 846
.996 746
.988 646
.979 546
.962 446
.936 346
.891 246
.996 146
.661 46
.366 944
.998 844
.994 744
.988 644
.979 544
.961 444
.934 344
.890 244
.992 144
.647 44
.361-942
.990 842
.994 742
.988 642
.979 542.961 442
.933 342
.SSS 242 799 142
.643 42
.356 948
.998 848
.994 749
.988 648
.979 549
.969 448
.932 34S
.387 248
.796 149
.648 48
.358 939
.998 838
.994 738
.988 639
.978 538
.900 438
.932 338
.886 238
.793 138
.635 38
.348
'i 936
.998 836
.994 736
.987 636
.978 536
.968 436
.931 336
.984 236
.799 136
.639 36
.347 i
934
.998 834
.994 734
.987 634
.978 534
.969 434
.930 334
.982 234 787 134
.626 34
.345 my j 932
.998 832
.994 732
.987 832
.977 532
.969 432
.929 332. Set 232
.795 132
.629 32
.343
- r. t j 938
.998 SSS
.994 738
.967 SSS
.977 539
.958 438
.928 339
.379 238
.782 138
.616 38
.341 929
.998 928
.994 729
.907 628
.977 528
.968 428
.927 328
.878 229' 779 129
.611 28 ~.339 926
.997 826
.994 726
.907 628
.977 526
.967 426
.927 326
.876 226
.776 126
.687 26
.336 o l 924
.997 024
.993 724
.998 624
.976 524
.957 424
.926 324
.975 224
.773 124
.693 24
.333 i
922
.997 022
.993 722
.986 622
.976 522
.966 422
.926 322
.374 222
.771 122
.698 22
.33e a
I g
92S
.997 See
.993 729.9e6 628
.976 529
.966 429
.924 328
.872 229
.768 129.s94 -
28
.328.
o<7. - j 919
.997 Sie
.993 710
.906 618
.976 Ele
.966 418
.923 318
.871 218
.765 118
.684 IS
.328 916
.997 816
.993 716
.996 616
.975 516
.966 416
.922' 316
.969 216
.783 116
.583 16
.328
- e s ea. -'i 914
.997 814
.993 714
.996-614
.975 514
.964 414
.922 314
.SSS 214
.789 114
.677 14
.328 uO 912
.997 012
.993 712
.996 612
'.976 512
.964 412
.921 312
.967 212 767 112
.671 12
.328 gle
.997 Sie
.993 719
.986 Sie
.975 EIS
.964 418
.929 318'.SSE 218
.766 liS
.666 IS
.328 t*
l 998
.997 SSS
.993 798
.986 SSS
.976.
ESS
.963 488
.919 388
.364 298
.752 180'.661 8
.328 Q'l i
986
.996 SS6
.993 786
.986 6SS
.974 586
.963 486
.919:.
3SS
.362 286
.768 ISS
.566 6
.328 r '
984
.996 884
.992 784
.986 SS4
.974 584
.962 484
.917 384
.961 284
.747 164
.661 4
.328 992
.996 882
.992 792
.Sf 5 682-.974 ES2
.962 482
.917 392
.969 292
.746 102
.546 -
2
.128 h,
i l
}
. _.