ML20132A827
| ML20132A827 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 08/20/1979 |
| From: | Warembourg D PUBLIC SERVICE CO. OF COLORADO |
| To: | Kuzmycz G Office of Nuclear Reactor Regulation |
| References | |
| P-79181, NUDOCS 7908220296 | |
| Download: ML20132A827 (25) | |
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Publie service conipany e conende P.O. Box 361, Platteville, Colorado 80651 August 20, 1979 Fort St. Vrain Unit No. 1 P-79181 Mr. Ge'orge Kuzmycz ,
U. S. Nuclear Regulatory Commission Division Project Management Special Projects Washington, D.C. 20555 Docket No. 50-267
Subject:
Fluctuation Testing
Reference:
P-79094 P-79131
Dear Mr. Kuzmycz:
Pursuant to the site meeting held on August 16, 1979, with Mr. Larry Phillips of your staff, we have revised RT-500E to incorporate comments discussed during the site meeting as well as
-- comments presented in the ten (10) informal questions submitted by your office on August 13, 1979.
Please find enclosed three copies of RT-500F. The areas revised in Revision F have been designated as such.
The following represents our comments and/or the action taken with respect to the ten (10) inforcal questions mentioned above.
Response has been keyed to the question numbers as presented.
Question 1 Reference 2 revises item 2 on page 4 of Reference 1 (under Corrective Action). However, the " Limits During Fluctuation Testing" given in RT-500E (Sheet 7) also appear to need revisi,n o for consistency with Reference 2. Please clarify.
Response
Revision F of RT-500 contains all test limits and corrective action and reporting requirements consistent with P-79094 and P-79131 (see pages 6 and 7, RT-500F).
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peg 2 Two Ouestion 2 On Sheet 4 of RT-500E, it is estimated that the Part I testing is expected to be no more than 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> in the fluctuating mode for a total of about 15 fluctuations.
. However, item (4B) on Sheet 9 of RT-500 (Ref.1) requires data acquisition for one hour at each core flow resistance. Is the 1/2 hour testing in item (4C) on Sheet 10 part of the one hour in item 4B, or is the total test time to be 11/2 hours? Is the testing to commence at 30% power or 40% power? If not at 30%,
why not? Clarify and detail the basis for your estimated time in Fluctuations?
What are your plans for evaluation and maintenance of records and cumulative f atigue damage effects of the fluctuation tests on system components which are affected? What assurance can you provide that the fatigue design life of affected components will -
not be exceeded due to the unplanned thermal cycling?
' Response Concerning the time spent in the fluctuating mode versus the cycles we would agree that RT-500E was not very cleary written.
Revision F attempts to clarify this matter. It was pointed out in our meeting on August 17 that tests would be conducted as follows:
Total Duration Total Test Tests Each Test Test Hours
- 1. One test at four different 4 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 4 power levels (core resist-ance values) for the purpose of obtaining fluctuation test data.
- 2. A repeat of the test at 4 1/2 hour 2 each power level with fluctuations initiated by power changes only to verify repeatability.
- 3. A repeat of the test at 4 1/2 hour 2 each power level with .
fluctuations initiated by pulsing the circulators.
- 4. A repeat test of item 3 to 4 1/2 hour 2 verify repeatability.
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Mr. G;org2 Kuzmyc.z Pag 2 Thrso ' Auguat 20, 1979 Total Duration Total Test Tests Each Test Test Hours
- 5. One test at only one power 1 1/2 hour 1/2 hour level of the tests in Item 1 with the regulating rod in manual.
Tetal Test Time 10 1/2 hours Concerning the test power levels and the question of beginning at 40% rather than 30%, it was pointed out in the meeting that the tests are to begin at a nominal 40% power level. Based on cycle 1 information, none of the fluctuations experienced at 28 - 30%
power exceeded a 1% change in the nuclear channels. Fluctuations
- at these low power levels, therefore, are no longer classified as fluctuations per the current definition of fluctuations. In addition, the core configuration must be drastically changed to obtain conditions conducive to fluctuations which represents con-ditions which are never approached during normal operation. Tests at 30% power, therefore, do not serve any useful purpose in establish-ing the operating threshold line.
Concerning the question of maintaining records for cumulative fatigue damage it was agreed that large system swings that may result from fluctuation tests would be logged along with the information that we maintain for plant life cycles to ensure that such swings would be considered along with other plant cycles. As pointed out in our meeting of August 16, 1979, fatigue damage resulting from fluctuations within the proposed test limits repre-sents negligible damage to the steam generators design life.
Larger swings beyond the test limits were only observed once during cycle 1 (November 4,1978) for a brief period of time, and
- we have established adequate precaution to terminate fluctuation tests if limits are exceeded for Cycle 2 testing. Although we believe that any thermal cycling resulting from fluctuation tests will have negligibic effect on the steam generators we will ensure that large swinga beyond the test limits are properly logged for future consideration of overall plant cycles.
Question 3 .
On Sheet 5 of RT-500E, why is emphasis now placed on core AP rather than core resistance for evaluation of the fluctuation threshold.
Response
As far as test control is concerned our emphasis has always been on AP rather than core resistance, as AP is the only para-meter that can be readily monitored in the control room. We still
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( August 20,'1979 Mr. G:org2 Kuzsycz ; Page. Four-
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believe that there is some d'eiiUite relationship between; core SP and core resistance, and that there is some definite reintionship between core resistance,and thq fluh uation threshold 1 % . PWe have elected, however, to controiron the basis of core AP, but will continue to develop relationships and correlations of these parameters in the fluctuatio. test program,
- t. y Question 4 Under Operating Considerations (Sheets 5 and} 6 of RT-500),
it is not likely that theLchanges in region outice temperatura experienced during cycle 1 provide a good basis for the Figure 1 limits on cycle 2. Your note indicates that. F,tgure 1 will be administrative 1y revised based on cycle 2 experience. The staff should be consulted on changes to '/igure 1 or a more general limitation should be. defined in RT-500.
Response _
It was pointed out in the meeting of August 16, that Figure
. 1 represented our best ostimala of, temperature margins. These margins were necessarily based on Cycle 1 as there is no other basis for the estimate. In addition the margins established, while they only represent a starting point, are necessary in order to obtain a core temperature outlet configuration that will keep us within Technical Specification limits.
It was agreed that PSC would keep the staff informed of changes to Figure 1,~as well as other significant test procedure changes. PSC would. intend to notify the staff of significant procedural changes'or the intent to revise procedurer when the summary test data is furnished bee' attachment to P-79131).
The summary test data will be submitted to the staff within one (1) week of completion of 'cesting for each power level.
Question _5 Reference 2 limits the module main steam temperature to 1075F for,NRC review. What is "Nthe technical specification limit on this parameter?
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-Response' .
There d.n no Technical Specification limit for a main steam ,
It was pointed out, however, that there temierature'of 1075'F.
is n Technical Specification limit:ct 1075' for het aeheat steam.
Since hot reheat, steam and main steam are basican) at the same temperature, and hot riheat steam is much more s'ensities to power and flow change's it can be inferred that main steem da essentially limited to 107!'F. - '
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Mr. G:orgs Kuzmyc; Paga Fiva August 20, 1979 Question 6 How do the testing procedures of RT-500 (Sheets 8 and 9) assure that adequate power / flow ratios are maintained?
Response
The tests are conducted with the plant control systems in automatic. Therefore any changes in power will result in automatic changes in flow and vice-versa. Power to flow ratios will there-fore be maintained automatically. There is one test where the regulating rod is placed in manual control. The remaining control systems remain in automatic during this test.
We have added, in addition, a precaution that the power / flow ratio as dictated by SL 3.l'and associated Figure 3.1.2 is not to be exceeded (see. paragraph 10 sheet 12 of 17 RT-500F). .
Question 7 In RT-500E Procedure, explain the deletion of waiting periods to allow thermal conditions to stabilize.
Response
Waiting periods were not deleted. See Note 3 page 9 of 17 of RT-500F.
Question 8 Steps 5 and 6 of RT-500E (Sheet 10) appear to increase the number of fluctuation cycles to more than the estimated total of
- 16. Explain.
Response
Discussed above as part of the response to Question 1.
, Question 9 Step 10 of RT-500E (Sheet 11) indicates that the lowest power level for testing should be 40 percent. Why not 30 percent? ,
Response
Discussed above as a part of the response to Question 1.
Question 10 What are the consequences of operating with a lower core flow resistance than was planned (FSAR)?
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Mr. Grorg2 Kuzmyc;: Pega Six August 20, 1979
Response
Operations postulated in the FSAR were for an equilibrium core with high region peaking factors up to the Technical Specifi-cation limits. Accident re-analyses were submitted by P-77221 bounding conditions for other core configurations. Current plant operations are well within these limits and therefore are en-veloped by the above re-analyses. This is further demonstrated by the example of results for the less demanding expected condi-tions for accident cooldowns as submitted by P-78178.
We trust that the revisions to RT-500 adequately address your comments and we request your approval to resume the fluctua-tion test program as soon as possible. As discussed during our recent telecon the outage for Fort St. Vrain Unit No. 1 for install-ation of the Region Constraint Devices is presently scheduled to begin on October 20. It is essential that we receive your release -
to resume the fluctuation test program as soon as possible to permit analysis of the test results prior to our scheduled shutdown.
Very truly yours, PUBLIC SERVICE COMPANY OF COLORADO-lbW %
Don Warembourg
, f Manager Nuclear Production DW:dkm Attachment t
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/N DATE 8/17/79 REQUEST PCR TE i_ ','
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-k, FORc S 2 2 AUG 2 01979 SYSTEM 12 ,
REQUESTOR R. Kate =ick/W. Sinen D PURPCSE/CEJECTIVE - There are two =ain objectives of this test:
D 1. To dete=ine the fluctuation threshold in te=s of core pressure drop
- D vs flow (power) for cycle 2 operation.
D 2. To obtain FM data during fluctuations with the revised instrumentation D systems for cc parison with cycle 1 data.
C -
C DESCRIPTION OF TEST - With the plant in no=al operation, core orifices D will be adjusted to achieve a specified core pressure drep. Load increases in ~3'. steps and pulse changes in circulater speed of ~5% will be used as D
D trigger nechanis s to induce fluctuations and to dete=ine the fluctuaticn D threshold in te=s of core pressure drop as a function D of core flow rate (power level). tTnen a flue: nation occurs, the step causing the flue:uation will be repeated to demonstrate repeatability.
Fluc uations will be initiated first at ~40's power and then a: ~10's intervals D
D Par 1 i
_..- D so as to provide a good definition of the stability threshold line.
2 refers to testing D cf the tes: enccmpases testing at <J0's power w' nile Par:
C at >70'. power. For at least one fluctuation, PM data will be obtained
.D with the reg-rod held in a constant position.
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evision T incorporates incorporatesPSC NR comentsments onon 'R vision evision ~ D'$.
r DATA REQUIRED
- See attac e .
- The test will provide data to AhTICIPATED RESULTS/ ACCEPTANCE CRITERIA D aid in predicting conditions for stable operation. Additionally, data D will be obtained which will aid in understanding the fluctuation phenomenon D and for co=parison with cycle 1 observations. There are no specific anti-cipated results or acceptance criteria.
P.EF SCP CR AENORPAL CCNDITIONS
- SOP 12-04 SC*>EDULE REQUIRDIENTS SAR 4 APPROVAL SEEET ATTACHED WORK ASSIGNED EY
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NameF.'a:e .
REVIEWED BY Na=e/Date
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Distributien:
V. Tersint' K. Asmussen R. Phelps Requestor W. Mcwhins CA-SD Ref. Library D. Scot R. Nirschl R. Xapenick A. Kennedr
A linsy _ W. F =nek E. Hill F. Mathie L. Johnson _
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.10. ?>_ SIS 701 SAITI! I7ALUATION: (Add addi-Jonal Sheets if Recuirsd): N During this test, oceration will be within Tech Soec and dation lim 4+e.
__ test is performed to investigate the threshold for fluctuations, and althouch they might be encountered, the time at fluctuation would be minimal. Consecuently, Main any fatigue damage to -the core and/or steam cenerators would b neolicible.
steam temperature fluctuation limits have been set accordinolv. In additinn.
.throughout the test, sufficient margin will be maintained betwean tha T b era-limit and the region exit temperatures so that even durino the most severe fluctuation observed to date the Tech Soec limits will not be violated.
(See Figure 1.) Although there will be a period of time that the rea-rod ie ,
disabled and not responding to the. auto flux (continued on attadh'ad chaa*) - .
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- 10. BASIS FOR SAFETY EVALUATION (continued) .
control syste=, test procedures will assure any rec,uired rod runbacks will take place and will produce the subsecuen: desired reactor pcwer control. Therefore, this test will not adversely affect the integrity of the core or steam generator and will not affect public safety.
Since firsr being enceunterei en October 31, 1977, fluctuatiens have-been initiated several rises in a centinuing effer: to undersand their cause. The powe:- levels at which fluctuations were initiated have ranged D frca 30% to 68%. A total of about 65 hcurs has been spent in a fluctuating D =cde, which is equivalent to 390 cycles with a peried of ten sinates.
Althcugh the cause of the fluctuations is not known, there are several reasons for concluding that continued testing is saf e. The total core C power, flow, and average resperatures are relatively stable. An inspection of the top plents in Dec=:ber 1977 after fluctuatien testing at power levels between 53% and 68% showed. it was in goed condi icn. An inspection at that tine of the control rods in region 34 (which were inserted throughou:
the entire period of flue:2ation testing) also showed no signs of excessive D te=perature or L:pect. During the first refueling cutage, eleven blocks D from region 35 were carefully inspected in the PSC hot. service facility and there was no evidence of da= age. An in-core inspection of region 35 D
D and its sur cundings with the fuel handling =achine T.V. camera revealed D no da= age or excessive wear to any cc=penent. The upper plenum area D looked fine; the gaps in the regicns and side reflector surrounding the D cavity left when region 35 was unicaded were very regular with no evidence
- D of wear or damage. An inspection of the core support blocks in regions 13 &
D 35 havelikewise revealed no damage.
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D Every element removed from the core during the refueling of six D . regions has been photographed as has each block in five additional regions D which were unloaded to permit installation of test assemblies. Examinations D of these photographs have revealed no damage.
D Testing Above 70'a Power (Part 2)
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Since f)nctuations' were 'first encountered, tests have been con-i D ducted under various core conditions. In large par:g these tests were D designed to gather specific infor:ation on what key para:eter or cc=bina-l D tion of parameters l'eads to the fluctuations, since this knowledge could D be instru= ental in understanding their cause. These tests have shown ,
D fairly conclusively that power level is not by itself a parameter or prl:arY D i=portance to the fluctuation threshold, and they have established core .
D pr' essure' drop as a key parameter, probably closely related to the cause or, D the flue:uations. Another result from these tests is that 1: appears tha: ,
l D the core pressure drop at which fluctuations are produced is higner at l
D higher core power levels.
l D
Differences in fluctuation =agnitudes and character have been cbserved D in the ~65 fluctuations that were initiated during cycle 1 cperation.
These differences have been carefully studied and reported extensively.
l- D L, D No apparent correlation with power level has been noted, nor has a change 1
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D been observed with ti=e that would indicate increasing fluctuation magni-3.
D tudes or significant differences in character. All of the fluctuation D testing limits and operating considerations as well as nor=al plan tech-D nical specification limits and SCPs are in effect both below 70% power D and above 70% power. One exception is the limit on nuclear detector D fluctuations. This limit is increased from 10'. at <70*. power to 20's for D >70% power. This increase is justified because nuclear channel fluctua-D tions are believed to be due primarily to a streaming effect and are thus D expected to be nearly proportional to the power (neutron flux) level.
D in.this test, fluctuations will be- initiated at successively higher power D levels. 'Ihe magnitude and character of the fluctuations at each power
. D level will be carefully observed fer differences in sddition to monitoring D the Technical Specification and fluctuation testing limits. Consec,uently, D testing above 70% power will not affect public safety.
D' Ti=e Spen: Fluctuating D It is anticipated.that a total of about 16 fluctuations will be .
D initiated during par 1 of this test (testing 170*4 power). Total ti=e D in the fluctuating mode during Par: 1.is expected to be no more than F N101/2 hours. For each of the four power levels at which the fluctuation I threshold. li=it- v111. be.defided, a first fluctuation ~will be initiated and
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F 'sustaided for ,a I-houi period (Step 4,3 of' the Proce' dure) . To verify repeat-F ability, three additional fluctuatio'ns, will then be initiated and 1 adiately F halted at each of these power levels (Steps 5, 6 and 7 of the Procedure).
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F One-half (1/2) hour in the fluctuati'ng mode has been allotted for each of the F latter three fluctuations. In addition., for one fluctuation during the 2 F conduct of this RT, the fluctuation will be sustained for one-half (1/2) hour F with the reg-rod disabled and all rods held in a constant position (Part 1, F Step 4C.of the Procedure). .
D During Part 2 of this test (testing at >70% power), fluctuations may be .
D initiated hbout 8 times, with a total time in the fluctuation mode of D %4 hours.
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PREFACE Revision A accomplished the following changes: (1) The Operatin'g Limits Section was redefined to incorporate limits required by the NRC.
(2) The re=ainder of the previous limits were redesignated as Operating Considerations. (3) The ecuation for core resistance was redefined to better fit observed opera:ing data. (4) Addendum I was added to deter-mine the fluctuation threshold at 2Si power.
s Revision B accomplished the following changes: (1) The 10% 14-4 t on a nuclear channel fluctuation was extended to cover all six channels. -
(2) The required instru=entation was increased' to have brush recorders for all twelve steam generator =odule outlet te=peratures and all six nuclear channels; the steam generator te=peratures will be monitored both by wide range brush recorders (700*F - 1100*F) and by either narrow range -
brush recorders (100*F range, :ero suppressed) or digital display of fluc-tuation magnitudes from the stean generator data acquisition system.
(3) The limit on =edule =ain steam te=perature a: which testing is sus-pended until authorized by PSC manage =ent is increased fres ;,30*F to 150*F. (4) In Figure 1, the region te=perature mis =atch =argin for region 12 is increased to 100*F. (5) The instruments to be =onitored by the trend recorders are not specified: any four thought to be of most use may be trended. (6) A two hour waiting period between fluctuation tests is specified. ,
Revision C accomplished the following changes: (1) Corrective action is to be taken to stop the fluctuation if a =odule main steam ten-perature reaches 1025'F. (2) Editorial changes were made to the other linits on module =ain steam temperature. (3) The tes: team members respon-l
- sibic for conducting the test are specified. (4) The physical location l of the data systems to be monitored are specified, as are the respective I
team members responsible for monitoring them. (5) Figure 2 of Addendus I
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has been " cleaned up" and updated to reflect the current actual locations for ther= occupies 3, 4, 5, 7, 19, 23, and 25. (6) In Figure 1, the region te=perature nis:stch margin on regions 17,18, 26, and 27 have been increased.
Revision D accomplished the following changes: (1) The detailed test procedure has been rewritten. The nu=ber of anticipated fluctuations However, and the total ti=e spent in the fluctuation mode has been reduced.
the basic test philosophy and the limits during fluctuations remain un-chang ed. (2) RT-502 (Threshold Testing >70% Power) has been incorperated -
as Part 2 of this RT. (3) The objectives of the test have been modified to reflect testing during cycle 2 (for co=parison with cycle 1) with the e=phasis on gathering data to aid in predicting conditions for stable operation. (4) Addendum I of RT-500 Revision C has not been repeated here because it was successfully completed *during cycle 1 testing. (5)
A definition of a fluctuation has been included. (6) There have been
- nu=erous editorial changes (changes are denoted by a D in the =argin).
k" Revision E incorporates ce==ents frc: PSC to delete the detailed crifice adjuse en: procedure, update Data Shee: 1 to i=clude all li=its and other
=inor ce=en:s as noted in the lef: =argin.
Revision F incorporates co==ents fro = NRC as noted.
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IhTAODUCTION D
D a distinct influence of core .d.P on the threshold However, es for f D the cycle 1 data shows a lot of scatter and fresh fuel has b .
D into six regions of the core; therefore, een loaded the beginning of cycle 2 is necessary. fluctuation threshold testing at D T D-
~ ~ his Rf will determine the fluctuation threshold n. o f " ~~afifuiic~~ ~
D D
the amount of scatter in the data). core pressure drop for cycle 2 (wi The FM Data System now includes D 24 traversable thermocouples, PCRV displacement probes ersand magn D for atte=pring to monitor core bar el motion, and two ins: eu=ented rol cont D and orificing asse=blies having in-core instr.:nent packages. These data D
stable operation and in understanding the fluctuation .
or D
D increase Theatexpected 3*4 =ethods for triggering a fluctuation will be alead 3'4 D to produce ~3'4 per minute and a pulse change in circulator speed sufficient D increase in flow.
hnen a fluctuation develops, the steps D preceding and resulting in the fluctuation will be repeated to de=enstrat
. repeatability and to provide a reasonably accurate deter =ination of th D
threshold .oower.
. .. .- e -
' The tes: -
D threshold for a: scope includes the determination of the' fluctuation ~ _ -
u .-
least three values of cor'e flow resistance. ~
~~
censisting of, but notTesting will be conducted by the cocedinated team efforts of a t li=ited to, the following ce=bers:
1.
- 2. PSC Shift Suoervisor ,
PSC Reactor O'perator(s)
D 3. Test Coordinator ,
D 4 Core Performance Engineer D 5. Data Systems Engineer F
F F
each The powerNRC level vill be provided, within,one week, with a sn- wy the procedure as.
OPERATING a result of the test results. Included with these results CONSIDERATIONS change will to be the following should be observed:In addition to the nor=al a-ions, plant operatin 1.
C The HRH and MS te=perature imbalance between each SG :odule and C the average for the loop should not exceed 30*F '
the limits given in SOP 12-04 whichever are more(restriin ctive. steady state) or In addition, the maxi =um ture should be limited to 995*F.
individual module MS steady state te:pera-is to provide =argin on MS temperature when fluctuatiThe purpose of the 995 2.
, ons occur.
Steady state module helium inlet 145'F are more about the mean or the li=its given in SOP 1':-04 whichevere:perature restrictive.
Sheet 6 of 17
'. /
Q
(
s l
D 3. In order to minimite the chance of getting into a degraded perfor- ,
ncnce condition during fluctuations, the maximum regicn outlet gas tenperature during steady state conditions shall be thelimited as follows:
following core From previous fluctuation data, it was noted that regions exhibited the nest severe te=perature changes during the C fluctuation: All Regions 1, 2, 3, 4, 5, 6, 7, 9, 12, 20, 33, 34, 35, 36, ind 37. of these regions must be kept at least 60*F, 80*F, B
or 100*F below the allowable temperature limit of LCD 4.1.7 as shown
.B in Figure 1.
All other regions =ust be kept at least 35*F below the allowable limit. .
s When E N0 i:.: ine margins per Figure I are based on cycle 1 experience.
fluctuations are observed in cycle 2, the regionsAs that exhibit the differences, ' -
~
largest temperature variations may be different.if any, are observ --
accordingly. -
F 4. .The plant is defined to be in a fluctuation operating = ode when a D single nuclear channel exhibits offset deviation from the average D equal to or greater than 1" of full power reading on a cyclic basis not D exceeding a 30 minute period.
F 5. Operation and/or testing at power levels >70 should be in accordance
.D - with the 3-0 startup test program.
F 6. Throughout the duration of this RT. all plant control systa-= are to be
~
F in aut'o=atic (except for the one test with the reg-rod in =anual, see F Step 4C of the Procedure), and with MS and EUI te=perature controls set F to a m i um of 980 07.
F Note: The reason for selecting the te=perature setpoint at 980 F vs F
1000 F is to allow margin for the te=perature svings that F
occur when fluctuations develop.
LIMITS DURING FLUCTUATION TESTING Test Limits F 1. Proposed testing vill be conducted within the Technical Specification F 11=its.
? 2. Throughout the test, the intent vill be to mini =ize the time spent F
in fluctuation except when necessary to record ni data. When fluctu- -
F ations are present, the following should be observed:
F A te=perature fluctuation of0 codule =ain steam te=perature F about its mean of 1100 (20 F total a:_plitude) is acceptable F vltli n6 ' specific ti=e considerations.
F A te=perature fluctuation of =odule =ain steam te=perature F about its mean greater than A10 F (20 F total z plitude) but
~
F less than 1300F (60 F total a plitude) should not exceed one F hour in duration per event.
c 225mrw A Sheet 7 of 17
- (
F A te=perature fluctuation of module =ain steam te=perature F about its =ean of 130 F (60 F total a=plitude).is cause to F take 4-ediate corrective action by reducing power to stop F the fluctuations.
F A uni-directional =odule main steam ta=perature change of 60 F F (excluding the average co=ponent of intentional steam te=perature-F changes) is cause to take i= mediate corrective action by reducing F. power to stop the fluctuations.
F A module =ain steam te=perature of 1025 F is cause to take 4 edi-F ate corrective action by reducing power to stop the fluctuation.
E' A pri=ary coolant activity increase greater than a factor of h5 F but less than a factor of 5 over the prior eouilibrium value for F that power level is cause to take i==ediate corrective action by F reducing power to stop the fluctuations.
F 3. A limit of 110% of. full power range en any nuclear channel w4'1 be F =aintained.
i F 4. The helium purification system will be in service during all testing.
I F 5. An increase in pri=ary coolant activity levels greater than a factor of F five (5) over prior equilibrium values for hhat power level during any F fluctuation test will be cause for ter=inating the testing and proceeding F vich an orderly plant shutdown.
Corrective Action F 1. If any of the established limits or donditions outlined in ite=s 2 F through 4 above are exceeded during a fluctuation test, the test will F be ter=1nated, and further plant testing in the fluctuating mode will F be suspended until specifically authorized by PSC =anagement.
F 2. If any of the following conditions are exceeded,. 4-ediate action will F be taken to terminate the fluctuation test and further testing in F fluctuation mode will be suspended until authorization to proceed F .is obtained from the Co= mission: .
y a) Technical Specification 14-4 ts are exceeded y b)' An increase in primary coolant activity levels greater than'.
F a factor of five (5) over prior equilibrium values for that F power level. .
F c) A te=perature change of module =ain steam temperature of F 150 F relative to the initial steady state te=perature and F exclusive of te=perature change ~ due to load changes F d) A =odule m in steam te=perature which exceeds 1075 7.
F 3. If inadvertent fluctuations are observed (see page 6 for the definition F of a fluctuation) in nor=al operation, corrective action v4'1 be taken
- M -tT@ Dr 3 Sheet 8 of 17
(
F to ter=inate the fluctuation, and PSC =anage=ent authorization will F be required prior to returning to a power level that would approach F
~
- that level that the inadvertent fluctuations were observed.
INSTRU'ENTATICN/ DATA SYw!S .
Through the duration of this test, the following data systems shall D be operating and personnel should be presen; for monitcring: .
C 1. Erush recorders (located in the auxiliary control room) with all D steam generator module main steam outlet te=peratures and nuclear-C channels. A data system engineer will be present to =enitor the recorders. Both wide range brush recorders (700*F - 1100*F) and either narrow range brush recorders (100*F, :ero suppressed) or digital display by the steam generator data acquisition system will be D available to monitor the steam generator =cdule main steam outlet te=peratures.
C 2. Data logger (located in the control room). The core perfor=ance
. engineer will be present to monitor the core te=perature limiting conditions for operation.
C 3. The pri=ary coolant activity monitor (located in the centrol room).
~ d. 4. FM data acquisition system.
If any of the above systems becomes ineperable, testing shall be halted until the system is reinstated. If fluctuations are encountered when any of these syste=s is inoperable, core power shbuld be reduced until the fluctuations cease.
~~
D During power increases or pulsed circulator speed changes and for a '
.s__D_. period .of _2 hours (power increase) or_ 1jout(ci=ulat_or_ speed pulse) _
- t. ,,
following either of these system- changes, the following data systen-D f
_and. data taking frequencies are desired: r~ -
- 1. Data logger on a fast sample rate (15 seconds or less)
- 2. Steam generator Fox II co=puter on a fast sa=ple rate ( 5 seconds)
- 3. Model-verification co=puter
. 4. FM data acquisition system .
- D 5. Brush recorders .
AIt periods during the test when the initial conditions for a flue-
~
~
tuation test are being established (orifice adjustments, flow /desired.
,t,he ,following data systems and data taking frecuencies are
- 1. Data logger en a sa=ple rate of 2 sinutes or faster !
- 2. Steam generator Fox II co=puter on a sa=ple rate of 15 seconds or . I faster
. a i
RT-500 F '
'/
{ {' Shest 9 of 17
- 3. Model verification co=puter D 4 FM data accuisition system
. D 5. Brush recorders D
The traversable ther=occuples are to be positiened per RT-524.
~ ' ' T.-
PART 1: TESTING AT 170% POWER Initial Conditions F 1. Plant at approx 1=ately 40% power. ,
. . . . . . . . . . - - . .. - - - - - - - - - - - - - - -- - - =
- 2. The orifices are to be adjusted such that the regica exit tempera- ,
tures and steam generator inlet'te=peratures are reasonably balanced D per nor=al procedures and per the Coerating Considerations section i
D of this RT. '
Procedure-D 1. The objective of this test is to develop a core pressure drop vs D core flow rate (or power) stability threshold line. Thus it is D
desired to initiate fluctuations at three or more values of core
- - D flow rate. This will be done by orificing the core to different D flow resistances. Depending on the core ' flow rate at which flue-
, . _ . D* _ tuations,are initiated _in_the_first. test, higher or,, lower values D of core. resistance may be selected. To generate a reasonably good -
D stability threshold line it is desired to initiate fluctuations a:
D a lowest power level of about 40% to 505, and at abcut every 10%
D, increase in power thereafter.
D NOTES: 1. Each time fluctuations are initiated, Data Sheet 1 must
- D be completed.
l D 2. The most effective means of halting fluctuations is by l D power reduction. Experience has shown that to halt a D
fluctuation the power may have to be reduced by 5% to 10%
l D below the power level which prcduced the flue:uation.
l-D 3. Wait at leas: 1/2 hot =- to reach ther=al ec,uilibriu:n D , prior to performing any fluctuation test, wait 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> D after atte=pting to initiate a fluctuation by a load ,
D increase before continuing, wait I hour after atte=pting D to initiate a fluctuation by a pulse c .ange in circulator D sp,eed before continuing.
c e
e F
u-g@@ )f-3
- l .
Sheet 10 of 17
(
(
I D 2. For the first tes configuration, adjus: the core crifices in a series E of steps using the procedre supplied by the test : Ordinator as a guide D
to obtain an averace core pressure drop of 2.3 psi. Core resistance corres-D pending ta this ccre pressure dr p and core ficw7sta ; ay be calculated by:
tS Measured Pressure Resistance = 2.0 1013 Flow- oS - (Tin.+ 460) wher- * --asured is thec =easured core pressure drop in psi (ites 71
. i:t DF 76)
Pressure .is the circulato:- inle: heliu= pressure in psi (ite=
- 9 in DF.76) ,
Flow is the total circulator flow in Ibm /hr (item 72 in DF 76)
T. is the circulater inlet te=ceratr e in deg ees Fahrenheit (derage of ite=s l' and 2 in DF' 76) .
Verify that the regien outlet gas te=peratres have adecuate margin from LC3 4.1.7 per Figure 1 and that the S/G cedule tempera:ures are within the Operating Li=its Section of this RT befcre preceeding.
D 3. Begin a series of power rises by increasing :=bine Icad at 3% per Continue the D sinute in incremental load changes of 3% (~9 Mh'e).
- D incre= ental load increases until fluctuations develop er a plan:
D limit is reached. Prior to each incre= ental 1 cad ine ease, adjus orifices as necessary to balance region cutlet gas temperatures and nodule inlet gas temperatures. In addition, adjust the reg-rod position according to normal operations practice.
D 4' .
When fluctuations develop, there are three basic sets cf data to obtain:
It is desirable to obtain Di data during the ense: of all fluc- ,
A.
tuations.
B. For one fluctuation with each core flow resistance, cbtain FM data for one- hour during the flue:uations. The operating limits stated,.in this RT =ust be adhered to during the one-hour period.
- = _ , , , , , ,
F C. For one of the fluctuations described in Step 4B, it is desirable F to obtain FM data for an additional 1/2 hour, with the reg-rod E disabled and all rods held in a constant position. Attachment I ' '
defines the procedure for disabling the reg-rod. The operating limits stated in this RT must be adhered to during fluctuations.
The Core Perfor=ance Engineer will coordinate which particular fluctu-C ations will be monitored per ite=s B and C above.
C r_m -@ **9-
1
C RT-500 F
( -
(, Sheet 11 of .17 1
I l
D -5 . Tor each fluctuation encountered, repeat the step preceding the flue-F tuation and,.if fluctuations are not encountered, that step which D -
caused the fluctuation. For exa=ple, if fluctuations are encountered D. during a power rise from 50% to 53% power, return to 47% power and F I'epeat the 47% to 50% power rise. If no fluctuations occur, then D repeat the 50% to 53% power rise. ',
When a fluctuation thresheld has been defined per steps 2 - 4, return D 6.
a tot the highest pcwer level for which a fluct'.:stion was not initiated D (47% in the above n=Tl e). perform part II of RT'-499, the circulator D speed pulse test, where the pri=ary coolant flow is increased by 3%, held at the higher value for a short duration ( 10 seconds) and returned to its initial level. If fluctuations are not initiated, '
D D
D increase pcwer by 3% at 1/2's/ninute and repeat part II of RT-499, the D circulator speed pulse test. Continue until fluctuations are encountered -
D or until a power level 9% above the caxinum f em step 4 is achieved ,
D (until 62% in the above exa=ple). --
g D 7. Repeat the circulator speed pulse test (part II of RT-499) for the F step preceding the fluctuation and, if fluctuations are not F encountered, that step which caused the fluctuation.
F 8. The next test power level depends on the power level at which fluctu-F ations were encountered in Step 5 above. The objective is to initiate F fluctuations at power levels approximately 10% apart; that is, at
__ F about 40", 50"., 60% and 70% power. For the selected new power level D the next value of core resistance can be calculated from the conditions D which initiated the preceding fluctuation as follows: .
. . _ . . _ . _ . __ --__.m._ _
IyOLD \2 R "
D, NEW l
l OLD (FNEW/
D where ROLD is the resistance from the preceding test F' F is the core flow rate from the preceding test (step 5)
OLD --
F F is the flow rate corresponding to the power level where tbynext fluctuation is desired.
.F .
D 9. The starting point for the next test is with the core orificed to achieve thE l F'. new core resistance, Rygg, per the ec,uation given in step .2, and with a core D pressure drop 10% - 20% below that at which the preceding fluctuation was ini-D tiated. In getting to the new starting point, it is desired to keep the core D pressure drop at or below the value at ~which the fluctuation test will be D started to prevent inadvertent fluctuations. To do this it is suggested that:
A. uce fl w e re e sing e M ees.
D If R*EWh > ROLD, r D B. IfR.jy<ROLD, y pen ri ices before increasing flev t
'~ ~
_7 T..
~
.. RT-500
(' S* ' 3t 12 of 17
- \
p 10. Repeat steps 3 - 7 to obtain data for at least 3 values of core re- '
sistance.
To generate a reasonably accurate stability threshold, D fluctuations should be initiated at a lowest power level of about D 40 - 50% and at incre=ents of 10% power above this initial level.
D .
Depending upon the effect of refueling on the fluctuation threshold, ,!
D it =ay be necessary to vary attemperation flow (core P/F),(power region D outlet te=perature mis =atches, or partially inserthigh control powerrods
?
D 'k D ... levels.
flattening) in order to de= castrate the threshold atAny ore..all of t D Caution shoul.d_.be exercise.d t_o _ _ .
SCP,s and Tech.ni. cal S. pec. ifi_c__ations.
!=aintain the region te=perature margins for L.C.O. 4.1.7 given in - ~-
ShE uigure 1 and to not violate the core ther=al safety limit on core *l
..T' eF Power / flow ratio (S.L. 3.1, Figure 3.1-2) _
= ._ . . . . _ . , , , _ _ ,
_ _ . . I D If the pulse change in circulator speed test fails as a. " trig Q D necessary to continue atte=pting to initiate fluctuations via this l D t D cechanism. i e
i Part 2: Testing at >70% Power _ i D .
Frc= an initial steady-state condition of '70% power, the core power If no ili:cd.
D D
D will be increased slowly (1/2% per =inute) to ~73% and stabflu :
.D and a pulse change in circulator speed will be e= ployed to atte=pt toIf fluc D initiate fluctuations.
at 3% per minute will be effected to atte...pt to trigger fluctuations. '
D D
This process of slow power increases, circulator speed pulses, and then w D rapid power increases of 3% will be limit continued until fluctuations is encountered. If flue- are en-
,.' D countered or until 100% power or a plan: f time and the D
tuations occur, data will be recorded for a short period o D
step which initiated the fluctuation will be repeated to establish repro- -
ducibility of the onset of fluctuations.
D .
D Initial Conditions M c W s W.%. 4.M r =3:-*r+. m .J.y#5r,. Q
-~" - .
P 1. Plant at approxi=ately-.
70\ power. Jg. _1 . ,
2.
The orifices are to be adjusted such that the region exitdte=peratures per D and steam generator inlet te=peratures are reasonably balance f D nor=al procedures and per the coeratine Consideratiens_ section o D
D this RT. .
D Procedure _
1.
The objective of this test is to extend the core pressure in drop vs D core flow rate (or power) stability threshold line developed D
D Part 1. .
1.
Prior to each incre= ental load increase, adjust orifices as NOTES:
- D necessary to balance region outlet gas te=peratures andIn ad j D module gas te=peratures.
D position according to nor=al operations practice, D
i e a 90 4
RT-500 17 [
i
]
[ Shee(r 13 c:, l 2.
The most effective means of halting a fluctuation is by Experience has shown that to halt a
. ~
) to 10%
power reduction.
) fluctuation the power may have to be reduced to 5'6 O below the power level which produced the fluctuation. 1 =ust 0
3.
Each time a fluctuation is initiated, Data Sheet (
D be completed. bl i) 4.
Wait at least 1/2 hour to reach ther=21 equilibrium i
@ prior to performing any fluctuation test, wait d 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> [p [l D after- atte=pting to initiate a fluctuation by a loa (
increase before continuing, wait 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> after a D
D tot s
D speed before continuing. [I D in a series' : .*
2.
For the first test configuration, supplied adjust thetest by the core orifices as a guide coordinator D least 10% below .the threshold l E of steps using the procedureto obtain an be average calculated by corethe pressure drop I ;
l D AP determined in Part L for 70% power. i to this core pressure drop-and core flow rate may D
D equation given in Part 1 procedure step 2. i steam ten-f D :
setpoint, '
D perature =ay be reduced to 40'F below flatten the power .distri-
=peration the reh D core control rods may be partially inserted (to [/
D bution and thereby permit further opening of orifices), or attel Specifica <i D flow may be increased within the limits _
, ,of _ SCPs
_ _ _ and Technica i
D to further reduce-the core pressure drop.
_D gin are D Verify that the region outlet gasroceeding f temperatures to ha D within the Operating Limits Section of this' RT be ore p D the next orifice changes.
D If fluctuations '
D 3. Increase power by 3% (~9 MWe) at 1/2% per =inute.If fluctuations are no do develop, go to step 6.
D D
power by ~3% to achieve initial conditions once again. h the Perform Part II of RT-499, the circulator speed ih pulse value test, for w ere
- 4. initial level. If D
D primary coolant flow is increased by ~3%, held at the h g er D a short duration (~10 seconds) and returned to its fluctuations develop, go to step 6.
D by 3% at If fluctuations Ifare not initiated by step 4, increase If fluctuations power level D S. fluctuations develop, go to step 6.
3% per minute.
D do not develop, repeat steps 3 through Continue 5 starti:ig with at the successively new power higher
% power or a D ('3% above the preceding power level).
D D
power levels until fluctuations do develop or until 100 D
plant limit is encountered. obtain:
6.
When fluctuations develop, there are two basic sets fluctuations.
of data to D
A.
It is desirable to obtain D1 data during the onset of all D
B.
For one fluctuation with each core flow resistance, obtain RITh D id s D data for one hour during the fluctuations. stated in this R D
=====- - - - - - _ _ '--m-.-- _
u l RT-500 F I, , ' -
e.
(; hest 14 of 17 i
.- ( ._ .
D The Core Performance Engineer will coordinate which particular fluc-L D tuations will be monitored per item 3 above. .
D 7. For each fluctuation encountered, repea the step (load increase or D circulator speed pulse change) preceding the fluctuation and if no fluctu-F. ations occur, that step which, caused the fluctuation,,,For era =ple, if F
fluctuations ~are"encounterbE d'u iing p. power' risa',froS 73% to' 76% power, re-
~
F turn. to 7D power and. repeat. the 70% to- 73 power rise then if no .
F, fluctuations occur,. repeat' the 73" to 76% power rise."
D Si=ilarly, if the circulator speed pulse changes initiated fluctua-D tions, then repear the circulator speed pulse tes: (Part II of RT-499)
D for the step preceding the fluctuation and that step which caused .
D the fluctuation.
D S. After de=enstrating repeatability, reduce power and re-establish D a stable plant configura:icn. If fluctuations were first initiated D by the 1/2% per minute load increase (step 3), then establish the D initial conditions preceding initiation of flue:uations and perform the D circulator speed pulse test, step 4. If fluctuations were first D initiated by the pulse change in circulator speed (step 4), then D
~
establish initial conditions preceding initiation of fluctuations and D effect a.3% load increase at 3% per minute, i.e., step 5. If fluc-D tuations were first initiated by the 35. per ninute load increase D (step 5), proceed to step 9.
- D 9. The next starting point is with a primary flow rate (power level)
D 55 - 10*6 above that of the preceding statting point but with the
~
D sa=e core pressure drop. This =ay be achieved as before, by opening D the orifices to a new value of core resistance. .
.D Partial rod insertion =ay be e= ployed to per=it further opening of D orifices and/or the main steam temperature set point may be reduced to D 40*F below the reheat te=perature setpoint to reduce core pressure D drop.
D' To guard against inadvertent fluctuations, the orifices should be D opened before increasing flow.
D 10. Repeat steps 3 - 5, at successively higher power levels, until 100%
D power is reached or until a plant limit is encountered.
O g t
9 V
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. i, , . ;
, (,. RT-500 Sheet 15 of 17
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{ ( 'heet 16 of 17 ATTACHMENT I REG-RCD INFLUENCE TEST
' D The purpose of this test is to deter =ine if taking the reg-rod out D of auto will reduce the amplitude of the fluctuations and to obtain data D from the out-of-core and in-core nuclear channels which are responding to D the influence of the fluctuation phenomenon alone, without the co= plicating D effect of reg rod motion influencing the signals. The procedure is as D follows:
- 1. After a fluctuation has developed, monitor the amplitude of the module MS temperature fluctuation to verify that the Operating 'i-its of this RT are met. Previous experience with fluctuations indicates thar the a=plitude may be reduced by slowly reducing power and thus allow a longer time in fluctuations.
- 2. - Disable the ability of the flux controller to move the reg-rod by placing the rehest temperature. controller in manual and then rotating the regulating red selector switch (HS-1218) to the Crr position.
This permits the automatic flux control to initiate a rod runback if needed as a result of any transient during this test. If necessary, manually position the reg-rod to the average position that existed
- prior to disabling the automatic control feature. This step is desirable in order to maintain a constant value for total reactor power and average core temperature.
CAUTION: If a runback occurs, the reheat te=cerature controller should be nulled out and returned to automatic and MS-1218 returned to the #1 position as soon as nossible.
D 3. Wait a period of approxi=ately 30 minutes to determine the effect on fluctuations. Control room trend recorders and brush recorders are to be used for this purpose. Return the reg-rod to auto by return-ing MS-121S to the il position, null out reheat temperature controller, and return it to automatic.
e O
.i RT-500 7
- ~ *!
{ .
(- Sheet 17 of. 17 (Completely Revised DATA SHEET I 3y gey, g)
This data sheet Complete this data sheet if fluctuations were encountered.
is to certify that test limits were not exceeded, A. If any of the followino limits are exceeded, testing must_
be stocoed until further autnorized oy PSC Management. Limit Were OPERATING CONSIDERATIONS _1,253 met? YES /NO N/A
- 1. "
N/A ,
- 2. Time / Data fluctuation started N/A
- 3. Power Level at start of fluctuation ,
1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />
- 4. Time /Date power reduced _
Time /Date fluctuation stopped N/A 5.
N/A
- 6. Power Level when fluctuation stopped N/A
- 7. Maximum fluctuation on Nuclear Channel !
Peak Magnitude r $7
- 8. Maximum fluctuation of Loop I MS Temp Module i N/A Fluctuation Magnitude goop p.p Hottest Module f *F 1025'F -
Maximum Fluctuation of Loop II MS Temp Module # N/A
. 9.
Fluctuation Magnitude 60*F P-P Hottest Module # 'F 1025'F
- 10. Equilibrium Value.of Primary Coolant Activity for N/A power level of test
- 11. Maximum Yalue of Primary Coolant Activity During 25% increase test
- 12. Were Data Systems in service? YES /NO h h ' ICI Required for 13 Was a purification train in service?'YES /NO-Testing
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j B. For any of the followinc testine must be stoceed and .
i recorted to the NRC:
Any Technical Specification exceeded? YES / NO -
1.
Any MS Temperature Fluctuation > 150*?- YES / NO
- 2. '
Primary Coolant Activity >5 times normal? YES / NO .
l 3.
I This requires an i=ediate orderly shutdown.
PSC SHIFT SUPERVISOR SignaturelDate i TEST CCORDINATOR Signature /Cate
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