ML20210T949
| ML20210T949 | |
| Person / Time | |
|---|---|
| Site: | Mcguire, McGuire, 05000000 |
| Issue date: | 01/29/1987 |
| From: | Brandi Hamilton, Roberson C DUKE POWER CO. |
| To: | |
| Shared Package | |
| ML20210T874 | List: |
| References | |
| PT--A-4150-21, PT-0-A-4150-21, TAC-62981, TAC-62982, NUDOCS 8702180350 | |
| Download: ML20210T949 (29) | |
Text
i 00E380N Y Attachment 1 (1) ID No.PT/0/A/4150/21 Form 34731 (R9 86)
"" 3 Incorporat i u ,
P2EPARATION (2) STATION McGUIRE POST REFUELING CONTROLLING PROCEDURE FOR CRITICALITY, ZERO POW (3) PROCEDURE TITLE AND POWER ESCALATION TESTING A T PA DATE I!/*
(4) PREPARED BY lb DATE / /a !&7 (5) REVIEWED BY Y- /I
/ / By WYN Cross Discipiinary leview N/R
/
(6) TEMPORARY APPROVAL (if Necessary)
(SRO) DATE By DATE By
(?) APPROVED BY Aut RvA u
DATE <h/n (8) MISCELLANEOUS DATE Reviewed / Approved By Reviewed / Approved By DATE (9) COMMENTS (For procedure reissue indicate whether additional changes, other than previously G2fio approved change ADDITIONAL CHANGES INCLUDED. C Yes Attach additional pages,if necessary.)
(101 COMPARED WITH CONTROL COPY W ITEA 4 DATE f /~L9
/
7 COMPLETlON (11) DATE(S) PE R FORM ED (12) PROCEDURE COMPLETION VERIFICATION O Yes C N/A Check lists and/or blanks properly initiated, signed, dated or filled in N/A or N/R, as appropriate?
O Yes C N/A Listed enclosures attached?
O Yes C N/A Data sheets attached, completed, dated and signed?
Cyes CN/A Charts, graphs, etc. attached and properly dated, identified and marked?
Cyes CN/A Acceptance criteria met?
-DATE-VERIFIED BY DATE (13) PROCEDURE COMPLETION APPROVED (14) REM ARKS (Attach additional pages,if necessary.)
0702100350 870211 ADOCK 05000369 fD9 PDR
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' PT/0/A/4150/21 lage 1 of 15 DUEE POWER COMPANY ;
McGUIRE NUCLEAR STATION '
POST RFJUELING CONTROLLING PROCEDURE FOR CRITICALITY, ZERO POWER PHYSICS, AND POWER ESCALATION TESTING 1.0 Purpose 1.1 To provide a sequence of tests for the orderly startup of the un!t after refueling.
1.2 To perform nuclear instrumentation overlap verification.
1.3 To determine the point of nuclear heat.
1.4 To establish the neutron flux levels corresponding to the Zero Power Physics Test Band.
1.5 To perform a checkout of the reactivity computer.
2.0 References 2.1 McGuire Nuclear Station Technical Specifications 2.2 WCAP-9648, Post-Refueling Nuclear Testing Program Criticality to Full Power.
2.3 The appropriate unit and cycle Nuclear Design Report.
3.0 Time Required 5 days, 2 engineers per shif t - 3 shifts 4.0 Prerequisite Tests Initial /Date
/ 4.1 PT/0/A/4600/148, NIS Intermediate Range Calibra-ion tunctional Test (see Step 7.4).
/ 4.2 PT/0/A/4600/14A, NIS Power Range Calibration Functional Test (see Step 7.5)
NOTE: The tests in 4.1 and 4.2 must be completed within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> prior to beginning Physics Testing. Physics testing is defined as beginning when Control Rods are being withdrawn to achieve criticality. This occurs in Step 12.9 of l PT/0/A/4150/28, Criticality Following a Change in Core Nuclear Characteristics.
5.0 Test Equipment
! 5.1 Reactivity Computer connected to one power range detector (Enclosure 13.6) (See Step 8.2 for installation step.)
I
' 7/0/A/4150/21 Page 2 of 15 5.2 Chart recorders to display reactivity, flux, pressurizer level, and T, .
5.3 Stopwatch or timer 5.4 Communications between Control Room operators and testing work station.
6.0 Limits and Precautions 6.1 The startup rate is administratively limited to 0.5 DPM.
6.2 During the Zero Power Physics Tests (Steps 12.3 - 12.10.20)
Special Test Exception 3.10.3 will be invoked. The appropriate Surveillance Requirements will be monitored by Operations.
6.3 Notify Westinghouse if any incore tilts exceed 2%.
6.4 The primary indication of core power will be AT, which should be l
cross checked with the NIS and the Thermal Power calculation on the OAC. If the thermal power and Power Range NIS disagree by more than 2%, then adjustment is necessary per Tech Spec 3/4.3.1, Table 4.3-1, notation 2. (IP/0/A/3007/17) 6.5 If the encore power indications are conservative, use caution when increasing power to avoid the high level trip setpoints.
6.6 Observe the Fuel Maneuvering Limits as outlined in Data Book Section 1.3.
7.0 Required Unit Status j
! Initial /Date
- / 7.1 The unit is in Mode 3 - Hot Standby
/ 7.2 The points listed on Enclosure 13.1 are being logged on OAC Gen.
l 24 program once per 6 minutes printed every 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.
l 7.3 Record the unit and cycle to which this procedure is being ,
, / )
l applied, in the test log.
8.0 Prerequisite System Conditions 8.1 All RCC control banks and shutdown banks are fully inserted.
/
/ 8.2 Begin to install the reactivity computer per Enclosure 13.6.
l The reactivity computer shall be installed before beginning Step
- 12.4.
1 l
i i
1
1 c
PT/0/A/4150/21 l Page 3 of 15 8.3 An evaluation of the impact of the core alterations on the
/
encore detector sensitivity has been made. Document the results Attach to this procedure any correspondence in the test 103 from offsite personnel on this subject.
8.4 Perform Enclosure 13.10 to demonstrate adequate Shutdown Margin
/
at the zero power insertion limits per Tech Spec 4.1.1.1.1d.
8.5 Perform Enclosure 13.9 to verify adequate Shutdown Margin during
/ <
Rod Sway, 8.6 Provide IEE 7300 Systems Engineer with the new cycle 100% F.P.
j /
predicted value of Reactor Vessel Tave.
- / 8.7 I&E 7300 Systems Engineers have set AT values to conservative i
numbers as necessary in the protection cabinets. Record in the j test los the values which have been set in the cabinata.
9.0 Test Method The reactor is brought critical with the procedure for criticality.
] Then, the Intermediate Range (I/R) NIS overlap data is recorded, the '
i point-of-nuclear-heat flux level determined, and the Zero Power Physics i Test (ZPPT) band is established. Also, the reactivity computer is i
verified to be set up correctly by making reactivity changes and
! comparing the computer response to the calculated reactor period.
]
Next, the ZPPT's are performed to measure the ARO boron concentration, l
control rod worths, moderator temperature coefficients, and the l
]
low power core power distribution (if necessary).
! l Finally, power escalation is begun, with a full core flux sap between
! 10% and 50% full power. During the escalation above 50% full power, I data is taken for the Power Range NIS calibrations. At N80% full power, the P/R NIS is calibrated, then power is increased 100% full
! power. At 100% full power, the core power distribution, the NIS
) calibration, the thermal power output program, and the reactivity anomo11es are all checked. Also, the target flux difference is 4
measured, and Reactor Coolant Systen Flow Test is performed.
l I
f i
4
5
< PT/0/A/4150/21 Page 4 of 15 l
10.0 Data Required
^
10.1 Nuclear instrumentation overlap will be recorded on l
Enclosure 13.2.
$ 10.2 The point of nuclear heat will be recorded on Enclosure 13.3. '
10.3 The reactivity computer checkout results will be recorded on l Enclosure 13.4.
10.4 Output of OAC Gen. 24 program per Enclosure 13.1.
10.5 Intermediate range high level trip setpoints on Enclosure 13.7.
4 10.6 Verification of adequate Shutdown Margin at the zero power 4
insertion limits on Enclosure 13.10.
10.7 Verification of Shutdown Margin during Rod Swap on
! Enclosure 13.9.
j
! 11.0 Acceptance Criteria 11.1 There is at least one decade overlap on the NIS between the ,
Source and Intermediate Ranges, and between the Intermediate and 4
Power Ranges (NOTE: Power Ranges are calibrated to Thermal .
Power, Best Est. (P1385). Use P1385 for Power Range overlap data).
, 11.2 The value of the reactivity measured by the reactivity computer is within .04 (4%) or 1 PCM, whichever is greater, of the reactivity inferred from the reactor period, or doubling time.
,OE ~ OEDT $ .04 (4%) or 1 pcs c
OE DT f All acceptance criteria in each test procedure for the tests l 11.3 i contained in this controlling procedure have been set.
I i
i
-,m - s., m. --e-.,-,,,-..% _--~--_,.---.-,w--- - - - - - - - - . - . - , . - - , - - , - , , - - , . -, -..--,~,,-----,--.r--. , -- -- - . - - - - - - - y
PT/0/A/4150/21
'Page 5 of 15 1
12.0 Procedure Initial /Date '
Attack as Page 2 of Enclosure 13.4 the table of " reactivity and l
/ 12.1 doubling time as a function of stable reactor period at BOL, HZP conditions" for the appropriate unit and cycle. Also attach as Page 3 of Enclosure 13.4 the curve (if provided) " Reactor Period and Doubling Time as a function of Reactivity at BOL, HZP, No Xenon" for the appropriate unit and cycle.
/ 12.2 Inform the Operations Shift Supervisor that Special Test J
Exception Tech Spec 3.10.3 will be entered during criticality and Zero Power Physics Testing (Steps 12.3 - 12.10). Operations shall monitor the appropriate Surveillance Requirementa during these Steps.
/ 12.3 Complete PT/0/A/4150/28, Criticality Following a Change in Core Nuclear Characteristics. It is permissible to sign off this step prior to signing off Steps 12.18 and 12.19 in PT/0/A/4150/28.
' NOTE: Section 7.0 of this procedure will have been completed earlier, i NOTE: See Step 4.1 and 4.2.
/ 12.4 Begin PT/0/B/4600/55, Reactivity Computer Periodic Test
' approximately 4-6 hours prior to Step 12.6.
/ 12.5 Record the IR high level trip setpoints on Enclosure 13.7.
3
/ 12.6 With a Source Range reading of 210 cps and the reactor just l critical withdraw Control Bank D or add desineralized water, to i
establish a slow positive startup rate (<50 pes). When the Intermediate Range indication comes on scale, halt the flux i level increase, establish just critical conditions, and record data as required by Enclosure 13.2, Page 1 of 2.
/ 12.7 Continue to increase the flux level, stopping, establishing just critical conditions, and recording data with each decade increase in the Intermediate Range until the Source Range is l blocked.
5 CAtTTION: Do not exceed 10 cps on the Source Range unless the
' Source Range is blocked, as a reactor trip will occur.
5 PT/0/A/4150/21 Page 6 of 15 CAITFION: I/R high level trip setpoints are on Enclosure 13.7; do not exceed these values.
/ 12.7.1 Verify from Enclosure 13.2 Page 1 of 2 that a minim a of one full decade of overlap exists between the Source Range and Intermediate Range before the Source Range reaches 10 cys.
12.8 Determine the flux level at which the point of nuclear heat occurs by the following steps.
/ 12.8.1 Set up 1, 2 pen strip chart recorder with T,,, and reactivity, another 2 pen strip chart recorder with pressurizer level and flux signal.
/ 12.8.2 Establish just critical conditions with reactivity
~8 l computer picoammeter reading of about 1 x 10 amps.
I Adjust the scale setting on the reactivity computer t
picoammeter (if necessary) such that the indicator is i l on scale and indicating a value near the low end of -
I the scale. Record start values on Enclosure 13.3.
l i
NOTE: Stop increase if nuclear heat is observed prior to reaching this level, and repeat Step 12.5.2 from i 1 x 10 ~9 amps on the reactivity computer picosameter.
/ 12.8.3 Establish a slow positive startup rate by rod withdrawal of about 20 pcm and allow the flux level to increase until nuclear heat is observed. At this time, re-establish just critical conditions by Control Bank D adjustment. Record Nuclear Heat Data on Enclosure 13.3.
NOTE: Nuclear heat can be best observed as an increase T,,, accompanied by a change in the reactivity trace and an increase in pressurizer level.
NOTE: It is permissible to also trend pressurizer l
1evel, Intermediate Range Level, and NC Loop Highest i Average Temperature on the OAC to aid in the determination of nuclear heat.
j / 12.8.4 Repeat Steps 12.8.2 and 12.8.3 a second time and record all data as requested on Enclosure 13.3.
PT/0/A/4150/21 Page 7 cf 15 12.8.5 Determine the Zero Power Physics Testing Range from
/
the reactivity computer picoamester flux levels on Enclosure 13.3. Record on Enclosure 13.3.
NOTE: The range for all Zero Power Physics Testing will be defined as the next lowest whole decade such that the upper end of the decade is not within /10 of nuclear heat. ~0 EXAMPLE: If nuclear heat is found at 5 x 10 amps on the picoammeter then
~0 5 x 10 ~0 = 1.5 x 10 and 410 the range for zero power testing is 1.0 x 10'I to
~0 1.0 x 10 amps.
NOTE: If the signal is not clear for the decade defined, evaluate the situation and if changes are ,
needed to be made to the testing decade, fully document in the test log the reason for the change before continuing, i / 12.8.6 Insert Control Bank D slightly, allow the flux to decrease until the reactivity computer picosameter reads near the low end within the Zero Power Physics Test range determined above, and level out again.
12.9 Perform a checkout of the reactivity computer.
12.9.1 Withdraw Control Bank D until a reactivity gain of
/
approximately +25 pea is indicated by the reactivity I
computer.
12.9.2 Let the flux increase to a stable period and measure
/
the doubling time at two or three different times over l the decada using a stopwatch or timer. From the l doubling time, calculate the period from the following equation and record on Enclosure 13.4, page it DT period =
0.693 i
PT/0/A/4150/21
' P:ge 8 cf 15 12.9.3 Using the table on Page 2 of Enclosure 13.4, or the
/
curve (if Provided) on Page 3 of Enclosure 13.4, convert the observed period to reactivity and record on page 1 of Enclosure 13.4.
/ 12.9.4 Record all data on Enclosure 13.4.
/ 12.9.5 Repeat measurement as needed until at least three checks have been performed.
/ 12.9.6 Repeat Steps 12.9.1 through 12.9.4 for a reactivity addition of +50 pcm.
/ 12.9.7 Repeat seasurement as needed until at least three checks have been performed.
/ 12.9.8 Verify the Acceptance Criteria of 11.2 has been met, for the positive reactivity insertions only.
/ 12.9.9 Verify a negative reactivity insertion check has been performed satisfactorily on the reactivity computer per PT/0/B/4600/55, Reactivity Computer Periodic Test.
/ 12.9.10 Position Control Bank D at 2220 steps by boration or dilution.
i / 12.10 Zero Power Physics Testing Complete the tests listed below. Normal operating procedures shall be used to reconfigure the plant to meet any prerequisites. All tests should be performed within the test band established in Step 12.8.5, except power will be increased up to 23-4% full power for the low power flux say if it is taken.
12.10.1 Perform PT/0/A/4150/10, Boron Endpoint Measurement.
/
/ 12.10.2 Perform PT/0/A/4150/12, Isothermal Temperature Coefficient Measurement for the ARO case.
' Pr/0/A/4150/21 Page 9 of 15 a
12.10.3 Perform PT/0/A/4150/31, Determination of Rod
/
- Withdrawal Limits to Ensure Nederator Temperatures Within Limits of Technical Specifications. Testing may continue under Special Test Exception Tech Spec 3.10.3; however, PT/0/A/4150/31 Section 12.1 aust be performed prior to the completion of data gachering for the Rod Sway test of Step 12.10.5. If the trtC calculated in Step 12.10.2 is less than 0 pen /*F, mark
^
this step N/A.
i 12.10.4 Record on Enclosure 13.8 the Reference Bank, rod j /
! banks, and sequence to be measured by rod sway.
1 NOTE: If the predicted worth of any bank is close to the predicted worth of the reference bank, measure this bank last.
/ 12.10.5 Perform PT/0/A/4150/11A,' Control Rod Worth Heasurement - Rod Swap. This seasurement is to be ,
I done for the rod banks identified on Enclosure 13.8. !
/ 12.10.6 Following Rod Swap Messurements swap Control Bank D with the reference bank until Bank D is fully :
inserted.
If Section 12.1 of PT/0/A/4150/31, Determination of j
/ 12.10.7 Rod Withdrawal Limits procedure indicates no rod j withdrawal limits are needed mark Step 12.10.8, t
12.10.9, and 12.10.11 as N/A and continue. If the i
indication is that rod withdrawal limits will be needed, perform Steps 12.10.8, 12.10.9 and 12.10.11.
NOTE. It is permissible to perform Steps 12.10.8 and 12.10.9 if desired even though it might not be required. In that case, N/A Step 12.10.11.
12.10.8 Place the rods close to a D in only configuration by
- /
borating the reference bank out, 12.10.9 Perform PT/0/A/4150/12 Isothermal Temperature j /
Coefficient Measurement for the D-in case.
l
) / 12.10.10 Perform PT/0/A/4150/11 Control Rod Worth Hessurement.
4 This measurement is to be done only for Control D as i
it is completely withdrawn by boration. .
_ _ _ _ _ _ _ _ _ _ _ _ _ - . _ _ ,-. _ -__- _.--- ___ _ -,-~ __ ._ -._. __ _ _ _ _
t
- PT/0/A/4150/21 Page 10 cf 15 12.10.11 Perform Section 12.2 of PT/0/A/4150/31, Determintaion
/_ _
of Rod Withdrawal Limits to Ensure Moderator Temperature Coefficient within Limits of Technical Specifications.
/ 12.10.12 Perform the following steps to reset bank overlap once Control Bank D is about 215 steps withdrawn.
12.10.12.1 Go to the Master Cycler Cabinet and reset
/
the Bank Overlap Digital Counter to 000 by pushing the reset button.
12.10.12.2 Reset the Bank Overlap Counter to 345 plus
/
the present Control Bank D position by pushing the button to count up from 000 to the desired value (one push of the button is one digit change on the display).
NOTE: Perform Steps 12.10.13 and 12.10.14 in any order or concurrently. ,
/ 12.10.13 Increase reactor power by dilution or Control D withdrawal so that both approximately 3-4% full power and Control D about 215 steps withdrawn are achieved.
NOTE: Control D may be placed in a configuration for l
power increase if Step 12.10.17 is to be marked N/A.
! / 12.10.14 Remove reactivity computer from the Power Range NIS Channel to which it is connected and return the ;
Channel to OPERABLE status using Enclosure 13.6. )
/ 12.10.15 Verify that Thermal Power, Best Est. reasonably agrees with the indicated loop AT's. Resolve any problems.
NOTE: Thermal Power should be approximately:
((loop avs AT(*F) * ( I H , between 0-75% fun 45 F power.
./
12.10.16 Verify all power range channels are operable.
CAUTION: Do not continue until Step 12.10.16 is completed.
12.10.17 Perform PT/0/A/4150/02A, Core Power Distribution if ,
/
any rod swap acceptance criteria were not met in PT/0/A/4150/11A. Hark N/A here and also Step 12.10.19 if all criteria were met. ,
4
_ _ . _ _ . . _ _ _ _ ~ _ __
r PT/0/A/4150/21-Page 11 of 15 NOTE: It is permissible to perform Step 12.10.17 in any case if desired. In that case do not mark Step
$ 12.10.19 as N/A.
/ 12.10.18 Record the Intermediate Range NIS overlap data at 3-4% ,
4 full power on Enclosure 13.2.
/ 12.10.19 Perform PT/0/A/4150/23, Quarter-Core Flux Map
' Qualification Test.
' NOTE: Testing may continue here; however, PT/0/A/4150/23, if performed now, must be complete i prior to starting Step 12.11.7. .
i
/ 12.10.20 Place Control Bank D at *160 to 180 steps withdrawn to have sufficient reactivity to put the turbine on line.
/ 12.10.21 Verify the following:
/ 12.10.21.1 Acceptance criteria for each Zero Power Physics Test performed was met or any discrepancies have been resolved. .
12.10.21.2 All shutdown banks completely withdrawn
/
i and within i 12 steps of group step counter demand position. '
i / 12.10.21.3 Control banks above insertion limits and i
within 1 12 steps of group step counter i
demand position.
./ 12.10.21.4 Verify that the rod withdrawal limits tre 1
in place if they were required.
/ 12.10.21.5 Verify NC lowest operating loop Tave
>551 F.
/ 12.10.22 Inform the Operations Shift Supervisor that Special j
Test Exception Tech Spec 3.10.3 is being left.
J Appropriste surveillance can be stopped, j Enclosure 13.1 data trending can be discontinued.
4 NOTE: Do not exceed 5% full power prior to completing steps 12.10.21 and 12.21.22.
/ 12.10.23 Review Data Book curves 6.1 and 6.3A and reissue these
- as needed to reflect actual measured data.
)
s PT/0/A/4150/21 Page 12 of 15 12.11 Power Escalation Testing
/ 12.11.1 Reset Power Range high level trip setpoints to
/ IV 109% F.P. This step need not be completed prior to going on-line, only'before S20% F.P.
NOTE: Prior to putting the turbine on-line, verify control D bank at *160 to 180 steps. This will ensure the availability of reactivity which will be needed while placing the turbine on-line. Make sure that Control D bank is returned to a position >200 steps before reaching 20% F.P. per Data Book Section 1.3.
/ 12.11.2 Verify the Power Range High Level Trip Setpoints are set to 109% full power and inform the Control Room operator of that fact. This step need not be completed prior to going on-line, only before S20% F.P.
/ 12.11.3 Between 10% and 50% F.P., perform PT/0/A/4150/02A, Core Power Distribution. (It is suggested to perform this at the 30% F.P. hold for Chemistry.)
NOTE: Equilibrium xenon is not necessary for this flux map. Boron samples may be waived also.
/ 12.11.4 Following the flux map, perform PT/0/A/4150/23 Quarter Core Flux Map Qualfication Test. This Step can be marked N/A if it was performed in Step 12.10.19.
/ 12.11.5 Begin increasing reactor power from 3-4% to 50% full power at a rate of approxicately 2.5% per hour (not to exceed 3%'per hour). See Limit and Precaution 6.6.
NOTE: A suggested sequence for power increase is to increase load at i HWe/ min for 30 minutes then hold for the remainder of the hour.
12.11.5.1 As power is increased and the unit goes
/
on-line, check all inputs to the Thermal Power Calculation by using OAC program i I
Nuclear 28 (Thermal Power outputs Dump).
Resolve all problems prior to the 50% full power plateau. ;
1
i PT/0/A/4150/21 Page 13 of 15 12.11.5.2 Record the Intermediate Range NIS overlap
/
- data at 10%, 20% and 25% full power on Enclosure 13.2.
12.11.5.2.1 Complete Enclosure 13.5.
/
12.11.5.2.2 Complete new Data Book
/
Table 2.2.1 from the data on Enclosure 13.5.
12.11.5.2.3 Write a procedure change to
/
place the new Table 2.2.1 in the appropriate unit's Data Book.
12.11.5.2.4 Generate a work request to
/
have IAE recalibrate N35 and N36 and calibrate bistables NC-203 and NC-206 usins IP/0/A/3206/01K and new Data Book Table 2.2.1.
NOTE: DO NOT exceed 25% Full Power until IAE has completed calibrations of Step 12.11.5.2.4.
/ 12.11.5.3 When approximately 40-50% full power, if the excore quadrant tilts exceed 1.02, and it is expected that these tilts might not clear within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of exceeding 50% RTP, perform the data taking for PT/0/A/4600/02F, Incore and NIS Interim Recalibration with a QCFM while reactor power is between power increases. If the excore quadrant tilts are less than 1.02, or expected to be less than 1.02, mark this step N/A.
12.11.5.4 Record the Intermediate Range NIS overlap
/
data at 50% full power on Enclosure 13.2. f l
4 l
PT/0/A/4150/21 Page 14 of 15 12.11.6 Begin increasing reactor power from 50% to
/
approximately 80% full power at a rate of approximately 2.5% per hour (not to exceed 3% per hour). See Limit and Precaution 6.6.
12.11.7 Perform PT/0/A/4600/02E, Incore and NIS Recalibration:
/
Post Outage, between 50% and 80% full power.
NOTE: Closely check the data acquired in Step 12.11.7 which is to be used for calibration for consistency '
since some of the data was acquired at <75% full power.
12.11.8 Record the Intermediate Range NIS overlap data at 75%
/
full power on Enclosure 13.2.
/ 12.11.9 Remain below approximately 80% full power until the recalibration work performed in Step 12.11.7 is completed by I&E.
12.11.10 While holding at below 80% power call I&E 7300 System 1
/
Engineer to take data on Thot and Tcold.
/ 12.11.11 I&E has evaluated data gathered in Step 12.11.10 to 1 ensure operation at 100% will be acceptable with respect to AT. Record in the log any I&E setpoint 1
changes in 7300.
/ 12.11.12 Begin increasing reactor power from 80% to 100% full
~
power at a rate of 2.5% per hour (not to exceed 3% per hour). See Limit and Precaution 6.6.
12.11.13 At 100% full power, perform the following tests (steps) in any order (a suggested order is listed).
12.11.13.1 Perform PT/0/A/4150/03, Thermal Power
/
Output Calculation. l l
12.11.13.2 Perform PT/0/A/4150/02A, Core Power
/
Distribution.
12.11.13.3 Perform PT/0/A/4150/08, Target Flux
/_
Difference Calculation.
12.11.13.4 Perform PT/0/A/4600/02A, Incore and NIS
/
Correlation Check.
12.11.13.5 Perform PT/0/A/4150/04, Reactivity
/
Anomolies Calculation.
PT/0/A/4150/21 Page 15 of 15 12.11.13.6 Record the Intermediate Range NIS overlay
/
- data at 100% full power on Enclosure 13.2 and forward a copy of the enclosure :o the appropriate I&E engineer.
12.11.13.7 Perform PT/1 or 2/A/4150/13, NC Flow Test.
/
NOTE: Once Step 12.11.13.6 is complete, Step 12.11.14 may be performed.
NOTE: Perform the next two steps in any order.
j / 12.11.14 I&E has received data from the NC Flow Test and has made a final AT evaluation for the cycle at 100% F.P.
13.0 Enclosures 13.1 PA0 Data 13.2 Nuclear Instrumentation Overlap Data Sheet 13.3 Nuclear Heat Determination Data Sheet 13.4 Reactivity Computer Checkout Data Sheet 13.5 Intermediate Range Channels Worksheeta .
13.6 Connecting the Reactivity Computer 13.7 Intermediate Range High Level Trip Setpoints 13.8 Sequence of Control Rod Banks for Rod Swap 13.9 Verification of Shutdown Martin During Rod Swap i 13.10 Shutdown Margin at Zero Power I
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'1
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PI/0/A/4150/21 Page 1 of 1.
Enclosure 13.1
- PA0 Data Post Refueling Controlling Procedure for Criticality, Zero Power Physics, and Power Escalation Testing P1393 Control Bank D Position A0819 Loop A T,y, A0825 Loop B T,y, A0831 Loop C T,y, A0837 Loop D T,y, A1058 Loop A AT A1070 Loop B AT A1082 Loop C AT A1094 Loop D AT A1106 Reference Temperature T,,g P1355 Rx. Thermal Power - Best Estimate P1385 Rx. Thermal Power - Best Estimate A1081 Generator Megawatts P1447 Primary Thermal Output %
P1445 Secondary Thermal Output %
P1469 P/R Avg. Level 1 Min. Avg.
Quad. 4 (N-44) ,
P1467 P/R Avs. Level 1 Min. Avg.
Quad. 2 (N-42)
P1466 P/R Avg. Level 1 Min. Avg.
Quad. 1 (N-43) ,
I P1468 P/R Avg. Level 1 Min. Avg.
Quad. 3 (N-44)
A1006 Turbine Impulse Chamber Pressure I 1
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PT/0/A/4150/21 Page 1 of 2
' nclosure 13.2 a
Nuclear Instrumentation Overlap Data Sheet Post Refueling Controlling Procedure for Criticality, Zero Power Physics, and Power Escalation Testing -
source ==ase Intermediate 8-aea N-32 N-35 N-36 N-31 amps amps CPS CPS Control Board amps amps CPS CPS EIS Cabinet Picoammster amps After one decade increase on IR Source Ranas Intermediate *- --
N-32 N-35 N-36 N-31 amps amps "ontrol Board CPS CPS CPS amps amps IIS Cabinet CPS Picosameter amps !
After one decade increase on IR Source Range Intermediate Ranae N-32 N-35 N-36 N-31 CPS amps amps Control Board CPS CPS amps amps MIS Cabinet CPS Picoammeter amps Readings when Source Range blocked Source Ranas Intermediate Ranae N-32 N-35 N-36 N-31 l CPS amps amps !
Control Board CPS CPS amps amps NIS Cabinet CPS Picosameter amps Date Unit Cycle Recorded By Checked By - Date
PT/0/A/4150/21 Page 2 of 2 Enclosure 13.2 Nuclear Instrumentation Overlap Data Sheet Post Refueling Controlling Procedure for Criticality, Zero Power Physics, and Power Escalation Testing Volts Volts Thermal Power, Recorded By Power Level N-35 N-36 Best Est. (P1385) (Date/ Time) 3%
10%
201 25%
50%
75%
100%
1 Unit Cycle NOTE: Data at 20 and 25% are needed to complete Enclosure 13.5. All other data are for info only.
l
. Note: IR voltage data is to be Al OUT A2 OUT ,,jy' taken inside each IR drawer.
Take readings across terminals 4 0 0Q TP3 and TP4 as shown on
- k' schematic. Set Fluke to DC Volts, O to 10 volt scale.
A3 OUT GN TP3 is a grey terminal and o{ TP4 is a black terminal.
I
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+1 y -
V '
4 O O g w
PT/0/A/4150/21 Page 1 of 1 Enclosure 13.3 Nuclear Heat Determination Data Sheet Post Refueling Controlling Procedure for Criticality, Zero Power Physics, and Power Escalation Testing Fluz Levels (amps)
Reac. Comp. Picoam-N-35 N-36 Time meter from P.R.
Try 1 Start Nuclear Heat e
Try 2 Start Nuclear Heat Avg. of 2 nuclear heat readings Zero Power Physics Testing Range I amps to amps on power range NI a
Recorded By Date 1
Checked By Date McGuire Unit Cycle ,
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PT/0/A/4150/21 1 Page 1 of 3 l Enclosure 13.5
- Intermediate Range Channels Worksheet l 4
Post Refueling Controlling Procedure for Criticality, Zero Power Physics, and Power Escalation Testing i
Step 1: From Enclosure 13.2 record below the values of Thermal Power Best Eatinate which most closely correspond to 20% and 25% power levels.
Step 2: From Enclosure 13.2 record below the voltage data given for the power ;
levels above.
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Step 3: Convert amp voltage, Eout, from Step 2 to Current, Iin, by using the ;
- following equation. Record values below on table. l 3
~
'Eout 9
~11 Iin = (1 x 10 ') (10 L 1.25 "I,)
~
,- 1 x 10 s
) Step 3 Step 3 4
, Step 2 Step 2 Iin Iin Step 1 Eout Eout Current Current Power N35 N36 N35 N36 Level Volts Volts Amps Amos i
a) f b) i 4
Step 4: Complete page 2 of 3 and 3 of 3 of this enclosure by linearly ,
extrapolating above data to 15%, 20%, 25% and 30% Power as indicated, and then converting to volts as indicated.
t l Calculated By Date l Checked By Date i
1 i
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PT/0/A/4150/21 Page 2 of 3 Enclosure 13.5 Intermediate Range Channels Worksheet
- Post Refueling Controlling Procedure for Criticality, Zero Power Physics, and Power Escalation Testing NOTE: Data is from Enclosure 13.5 page 1 of 3.
= amps
- 1. 20% power current for N36 (Rod Stop)
= amps
- 2. 25% power current for N36 (High Flux Trip)
= amps
- 3. 30% power current for N36 (T.S. Allowable Value)
= amps
NOTE: Convert the values found in Step I through 5 from amps to volts using the following equation.
(Round to 3 decimal places.)
Eout = 8.75 + 1.25 I,og 10 , volts
,f where Iid = 1 x 10 ~II amps
~
Iref = 1 x 10 ' amps o
- 6. N36 20% power voltage (Rod Stop) (Use Step 1.0 as Iin) volts
- 7. N36 25% power voltage (High Flux Trip) (Use Step 2.0 ,
volts
) as lin) i
- 8. N36 30% power voltage (T.S. Allowable Value) (Use volts Step 3.0 as lin)
- 9. N36 Hi Flux Rod Stop Reset at 15% Power (Use Step 4.0 as Iin) volts
- 10. N36 Hi Flux Trip Reset at 20% Power (Use Step 5.0 volts as Iin)
Calculated By Date Checked By Date i
PT/0/A/4150/21 Page 3.of 3
~ Enclosure 13.5
- Intermediate Range Channels Worksheet Post Refueling Controlling Procedure.for Criticality, Zero Power Physics, and Power Escalation Testing NOTE: Data is from Enclosure 13.5 page 1 of 3.
= amps
- 1. 20% power current for N35 (Rod Stop)
= amps
- 2. 25% power current for N35 (High Flux Trip)
= amps
- 3. 30% power current for N35 (T.S. Allowable Value)'
N35 Hi Flux Rod Stop Reset at 15% RTP = - amps 4.
N35 Hi Flux Trip Reset at 20% RTP = amps 5.
NOTE: Convert the values found in Step 1 through 5 from amps to volts using the following equation.
(Round to 3 decimal places.)
II"
- Iid\ L '
Eout = 8.75 + 1.25 Log 10 77,f j , volts
-11 amps where Iid = 1 x 10
-0 Iref = 1 x 10 amps
- 6. N35 20% power voltage (Rod Stop) (Use Step 1.0 as Iin) volts
- 7. N35 25% power voltage (High Flux Trip) (Use Step 2.0 volts i as Iin)
- 8. N35 30% power voltage (T.S. Allowable Value) (Use volts l Step 3.0 as lin)
- 9. N35 Hi Flux Rod Stop Reset at 15% Power (Use Step 4.0 volts as lin)
- 10. N35 Hi Flux Trip Reset at 20% Power (Use Step 5.0 volts as Iin)
Calculated By Date Checked By Date )
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PT/0/A/4150/21 Page 1 of 1 Enclosure 13.6 Connecting the Reactivity Computer
- Post Refueling Controlling Procedure for Criticality, Zero Power Physics, and Power Escalation Testing NOTE: Any one of the four power range channels may be used. For clarity NI-43 is chosen arbitrarily.
Initial /Date
/ 13.6.1 Have IAE place Channel NI-43 in the tripped condition with
/ IV input plugs removed by using the " Prerequisites" and.
" Removing Power Channel from Service" sections of IP/0/A/3207/03K (power range cal.) in their entirety.
NOTE: This procedure does not necessarily require that.the channel be placed in the tripped condition, or that the input plugs be removed. Inform the technician that these things are necessary for Performance testing.
/ 13.6.2 Verify detector A and B input plugs and high voltage .
/ IV plug have been disconnected.
/ 13.6.3 Clean all three cable connectors.
I / 13.6.4 Connect the A input plug to the A connector, the B input plug
/ IV to the B connector, and the HV plug to the HV connector on the Reactivity Computer Black Box.
/ 13.6.5 Connect the HV cable and P cable from the reactivity computer
/ IV to the HV and Det AB Signal terminals on the Black Box.
I
/ 13.6.6 Secure the Black Box to a rack mount with a tie wrap.
/ 13.6.7 To return NI-43 to service, verify the high voltage power supply and picosameter at the Reactivity Computer are off.
/ 13.6.7.1 Inform Shift Supervisor you are returning NI-43 to service.
/ 13.6.8 Disconnect the A and B input plugs and the HV input plug from
/ IV the Reactivity Computer Black Box.
/ _
13.6.9 Clean all three connectors.
/ 13.6.10 Have IAE return Channel NI-43 to service by performing the
/ IV " Prerequisites" and " Returning Power Range Channel to Service" sections of IP/0/A/3207/03K (power range cal.) in their entirety.
PT/0/A/4150/21 Page 1 of 1 Enclosure 13.7
- Intermediate Range High Level Trip Setpoints
-Post Refueling Controlling Procedure for Criticality, Zero Power Physics, and Power Escalation Testing N-35 trip setpoint (25% full power)
= amps N-36 trip setpoint (25% full power)
= amps Recorded By Date Unit Cycle I
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=
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1
}-
PT/0/A/4150/21 Page 1 of 1 Enclosure 13.8 Sequence of Control Rod Banks for Rod Swap Post Rgfueling Controlling Procedure for Criticality, Zero Power Physics, and Power Escalation Testing Reference Bank First Bank Second Bank Third Bank Fourth Bank Fifth Bank Sixth Bank Seventh Bank Eighth Bank NOTE: Some of the Banks may not be measured by rod swap; mark these Banks in the szquence N/A. Indicate justification in the test log if banks will not be measured.
Recorded By Date Unit Cycle l
I PT/0/A/4150/21 Page 1 of 1 Enclosure 13.9 Verification of Shutdown Margin During Rod Swap Post Refueling Controlling Procedure for Criticality, Zero Power Physics, and Power Escalation Testing
- 1. Inserted control rod worth at BOL and at zero power pcm insertion limits (from Enclosure 13.10, Step 2)
- 2. Rod swap Reference Bank worth pcm
- 3. Step 1. > 1.10 Step 2. Yes No (10% conservatism on the predicted Reference Bank Worth)
Recorded By Checked By Date Unit Cycle r-----v- - w y. -
y .e. ,- --g
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, 1 3/A/4150/21 Page 11of 1 Enclosure 13.10 **
- Shutdown Margin at Zero Power Post' Refueling Controlling Procedure for Criticality, Zero Power Physics, and Power Escalation Testing i
Centrol rod position at zero power insertion limits:
a) CB steps withdrawn b) CC steps withdrawn c) CD steps withdrawn Inserted control rod worth at BOL and at the zero power oca .
insartion limits (Data Book Curve 6.3A) l l
BOL, HZP, no xenon total rod worth pen i (D:ta Book Table 6.3.1) !
l Availchle rod worth at BOL and at zero power insertion ILuits (Sttp 3 - Step 2) pca Wsrth of highest worth stuck rod at BOL pcm (D:ta Book Table 6.3.2)
Available Shutdown Margin at BOL and at zero power insertion limits
[(Stap 4 - Step 5) 0.90] pcm Rsquired Shutdown Margin pcm Step 6 > Step 7 Yes No Recorded By -
Checked By Date Unit Cycle 7 i7 er -m- -
,yw - 9 -,i-- - - - , - ey, - - -e e- w- r-+e-- --=*y