ML20080S180
| ML20080S180 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 10/13/1983 |
| From: | Schroeder C COMMONWEALTH EDISON CO. |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| 7455N, NUDOCS 8310180281 | |
| Download: ML20080S180 (10) | |
Text
D Commonwealth Edison
) one First Nationti Plua, Chicago, Ilknois O
Addr:ss R: ply to: Post Offica Box 767
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Chicago, Illinois 60690 s.
l October 13, 1983 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, DC 20555
Subject:
LaSalle County Station Units 1 and 2 FSAR Changes to the Startup Test Program NRC Docket Nos. 50-?73 and 50-374
Dear Mr. Denton:
Per a telephone conversation between LaSalle County Station personnel and Mr. Bill Long of your office on October 5,
1983, we are transmitting the enclosed marked up changes to thc caSalle County FSAR.
Enclosed please find proposed changes to FSAR Table 14.2-130, Table 14.2-124, Table 14.2-114 and Figure 14.2-2.
A summary of each change is provided below.
Table 14.2-130 As this startup test is not included in the Unit 2 Startup Test program because the Unit 2
jet pump adapters are identical to the prototype (Tokai-2) this change allows for the collection of certain vibration data during the preoperational test program.
Appropriate changes have also been made to Figure 14.2-2.
Table 14.2-121 The performance of this test during the section activation between 62% and 85%
power will yield more meaningful data for purposes of extrapolation to higher power levels.
Table 14.2-114 During the performance of the Unit 1 Startup test program certain expansion data was collected during the non-nuclear heatup associated with STP-34.
Because STP-34 has been deleted in the Unit 2
Startup Test Porgram we are requerting permission to use expansion data collected during the non-nuclear heatups which have taken place during the performance of the O(
Unit 2
preoperational test program.
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. Figure 14.2-2 The performance of STP-5 at Test Condition 1 has been deleted from the Unit 2 Startup Test Program as a result of the deletion of STP '8 (reference FSAR Question 423.8) STP-5 is nerformed in conjuction with a plannet scram at the particular test condition.
With the deletion of STP-28, there are no planed scrams at Test Condition 1,
hence the deletion of this test.
The performance of STP-8 has been deleted from the Unit 2 Startup Test Program (reference FSAR Question 423.8) hence the deletion on the Figure.
The performance of STP-28 has ben deleted from the Unit 2 startup Test Program (reference FSAR Question 423.8) hence the deletion on the Figure.
The performance of STP-27 st Test Condition 6 has been deleted from the Unit 2 Startup Test Program (reference FSAR Question 423.8) hence the deletion on the Figure.
The performance of STP-34 has been deleted from the Unit 2 Startup Test Program because Unit 2 is identical to the prototype hence the deletion on the Figure.
The superscript "2"
for STP-31 at Test Condition 2 has been eliminated.
Scram timing is not possible during the loss of offsite power as the required equipment has no power source.
The remainin0 changes to the Figure are related to the Reactor Recirculation Flow Control System modes applicable during the performance of STP-23.
We feel the changes as shown are more applicable to the testi7g which occurs at the particular test condition.
. It is requested that you confirm the acceptibility of these i
changes by telecon so that they may be incorporated into an amendment to the FSAR.
One signed original and forty (40) copies of this lettc?
cre'provided for your use.
If there are any questions in this matter, please contact i
i this office.
Very truly-yours, C S M -bs/s3 C.
W.
Schroeder Nuclear Licensing Administrator 1
cc:
NRC Resident-Inspector LSCS W.-Long, NRR 7455N bg
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'LSCS-ISAR AMINDMENT 63 JULY 1983 l
TABLE 14.2-130 VIERA* ION M EASUREMEN7S STARTUP TEST i
PURPOSE 7e obtain vibration measurements on the jet pumps to confErm the mechanical integrity of the system with respect to-flo a induced vibration and _c verify the accuracy of the analytica11 vibration model.
This will be in ecnfermance with Regulatory Gulia 1.20 s
requirements f er Non-Prototype, Category II Plants (s im_33r. to prototype but some component dif f erences).
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DaSCRIPTION s
.s During operatica, the reactor structure may be forced _;to many modes of vitraticns.
Previcus vibraticn measurements f or internal structurec of similar design indicate that des tructive s
level vibrations will nct occur.
Since the LSCS Unit" 1 jet pump adapter is a unique design, which dif fers from the prototype (Tokai-2 ), and which may introduce different jet pump vibration characteristics f rom that of the ump pair is to be instrumented as described p roto type, one jet e p mp configuration is identical to
-below. --The--LSCS - U ni-t 2 jet u
that of the prototype (Tokai-2) an d, hence, no instrumentation is plann ed.
Sixteen internal sensors will be used for LSCS Unit 1:
a.
Four strain gauges on riser braces (loc.ation identical to the prctetype).
b.
Four strain gauges at 900 intervals on each jet pump adapter, below the shrcud support plate.
Two piercelectric accelerometers mounted just below c.
the slip joint en each diffuser.
This test program is in additien to that defined by the flow induced vibration test performed prior to startup (see Table 14.2-45).
The start 6p test will consist of a cold ficw test with the reacter vessel at pressures up to 1000 psig and fully loaded, followed by hot power tests performed with the system at normal coeratinc pressure and temperature.
During the vibration test v'ibratio5 ' amplitudes and f'requencies cbtained frem the sensors will be'menitored and recorded.
The measured amplitudes and frequencies are then ccmcarec to the acceptance criteria to assure that all measured vibration amplitudes are within acceptable levels.
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14.2-270
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LSCS-FSAR AMENDMENT 56 MAY 1981 TABLE 14.2-130 (Cont'd) f In addition, a visual inapection of reactor vessel level and pressure instrumentacion lines and CRD withd, raw and insert lines inside containment will be made in conjdngt' ion with this test.
The visusi inspoetion will be conducted to identify any excessive vibration, uu,e 2 uratarim Ah I.
sca! be-obt: toned dw ay peopuabonel tear- &#Mm (Pr-PV-lot)
ACCEPTANCE CRITERIA f
Level 1
.. fG '
1' The peak stress intensity may exceed 10,000 psi (single amplitude) when the component is deformed in a manner i
corresponding to one of its normal or natural m' odes but tha f atigue usage f actor must not exceed 1.0.
Level 2
-i The peak stress intensity shall not exceed 10,000 psi (single amplitude) when the component is deformed in a manner corresponding to one of its normal or natural modes.
This is the low stress limit which is suitable for sustained vibration in the reactor environment for the design life of the reactor components. -
INITI AL CONDITIONS 1.
All construction tests and preoperatio'al tests are completed and approved.
2.
All systems are operational to the extent necessary to perform this test.
s 14.2-271
a LSCS-FSAR AMENDMENT 57 JULY 1981
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TABLE 14.2-121 TURBINE VALVE SURVEILLANCE PURPOSE The purpose of this test is to demonstrate acceptable' pro- -
cedures and maximum power levels for recommended periodic surveillance testing of the main turbine control, stop and bypass valves without producing a reactor scram.
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DESCRIPTION
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Individual main turbine control, stop and bypass valves' are tested routinely during plant operation as required for..
turbine surveillance testing.
At several test points the response of the reactor will be observed.
.The maximum possible power level for performance of these tests along b E70 the 100% load line will be established.
First actuat' will be between 45% and 75% power on the 75% loa
'.e.
A second actuation will be between 62% and 7 power on the 100% load line.
These two test points will e used to extrapo-late to the maximum. power test condition on the 100% load.line l'e marii fto icram.
N6te proximity to APRM flow bias witE 5 [ int and PCIOMR envelope.
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scram po Each valve test will be manually initiated and reset.
Rate of valve stroking and timing of the cloce-open sequence will be such that the minimum practi-cal disturbance is introduced and that PCIOMR limits are not exceeded.
ACCEPTANCE CRITERIA Level 1 s
The decay ratio of any oscillatory response must be less than 1.0.
Level 2 a.
Peak neutron flux must be at least 7.5% below the scram trip setting.
Peak vessel pressure must remain at least 10 psi below the high pressure 3
scram setting.
Peak heat flux must remain at least 5.0% below its scram trip point.
b.
Peak steam flow in each line must remain 10% below the high flow isolation trip setting.
The decay ratio of any oscillatory response must c.
k be less than 0.25, when operating above the minimum core flow of the recirculation master manual mode.
14.2-255
LSCS-FSAR 1MENDMENT 47 OCTOBER 1979 TABLE 14. 2-121 (Cont'd)
INITIAL CONDITIONS 1.
All construction tests and preoperational tests are completed and approved.
2.
Instrumentation has been installed and calibrated.
3.
All systems are operational to the extent required to conduct the test.
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i 14.2-255a
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LSCS-FSAR AMENDMENT 57 JULY 1981
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TABLE 14.2-114 SYSTEM EXPANSION STARTUP' TEST l
PURPOSE 7
To verify that the reactor drywell piping system is free and unrestrained in regard to thermal expansion and that sus,
pension components are functioning in the specified manne.r.
The test also provides data for calculation of stress lev.bs,
in nozzles and weldments.
.. d, DESCRIPTIO'N
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Observations and. recordings of the horizontal and verticdz-movements of major' equipment and piping in the NSSS and auxiliary syster:s will be made in order to ensure that components are free to move as designed.
Adjustments will be made as necessary for freedom of movement.
ume a fxmnJ w preCPeurtsor.nf tc2 condtwnD Obtarned dwn)d dt<AI3 St2nKup D3V &^btwn &
d.xts s hoJI be.
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ACCEPTANCE CRITERIA
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There shall be no evidence of blocking of the displacement of any system component caused by thermal expansion of the system.
Hangers shall not be bottomed out or have the spring fully stretched.
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Shock and sway arrestors shall be in the operating' range about the midpoint of the total travel range at operating temperature.
Electrical cables shall not be fully stretched.
The measured steady-state displacement of the recirculation and main steam systems shall not exceed the ullowable values.
, Level 2 At a steady-state condition the displacements of instrumented points with displacement measuring devices shall not vary from'the calculated values, If measured displacements do l
not meet these criteria, the piping design engineer must be contacted to analyze the data with regard to design stresses.
14.2-245
7 LSCS-FSAR-AMENDMENT 47 OCTOBER 1979
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TABLE 14.2-114 (Cont' d)
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During-the heatup cycle, the trace of"the instrumented points shall fall within a range of 150% of the calculated,
value from the initial cold position in the direction'of.
the calculated value and 50% of the calculated value*from the initial position in the opposite direction of the s
calculated value.
Hangerswillbeintheiroperatingrangeb'etweenhotanbf cold settings.
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'i INITIAL CONDITIONS
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i 1.
All construction tests and preoperational tests ar J
completed and approved.
(Fu. Durc 2 eso appbca1tc 2.
Instrumentation is-installed and calibrated.
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I 14.2-246
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LSCS-FSAR AMENDMENT 26 OCTOBER 1977 QUESTION 423.8
" Identify the major transient tests that w'ill only be conducted for one unit or commit to.rovide an amend-ment to your application identifying these transients at least 9 months prior to fuel loading for NRR review and approval.
(Reference page 14.2-17)"
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RESPONSE
The startup tests that are to be conducted on Unit 1 only(N are the Control Red Sequence Exchange Startup Test, the. U' Shutdcwn from Outside the Main Control Room Startup Test, and the turbine trip from 100%. power portion of the Turbine c*ng Valve Trip and Generator Load Reiection Startup Test.
Upon successful demonstration of a method for control roc -
sequence exchange at the maximum power level (20%-40%) at which it will be permitted, the results will be applicable to Unit 1.
Attention is then focused on power distribution and available margin on thermal limits prior to.pplying Unit 1 test results to ? nit 2.
The demonstration of an orderly shutdown from outside the main control room is to be -conducted on Unit 1.
Because thd~l]5i F 2'rbdiots shutdown panel is identical and based on
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its preoperational test results, it is not necessary to
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perform a live chutdown from outside the main control room once the procedure has been established on Unit 1.
The logic and circuit verification test thoroughly validates this equipment in its preoperation1 test series.
If the turbine stop valve and/or control valve' trips on Unit 2 at low and intermediate power levels are co.mparable to those on Unit 1, the high-power trip-on Unit 2 will be extrapolated from the results of the high-power trip on Unit 1.
If the Unit 2 trips at low and intermediate power levels are not comparable the high-power trip will be per-formed on Unit 2.
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Q423.8-1
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