ML19290C989
| ML19290C989 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 01/08/1980 |
| From: | CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.) |
| To: | |
| Shared Package | |
| ML19290C988 | List: |
| References | |
| ADM-27, RT-500H, NUDOCS 8002150292 | |
| Download: ML19290C989 (23) | |
Text
fh{
- s..
AT"'vW7vr 10.9 Fort 6 1 rad" #1 Sheet 1 of 7 ADM-27 Ravision No. 3 TIST CONTROL RECORD Page 42 of 48 Test Raf. No.
RT-500 Rev. 4 (GA lasue H)
System Raf. No.
12 70RT ST. VRAIN NUCLEAR GENERATING STATION Page 1 of 23 REOUEST FOR TEST' Prepared 37:
M M /,b M J
// - u. -9N f
Dace
/A //, -7!
Reviewed By:
3d[A J'
Date I
original Issua Reviewaa, PORc #
Poac 3J 8 96T 4 6 WA Dace s/
A
/0 !/0!7f Data Safec7 Significanc:
Tes No 2 NFSC Review-RECORD AND CONTROL OF Rm SIONS Approved & Issued Rev.
Prepared 3y PORC Approval Effective Date of No.
Revision
_.3 0 ! MAY 1 0lb7 M N do b9 1
. M ED A 2 FRES:,, #Esa-&2 2 AUG 2 0 E7t h 7/7o/11 l
2
[f h //,
i:c 3 3 0 0CT1519E Nh
,o/f </97 l
3
/
d t c.4 PORC 3 4 2 JAI! 9 h8C "Mh_
i [/!fd l
a 5
l 6
7 Complaced Tast Reviewed:
8002150 -2f&
Superincancent, Operaticus (or designee)
.. ?.? N s.b__YY.,
b _ _2 3 ]
HAW [05"I?
\\
Ecr: Sc. /:sia 7.
ATTACEME'." 10.9 ADM-27 Rerision No. 3 Page 42 of 48 iheet 2 of 7 RT-500 (Revision 4) l !a=pora(N,A Issue H)
G
?ROCEDi!RE CHA'*GES:
?er=anen:
l ge 2 of 23 DESCRI?!!ON. tid REASON FOR
? AGE 'io.
CE.C.'GE OR DEV!ATION SA?E"~i E~lAL'1ATION I
i I
i AF?ROVALS:
Plant Managemen: Staff (Senior License)
Date
?lant Manage =en: Staff Date NOTICE TO TEST C O N D UCTO Rl
~
,,,,.ci_.,,,.,,...A_
,.. 1 >
3_,,
i _..,...
., D n. n,,_.
.. i
..O..__,,e...
,A..-
,A.
dawin...s.---..._..,
.,v-..
c
..w
.t uu..... t t
.u v.
m=e.o =..=.=. e...d v e.
. e.n. 2. 5.r s e...n.=.
.n.os -.
.. ~
ACAEME:TE 10.9 Fort St. Vrain 11 Sheet 6 of 7 ADM-27 Revision No.
3 Page 47 of 48 RT-500 Rev 4 Test Ref. No.
SystesRef.No.{GAIssueH) 2 Recuest for Test - Sheet 5
- 10) TEST EQUI? MENT (If required)
Last Calibration Na=e Identification Nu=ber Date 1L) TEST CONDUCTOR (Include all assistants)
Fer=issica to initiate test Shift Supervisor Date
- 12) ?RCCEDURE (See attached pages):
A m CE4ETT 10.9 Fort St. Vrain 11 Sheet 7 of 7 ADM-27 Revision No. 3 Page 47 of 48 Test Ref. No.
RT-500 Rev 4 (uA issue H)
System Ref. No.
12 Recuest for Test - Sheet 6 13 ) 7ERITY THAT TEE SYSTri HAS 3EET RETU'UED TO NORMAL:
s/ Shift Supertisor Date
- 14) TEC'HICAL SERVICES ACTION:
10 CFR 50.59 Report Required: Yes No Tech Spec Report Required:
Yes No Reviewed 'oy Signature Date O
e
RT-500-H GA RT - 500 Revision H Sheet 1 of 19 POT REF M
Eage 5 of 23 U
REOUEST FOR TEST ISSUED l2-$l~lf REQUESTOR K. Asmussen/W. Simon SYSTEM 12 D
PURPOSE /0BJECTIVE - There are two main objectives of this test:
D 1.
To deter =ine the fluctuation threshold in tems of core pressure drop vs flow H
(power) for cycle 2 operation af ter installation of region constraint devices.
D 2.
To obtain FM data during fluctuations with the revised instru=entation syste=s E
for comparison with cycle 2 data without region constraint devices.
C DESCRIPTION OF TEST - With the plant in normal operation, core orifices will be D
adjusted to achieve a specified core pressure drop. Load increases in =3% steps D
and pulse changes in circulator speed of -3: will be used as trigger =echanisms D
to induce fluctuations and to determine the fluctuation threshold in ter=s of core b
pressure drop as a function of core flow race (power level). If a fluctuation D
occurs, the step causing the fluctuation will be repeated to de=enstrate repeat-D ability. Atte= pts to initiate fluctuations will be performed first at 40% power D
and then at -10 intervals so as to provide a good definition of the stability D
enteshold line. Part 1 of the test encompases testing at 170: power while Part 2 C
refers to testing at >70% power. For at le==t one fluctuation, if fluctuations C
occur, FM data vill be obtained with the reg-rod held in a constant position.
E Revision E incorporates PSC co==ents on Revision D.
F Revision F incorporates NRC co==ents on Revision E.
G Revision G incorporates a revised definition of a fluctuation and increases the estimated time spent in a fluctuating =ede.
These revisions are based on experience gained from RT-300F testing at 40% and 50% povt.r.
H Revision H provides for fluctuation testing with the Region Constraint Devices H
(RCD's) installed, ANTICIPATED RESULTS/ ACCEPTANCE CRITERIA - The test will provide data to aid in D
predicting conditions for stable operation. Additionally, the test will demonstrate H
the effect of RCD's on fluctuations, and data will be obtained which will aid in D
understanding the fluctuation phenomenon and for comparison with previous cycle 2 D
observations. There are ne specific anticipated results or acceptance criteria.
REF SOP OR A3 NORMAL CONDITICNS - SOP 12-04 SCHEDULE REQUIREMENTS -
SAR & APPROVAL SHEET ATTACHED N
N lch c2Os '7 h WORK ASSIGNED 3Y
.m TO V
NamelDate EVALUATION CCMPLETED Name/Date REVIEWED BY Na=e/Date Distribution:
K. Asmussen W. Bushnell E. Hill A. Kennedy F. Mathie _R _?hel s G. 3rs=blett W. ::ane' J. Lopes R. NirschNL.j2ih Requestor GA-3D Ref. Library
This SAR is in Support of RT-500H
- nd is encloted as Par,c 2
of 17 of t. Lac RT, even thougn tse SAit la a ocparate Uncouttallca Documcut.
RT-500 Rev. H Sheet 2ofIf GENE *' V AT0l'IC c' :T.. il Page 6 of 23 TORT ST. VRAI!: 1.TCLIAR CC;E?aTING STATICN SAFm i "" LYSIS RI? ORT 1.
INITIATIIIC 00CT!I O:
RT-500 Revision H YES NO 2.
CATECCF.Y:
71 ANT CitA::CI L x_1
'DCCUMI::r CnANCE c:tLT CLASS I X
MAI2iTCIANCE I
SAFE SHUIDO*.?N C.CCLING W
3.
FAILUT2 MCCES ATTIC ID X
TEST W 4.
SAFE Y Ti!.ATID CO"?C!TT.:iT, N
FOR,-
_m~.. S CL._',,"dE BASIS -
ST/CE IN !!IM 10 :
SYSTDi OR Sir.UC Li.:. CHANCr.
.,CD 5.
SAFEU SIC';I7ICA:T CE.UICE W
6.
UNREVID ID SA.::..; QUESTION LX_!
7.
TECH SPECITICATICli CHA:!CE W
f, FSAP. CE.UICI X
9.
A??LICAILE FSAR OR TICE S?IC SICTIC:lS"RIVIE;?ID: T'.S. I.C0 4.1.4 AND LCO 4.1.7 10.
BASIS TCR SAFI""? EVALUATICN: (Add additional Sheets if Required):
During this test, operation vill be within Tech Soec and desien limits. The test is perfor=ed to investigate the influence of Reeion Constraint Devices on the threshold for fluctuations, and although they might be encountered, the time at fluctuation would be minimal. Consequently, any fatigus damage to the core and/or steam generators would be negligible. Main steam te=-
perature fluctuation limits have been set accordingly. In addition, through-out the test, sufficient margin vill be maintained between the Tech Spec 11=1t and the region exit temperatures so that even during the most severe fluctuation obseried to date the Tech Soec limits will not be violated.
(See Figure 1.)
Although there vill be a ceriod of time that the ree-rod is disabled and not responding to the auto flux teontinued en attached sheet) 11.
IS CC: DIICO SATIU A::ALYSIS/LICI': SING TCVID ?IQ"IRIJ? YES
- 0 [TT 12.
EAS SAN DIICO SATI-"i A';ALYSIS/LICI::SI' '; ?.1.~ lip; III" ?'""CRMID YIS NO
/2[/7!7[
13.
M[M [baA / 7 // 7 /7 o INITIATC.'/0AII LICI/;S!NC/DA!
d 14.
CAC C CR. T.IVIC?/DISTCSI!!C:::
(', */ aeM ta> r TW
'7N E A46YE bhFGTV hl Uk/7%/.
lb 't
/c2,/h N D C'it/0 ATE T0'U1: SAR 4/77
Kr-500 H Sheet 3 of 19 Page 7 of 23 10.
BASIS FOR SAFETY EVALUATION (continued) control system, test procedures will assure any required rod runbacks will take place and will produce the subsequent desired reactor power control.
Therefore, this test will not adversely affect the integrity of the core or steam generator and will not affect public safety.
Since first being encountered on October 31, 1977, fluctuations have been initiated several ti=es in a continuing effort to understand their cause. The power levels at which fluctuations were initiated have ranged H
from 30% to 68%. A total of 65 hours7.523148e-4 days <br />0.0181 hours <br />1.074735e-4 weeks <br />2.47325e-5 months <br /> was spent in a fluctuating mode in H
Cycle 1 and another 41 hours4.74537e-4 days <br />0.0114 hours <br />6.779101e-5 weeks <br />1.56005e-5 months <br /> in Cycle 2.
This is equivalent to about 640 E
Cycles with an average period of about 10 minutes.
Although the cause of the fluctuations is net known, there are several reasons for concluding that contir.ued testing is safe. The total core power, C
flow, and average temperatures are relatively stable. An inspection of the top plenum in Dece=ber 1977 af ter fluctuation testing at power levels be-tween 53 and 68%.hoved it waa in good condition. An ir.apection at that ti=a of the control rods in region 34 (which were inserted throughout the entire period of fluctuation testing) aise showed no signs of excessive D
te=perature or i= pact. During the first refueling outage, eleven blocks D
from region 35 were carefully inspected in the PSC hot service facility and D
there was no evidence of damage. An in-core inspection of region 35 and its D
surroundings with the fuel handling =achine T.V. camera revealed no damage D
or excessive wear to any ce=ponent. The upper plenum area looked fine; the D
gaps in the regions and sido reflector surroanding the cavity left when D
region 35 was unloaded were very regular with no evidence of vear or damage.
D.
An inspection of the core support blocks in regions 13 & 35 have.likewise D
revealed no da= age.
D Every ele =ent re=oved from the core during the refueling of six regions D
has been photographed as has each block in five additional regions which D
were unloaded to permit installation of ecst asse=blies. Examinations of D
these photographs have revealed no damage.
H Fluctuations have been initiated and observed on seven (7) occasions a
'during Cycle 2 at power levels between 38 and 63%. Four (4) of thest were H
initiated by power increases and three (3) co==enced during orifice valve H
adjustments. The data from the in pile test program has demonstrated that H
while the fluctuatienc encountered during Cycle 2 appear to be somewhat more H
regular and widespread throughout the core, it is basically the same pheno =-
E enon experienced during Cycle 1.
H Eighty-four Region Constraint Devices were added to the top layer of H
hexagonal ele =ents (keyed plenum elements) during the October and Nove=ber H
outage. These =echanical links are placed at locations in the core where H
3 regions intersect and will provide inter-region keying and preclude the H
accu =ulation of large sized gaps which might result if several regions are H
displaced in the sa=e direction. These have been installed to provide a H
per=anent solution to the core te=perature fluctuations that have previously H
occurred.
RT-500 E Sheet 4 of 19 Page 8 of 23 H
The installation of the Region Constraint devices is expected to have no H
1mpact on the nuclear design or projected nuclear performance of the core.
D Testing Above 70% Power (Part 2)
D Since fluctuations were first encountered, tests have been conducted D
under various core conditions. In large part, these tests were designed to D
gather specific infor=ation on what key parameter or comoination of para-D ceters leads to the fluctuations, since this knowledge could be instru= ental D
in understanding their cause. These tests have shown fairly conclusively that D
power level is not by itself a parameter of pri=ary i=portance to the fluctua-D tion threshold, and they have established core pressure drops as a key para-D
=eter, probably closely related to the cause of the fluctuations. Another D
result from these tests is that it appears that the core pressure drop at which D
fluctuations are produced is higher at higher core power levels.
D Differences in fluctuation magnitudes and character have been observed D
in the fluctuations that were initiated during Cycle 1 and Cycle 2 operation.
D These differences have been carefully studied and reported extencively. No D
apparent correlation with power level has been noted, nor has a change been D
observed with ti=e that would indicate increasing fluctuation =agnitudes or D
significant differences in dharacter. All of the fluctuation testing limits D
and operating considerations as well as normal plant technical specification D
limits and SOPS are in e'.fect both below 70% power and above 70% power. One D
excaption is the limit au nuclear detector fluctuations. This 11:1c is in-D creased from 10% at <70% power to 20% for >70% power. This increase is just-D ified because nuclear channel fluctuations are believed to be due primarily D
to a streaming effect 2nd are thus expected to be nearly proportional to the D
power (neutron flux) level. In this test, fluctuations will be initiated at D-successively higher power levels. The =agnitude and character of the fluc-D tuations at each power level will be carefully observed for differences in D
addition to scnitoring the Technical Specification and fluctuation testing D
limits. Consequently, testing above 70% power will not affect public safety.
Time Spent Fluctuating H
It is anticipated that no additional temperature fluctuations will be H
encountered with the RCD's installed. The purpose of this test is to demon-H strate that fact or to determine what i= pact their installation has on the H
fluctuation threshold. In the event that fluctuations are again observed, H
it is anticipated that operation in the fluctuating mode would be limited to H
about 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br /> for co=nletion of part 1 (< 70*. power) and another 10 hours1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> H
for part 2 (70% to 100% power). This is based on previous test operating H
experience. It assu=es that fluctuations are initiated from 2 to a times at H
3 power levels or core configurations during part 1 and another 2 power levels H
or core configurations during part 2.
RT-500 'd Sheet 5 of 19 PREFACE Page 9 of 23 Revision A acco. plished the following changes:
(1) The Operating e
I.imits Section was redefined to incorporate limits required by the NRC.
(2) The re=ainder of the previous limits were redesignated as Cperating Considerations.
(3) The equation for core resistance was redefined to better fit observed operating data.
(a) Addendum I was added to deter-sine the fluctuation threshold at 23% power.
Revision B acec=plished the following changes:
(1) The 10% limit 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 =edule outlet temperatures and all six nuclear channels; the steam generator temperatures will be sonitored both by wide range brush recorders (700*F - 1100*F) and by eicher narrow range brush recorders (100*F range, :ero suppressed) or digital display of fluc-tuation sagni:udes from the steam generator data acquisition system.
(3) The limit on =cdule main steam te=perature a which testing is sus-pended until authori:ed by PSC canagement is increased fres 130*F to 150*F.
(4) In Figure 1, the region temperature missatch margin for region 12 is increased to 100*F.
(5) The instruments to be =onitored by the : rend recorders are not specified: any four thought to be of =est use may be trended.
(o) A two hour waiting period between luctuation :ests is specified.
t Revision C accomplished the following changes:
(1) Corrective action is to be taken to s:cp the fluctuation if a :odule main steam tem-perature reaches 1025*F.
(2) Editorial changes were made to the other limits on =odule =s.n steam temperature. (3) The test team members respon-(
sible for conducting the test are specified.
(4) The physical location of the data systems to be monitored are specified, as are the respective team = embers responsible for monitoring thes.
(5) Figure 2 of Addendum I has beer " cleaned up" and updated to reflect the current actual locations for thr. =ccouples 3, 4, 5, 7, 19, 23, and 25.
(6) In Figure 1, the regien te=perature mismatch margin on regions 17, 13, 25, 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 and the total ti=e spent in the fluctuation mode has been reduced. However, the basic test philosophy and the limits during fluctuations remain un-changed.
(2) RT-502 (Threshold Testing >70*. Power) has been incorporated as Part 2 of this RT.
(3) The objectives of the :es have been modified to reflect testing during cycle 2 (for comparison with cycle 1) with the e=phasis on gathering data to aid in predictin;; conditions for stable operation.
(4) Addendum I of RT-300 Revision C has not been repeated here because it was successfully completed during cycle 1 testing.
(3)
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).
Revision I incorporates co=en:s from PSC to delete the detailed crifice adjust _.ent procedura, update Data Sheet i to include a
'4-4 s and other minor co==en:s as coted is the lef: =argin.
Revision F incorporates co=ents from NRC as noted.
(
RT-500-H Sheet 6 of 19 Page 10 of 23 Revision G incorpora*es a revised definition of a flucutation and increases the estimated ti=e spent in a fluctuation mode. These revisions are based on experience gained from RT-500F testing at 40% and 50% power. The increased time is the result of approxinately 15 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br /> spent in a fluctuation mode during com-plation of the first half of RI-500F.
Revision H provides procedures for fluctuation threshold testing up to 100%
reactor power af ter installation of the RCDs. In essence the test is a contin-uation of that previously performed in Cycle 2.
After establishing the core con-figuration for which fluctuations were initiated at the lowest power level during previous Cycle 2 operation, an attenpc will be =ade to initiate fluctuations by a power level increase. The power level will be increased incre=entally up to 70%
and if no fluctuations are encountered, the power level *111 be reduced to 40%,
and the core ap increased by adjusting the orifice valve opening. This will be repeated until a stable power operation at 1. power level of 70% with a core ap of about 4.5 is achieved or a fluctuation threshold established. Part 2 would be a continuation of this operation up to 100% power. Other than the method for deter-mining system operating lines, the condirdons and controls of this test are the same as those for the previous RT-500G. Test prerequisites, administrative con-trols, system and operating ifmits, and reporting requirements are all unchanged.
RT-500-H Sheet 7 of 19 Page 11 of 23 INTRODUCTION D
The collection of data from all Cy:le 1 cora fluctuations indicates a distinct influence of core op on the threshold for fluctuations. However, D
the Cycle 1 data shows a lot of scatter and fresh fuel has been loaded into D
six regions of the core; therefore, fluctuation threshold testing at the D
beginning of Cycle 2 is necessary.
H This RT will determine the effect of RCD's on the flucutation threshold D
as a function of core pressure drop for Cycle 2 (with a procedure aimed at D
minimizing the a=ount of scatter in the data). The Di Data System now includes D
24 traversable ther=occuples, PCR7 displace =ent probes and magnetometers for D
attempting to monitor core barrel motion, and two instru=ented control and D
orificing assemblies having in-core instrument packages. These data will be D
collected during fluctuations to aid in predicting conditions for stable oper-D ation and in understanding the fluctuation phenomenon.
D The expected methods for triggering a fluctuation will be a 3% load increase D
at 3% per minute and a pulse change in circulator speed sufficient to produce -3:
D increase in flow. If a fluctuation develops, the steps preceding and resulting D
in the fluctuation will be repeated to 4-monstrate repeatability and to provide a D
reasonably accurate determination of the threshold power.
The cast scope includes atte= pts to induce fluctuations for at least three D
valves of core flow resistance.
Testing will be conducted by the coordinated efforts of a test taan consisting of, but not limited to, the following members:
1.
PSC Shift Supervisor 2.
PSC Reactor Operator (s)
D 3.
Test Coordinator D
4 Core Perfor=ance Engineer D
5.
Data Systems Engineer F
The NRC will be provided, within one week, with a s m ry of test results for F
each power level. Included with these results will be notification of any change F
to the procedure as a result of the test results.
OPERATING CONSIDEPATIONS In addition to the nor=al plant operating procedures and limitations, the folicving should be observed:
1.
The HRH and MS te=perature i= balance between each SG :odule and C
the average for the loop should not exceed 30 F (in steady state)
C or the limits given in SOP 12-04 whichever are = ore restri tive.
In addition, the
- individual module MS steady state temper-m ature should be 11=ited to 995cF. The purpose of the 9950F linit is to provide nargin on MS te=perature when fluctuations occur.
2.
Steady state =edule helium inlet te=perature shall be limited :o 1450F about the mean or the li=its given in SOP 12-04 whichever are = ore restrictive.
RT-500-H Sheet 8 of 18 Page 12 of 23 D
3.
La order to minimi:e the chance of getting into a degraded perfor-mance condition during fluctuations, the maxim m region outlet gas temperature during steady state conditions shall be limited as follows:
Fror previous fluctuation data, it was noted that the following core regions exhibited the most severe temperature changes during the C
fluctuation: Regions 1, 2, 3, 4, 5, 6, 7, 9, 12, 17, 20, 33, 34, 35, 3
36, and 37.
All of these regions must be kept at least 60 F, 800F, 3
or 100 F below the allowable temperature limit of LCO 4.1.7 as shown in Figure 1.
All other regions must be kept at least 350F below the allowable limit.
E NOTE: The margins per Figure 1 are based on Cycle 1 experience and have H
preven to be adequate for previous Cycle 2 testing.
G 4
The plant is defined to be in a fluctuation operating mode when G
individual nuclear channels exhibit cyclic deviations from the G
average power equal to or greater than 0.5% peak-to-peak of full G
power not exceeding a 30-minute period.
F 5.
Operation and/or testing at powar 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 systems are to F
be in automatic (except for the one test with the reg-red in manual, F
see Step 4C of the Procedure), and with MS and ERH te=perature controls F
set to a :: x1=um of 980 F.
a F
NOTE: The reason for selecting the te=perature setpoint at 980 F vs 1000 F is to allow margin for the temperature swings that occur when fluctuations develop.
LIMITS DURING FLI'CTUATION TESTING Test Limits F
5 Proposed testing will be conducted within the Technical Specification F
li=its.
F 2.
Throughout the test, the intent will.be to ninimize the time spent in F
fluctuation except when necessary to record FM data.
'4 hen fluctuations are present, the following should be observed:
F A temperature fluctuation of module main steam temperature F
about its mean of 110 (200F total amplitude) is acceptable F
with no specific time considerations.
F A te=perature fluctuation of module main steam temperature F
about its nean greater than +10 F (200F total amplitude) but F
less than 330 F (60 F total E plitude) should not exceed one F
hour in duration per event.
RT-50C4 Sheet 7 of 4 Page 13 of 23
,.F A temperature fluctuation of =odule main steam te=perature F
about its =ean of 130 F (60 F total amplitude) is cause to F
cake i==ediate corrective action by reducing power to stop F
the fluctuations.
F A uni-directional module =ain steam te=perature change of 60 F F
(excluding the average component of intentional steam temperature F
changes) is cause to take i==ediate corrective action by reducing F
power to stop the fluctuations.
F A =odule -Mn steam te=perature of 1025 F is causa to take i==edi-F ate corrective action by reducing power to stop the fluctuation.
F A pri=ary coolant activity increase greater than a factor of 257.
F but less than a factor of 5 over the prior equilibrium value for F
that power level is cause to take i==ediate corrective action by 8
reducing power to stop the fluctuations.
F 3.
A li=1t of 110: of full power range on any nuclear channel will be F
=aintained.
F 4
The hel*.um purification system will be in service during all testing.
F 5.
An increase in pri=ary coolant activity levela greater than a factor of F
five (5) over prior equilibrium values for that power level during any F
fluctuation test will be cause for ter=inating the testing and proceeding
-F with an orderly plant shutdown.
Corrective Action F
1.
If any of the established HM ts or conditions outlined in ite=s 2 F
through 4 above are exceeded during a fluctuation test, the test will F
be terminated, and further plant testing in the fluctuating = ode will F
be suspended until specifically authorized by PSC =anagement.
F 2.
If any of the following conditions are exceeded, i==ediate action will F
be taken to ter=inate the fluctuation test and further testing in F
fluctuation =ede will be suspended until authorization to proceed F
is obtained from the Co==1ssion:
y a) Technical Specification li=1ts are exceeded.
p 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 te=perature 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 module -Mn steam ce=perature which exceeds 1075 F.
F 3.
If inadvertent fluctuations are observed (see page 8 for the definitien F
of a fluctuation) in nor a1 operation, corrective action will be taken
RT-500H Sheet lC of 19 Page 14 of 23 fF to terminate the fluctuation, and PSC =anage=ent authorization vill F
be required prior to returning to a power level that would approach F
that level that the inadvertent fluctuations were observed.
INSTRISENTATION/ DATA SYSTBtS Through the duration of this test, the following data systems shall D
be operating and personnel should be present for =onitoring:
C 1.
Brush recorders (located in the auxiliary control room) with all D
steam generator =odule main steam cutlet temperatures and nuclear C
channels. A data system engineer will be present to monitor 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 =enitor the steam generator sedule = sin steam outlet te=peratures.
C 2.
Data logger (located in the control room). The core performance engineer will be present to sonitor the core te=perature liaiting conditions for operation.
3.
The pri=ary coolant activity =cnitor (located in the control room).
D 4
FM dets acquisition system.
(
If any of the above systems becomes inoperable, testing shall be halted until the system is reinstated. If fluctuations are encountered when any of these systems is inoperable, core power shbuld be reduced until the fluctuations cease.
D During power increases or pulsed circulator speed changes and for a D
period of 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> (power increase) or 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> (cirtulator speed p21sel D
following either of these system ehenges, the following data sys o-and data taking frequencies are desired:
1.
Data logger on a fast sa=ple rate (15 seconds or less).
2.
Steam generator Fox II cc=puter on a fast sa=ple rate (~5 seconds).
3.
Model verification co=puter, 4
FM data acquisition system.
D 5.
3 rush recorders.
At periods during the test when the initial conditions for a fluc-tuation test are being established (orifice adjust:entt, flow / power changes),
the following data systems and data taking frequencies are desirec.
1.
Data logger on a sa=ple rate of 2 minutes or faster.
2.
Steas generator Fox II co=puter on a sa=ple rate of 13 seconds or faster.
RT-500-H Sheet 11 of 19 Page 15 of 23 3.
Model verification co=puter-D 4.
EH data acquisition system.
D 5.
Brush recorders.
D The traversable ther=occuples are to be positioned per RI-524.
PART 1: TESTING AT 170% POWER F
Initial Conditions F
1.
Plant at approrientely 40% power.
2.
The orifices are to be adjusted such that the region exit temperatures and steam generator inlet temperatures are reasonably balanced per normal D
procedures and per the Ooerating Considerations section of this RT.
Procedure D
1.
The objective of this test is to demonstrate that no fluctuations occur H
with RCD's installed or to develop a core pressure drop vs core flow rate D
(or power) stability threshold line. Thus it is desired to attempt to D
initiate fluctuations at three or more values of core flow rate. This D
will be done by orificing the core to different flow resistances. Depending D
on the core flew rate at which fluctuations are initiated in the first test, D
higher or lower values of core resistance =ay be selected. To generate a D
reasonably good stability threshold line it is desired to initiate fluctu-D acions at a lowest power level of about 40% to 50% and at about every 10%
D increase in power thereafter.
D NOTES:
1.
Each time fluctuations are initiated, Data Sheet 1 cust be completed.
D 2.
The nest effective means of halting fluctuations is by power reduction. Experience has shown that to halt a fluctuation the power say have to be reduced by 5% to 10%
below the power level which produced the fluctuation.
D 3.
Wait at least 1/2 hour to reach ther=al equilibrium prior D
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 /> after D
atte=pting to initiate a fluctuation by a load increase D
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 atte=pting to initiate D
a fluctuation by a pulse change in circulator speed before D
continuing.
E 2.
For the first test configuration, adjust the core orifices in a serfas of H
steps to obtain an average core pressure drop of about 1.7 psi with a core a
resistance of about 46.
Core resistance corresponding to this core cressure D
drop and core flow rate =ay be calculated by:
0.0 1013$clow--[i#
' S "#'
Resistance
=
Je0)
(..
'3
RT-500 H Sheet 12 of 19 Page 16 of 23 where iP measured is the =easured core pressure drop in psi (item 71 in DF 76)
Pressure is the circulator inlet helium pressure in psi (ices 9 in DF 76)
Flow is the total circulator flow in Ibm /hr (item 72 in DF 76)
T is the circulator inlet temperature in degrees Fahrenheit (a9erage of items 1 and 2 in DF 76)
Verify that the region outlet gas ta=peratures have adequate =argin from LCO 4.1.7 per Figure 1 and that the S/G =adule te=peratures are within the Operating L1=1ts Section of this RT before proceeding.
D 3.
Begin a series of power rises by increasing turbine load at 3% per minute D
in incremental load changes of 3% ( 9 MWe). Continue the incremental load D
increases until fluctuations develop or a plant limit is reached. Prior to D
each incremental load increase, adjust orifices as necessary to balance D
region outlet gas te=peratures and module inlet gas te=peratures. In D
addition, adjust the reg-rod position according to nor=al operations practice.
H If 70% power is reached and no fluctzations have been encountered, reduce H
the power to 40% and begin a series of orifice adjuct=ents to increase the H
core ap to about 2.2 psi. The orifices will be closed incre=entally so that H
approx 1=ately the same regional core flow distribution is =aintained. Verify H
that the r$gion outlet gas te=peratures have adequate cargin from LC04.1.7 H
per Figure 1 and that the steam generator =adule temperatures are within the H
operating li=its.
Begin another series of power increases by increasing the H
turbine load at 3% per minute in increments of about 3%.
Centinue these H
power increases until a povar level of 70% is achieved or fluctuations are H
encountered.
H Repeat the above procedure until a stable operation at 70% power is H
achieved with a core Ap of about 4.5 psi.
D 4
If fluctuations develop, there are three basic sets of data to obtain:
A.
It is desirable to obtain FM data during the onset of all fluctuations.
3.
For one fluctuation with each core flow resistance, obtain FM data for one hour during the fluctuations. The operating li=its stated in this RT =ust be adhered to during the one-hour period.
F C.
For one of the fluctuations described in Step 43, it is desirable to F
obtain FM data for an additional 1/2 hour, with the reg-rod dis-E abled and all rods held in a cons tant position. Attach =ent I defines the procedure for disabling the ret-rod. The operating limits stated in this RT =ust be adhered to during fluctuations.
G For one of the fluctuations described in Step 43, it is desirable to G
obtain FM data for an additional 1/2 hour with the steam generator module G
trim valves in =anual control -- (in a fixed position). During this G
fluctuation period, the operating li=its stated in this RT =ust be ad-G hered to.
At the end of this 1/2 hour the trim valves will be returned G
to auto =atic control.
C The Core Ferfor=ance Engineer will coordinate which particular fluctu-C ations will be =onitored per ite=s 3 and C above.
RT-500 H Sheet S of $7 Page 17 of 23 D
-5.
For each fluctuation encountered, repeat the step preceding the fluc-p 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, raurn to 47% power and F
repeat the 47% to 50% power rise. If no flue :uations occur, then D
repeat the 50% to 53% power rise.
D 6.
When a fluctuation threshold has been defined per steps 2 - 4, return D
to the highest power level for which a fluctuation was not initiated D
(47% in the above example). Perfors Part II of RT-499, the circulater D
speed pulse test, where the prinary coolant ficw is increased by D
~31., held at the higher value for a shcr: duration (~10 seconds) and D
returned to its initial level.
If fluctuations are not initiated, D
increase power b' 3% at 1/21/=inute and repeat Part II of RT-499, the D
circulator speed pulse test. Continue until fluctuations are encountered D
or until a power level 95 above the naxinus frem step 4 is achieved D
(until 62% in the above exa ple).
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 approx 1=ately 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 frem the conditions D
which initiated the preceding fluctuation as follows:
(F V
CI.D g l\\ NEW/
D R
= R g
F D
where R s
resistance h the pn e d ng test OLD F
F is the core flow rate from the preceding tes: (step 5)
OLD F
F is the flow rate corresponding to the power level where F
tbnext fluctuation it desired.
D 9.
The starting point for the nex: test is with the core orificed to achieve the F
new core resistance, Rygg, per the ec,uatica given in step 2, and with a ccre D
pressure drop 104 - 205 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 d:cp at or below the value at which :he fluctuation tes; will be D
started to prevent inadverten: fluctuations. To do this it is suggested that:
D A.
If RNEW " OLD, re ce ficw befon closing oMees.
D B.
If RNEW
- OLD, pen ri ices before increasing flew
RT-500 Sheet 14 of 19 Page 18 of 23 e
D 10.
Repeat steps 3 - 7 to obtain data for at least 3 values of core re-t D
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 increments of '10' power above this initial level.
D Depending upon the effect of RCD's on the fluctuation threshold, D
it say be necessary to vary attemperation flow (core P/F), region D
outlet te=perature mis =stches, or partially insert control rods (power D
flattening) in order to demonstrate the threshold at high power D
levels. Any or 'f.1 of these operations may be used as permitted by F
SOPS and Technical Specifications. Caution should be axercised to I
F maintain the region temperature margins for L.C.O. 4.1.7 given in F
Figure 1 and to not violate the core ther=al safety limit on core power / flow ratio (S.L. 3.1, Figure 3.1-2).
i D
If the pulse change in circulator speed tes: fails as a " trigger" ll D
for fluctustions for two values of core resistance, then it is not D
necessary to continue attempting to initiate fluctuations via this D
mechanism.
6 D
Part 2: Testing at >70% Power D
Frem an initial steady-s:ste condition of '70% power, the core power D
will be increased slowly (1/25 per sinute) to '733 and stabili:cd.
If no D
fluctuations occur, power will be reduced to 70*,, stable aparation achieved, D
and a pulse change in circulator roeed will be employed to attemp: to D
initiate fluctuations. If flue: nations do not develep, a 3% load increase
(-
D at 3% per minute will be effected to attempt to trigger fluctuations.
D This process of slow power increafss, circulator speed pulses, and then
,s D
rapid power increases of 3% will be continued until fluctuations are en-D.
countered or un:11 100'. power or a plant limit is encountered.
If flue-
'~
D tuations occur, data will be recordec for a short period of time and the D
step which initiated the fluctuation will 5e repeated to establish repro-D ducibility of the onset of fluctuations.
D Initial Conditions F
1.
Plant at approxi=ately 70t, power.
D 2.
The orifices are to be adjusted such : hat the region ext: :emperatures D
and steam generator inlet temperatures are reasonably balanced per D
normal procedures and per the Coeratine Considerations section of D
this R7.
D Procedure D
1.
The objective of this test is to extend the core pressure drop vs D
core flow rate (or power) stability threshold line developed in D
Part 1.
D NDTES:
1.
Prior to each incremental load increase, adjust orifices as s'
D necessary to balance region outler gas te=peratures and D
- odule 3-as temperatures. In addi: ion, adjus: the reg-red D
positien acecrding to normal operations practice.
RT-500N Sheet f6 of W Page 19 of 23 D
2.
The most effective means of halting a fluctuation is by
,[
D power reduction. Experience has shown that to hal: a D
fluctuation the power ray have to be reduced to 5'. to 10%
D below the pcwer level which produced the fluctuation.
D 3.
Each ti=e a fluctuatiran is initia:ed, Data Sheet 1 must D
be completed.
D 4.
Wait at least 1/2 hcur to reach thermal equilibrius 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 attempting D
to initiate a fluctuation by a pulse change in circulator D
speed before continuing.
D 2.
For the first test configuration, adjust the core orifices in a series E
of steps using the procedure sucolied by the test coordinator as a guide D
to obtain an average core pressure dr0p at least 10% below.the threshold AP detemined in Part I for 70% pcwer. The core resistance corres;:endine D
to this core pressure drop and core ficw rate may be calculated by the D
equaticn given in Part 1 precedure step 2.
D If the core orifices are opened as :uch as possible, the main steam tes-D perature =ay be reduced to 40*F below the reheat te=terature se:poinr, D
core control rods =ay be partially inserted (to flat:in the power distri-D bution and thereby per=it further opening of orifices), or atte=peration D
flow =sy be increased within the limits of SCPs and Technical Specifications D
to further reduce the core pressure drop.
(
D Verify that the region outlet gas te:peratures have adecuate margin D
from LCD 4.1.7 per Figure 1 and that the S/G :odule temperatures are D
within the Operating Limits Section of this RT before proceeding to D
the next crifice changes.
D 3.
Increase power by ~3% ('9 MWe) at 1/2% per minute.
If fluctuations D
do develop, go to step 6.
If fluctuations are not initiated, decrease D
power by ~3*6 to achieve initial conditions once again.
D 4
Perform Part II of RT-499, the circulator speed pulse test, where the D
pri=ary coolant flow is increased by '3*S, held at the higher value for D
a shore. duration ( 10 seconds) and returned to its initial level.
If D
fluctuations develep, go to step 6.
D 5.
If fluctuations are not initiated by step 4, increase power by 3*a at D
3% per minute. If fluctuations develop, go to step 6.
If fluctuations D
do not develop, repeat steps 3 thrcugh 3 starti.3 at the new power level D
(~3*. above the preceding power level). Continue with successively higher D
power levels until fluctuations do develop or until 100i power or a D
plant limit is enccuntered.
D 6.
When fluctuations develop, :here are two basic sets of data to obtain:
D A.
It is desirable to obtain FM data during the onset of all fluctuations.
D 3.
For one fluctuatien with each core flow resistance, obtain FM
\\
D data for one hour during the fluctuations. The operating limits D
stated in this RT =ust be adhered to during the one-heur period.
RT-500H Sheet 16 of 19 Page 20 of 23 D
The Core Perfor=ance Engineer will coordinate which particular flue-r-/
D tuations will be monitored per ites B above.
7 7.
For each fluctuation encountered, repeat the step (load increase or D
circulator speed pulse change) preceding the fluctuation and if no fluctu-F acions occur, that step which caused the fluctuation,. For example, if fluctuations are ncountercd during a power rise frca 73% to 76 power, re-F e
F curn to 70% power and repeat the 70% to 73% power rise, then if no F
fluctuations occur, repeat the 73% to 76% power rise.
D Similarly, if the circulator speed pulse changes initiated fluctus-D tions, then repeat the circulator speed pulse test (Part II of RT-499)
D for the step preceding the fluctuation and that step which caused D
the fluctuation.
D 3.
After demonstrating repeatability, reduce power and re-establish D
a stable plant configuration.
If fluctuations were first initiated D
by the 1/24 per minute lead increase (step 3), then establish the D
initial conditiens preceding initiation of fluctuations 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 fluctuatiens and D
effect a 3% Icad increase at 3% per minute, i.e.,
step 3.
If fluc-D tuations were first initiated by the 3*, per =inute lead increase D
(step 5), proceed to step 9.
D 9.
The next starting point is with a pri=ary flow rate (power level)
((-
D 54 - 10% above that of the preceding starting 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 red insertion =ay be e= ployed to permit further opening of D
orifices and/or the main steam temperature set point may be reduced to D
40*F below the reheat temperature 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 pcwer levels, until ICC's D
power is ~ reached or until a plant lisit is encountered.
RT-500 H Sheer 17 of f
.s Page 21'of 23 c.t.-L
~
- n. g.s v
n b6 Q.Z.$
~
g h) b
~
n a
m n
s y~
45-5 3,7 3
u y*
o 3G CO Ssc
/
G-L-t
.O o c n
nu y
O) m
}
o A-O 3 *-
i t.e
{0 c'.)
u 3c'
$.0
- M 3,
3r s
i 3-
- )
{.
,0,,jg u
/
- s Et3
,d pu e
u r
bs
/e h-u 7-4.
db
- s y
.. ~.
=.5 -
3 u
o G-:-5 n
g0 ef 33 s
s g.2- ?.
.., B-t-7.
.. \\.
& L
...aH
=
' l--
- f..
't L'/iW
?$i?J OJ / Nd 25.'s.
.,:',y,; ; q.
/
A1
-7 i
( +/ /2L O. Y./. T j/C/, - / c4 7,/
(new figure in Revisien 3) s e
RT-500 N Sheet 19 of 19 Page 22 of 23 b
ATTACStENT I REG-RCD INFLUENCE TE3T D
The purpose of this test is to determine if taking the reg-rod out D
of auto will reduce the a=plitude of the flue:uations 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 red :otion influencing the signals. The procedure is as D
follows:
1.
After a fluctuation has developed, monitor the a=plitude of the module MS temperature fluctuation to verify that the Operating Li=its of this RT are met.
Previous experience with fluctuations indicates that 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 =ove the reg-rod by placing the rehes: temperature. controller in manual and then rotating the regulating red selector switch (HS-1213) to the CFF position.
This permits the automatic flux control to initiate a rod runback if needed as a result of any transient during thi.; test.
If necessary,
=anually position the reg-rod to the average position that existed c
prior to disabling the auroca:ic control feature. This step is
(_
desirable in order to maintain a constant value for total reactor power and average core ce:perature.
CAUTICN: If a ntnback occurs. the rehea: te=cerature centro 11er should be nulled out anc returned to automatic anc H5-1213 returned to the +1 cosition as soon as oossible.
D 3.
Wait a period of approximately 30 minutes to determine the effect on fluctuations. Control rocm 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 #1 position, null out reheat temperature controller, and retu a it to automatic.
\\
RT-500 fl Sheet 6 of g (C;mpletely Revised DATA SHEET I by Rev. E)
Page 23 of 23 r"
Ccmolete this data sheet if fluctuations were encountered. This data sheet is to certify that test limits were not exceeded.
A.
If any of the followino limits are exceeded, tasting must be stoceed until furtner autnerized ov PSC. Management.
Limit _
1.
Were OPERATING CONSIDERATICNS 1,233 met? YES
/NO N/A 2.
Time /Date fluctuation started N/A 3.
Pcwer Level at start of fluctuation N/A I hour 4.
Time /Date power reduced 5.
Time /Date fluctuation stopped N/A 6.
Pcwer Level when fluctuation stopped N/A 7.
Maximum fluctuation on Nuclear Channel #
N/A
~ f, I
Peak Magnitude r
8.
Maximum fluctuation of Loop I MS Temp Mcdule p 374 Fluctuation Magnitude 60*F P-P Hottest Mcdule #
- F 1025'F 9.
Maximum Fluctuation of Loop II MS Temp Module #
N/A Fluctuation Magnitude 60*F P-P Hottest Module #
- F 1025*F
- 10. Equilibrium Value of Primary Coolant Activity for power level of test N/A
- 11. Maximum Value of Primary Cociant Activity Curing 257, increase test 8C #C"
$hg
- 12. Were Data Systems in service? YES
/NO
- 13. Was a purification train in service? YES
/NO Recairec for nesting 3.
Fcr anv of tra followine, testinc must be stoceed and recorted to the NRC:
1.
Any Technical Specification exceeded? YES
/ NO 2.
Any MS Temperature Fluctuaticn > 150*? YES
/ NO 3.
Primary Coolant Activity >5 times normal? YES
/ NO This recuires an i = ediate Orderly shutdown.
?SC SHIFT SUPERV!50R Signa ture/ Cate TEST COCRDINATCR Signature Cate